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POLICY ISSUE
(INFORMATION)

SECY-01-0059

April 5, 2001

• PURPOSE:
• SUMMARY:
• BACKGROUND:
• DISCUSSION:
• WORK AT THE RUSSIAN RESEARCH CENTER
• Work Completed in 2000
• Work Planned for 2001
• WORK AT THE RUSSIAN ACADEMY OF SCIENCES
• Work Completed in 2000
• Work Planned for 2001
• CONCLUSION:
• RESOURCES:
• COORDINATION:

PURPOSE:

To inform the Commission of progress made in 2000 on research sponsored by the U.S. Nuclear Regulatory Commission (USNRC) at the Russian Research Center (RRC) (the Kurchatov Institute) and the Institute of Nuclear Safety of the Russian Academy of Sciences (IBRAE/RAS). Also, to inform the Commission of the staff's plan to continue these arrangements in 2001 provided that research results continue to be of value to the USNRC and that measurable progress is being made. We will inform the Commission annually of these programs.

SUMMARY:

For the past several years, the RRC and the RAS have performed research work for the USNRC under bilateral agreements. This work is funded by the Office of Nuclear Regulatory Research and has involved research in code development and assessment, hydrogen combustion experiments, evaluation of high-burnup fuel test data, in-vessel debris coolability experiments, evaluation of reactor pressure vessel surveillance capsule data, uncertainty analysis methods, and development of concrete containment failure criteria.

The results of this work have led to code improvements, expanded data bases and confirmatory research information. This work has also helped the Russians become familiar with USNRC analytical tools, safety issues, and Western approaches to safety. It is our intent to continue these programs in 2001 at a level comparable to that in 2000. The proposed Implementing Agreements for the 2001 work are attached to this paper.

BACKGROUND:

In SECY-91-375, "Proposed Arrangement with the I.V. Kurchatov Institute for Atomic Energy of the U.S.S.R. on Severe Accident Experiments," SECY-92-015, SECY-93-350, SECY-95-021, SECY-96-036, SECY-97-050, SECY-98-049, SECY-99-078, and SECY-00-0072, "Status of NRC Research Conducted by the Russian Research Center (I.V. Kurchatov Institute) and the Institute of Nuclear Safety of the Russian Academy of Sciences," the staff provided descriptions of research programs being conducted in Russia for the USNRC and recommended to the Commission that continued research cooperation between the USNRC and the RRC and the RAS was in the best interest of the USNRC. The Commission endorsed the staff recommendation.

The work currently being performed for the USNRC by the RRC is described in the Implementing Agreement on Severe Accident Research between the USNRC and RRC. A copy of Addendum 4 to this Implementing Agreement describing the work in 2000 was enclosed with SECY-00-0072. The work covered by the addendum consisted of :

• Measuring mechanical properties of cladding from high-burnup fuel and evaluating those results for applicability to the analysis of safety transients

• Developing and demonstrating a 3-D reactor transient physics code

The FY 2000 cost to the USNRC for this work specified in the addendum was $150K in accordance with the Agreement.

The work being performed for the USNRC by RAS is described in the Implementing Agreement on the Development and Application of Nuclear Safety Analysis Codes between the USNRC and the Institute of Nuclear Safety (IBRAE) of the RAS. A copy of Addendum 5 to this Implementing Agreement describing the work in 2000 was also enclosed with SECY-00-0072. The 2000 work covered by the addendum consisted of:

• Probabilistic risk assessment contributors to uncertainty

The FY 2000 cost to the USNRC for this work was $80K in accordance with the Agreement.

An additional task was added to Addendum 5 (under Article II.B.2 of the addendum) in early FY 2001 to assess the latest version of the MELCOR code (Version 1.8.5) which was released in December 2000. The FY 2001 cost to the USNRC for this work is $100K of which $75K has already been paid.

DISCUSSION:

Discussed below is a summary of the work performed in 2000 under Addenda 4 and 5 of the Implementing Agreements, and our plans for continuing work in 2001. The Implementing Agreement with the RRC expired on February 23, 2001, and the Implementing Agreement with the RAS expired on December 31, 2000. The proposed Implementing Agreements to continue this work at the RRC and RAS for a 5-year period are attached to this paper.

WORK AT THE RUSSIAN RESEARCH CENTER

Work Completed in 2000

• High-Burnup Fuel

During 2000, the high-burnup fuel work consisted of performing axial tensile tests on irradiated and unirradiated Alloy E110 fuel rod cladding and reassessing and summarizing earlier Russian data on that alloy that were not generated in this program. The temperature range was expanded in 2000 to cover conditions of loss-of-coolant accidents (high temperatures) as well as reactivity accidents (low temperatures), which were the focus of earlier work. These are the two accident types that are postulated for safety analysis around the world to ensure that plausible events do not degrade into core melt accidents. A report on Mechanical Properties of Unirradiated and Irradiated Zr-1%Nb Cladding covering the low temperature regime was submitted and is currently in publication as a NUREG/IA report. Mechanical properties from this program will be incorporated in USNRC's FRAPTRAN fuel rod computer code, which is being used to resolve high-burnup issues associated with reactivity accidents and loss-of-coolant accidents. These mechanical properties will let the staff make estimates of the behavior of the newer niobium-bearing alloys (M5 and ZIRLO) that are in use in the U.S. for which mechanical properties data are not yet available (or not available to the USNRC). While there may be some differences in the mechanical properties of niobium-bearing alloys manufactured by different vendors, the general effects of adding niobium should be apparent. Insights from the Russian data have also been used directly by USNRC in reviewing licensing submittals for the newer alloys and in assessing regulatory criteria.

• 3-D Reactor Physics

Comparisons of the Russian BARS code and USNRC's PARCS code have been very useful because they are state-of-the art detailed codes that are needed for the analysis of reactivity accidents in light of substantially reduced acceptance criteria for high-burnup fuel. These two codes have completely different developmental origins, and their comparison provides insights and confidence in their analytic capabilities. During 2000, sensitivity analyses were carried out on important parameters for the TMI-1 rod-ejection benchmark calculations that had been previously performed. A report on this work (NSI RRC KI 90-12/1-1-01) has been issued. Analysis of boron-dilution events, another type of reactivity accident, was begun. The PARCS code will be used by USNRC for confirmatory plant transient analysis once high-burnup criteria are established for the reactivity accidents.

Work Planned for 2001

Attachment 1 to this paper describes the work planned in 2001 at the RRC. This work is summarized below:

• High-Burnup Fuel

Continue assessment of earlier Russian data for conditions of loss-of-coolant accidents. Perform ring-compression tests and axial tensile tests of oxidized specimens of irradiated and unirradiated E110 cladding to determine the zero-ductility conditions for analysis of loss-of-coolant accidents. Transfer all Russian special modeling that was incorporated in USNRC 's FRAP-T6 fuel rod transient code and MATPRO materials property library to USNRC's new FRAPTRAN code and updated MATPRO library.

• 3-D Reactor Physics

Additional calculations will be made of a TMI-1 rod-ejection accident to compare beginning-of-cycle and end-of-cycle behavior, and to compare central-rod and peripheral-rod behavior. Sensitivity studies will be initiated on boron-dilution accidents to examine major uncertainties. Modifications will be made to the BARS code for calculating partial cores of mixed-oxide fuel (MOX) to benchmark the results to those using the USNRC PARCS codes. The cost to the USNRC for the 2001 work described above is $150K.

WORK AT THE RUSSIAN ACADEMY OF SCIENCES

Work Completed in 2000

• Probabilistic Risk Assessment - Contributors to Uncertainty

The RAS effort during FY 2000 was focused on assessing the change in acceptance criteria for loss of coolant accidents (LOCA) as the break size is reduced from the large break LOCA to smaller breaks. A draft report was received and is undergoing review. This work is being used by the staff in its evaluation of the feasibility of risk-informing 10 CFR 50 (Option 3)

Work Planned for 2001

Attachment II to this paper describes the work planned in 2001 at the RAS. This work is summarized below:

• Assessment of MELCOR Version 1.8.5

RAS will assess MELCOR Version 1.8.5 using application to a VVER-1000 plant as a test case. Feedback on models and user characteristics will be provided to USNRC. It should be noted that this work was started in December 2000, upon release of the code, under Addendum 5. The cost to the USNRC for this work is $100K, of which $75K has already been paid as discussed in the background section of this paper.

• Risk Communication

RAS plans to explore approaches to improve risk communication. The objective of the work is to assess approaches in various countries and industries with respect to the risks to the public, how these risks are managed and communicated. FY 2001 USNRC funding of $50K will help to support this activity.

CONCLUSION:

Given the progress to date on the ongoing programs, the expectation that the 2001 work described above can be successfully carried out, and the relatively small funding involved, we believe that it is in the best interest of the USNRC to continue our agreements with the RRC and RAS. The benefits from the research conducted by the RRC and the RAS are discussed in Attachment III. As noted in the Discussion Section, the Implementing Agreement with the RRC expired on February 23, 2001, and the Implementing Agreement with the RAS expired on December 31, 2000. Accordingly, new Implementing Agreements with the RRC and RAS for a period of 5 years have been prepared and are attached. I intend to forward these to the RRC and RAS for signature.

RESOURCES:

The cost to the USNRC in FY 2001 of the research summarized above would be $150K for the RRC and $150K for the RAS of which $75K has already been paid due to the early start of this work under Article II.B.2 of Addendum 5. These costs do not include the cost of travel, which will be paid for by the RRC and RAS. Funds for this research work are in the FY 2001 Office of Nuclear Regulatory Research budget.

COORDINATION:

This paper has been coordinated with the Office of International Programs, which has no objection, the Office of the Chief Financial Officer, which has no resource objection, and the Office of the General Counsel, which has no legal objection.

I will continue to keep the Commission informed of progress on the USNRC sponsored research at the RRC and the RAS.

ATTACHMENT I

IMPLEMENTING AGREEMENT
BETWEEN
THE UNITED STATES NUCLEAR REGULATORY COMMISSION (USNRC)
AND
THE RUSSIAN RESEARCH CENTER (RRC)
FORMERLY THE I.V. KURCHATOV INSTITUTE FOR ATOMIC ENERGY (KI)
ON FUEL BEHAVIOR RESEARCH

• ARTICLE I - PROGRAM COOPERATION
• ARTICLE II - FORMS OF COOPERATION
• ARTICLE III - SCOPE OF COOPERATION
• ARTICLE IV - FINANCIAL CONSIDERATIONS
• ARTICLE V - ADMINISTRATION OF THE IMPLEMENTING AGREEMENT
• ARTICLE VI - EXCHANGE AND USE OF INFORMATION AND INTELLECTUAL PROPERTY
• ARTICLE VII - FINAL PROVISIONS

Considering that the United States Nuclear Regulatory Commission (USNRC) and Russian Research Center, formerly the I.V. Kurchatov Institute for Atomic Energy (RRC-KI):

1. Have been cooperating in the area of civilian nuclear reactor safety as part of a 5-year Agreement Between the Government of the United States of America and the Government of the Russian Federation Concerning Operational Safety Enhancements, Risk Reduction Measures and Nuclear Safety Regulation for Civil Nuclear Facilities in the Russian Federation signed on December 16, 1993, hereinafter "Agreement";

2. Have been conducting joint cooperative nuclear safety activities through the Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS) (pursuant to the Memorandum of Cooperation in the Field of Civilian Nuclear Reactor Safety of April 26, 1988, and the Agreement between the United States of America and the Union of Soviet Socialist Republics on Scientific and Technical Cooperation in the Field of Peaceful Uses of Atomic Energy of June 1, 1990; hereinafter Peaceful Uses Agreement). The JCCCNRS has been acknowledged as the implementing committee for the above Agreement;

3. Have a mutual interest in cooperation in the field of nuclear safety research, with the objective of improving the safety of reactors on an international basis;

4. Have, as a mutual objective, reciprocity in the exchange of technical information in the field of reactor safety research;

The USNRC and the RRC have adopted the following terms and conditions as an implementing agreement.

ARTICLE I - PROGRAM COOPERATION

The USNRC and the RRC, in accordance with the provisions of this Implementing Agreement and subject to applicable laws and regulations in force in the respective Countries, will join together in nuclear safety programs related to the behavior of reactor fuel, especially the behavior of reactor fuel with high burnup.

ARTICLE II - FORMS OF COOPERATION

Cooperation between the parties may take the following forms:

1. The exchange of information in the form of experimental results, technical reports, code validation data, correspondence, newsletters, visits, joint meetings, and such other means as the parties agree.

2. The temporary assignment of personnel of one party or of its contractors to laboratories or facilities owned by the other party; each assignment to be considered on a case-by-case basis and to be the subject of a separate attachment-of-staff arrangement between the parties.

3. The execution of joint programs and projects, including those involving a division of activities between the parties; each joint program and project may be considered on a case-by-case basis and may be the subject of a separate arrangement between the parties.

4. The use by one party of facilities that are owned by the other party; such use of facilities may be the subject of separate arrangements between the parties and may be subject to commercial terms and conditions.

5. If either party wishes to visit, assign personnel, or use the facilities owned or operated by entities other than the parties to this Implementing Agreement, the parties recognize that the approval of such entities will in general be required with respect to the terms upon which such visit, assignment, or use will be made.

6. Any other form agreed between the parties.

ARTICLE III - SCOPE OF COOPERATION

The objectives of this Implementing Agreement are to (a) obtain experimental data on the behavior of Zr-1%Nb fuel rod cladding under postulated accident conditions, (b) advance the development of fuel rod codes that are used to analyze fuel behavior under accident conditions, and (c) explore and modify plant transient codes for analyzing postulated accidents in light-water reactors containing high-burnup fuel.

ARTICLE IV - FINANCIAL CONSIDERATIONS

The ability of the parties to carry out their obligations is subject to the appropriation of funds by the appropriate governmental authorities and to laws and regulations applicable to the parties. Subject to the availability of funds, the USNRC will provide the RRC the sum of $150,000 in Fiscal Year 2001. The first payment of $75,000 will be made upon approval of a work plan called a Description of Work. RRC will complete a Description of Work acceptable to both parties within 60 days after entry into force of this Implementing Agreement. A second payment of $75,000 will be made in July 2001. Payment will be made upon receipt of RRC invoices, subject to U.S. Government rules and regulations.

If other technical appendices are developed during the course of this cooperation, the resulting financial considerations will be included in those appendices.

ARTICLE V - ADMINISTRATION OF THE IMPLEMENTING AGREEMENT

1. The USNRC and the RRC will each designate one representative to coordinate and determine the detailed implementation of this Implementing Agreement. This designated representative will be referred to as an Administrator of the Implementing Agreement. The Administrators may, at their discretion, delegate this responsibility to the appropriate individuals with respect to a given issue.

2. This Implementing Agreement states restrictions concerning dissemination of proprietary or other confidential or privileged information. Other information that my be restricted includes matters related to organization, budget, personnel, or management.

3. Each party to this Implementing Agreement will have access to all reports written by its partner's technical personnel assigned to the respective activities that derive from participation in this Implementing Agreement.

4. Subject to Article VG. and VH., USNRC-supplied codes and analytical techniques and any improvements, modifications or updates to such codes or techniques will not be disseminated to other parties outside the Russian Federation without the consent of the USNRC.

5. Except for dissemination to USNRC and its principal contractors in accordance with this Implementing Agreement, RRC-supplied codes and analytical techniques and any improvements, modifications or updates to such codes and techniques will not be disseminated to other parties outside the U.S. without the consent of the RRC.

6. The application or use of any codes exchanged or transferred between the parties under this Implementing Agreement shall be the responsibility of the receiving party, and the transmitting party does not warrant the suitability of such codes for any particular use or application.

7. The USNRC computer codes disseminated under this Implementing Agreement are to be considered privileged information unless otherwise noted, are protected as such by the USNRC, and shall be treated likewise by RRC. They are in particular, subject to all the provisions of Article VI including the requirements for an agreement of confidentiality prior to dissemination, with the exception that they need not be marked with the restrictive designation. The codes are subject to this protection in both object and source forms and as recorded in any media.

8. The USNRC computer codes and other related analytical techniques that are provided to the RRC under this Implementing Agreement and any improvements, modifications or updates to such codes or techniques are for the purpose of this Implementing Agreement and shall not be used by RRC or other parties within the Russian Federation for commercial purposes; that is, for financial or other benefits not concerned with the study of reactor safety.

Among the code uses that will be permitted under this Implementing Agreement are those related to research in the reactor safety area and analyses performed by the members or their contractors that can assist regulators and plant personnel in assessing the safety of the plant, analyzing operating events, and training of operators. Specific examples of permitted analyses include: design basis accidents (e.g., loss-of-coolant accidents), anticipated transients, accident management and emergency operating procedures, mid-loop operation, analysis to support PRA success criteria, power upgrades and reload.

Prohibited uses of the code include: (1) analyses to develop a new reactor design, and (2) analyses to support power upgrades and reload in the U.S. unless performed by a U.S. subsidiary.

9. The USNRC codes and other related analytical techniques shall not be advertised directly or by implication to obtain contracts related to the construction, servicing, or refueling of nuclear facilities, nor shall advertising imply that the USNRC has endorsed any analysis or techniques.

10. It is understood that the USNRC makes no warranties whatsoever for the ability or suitability of any USNRC code or other analytical technique to perform in any particular manner for any particular purpose, or to accomplish any particular task. It is further understood that the USNRC accepts no liability for damages of any type that may result from the use of the USNRC codes or other analytical techniques provided under this Implementing Agreement.

11. Travel costs, living expenses, and salaries will be borne by the parties who incurred them unless specified otherwise.

ARTICLE VI - EXCHANGE AND USE OF INFORMATION AND INTELLECTUAL PROPERTY

ARTICLE VII - FINAL PROVISIONS

1. This Implementing Agreement shall be effective from the date of signature by the USNRC and the RRC and shall be effective for a period of 5 years. It may be extended for a further period of time by written agreement of the parties.

2. Either party may withdraw from the present Implementing Agreement after providing the other party written notice at least 180 days prior to its intended date of withdrawal.

3. All costs arising from implementation of this Implementing Agreement will be borne by the party that incurs them except when specifically agreed to otherwise by both parties.

4. The parties to this Implementing Agreement reserve the right to modify or extend the activities described in Article III within the intended scope of this Implementing Agreement upon written concurrence of its Administrators.

5. Any dispute between the parties concerning the interpretation or application of this Implementing Agreement will be settled by mutual agreement of the parties.

DONE at Rockville, Maryland on , 2001 , and at Moscow, Russia on , 2001 .

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION:

FOR THE INSTITUTE OF NUCLEAR SAFETY OF THE RUSSIAN ACADEMY OF SCIENCES:

INTELLECTUAL PROPERTY ADDENDUM

• I. SCOPE
• II. ALLOCATION OF RIGHTS

Pursuant to Article VI of this Implementing Agreement:

The parties shall ensure adequate and effective protection of intellectual property created or furnished under this Implementing Agreement and relevant implementing arrangements. The parties agree to notify one another in a timely fashion of any inventions or copyrighted works arising under this Implementing Agreement and to seek protection for such intellectual property in a timely fashion. Rights to such intellectual property shall be allocated as provided in this Addendum.

I. SCOPE

II. ALLOCATION OF RIGHTS

ATTACHMENT II

IMPLEMENTING AGREEMENT
BETWEEN
THE UNITED STATES NUCLEAR REGULATORY COMMISSION (USNRC)
AND
THE INSTITUTE OF NUCLEAR SAFETY (IBRAE)
OF THE
RUSSIAN ACADEMY OF SCIENCES (RAS)
ON THE DEVELOPMENT AND APPLICATION OF NUCLEAR SAFETY ANALYSIS CODES
AND PROBABILISTIC RISK ASSESSMENT TECHNIQUES

• ARTICLE I - PROGRAM COOPERATION
• ARTICLE II - FORMS OF COOPERATION
• ARTICLE III - SCOPE OF COOPERATION
• ARTICLE IV - FINANCIAL CONSIDERATIONS
• ARTICLE V - ADMINISTRATION OF THE IMPLEMENTING AGREEMENT
• ARTICLE VI - EXCHANGE AND USE OF INFORMATION AND INTELLECTUAL PROPERTY
• ARTICLE VII - FINAL PROVISIONS

Considering that the United States Nuclear Regulatory Commission (USNRC) and Institute of Nuclear Safety of the Russian Academy of Sciences (IBRAE/RAS):

1. Have been cooperating in the area of civilian nuclear reactor safety as part of a 5-year Agreement Between the Government of the United States of America and the Government of the Russian Federation Concerning Operational Safety Enhancements, Risk Reduction Measures and Nuclear Safety Regulation for Civil Nuclear Facilities in the Russian Federation signed on December 16, 1993, hereinafter "Agreement";

2. Have been conducting joint cooperative nuclear safety activities through the Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS) (pursuant to the Memorandum of Cooperation in the Field of Civilian Nuclear Reactor Safety of April 26, 1988, and the Agreement between the United States of America and the Union of Soviet Socialist Republics on Scientific and Technical Cooperation in the Field of Peaceful Uses of Atomic Energy of June 1, 1990; hereinafter Peaceful Uses Agreement). The JCCCNRS has been acknowledged as the implementing committee for the above Agreement;

3. Have a mutual interest in cooperation in the field of nuclear safety research, with the objective of improving the safety of reactors on an international basis;

4. Have, as a mutual objective, reciprocity in the exchange of technical information in the field of reactor safety research;

The USNRC and the IBRAE/RAS have adopted the following terms and conditions as an implementing agreement.

ARTICLE I - PROGRAM COOPERATION

The USNRC and the IBRAE/RAS, in accordance with the provisions of this Implementing Agreement and subject to applicable laws and regulations in force in the respective Countries, will join together in nuclear safety programs related to the development and application of nuclear safety analysis codes (i.e., CONTAIN, SCDAP/RELAP, CORCON, HMS, VANESA, MELCOR) probabilistic risk assessment techniques to RBMK, VVER-type and U.S. LWR reactors.

ARTICLE II - FORMS OF COOPERATION

Cooperation between the parties may take the following forms:

1. The exchange of information in the form of technical reports, code validation data, correspondence, newsletters, visits, joint meetings, and such other means as the parties agree.

2. The temporary assignment of personnel of one party or of its contractors to laboratories or facilities owned by the other party; each assignment to be considered on a case-by-case basis and to be the subject of a separate attachment-of-staff arrangement between the parties.

3. The execution of joint programs and projects, including those involving a division of activities between the parties; each joint program and project may be considered on a case-by-case basis and may be the subject of a separate arrangement between the parties.

4. The use by one party of facilities that are owned by the other party; such use of facilities may be the subject of separate arrangements between the parties and may be subject to commercial terms and conditions.

5. If either party wishes to visit, assign personnel, or use the facilities owned or operated by entities other than the parties to this Implementing Agreement, the parties recognize that the approval of such entities will in general be required with respect to the terms upon which such visit, assignment, or use will be made.

6. Any other form agreed between the parties.

ARTICLE III - SCOPE OF COOPERATION

The objective of this Implementing Agreement is to develop and assess improved models to selected USNRC severe accident codes and to develop, apply or assess probabilistic risk assessment techniques to improve safety and public confidence. In particular, this agreement will include assessment of models for the MELCOR, SCDAP/RELAP and SAPHIRE codes and development of risk communication techniques.

ARTICLE IV - FINANCIAL CONSIDERATIONS

The ability of the parties to carry out their obligations is subject to the appropriation of funds by the appropriate governmental authority and to laws and regulations applicable to the parties. Subject to the availability of funds, the USNRC will provide the IBRAE/RAS the sum of $75K in Fiscal Year 2001.

A payment of $75K will be made upon approval of the work plan. IBRAE/RAS will complete a work plan acceptable to both parties within 60 days after entry into force of this Implementing Agreement. Payment will be made upon receipt of IBRAE/RAS invoices, subject to U.S. government rules and regulations.

If other technical appendices are developed during the course of this cooperation, the resulting financial considerations will be included in these appendices.

ARTICLE V - ADMINISTRATION OF THE IMPLEMENTING AGREEMENT

1. The USNRC and the IBRAE/RAS will each designate one representative to coordinate and determine the detailed implementation of this Implementing Agreement. This designated representative will be referred to as an Administrator of the Implementing Agreement. The Administrators may, at their discretion, delegate this responsibility to the appropriate individuals with respect to a given issue.

2. This Implementing Agreement states restrictions concerning dissemination of proprietary or other confidential or privileged information. Other information that my be restricted includes matters related to organization, budget, personnel, or management.

3. Each party to this Implementing Agreement will have access to all reports written by its partner's technical personnel assigned to the respective activities that derive from participation in this Implementing Agreement.

4. USNRC-supplied codes and analytical techniques and any improvements, modifications or updates to such codes or techniques will not be disseminated to other parties outside the Russian Federation without the consent of the USNRC.

5. Except for dissemination to USNRC and its principal contractors in accordance with this Implementing Agreement, IBRAE/RAS-supplied codes and analytical techniques and any improvements, modifications or updates to such codes and techniques will not be disseminated to other parties outside the U.S. without the consent of the IBRAE/RAS.

6. The application or use of any codes exchanged or transferred between the parties under this Implementing Agreement shall be the responsibility of the receiving party, and the transmitting party does not warrant the suitability of such codes for any particular use or application.

7. The USNRC computer codes disseminated under this Implementing Agreement are to be considered privileged information unless otherwise noted, are protected as such by the USNRC, and shall be treated likewise by IBRAE/RAS. They are in particular, subject to all the provisions of Article VI including the requirements for an agreement of confidentiality prior to dissemination, with the exception that they need not be marked with the restrictive designation. The codes are subject to this protection in both object and source forms and as recorded in any media.

8. The USNRC computer codes and other related analytical techniques that are provided to the IBRAE/RAS under this Implementing Agreement and any improvements, modifications or updates to such codes or techniques are for the purpose of this Implementing Agreement and shall not be used by IBRAE/RAS or other parties within the Russian Federation for commercial purposes; that is, for financial or other benefits not concerned with the study of reactor safety.

Among the code uses that will be permitted under this Implementing Agreement are those related to research in the reactor safety area and analyses performed by the members or their contractors that can assist regulators and plant personnel in assessing the safety of the plant, analyzing operating events, and training of operators. Specific examples of permitted analyses include: design basis accidents (e.g., loss-of-coolant accidents), anticipated transients, accident management and emergency operating procedures, mid-loop operation, analysis to support PRA success criteria, power upgrades and reload.

Prohibited uses of the code include: (1) analyses to develop a new reactor design, and (2) analyses to support power upgrades and reload in the U.S. unless performed by a U.S. subsidiary.

9. The USNRC codes and other related analytical techniques shall not be advertised directly or by implication to obtain contracts related to the construction, servicing, or refueling of nuclear facilities, nor shall advertising imply that the USNRC has endorsed any analysis or techniques.

10. It is understood that the USNRC makes no warranties whatsoever for the ability or suitability of any USNRC code or other analytical technique to perform in any particular manner for any particular purpose, or to accomplish any particular task. It is further understood that the USNRC accepts no liability for damages of any type that may result from the use of the USNRC codes or other analytical techniques provided under this Implementing Agreement.

11. Travel costs, living expenses, and salaries will be borne by the parties who incurred them unless specified otherwise.

ARTICLE VI - EXCHANGE AND USE OF INFORMATION AND INTELLECTUAL PROPERTY

ARTICLE VII - FINAL PROVISIONS

1. This Implementing Agreement shall be effective from the date of signature by the USNRC and the IBRAE/RAS and shall be effective for a period of 5 years. It may be extended for a further period of time by written agreement of the parties.

2. Either party may withdraw from the present Implementing Agreement after providing the other party written notice at least 180 days prior to its intended date of withdrawal.

3. All costs arising from implementation of this Implementing Agreement will be borne by the party that incurs them except when specifically agreed to otherwise by both parties.

4. The parties to this Implementing Agreement reserve the right to modify or extend the activities described in Article III within the intended scope of this Implementing Agreement upon written concurrence of its Administrators.

5. Any dispute between the parties concerning the interpretation or application of this Implementing Agreement will be settled by mutual agreement of the parties.

DONE at Rockville, Maryland on , 2001 , and at Moscow, Russia on , 2001 .

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION:

FOR THE INSTITUTE OF NUCLEAR SAFETY OF THE RUSSIAN ACADEMY OF SCIENCES:

INTELLECTUAL PROPERTY ADDENDUM

• I. SCOPE
• II. ALLOCATION OF RIGHTS

Pursuant to Article VI of this Implementing Agreement:

The parties shall ensure adequate and effective protection of intellectual property created or furnished under this Implementing Agreement and relevant implementing arrangements. The parties agree to notify one another in a timely fashion of any inventions or copyrighted works arising under this Implementing Agreement and to seek protection for such intellectual property in a timely fashion. Rights to such intellectual property shall be allocated as provided in this Addendum.

I. SCOPE

II. ALLOCATION OF RIGHTS

ATTACHMENT III

BENEFITS FROM RESEARCH CONDUCTED BY THE
RUSSIAN RESEARCH CENTER AND RUSSIAN ACADEMY OF SCIENCES

• Russian Research Center
• Russian Academy of Sciences

Russian Research Center

The cost of this work is leveraged by about 20 as a result of low staff costs and the sharing of costs with the French safety institute, IPSN, and the Russian ministry, MINATOM, and other Russian organizations. Further, large quantities of raw data are brought into this program for assessment from other Russian programs that did not receive USNRC support. These programs include (a) testing under reactivity accident conditions in two test reactors, (b) testing under loss-of-coolant conditions in the Impulse Graphite reactor, (c) testing of fresh and irradiated cladding out of pile under loss-of-coolant conditions, and (d) studies of properties of zirconium alloys, especially those with niobium.

Standard Russian VVER cladding is a Zr-1%Nb alloy that is almost identical in composition to the Framatome M5 alloy and similar to the Westinghouse ZIRLO cladding that are being used in the U.S. High-burnup studies of these alloys have not yet been made in the U.S., and the Russian work gives some insights into the behavior of these cladding types under postulated accident conditions that must be considered in safety analyses.

The first major result from this program was the demonstration that the niobium alloy cladding with its much lower corrosion level behaved much differently than Zircaloy under conditions of a reactivity accident. The failure mechanism was a ductile burst rather than a brittle fracture and it occurred at a significantly higher energy deposition. This demonstrated the importance of the failure mechanism, corrosion level, and alloy type, and it indicates a potential for improved transient behavior of the newer alloys being used in the U.S.

A Russian-French-American round-robin tensile test was performed on Russian cladding tubes to check reproducibility of measurement techniques. This led to state-of-the-art developments of ring-tensile specimen design that will allow testing of small specimens of irradiated material to obtain mechanical properties. These properties are needed to perform analyses that will reduce the number of in-reactor and large integral tests in hot cells to determine damage criteria for new cladding alloys at high burnups.

A recent Russian handbook of zirconium alloy properties was given to the USNRC along with permission to pass the information along to the U.S. industry. The USNRC had this handbook translated and then gave the original and translated versions to EPRI for distribution to the U.S. industry, subject to cost and copyright arrangements with the publisher.

Information on phase transformations and mechanical properties of Zr-1%Nb alloys generated in this Russian program were used by USNRC's reviewer in the review of Framatome's licensing topical report on M5 cladding. These results helped the reviewer perform this review on schedule and issue an approval in 1999.

Results show that the difference between mechanical properties of unirradiated and irradiated cladding disappears completely at temperatures above 860 K and that a pronounced anisotropy effect in unirradiated cladding is insignificant in irradiated cladding. These insights help design related tests being done in the U.S. and contribute to our understanding of the behavior of new cladding alloys in the U.S. at high burnups.

Models and coding were developed in this program for calculating heat transfer and rewetting in water-filled test capsules where there is no flow over the fuel rod surface. These models were installed in the VVER version developed by the Russians of USNRC's FRAP-T6 fuel rod transient code. These models will be imported into USNRC's current FRAPTRAN fuel rod transient code, and the models will improve the analysis of data from Japanese tests in stagnant water capsules. Such analysis will help avoid unnecessary conservative biases in interpreting the important data set from Japan.

Excellent agreement between the Russian neutron kinetics code, BARS, and western codes like USNRC's PARCS code gives added confidence in all of these codes to predict fuel rod power during transients, and the studies of uncertainties being done in this program will allow more accurate uncertainty estimates thus avoiding unnecessary conservative margin. These codes are used primarily for the postulated reactivity accidents.

Russian Academy of Sciences

The work performed by the RAS has involved analytical modeling of core melt progression, assessment of RELAP against Russian thermal-hydraulic data and PRA methods development.

RAS analytical modeling work led to the development and implementation of four analytical models for USNRC's SCDAP/RELAP code. These models address:

• steam/zirconium interactions
• fuel and clad melting
• zirconium and UO₂ dissolution
• cladding mechanical behavior

These analytical models are based more on first principles than the previous models and thus make the code applicable to a wider range of conditions.

RAS thermal-hydraulics work screened and identified unique Russian thermal-hydraulic data of potential use in assessing USNRC's RELAP code. This will help focus assessment efforts on the data most relevant to RELAP.

RAS has also developed a report on the desired attributes of a consolidated severe accident code, which will be used to assist USNRC severe accident code consolidation work.

RAS PRA work led to the development of a technique for incorporating uncertainties into a risk assessment not traditionally modeled (i.e., success criteria). This method was used in follow on work to assess the sensitivity of LOCA PRA analyses to uncertainties in LOCA success criteria. Such work is being used in our efforts to risk-inform 10 CFR 50.46 (Option 3).

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Thursday, February 22, 2007