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SECY-03-0043

March 20, 2003

Contact: C. Glenn, OEDO

Enclosure A

Exelon License Renewal Application for Peach Bottom Units 2 and 3

On March 6, 2003, the staff presented the results of its evaluation of the Peach Bottom license renewal application (LRA) to the Advisory Committee for Reactor Safeguards (ACRS). The staff's final safety evaluation report (SER) was issued February 5, 2003. The ACRS was provided copies of the SER before the presentation. The staff discussed the closure of several open items and other topics requested by the ACRS. Exelon also made a presentation to the ACRS regarding how they are implementing their aging management programs for license renewal.

Public Meeting with NEI and Industry to Discuss Emergency Staffing Study

On March 4, 2003, Nuclear Regulatory Commission (NRC) emergency preparedness staff conducted a public meeting with the Nuclear Energy Institute (NEI) and nuclear industry representatives at NRC headquarters. The purpose of the meeting was to discuss guidance that is being developed to address on-shift and augmentation staffing needed to respond to a radiological emergency at a nuclear power plant. In addition to the NEI representative, 17 licensee representatives attended. No other members of the public were present. A tentative schedule for future public meetings and opportunities for industry and public input into the project were discussed.

ACRS Full Committee Brief

The staff briefed the ACRS Full Committee on March 6, 2003, on their position and plans to address specific ACRS concerns regarding the Reactor Oversight Process (ROP). The discussions focused on a Commission Staff Requirements Memorandum that directed the staff to work with the ACRS to resolve apparent conflicts and discrepancies between aspects of the ROP that are risk-informed and those that are performance-based.

AP1000

On March 5, 2003, representatives from the NRC and Westinghouse held a public meeting at Westinghouse's Automation Headquarters. The purpose of the meeting was to discuss the NRC staff's unresolved instrumentation and controls issues for the AP1000 advanced reactor design. Fourteen unresolved issues were discussed at the meeting. Upon conclusion of the meeting, the NRC staff required no additional information for seven of the issues. In addition, Westinghouse agreed to provide a revised response for six of the issues, and the NRC staff identified one issue that needed further review. The New Reactor Licensing Project Office (NRLPO) staff is currently tracking 186 unresolved issues to ensure Westinghouse has been engaged on each item prior to the issuance of the Draft Safety Evaluation Report.

Public Meeting with NEI on Early Site Permit (ESP) Application Issues

On March 5, 2003, representatives from NEI met with the NRC staff to discuss issues related to ESP applications and reviews. Representatives from Dominion Generation, Exelon Generating Company, and Entergy Operations, Incorporated (prospective applicants for an ESP) were also in attendance. The staff and NEI discussed (1) industry comments on the staff response letters to the NEI issue resolution letters regarding various generic ESP topics (e.g., Plant Parameter Envelope), (2) ESP inspection guidance, (3) NEI comments on the NRC nominal review timeline, (4) criteria for assuring control of the site by an ESP Holder, and (5) addressing effects of potential new units at an existing site.

Meeting with the ACRS on ESP Issues and Review Standard

On March 7, 2003, the NRLPO staff made a presentation on the ESP process and the staff's draft ESP Review Standard (RS-002) to the ACRS. The discussion addressed recent issues raised by NEI related to the ESP review process, as well as issues that the staff addressed during development of draft RS-002. The ACRS plans to send a letter to the Commission regarding the ESP review process and draft RS-002.

Enclosure B

Package Performance Study Test Protocols Roundtable Public Workshops

On March 6, 2003, NRC hosted the first of three roundtable public workshops on NUREG-1768, "Package Performance Study Test Protocols," at NRC Headquarters. Approximately 100 people attended the workshop. A broad spectrum of interests were represented at the meeting, including citizens, nuclear and transportation industry, and governmental representatives at the Federal, State, and local level. Some of the issues the participants raised included the potential for conflicting test objectives of public confidence and model validation; the scale of the testing; the criteria to determine whether the tests are successful; clarification of the need to validate computer models; the meaning of public confidence; and the location of the surrogate fuel assemblies. The staff emphasized that no decisions about how the tests will be conducted have been made and stated it will consider all comments before finalizing test plans.

Meeting of the Radiation Therapy Committee of the American Association of Physicists in Medicine

On March 6-7, 2003, a staff member from the Division of Industrial and Medical Nuclear Safety represented NRC, as Liaison, at the spring meeting of the Radiation Therapy Committee of the American Association of Physicists in Medicine, held in Houston, Texas. The staff member discussed current publicly available information about a number of topics related to 10 CFR Part 35 implementation.

Cameco Decides Not to Join Louisiana Energy Services Partnership

On March 10, 2003, Cameco, a Canadian uranium mining firm, announced it had decided not to join the Louisiana Energy Services (LES) partnership. Cameco indicated the gas centrifuge enrichment plant project proposed for Hartsville, Tennessee, did not meet its requirements. LES indicated that Cameco's share would be taken up by the other partners and that LES still intends to submit a license application to NRC. It is expected that the license will not be filed until a final partnership agreement is completed, which could delay the scheduled March date for submittal.

Meeting with Japanese Representatives from the Ministry of Economy, Trade, and Industry, and the Nuclear Power Engineering Corporation

On March 11, 2003, Division of Fuel Cycle Safety and Safeguards staff met with Japanese representatives from the Ministry of Economy, Trade, and Industry, and from the Nuclear Power Engineering Corporation, to discuss technical issues associated with the Mixed-Oxide Fuel Fabrication Facility. Topics discussed include fire protection, nuclear criticality safety, explosions, and confinement ventilation. The staff continued the meeting on March 13, 2003, to discuss natural phenomena, external and internal hazards, and NUREG-1513, "Integrated Safety Analysis Guidance Document."

NRC Finds U.S. Enrichment Corporation, Inc.'s, License Application Acceptable for Review

By letter dated March 13, 2003, NRC notified the U.S. Enrichment Corporation, Inc., that its license application dated February 11, 2003, to possess and use, for 5 years, special nuclear, source, and by-product material in the American Centrifuge Lead Cascade Facility (Lead Cascade), was found to be acceptable for technical review. NRC anticipates completing its review by February 2004. The Lead Cascade, which is to be located at the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio.

Enclosure C

Implementing Agreement between the USNRC and the Canadian Nuclear Safety Commission (CNSC) Regarding Participation in the Third USNRC International Steam Generator Tube Integrity Research Program (ISG-TIP-3)

On March 6, 2003, the Executive Director for Operations (EDO) signed the Implementing Agreement between the USNRC and the Canadian Nuclear Safety Commission (CNSC) regarding participation in the Third USNRC International Steam Generator Tube Integrity Research Program (ISG-TIP-3) and the Office of Nuclear Regulatory Research forwarded this Implementing Agreement, on March 10, 2003, to CNSC Canada for counter-signature.

Under this Implementing Agreement, the USNRC and the CNSC will continue cooperating in safety research in order to develop the experimental data and predictive correlations and models to evaluate the integrity of steam generator tubes as plants age and degradation proceeds, new forms of degradation are identified, and new defect-specific management schemes are implemented. This cooperative research program will be performed on the basis of mutual benefit and reasonable equity and reciprocity. The work performed under this Implementing Agreement will contribute to NRC's goals of maintaining safety and enhancing our efficiency and effectiveness in independently evaluating the integrity of steam generator tubes. In addition to sharing research results, the CNSC will provide a yearly cash contribution in support of this program. This Implementing Agreement will enter into force upon signature of both parties and will remain in effect through December 31, 2006.

Agreement between the USNRC and the Korea Atomic Energy Research Institute (KAERI) and the Korea Institute of Nuclear Safety (KINS) Regarding Participation in the Third USNRC International Steam Generator Tube Integrity Research Program (ISQ-TIP-3)

On March 6, 2003, the EDO signed the Agreement between the USNRC and the Korea Atomic Energy Research Institute (KAERI) and the Korea Institute of Nuclear Safety (KINS) regarding participation in the Third USNRC International Steam Generator Tube Integrity Research Program (ISG-TIP-3) and the Office of Nuclear Regulatory Research forwarded this Agreement on March 10, 2003 for counter-signature.

Under this Agreement, the USNRC and the KAERI and KINS will continue cooperating in safety research in order to develop the experimental data and predictive correlations and models to evaluate the integrity of steam generator tubes as plants age and degradation proceeds, new forms of degradation are identified, and new defect-specific management schemes are implemented. This cooperative research program will be performed on the basis of mutual benefit and reasonable equity and reciprocity. The work performed under this Implementing Agreement will contribute to NRC's goals of maintaining safety and enhancing our efficiency and effectiveness in independently evaluating the integrity of steam generator tubes. In addition to sharing research results, the KAERI and KINS will provide a yearly cash contribution in support of this program. This Implementing Agreement will enter into force upon signature of both parties and will remain in effect through December 31, 2006.

Implementing Agreement on Thermal-Hydraulic Code Applications and Maintenance between The United States Nuclear Regulatory Commission and the State Office for Nuclear Safety of the Czech Republic (SÚJB)

On March 6, 2003, the EDO signed an international agreement between the USNRC and the State Office for Nuclear Safety of the Czech Republic (SÚJB) relating to Cooperation in the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).

This Implementing Agreement defines the terms and conditions by which the USNRC and the SÚJB will continue their cooperation in the USNRC thermal-hydraulic code applications and maintenance program (CAMP) on the basis of mutual benefit and reasonable equity and reciprocity. The work performed under this Implementing Agreement will contribute to the NRC's goal of maintaining safety by verifying the adequacy of NRC thermal hydraulic codes. In addition to exchanging technical information in this area, which contributes to the NRC goals of efficiency and effectiveness, the SÚJB will provide a cash contribution plus one code assessment report per year for the duration of this Implementing Agreement. This Implementing Agreement will enter into force upon signature of both parties and will remain in effect through September 20, 2005.

DG-1122 and Associated SRP Chapter 19.1 "An Approach for Determining the Technical Adequacy of PRA Results for Risk-Informed Activities" Public Workshop March 11, 2003

The Office of Nuclear Regulatory Research (RES) held a public meeting on March 11, 2003, to further discuss and solicit comments on the approach and guidelines in the draft regulatory guide (DG)-1122, "An Approach for Determining the Technical Adequacy of PRA Results for Risk-Informed Activities" and the associated Standard Review Plan (SRP) Chapter 19.1. This meeting, which was one of a series of meetings and workshops to discuss the draft guide, included discussions on the differences between the industry and staff's views on elements of the draft guide, including the terms "important," "dominant", and "significant". With respect to the use of these terms, the meeting made significant progress in resolving outstanding issues. The staff also presented its position on American Society of Mechanical Engineers (ASME) comments. A representative of ASME stated that he will present these comments to the Committee (meeting on March 24-26, 2003) for resolution. Further, the representative indicated that ASME still plans to issue an addendum to its standard, the content to be decided at the March meeting. The staff plans to hold another follow up meeting during the week of April 28, 2003, to present staff's response to public comments and the next draft of DG-1122.

Public Meeting on GSI 191, "Assessment of Debris Accumulation on PWR Sump Performance"

On March 5, 2003, staff from the Division of Engineering Technology (DET) attended a public meeting on industry's efforts for resolving GSI-191, "Assessment of Debris Accumulation on PWR Sump Performance", at the University of New Mexico (UNM) in Albuquerque, NM. The purpose of the meeting was to discuss industry's evaluation methodologies ground rules which will be used by the licensees in their plant specific evaluation. The public meeting was attended by NEI and representatives from licensees, insulation vendors, Electric Power Research Institute (EPRI), PWR Owners Group, and the Los Alamos National Laboratory (LANL). The University of New Mexico provided a tour of their experimental facilities that are being used in the NRC sponsored GSI-191 research activities. The LANL provided an update on their current NRC sponsored research activities (Debris Accumulation and CalSil Head Loss Testing, Chemical Testing, Volunteer Plant Containment Pool Flow Analysis, Analysis of Recovery Options) and exchanged and disseminated information pertinent to the industry resolution of GSI 191. The RES staff informed the industry that the draft Regulatory Guide - 1107 has been issued for public comments. The staff also stated that the knowledge base report on debris impact on Emergency Core Cooling System (ECCS) performance (NUREG/CR-6808) has also been sent to publication. The PWR Owners Group presented the industry action plan to address the PWR sump performance issue.

Advisory Committee on Reactor Safeguards (ACRS) Briefings

On March 6, 2003, DET staff briefed the ACRS on Draft Regulatory Guide DG-1119, "Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems." DG-1119 was issued for public comments on November 8, 2002. Four respondents provided comments. The staff presented the proposed final Regulatory Guide, including a discussion of its regulatory positions, technical basis and resolution of the public comments. DG-1119 has been developed to update the existing Regulatory Guide 1.180 to include the most recent U.S. Electromagnetic Compatibility (EMC) standards and the comparable international EMC standards, to provide relief concerning the operating envelopes as warranted by an enhanced technical basis, and to address phenomena that were not covered by previous guidance.

Enclosure D

Preliminary Notifications

1. PNO-III-03-011, Oakwood Hospital and Medical Center - MEDICAL EVENT DUE TO 1-125 SEEDS IMPLANTED IN WRONG TREATMENT SITE.

2. PNO-I-03-004, Millstone Nuclear Power Station, Unit 2 - UNUSUAL EVENTS DECLARED DUE TO REACTOR TRIP WITH LEAKAGE FROM CHARGING SYSTEM (EN Nos. 39644 and 39645).

3. PNO-IV-03-016, Professional Services Industries - STOLEN PORTABLE GAUGE.

4. PNO-I-03-005, Cabot Corporation - SPILL OF MATERIAL CONTAINING VERY SMALL AMOUNTS OF URANIUM AND THORIUM.

Enclosure G

Freedom of Information and Privacy Act (FOIA/PA) Requests received during the period of March 7 through March 13, 2003:

Enclosure I

Enclosure M

Media Interest

Extensive media attention resulted from the Private Fuel Storage/Skull Valley ruling by the Advisory Safety and Licensing Board.

Emergency preparedness at Indian Point received widespread coverage, especially the Witt Report and a congressional hearing that included testimony from the Federal Emergency Management Agency and NRC officials. In addition, Ohio papers reported that Davis-Besse's startup is likely to be delayed beyond April.

The International Atomic Energy Agency conference in Vienna on radiological dispersal devices (RDDs) received significant coverage by various media outlets, including Associated Press. Concern over radioactivity in California landfills and lost/stolen sources (moisture density gauges) led to calls for tighter controls by the Los Angeles media.

Enclosure O

Commission Correspondence

1. Letter to Congress dated March 7, 2003 provides the December 2002 report on the status of NRC's licensing and regulatory duties.

2. Letter to Sandra R. Galef, New York State Assembly, dated March 4, 2003, responds to request for the NRC to make an immediate change in its regulations to require a more secure facility be developed for the spent nuclear fuel.

3. Letter to Representative Mark Udall, dated March 4, 2003, concerns comments on NRC's Proposed rulemaking concerning transfers of low concentrations of radioactive "source" material to persons exempt from NRC licensing requirements.

4. Letter to Representatives Edward J. Markey, dated March 4, 2003, concerns the proposed export to Japan of approximately 13 tons of depleted uranium for use as test material in the Rokkasho Nuclear Fuel Reprocessing Plant (NRC Export License Application number XSOU8790).

5. Letter to Congress (Representatives Edward J. Markey and Nita M. Lowey), dated March 4, 2003, concerns security at the Indian Point nuclear facility.

Federal Register Notices Issued

1. ACRS Meeting of the Subcommittee on Plant License Renewal - Notice of Meeting.

2. ACRS Subcommittee Meeting on Planning and Procedures - Notice of Meeting.

Region I

Regional Administrator Testifies before House Subcommittee

On March 10, 2003, the Region I Regional Administrator testified before the U.S. House of Representatives subcommittee on National Security, Emerging Threats and International Relations. The subcommittee, chaired by Representative Christopher Shays, requested testimony on security and emergency preparedness issues, agency comments on the July 2001 U.S. General Accounting Office (GAO) Report No. GAO-01-605, on emergency preparedness at Indian Point, and on the recent report prepared by James Lee Witt and Associates for the State of New York.

Millstone Licensed Operator Certificate Presentation

On March 11, 2003, the Region I Deputy Regional Administrator met with representatives of Dominion Nuclear Connecticut, Inc. at the Millstone Power Station and toured the site. In the evening, he presented Operator License Certificates to twelve recently licensed Reactor and Senior Reactor Operators.

Permagrain Site Visit

On March 10, 2003, Region I staff, including the Deputy Regional Administrator, a Branch Chief and a Health Physicist, met with representatives of the Environmental Protection Agency (EPA) and the Commonwealth of Pennsylvania at the Permagrain site in Karthaus, PA. The purpose of the visit was to increase familiarization with the site and to discuss information needed by EPA to pursue emergency removal of the cobalt-60 source inventory at the site. The NRC and Commonwealth of Pennsylvania representatives agreed to provide needed information to EPA and to continue biweekly coordination calls.

Region II

Carolina Power and Light Company - Harris Nuclear Plant

On March 10, 2003, representatives from Carolina Power and Light Company attended a management meeting in the Regional Office. The purpose of the meeting was to discuss plans and schedules for addressing NRC and licensee identified fire protection program issues at the Shearon Harris Nuclear Plant.

NRC Information Technology Security Program

On March 10, 2003, the NRC's Senior Information Technology Security Officer met with the Chief, Information Resource Branch, and other Region II managers to discuss Regional Office implementation of the NRC Information Technology Security Program. The discussion included efforts to develop uniform security procedures.

Risk Communications Training

On March 11-12, 2003, Risk Communications training was held in the Regional Office and presented by Dr. Vincent Covello. This training was conducted for team leaders, supervisors, and managers as a part of implementing the Regional Offices internal and external Communication Plan.

Senior Resident Inspector Counterpart

On March 13-14, 2003, the Regional Office held a Special Senior Resident Inspector Counterpart meeting. The purpose was to discuss lessons learned from inspections in the Reactor Oversight Program. On March 14, 2003, the Davis-Besse Lessons Learned Issues and Actions were discussed by the Chief, Reactor Projects Branch 1, Division of Reactor Projects.

Region III

NRC Davis-Besse Oversight Panel Public Meetings

On March 11, 2003, the NRC Davis-Besse Oversight Panel held two meetings at the Camp Perry Ohio National Guard facility in Oak Harbor, Ohio. The first meeting was between the panel and FirstEnergy Nuclear Operating Co. officials to discuss the status of activities at the Davis-Besse plant, including completion of refueling the reactor. The second meeting was an evening public session to review NRC activities involving Davis-Besse and to respond to questions and concerns from the public.

Enclosure R

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