Search Options
Index | Site Map | FAQ | Facility Info | Reading Rm | New | Help | Glossary | Contact Us

SECY 98-031

February 27, 1998

Contact: S. Shaeffer, OEDO

ENCLOSURE A

Office of Nuclear Reactor Regulation
Items of Interest
Week Ending February 20, 1998

Maine Yankee

The staff has scheduled an enforcement conference with the Maine Yankee licensee for Friday, March 27, 1998. The matters to be discussed were presented in a letter dated December 19, 1997, from the Region I Regional Administrator to the licensee. They include the RELAP5YA small-break LOCA analysis, atmospheric steam dump valve capacity, and failure to follow a surveillance test procedure.

Turkey Point, Unit 3

On February 16, 1998, Unit 3 was manually tripped from full power when the operators noticed a total loss of load on the main generator. Following the manual trip, a "fish mouth" steam leak occurred in the 2-inch drain line off the train 2 steam supply to the turbine driven auxiliary feedwater (AFW) pumps. Control room operators could not initially determine the source of the steam leak and, following procedures, declared an unusual event. All other systems responded as expected. The leak was isolated and the licensee terminated the unusual event approximately 90 minutes after the event.

Inspection revealed that the 2-inch schedule 80 carbon steel piping exhibited externally initiated corrosion in the area of piping support straps. The piping system is open to the effects of weather and is insulated. This portion of the system is normally isolated until initiation of AFW, which is tested monthly. The system was last pressurized for testing on January 23, 1998.

The licensee is removing insulation and inspecting piping susceptible to this condition on both units and both trains. The operating unit was in a 72-hour TS action statement; however, the system was operable before a shutdown was required. The loss of load was caused by a total loss of control oil which caused the control and intercept valves to close. The licensee is still investigating the cause of the loss of control oil and Unit 3 is expected to remain off line for several days.

Salem, Units 1 and 2

Operational Status - The licensee shut down Salem Unit 2 on February 11, 1998, after the turbocharger on the 2A emergency diesel generator failed. This was the most recently refurbished turbocharger that was performed by a vendor (Canadian Allied Diesel) not involved with the other turbochargers. The cause of the failure was due to driver side blade cracking that is believed at this time to be from fatigue induced by a flow anomaly. However, a metallurgical analysis is being performed on the failed blades. The licensee has inspected the engine and found no slide valve or other problems that could have accounted for the turbocharger failure. The replacement turbocharger received nondestructive examination, and the others will also be inspected.

On February 18, 1998, the licensee began heating up Salem Unit 1 to enter Mode 4 (hot shutdown). There are several hold points during the heatup to establish steam generator chemistry and perform dimensional inspections on the new steam generators. The 2-week NRC Readiness Assessment Team Inspection (RATI) began on February 9, 1998. The RATI exit meeting is scheduled for February 27, 1998. The licensee is also tentatively scheduled to brief the Regional Administrator on its readiness for restart on that same day. There are no technical and 2 programmatic items (MOVs and Integrated Test Program) that need to be closed before the unit can restart.

Salem Assessment Panel - The Salem Assessment Panel will meet on February 26, 1998, to discuss Unit 1 readiness for restart.

Licensing Actions - Currently, there are no licensing amendments that are needed before the scheduled restart of Unit 1.

D.C. Cook, Units 1 and 2

The licensee has completed work on the cracked covers on the solid state protection system relays and the balancing of the hydrogen distribution system (CEQ) fans.

However, the licensee continues to identify issues involving their ice condenser. The licensee has determined that the ice condenser weights used to determine compliance with technical specifications may not constitute a representative sample. Although an estimate of the total ice mass indicates that the total ice mass requirement was met, additional data is needed to determine if the current sample methodology is representative. The licensee also determined through testing that damaged ice baskets may not be able to withstand operational basis earthquake and dead weight loads. Baskets which should have withstood a compressive load of 4,933 lbs, failed at approximately 2,000 lbs. Additionally, an inspection of the bottom coupling rings for the ice baskets identified two where the total number of missing fasteners exceeded the allowed limit. Inspections of additional rings will continue. The licensee is currently assessing the impact of these issues.

In addition, a review of past surveillance data on the hydrogen recombiners indicated that the measured resistance to ground following the completion of the functional test was less than required. The licensee believes that the recombiner would have performed its safety function even with the lower resistance value. The licensee's investigation is continuing.

No official request for having the next meeting with the NRC to discuss the CAL has been made to date.

Zion, Units 1 and 2

On February 13, 1998, Commonwealth Edison provided written certification that operations had been permanently ceased at Zion Units 1 and 2 effective February 13, 1998. This certification was provided in accordance with the requirements of 10 CFR 50.82(a)(1)(I) and 10 CFR 50.4(b)(8).

The station is preparing to begin defueling Unit 2 by February 23, 1998. Unit 1 is defueled.

ENCLOSURE B

Office of Nuclear Material Safety and Safeguards
Items of Interest
Week Ending February 20, 1998

U.S.-Japan Safeguards Bilaterals

During the week of February 9, 1998, a staff member from the Division of Fuel Cycle Safety and Safeguards participated on an interagency team that met with representatives from the Japanese government and industry to discuss the implementation of nuclear material safeguards in Japan and the U.S. The meetings were held in Tokai and Tokyo, Japan. The principal focus of the bilateral meetings was the implementation of the International Atomic Energy Agency's Strengthened Safeguards System. The Japanese described proposed changes to the structure of the Power Reactor and Nuclear Fuels Development Corporation and within the Japanese government. These changes are being made in response to the accidents at the Tokai Bituminization Plant and the Monju Reactor.

International Atomic Energy Agency Coordinated Technical Support Program Meeting

On February 9-11, 1998, a staff member from the Division of Fuel Cycle Safety and Safeguards participated in the Third Annual Review Meeting of the Coordinated Technical Support Program to the Newly Independent States (NIS) at the International Atomic Energy Agency Headquarters in Vienna, Austria. The purpose of the meeting was to review the status of the support of donor nations to the NIS in the areas of material protection, control, and accounting and export control. The review meeting enables donor nations to coordinate their support efforts to the recipient states to optimize the use of resources.

German Observation of the Nuclear Regulatory Commission Evaluation

On February 9-12, 1998, a staff member from the Division of Fuel Cycle Safety and Safeguards accompanied a delegation from Germany to observe a Nuclear Regulatory Commission Operational Safeguards Response Evaluation at the Wolf Creek Nuclear Power Plant. The purpose of the visit was to observe how specialized NRC performance-based evaluations augment NRC safeguards regulatory programs. Germany will soon be conducting a comprehensive review and assessment of the physical protection systems at nuclear power plants and requested to observe NRC power reactor vulnerability analysis methods.

Meeting with the Department of Energy to Discuss Task Order Related to Drafting Legislative Language to Support the Nuclear Regulatory Commission Licensing of a Mixed Oxide Fuel Fabrication Facility

On February 13, 1998, staff from the Office of Nuclear Material Safety and Safeguards, Office of the General Counsel, and the External Regulation Department of Energy (DOE) Task Force participated in a meeting with DOE's Office of Fissile Materials Disposition. The meeting was requested by DOE to discuss the draft task order 97-2 initially submitted to the Nuclear Regulatory Commission in December 1997. Under the Reimbursable Agreement, this task order requests NRC's collaboration in drafting legislation to allow NRC to license a mixed oxide fuel fabrication facility owned by DOE and operated by a contractor.

Meetings with the Department of Energy Regulatory Unit

During the week of February 9, 1998, in a meeting at Hanford, Washington, the Division of Fuel Cycle Safety and Safeguards staff provided comments to the Department of Energy's (DOE) Regulatory Unit (RU) on the British Nuclear Fuels Limited (BNFL), Inc., Initial Safety Analysis Report for the Hanford Tank Waste Remediation System (TWRS). Out of the approximately 150 comments submitted to DOE by the Nuclear Regulatory Commission staff, roughly 30% were already incorporated into existing RU questions to be submitted to BNFL. The RU agreed to submit another 40% to BNFL, Inc., as new questions, and the rest were considered as open issues pending clarification on further review of BNFL's technical report addendums.

While at Hanford, NRC staff also attended a Hanford Advisory Board (HAB) meeting at which BNFL and Lockheed Martin Advanced Environmental Systems, Inc., presented an overview of the TWRS Phase 1a status and their overall approach to Phase 1b. The HAB was concerned about the lack of attention by Congress to the TWRS program and budget, and has sent a letter to Congress urging priority consideration.

Visit to Sohio L-Bar Uranium Recovery Site

On February 11, 1998, staff from the Division of Waste Management and its Colorado State University Contractor visited the Sohio L-Bar, New Mexico, site to discuss the licensee's approach to dealing with site degradation due to sedimentation of erosion protection channels. The L-Bar site is one of the eight old uranium mill tailings sites where previously-approved reclamation plans may not meet current staff guidance for erosion protection. For these sites, the Commission determined that the licensees should not be required to redesign to meet current criteria unless the staff identified a situation where significant degradation had occurred. The staff observed trenching and trench logging activities conducted by the licensee to ascertain the amount of sediment deposited in drainage channels at the site since construction in 1989. The licensee proposes to provide the Nuclear Regulatory Commission with a report of the results of its findings, including a plan of action to correct and prevent future degradation of the reclaimed tailings, in early March.

Meeting with the Department of Energy Uranium Mill Tailings Remedial Action Project Office

On February 10, 1998, staff from the Division of Waste Management met with representatives of the Department of Energy (DOE), Uranium Mill Tailings Remedial Action (UMTRA) Project Office, in Albuquerque, New Mexico, to discuss schedules for completion of surface reclamation and long-term licensing of Uranium Mill Tailings Radiation Control Act (UMTRCA) Title I sites. Under UMTRCA, DOE is to have completed all surface reclamation by September 30, 1998, with the exception of the Grand Junction, Colorado, site, which will remain open to accept contaminated material from vicinity properties until the cell is filled or 2023, whichever comes first. DOE laid out tentative dates for all submittals necessary to complete the surface cleanup activities under UMTRCA. Of the 22 sites under UMTRCA, only five remain to be licensed by the Nuclear Regulatory Commission, and, of those five, only two sites are still under construction. DOE proposes to have all construction completed at these two sites by September 1998, but for one of those sites, it will not be able to submit the necessary documentation of construction completion, long-term care plans, or land annotation until late October 1998.

Approval of Reclamation Plan for American Nuclear Corporation's Gas Hills Site

On February 13, 1998, staff from the Division of Waste Management issued a letter approving the Final Reclamation Plan for Tailings Pond No. 2 at the American Nuclear Corporation (ANC) uranium mill and tailings site, Gas Hills, Wyoming. The plan was submitted by the Wyoming Department of Environmental Quality (WDEQ), which is reclaiming the site under a Confirmatory Order issued by the Nuclear Regulatory Commission. ANC, the site owner and licensee, discontinued operation and went out of business in May 1994; the reclamation bond was forfeited to WDEQ, which accepted responsibility for site reclamation.

The ANC site reclamation plan was approved by NRC in 1984, and was one of the eight plans determined to be acceptable under Commission Paper SECY-95-155 on June 29, 1995.

WDEQ and its contractors worked with NRC staff to improve the ANC plan, and it is this improved plan which was approved February 13, 1998. The plan also included a preliminary reclamation plan for Pond No. 1; a final plan for Pond No. 1 will be submitted by WDEQ for NRC review and approval prior to reclamation of Pond No. 1.

Advisory Committee on Medical Uses of Isotopes - Subcommittee Meeting with Part 35 Working Group Members

On February 9-10 and February 12-13, 1998, the Part 35 Working Group met with two Advisory Committee on Medical Uses of Isotopes (ACMUI) subcommittees. The purpose of the meetings was to discuss proposed revisions to the 1979 Medical Policy Statement; the Part 35 draft rule text that was placed on the INTERNET on January 30, 1998; and associated draft guidance for the rule. These meetings were held in preparation for the March 1-2, 1998, meeting of the full ACMUI. The meeting on February 9-10, 1998, focused on diagnostic and

therapeutic uses of unsealed radionuclides. The meeting on February 12-13, 1998, focused on therapeutic uses of sealed radionuclides. Major areas of discussion included training and experience for authorized users and requirements for written directives, patient notification following medical events, and reporting of medical events and significant precursors to the Nuclear Regulatory Commission. In addition, committee members discussed technical requirements for teletherapy, remote afterloaders, and gamma stereotactic radiosurgery units.

Integrated Materials Performance Evaluation Program Review of Region II's Nuclear Materials Program

On February 9-13, 1998, a multidisciplinary review team led by the Office of Nuclear Material Safety and Safeguards (NMSS), and composed of technical staff from NMSS, Region III, the Office of State Programs, and the State of California conducted an Integrated Materials Performance Evaluation Program (IMPEP) review of Region II's nuclear materials program. The review assessed the five common performance indicators for materials programs (quality of licensing, quality of inspections, technical staffing and training, status of the inspection program, and response to incidents and allegations). The review also focused on two non-common performance indicators: the fuel cycle program, and performance with respect to the Operating Plan goals and resource utilization. The team held exit meetings with the Regional Administrator and the Region II Division of Nuclear Material Safety (DNMS) managers on February 13, 1998, to report preliminary results. The review team made a small number of recommendations to Region II and commented that the team will recommend a finding of adequacy for the DNMS program, based on the review team's recommendations of "Satisfactory" for each of the indicators (the highest IMPEP finding). The review team is currently preparing a draft report, to be followed by Regional review of the draft report in March and a Management Review Board (MRB) meeting in late April or early May. Final determination of DNMS' program adequacy is made by the MRB.

Meeting with Amersham Corporation Regarding Transportation Packages

On February 19, 1998, the Spent Fuel Project Office met with Amersham Corporation regarding possible design changes and retesting of the Model No. 660 radiography device with respect to the transportation requirements in 10 CFR Part 71. Amersham discussed possible design modifications of the Model No. 660 and their plans for re-testing the package to demonstrate that the modified design meets Part 71.

Amersham plans to submit a revised test plan for Nuclear Regulatory Commission review and approval and proposes to retest the package shortly thereafter.

ENCLOSURE C

Office of Nuclear Regulatory Research
Items of Interest
Week Ending February 20, 1998

Fuel Behavior

During normal operation, fuel rod cladding oxidizes on the water side, and the rate of oxidation accelerates at high burnups leading to heavy accumulations of oxide in some cases. Because one of the licensing criteria on fuel damage during a postulated loss-of-coolant accident (LOCA) is a limit on cladding oxidation (17% limit specified in 10 CFR 50.46), questions have been raised about the adequacy of regulatory criteria and safety analyses for high-burnup fuel. In 1997, RES initiated a program at the Argonne National Laboratory to directly measure the effects of high burnup on the LOCA criteria and to measure the fundamental mechanical properties of cladding from commercial high-burnup fuel rods. From its inception, cooperation in this research program was sought from the U.S. industry and from the international community. While information is being shared with all parties, the Electric Power Research Institute offered a more substantial partnership. Thus, on February 12, 1998, EPRI and NRC signed an Addendum on Testing of High Burnup Fuel, which became the first specific application of the general Memorandum of Understanding on Cooperative Nuclear Safety Research that became effective October 1, 1997. The signing on February 12 by Malcolm Knapp of RES and Robin Jones of EPRI took place at EPRI offices in Palo Alto. Under this agreement, EPRI will provide all the fuel rods for testing. These fuel rods will be obtained from commercial power plants in the United States, precharacterized, cut into manageable lengths, shipped to Argonne National Laboratory, and given to the NRC program for testing, thus reducing NRC's costs significantly. EPRI is also providing important technical input that will enhance the quality of the effort. Interpretation and analysis of the data from this program will be performed separately and independently by NRC and EPRI to avoid conflicts of interest. The results will form a data base for confirming or revising criteria and models for LOCA analysis and for performing other detailed fuel rod analyses.

Publication of Draft Regulatory Guide DG-1029, "Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related I&C Systems"

Electromagnetic and radio frequency interference (EMI/RFI) and power surges are potentially risk significant environmental stressors for safety-related instrumentation and controls (I&C). The need to develop specific practices to address EMI/RFI and power surge issues in safety-related I&C systems is stated in SECY-91-273, "Review of Vendors' Test Programs to Support the Design Certification of Passive Light Water Reactors." The guidance in DG-1029 contributes to the goal of ensuring electromagnetic compatibility (EMC) in nuclear power plants for safety-related digital or analog I&C equipment. The draft guide also describes design, installation, and testing practices acceptable for addressing the effects of EMI/RFI and power surges on both analog and digital I&C systems that perform safety-related functions. The EMC guidelines are based on well-established, consensus military and commercial approaches. The technical basis behind selecting these particular practices is given in NUREG/CR-6431 (December 1997). This NUREG/CR presents recommended EMI/RFI operating envelopes that characterize the electromagnetic conditions at key locations in nuclear power plants, such as control rooms, cable spreading rooms, and turbing bays and has also been submitted for public comment.

The guidelines are intended to reduce the uncertainty of the effects from EMI/RFI and power surges on the performance of safety-related I&C equipment. This draft regulatory guide was issued on February 10, 1998, for a 60-day public comment period.

Ground-Water Monitoring Technology Transfer Workshop

An important regulatory issue for the site decommissioning management plan and for low-level waste and high-level waste and buried radioactive waste tank sites is the estimation of infiltration and ground-water recharge rates and distributions that affect radionuclide release and subsequent migration. A "hands-on" technology transfer workshop was held February 11-12, 1998, at the University of Arizona's (UAZ) Maricopa Agricultural Center (MAC) to provide NRC staff and invitees with field demonstrations and discussions on their research findings. The RES-funded research involves evaluating and testing ground-water monitoring strategies focusing on specific state-of-the-art field systems, methods, and instrumentation. Findings from the MAC field experiments that simulated infiltration events to test the monitoring systems and instrumentation were presented and discussed. The analysis of the field data will help to provide technical bases for reviewing site ground-water monitoring programs.

The 46 workshop attendees included NRC licensing and research staff, Agreement State (i.e., Utah, Washington, Arizona, Texas, California, and New York) developers, regulators and representatives, U.S. Geological Survey scientists, DOE national laboratory (Lawrence Berkeley NL, Pacific Northwest NL, Idaho National Engineering Laboratory) and Nevada Test Site contractor scientists, university scientists, and private sector consultants. The workshop was structured to maximize time in the field for demonstrating the field methods and instruments, to observe the meteorological, irrigation, and data storage systems, and to question the UAZ investigators on lessons learned. The workshop concluded with discussions on monitoring program objectives, relationship to facility performance confirmation, and reliability and durability aspects of the systems and instruments tested. It is expected that a NUREG/CR report outlining the field study research results, including lessons learned, will be issued in October 1998.

ENCLOSURE F

Office of Administration
Items of Interest
Week Ending February 20, 1998

USEC

A three member NRC inspection team (ADM, OCIO, and Region III) are scheduled to conduct a follow-up security inspection of the Paducah Gaseous Diffusion Plant during the week of February 23, 1998. The purpose of the inspection is to ensure that the findings noted during the last security inspection (May 5-9, 1997) which resulted in escalated enforcement have been adequately addressed and closed out.

Report on Cost Estimates for Security Classification Activities

The Information Security Oversight Office (ISOO) is required to report annually to the President and the Congress cost estimates for security classification activities. This requirement stems from Executive Order (E.O.) 12958, "Classified National Security Information," E.O. 12829, "National Industrial Security Program," and from Congress through a House Appropriations Committee Report. ADM, in coordination with OCFO, prepared and submitted the NRC portion of this report by providing FY 1997 costs, along with estimated costs for FY 1998 and FY 1999. ADM, also with OCFO support, provided statistical support to the Secretary of Defense, Executive Agent for the National Industrial Security Program, in developing the cost estimates for U.S. industry.

Documents Submitted for Publication

The following document has been forwarded to the Office of the Secretary for signature and transmittal to the Office of the Federal Register for publication:

• A Federal Register notice that will withdraw the Commission's direct final rule concerning criticality accident requirements and revoke the codified regulatory text contained in the direct final rule

Receipt of Petition for Rulemaking (PRM-71-12) from International Energy Consultants, Inc.

A notice of receipt of a petition for rulemaking submitted by International Energy Consultants, Inc. was published in the Federal Register on February 19, 1998 (63 FR 8362). The petitioner requests that the Commission amend its regulations governing the packaging and transportation of radioactive material to eliminate special requirements for plutonium shipments. The comment period for this action closes May 5, 1998.

ENCLOSURE G

Chief Information Officer
Items of Interest
Week Ending February 20, 1998

Freedom of Information and Privacy Act Requests Received during the 4-Day Period of February 13, 1998 - February 19, 1998:

ENCLOSURE I

Office of Human Resources
Items of Interest
Week Ending February 20, 1998

Human Resources Development (HRD) Staff Members Attend HRD Council Meeting

On February 18, 1998, Eileen Mason and Lillian vanSanten attended the Human Resources Development Council meeting at the Department of Health and Human Services. The Council, a group of training directors and staff from departments and agencies throughout the Federal government, provides leadership to the Federal government in human resources development issues and in building high performing organizations. Topics discussed were a demonstration of a CD Rom and Handbook on resolving poor performance issues, a bench marking forum sponsored by the American Society for Training and Development, forthcoming conferences sponsored by the American Society for Training and Development and by the Office of Personnel Management, and projects dealing with HRD professionalism and building high performing organizations.

ENCLOSURE M

Office of Public Affairs
Items of Interest
Week Ending February 20, 1998

Media Interest

Chairman Jackson was interviewed by The New York Times and The Day (New London, CT).

WNBC-TV is planning a story on radioactive materials users in the northeast.

Region III has been preparing for a meeting with Advanced Medical Systems next week.

School Volunteers Program

Students from Ridgeview M.S. visited NRC as winners of a computer ethics essay contest, organized by Louis Numkin, CIO. The students toured the technology center, the operations center, and the library and training centers, and were awarded certificates by Tony Galante. Also participating were: Lew Clayman, Ilyne Miller, Chris Hoxie, Judy Seeherman, Debbie Fling and Ron Deavers, OCIO, August Spector, OHR, John Jolicouer, AEOD, and Mindy Landau, OPA.

Jim Kennedy, NMSS, spoke at an environmental seminar at American University.

ENCLOSURE O

Office of the Secretary
Items of Interest
Week Ending February 20, 1998

Commission Correspondence Released to the Public

1. Letter to Representatives Stephen Horn and Carolyn Maloney, dated February 12, 1998, provides the NRC's February 1998 quarterly report on the Year 2000
   
   
2. Letter to Senator Kay Bailey Hutchinson, dated February 12, 1998, concerns the NRC's final decision on its independent radiation monitoring program

Federal Register Notices Issued:

1. 10 CFR Parts 50 and 70; Criticality Accident Requirements; Withdrawal of Direct Final Rule and Revocation of Regulatory Text

ENCLOSURE P

Region I
Items of Interest
Week Ending February 20, 1998

Removal of a Cobalt-60 Teletherapy Unit at Englewood Hospital and Medical Center, Englewood, New Jersey

On February 13, 1998, an NRC inspection was conducted at Englewood Hospital and Medical Center, Englewood, New Jersey, to review the activities related to the dismantling and removal of their Cobalt-60 teletherapy treatment unit. The removal of the Cobalt-60 machine was performed by X-Ray Equipment Company, Mansfield, Texas. The teletherapy machine head, containing the sealed source (approximately 2328 curies of Cobalt-60) was packed in the shipping cask USA 5796 B(U) and loaded into a truck owned by X-Ray Equipment Company. The X-Ray Equipment Company took the rest of the machine, including all depleted uranium shielding contained within the Picker C-9 unit. A survey of the teletherapy room, performed after the source removal, confirmed that there was no radioactivity remaining in the room. The teletherapy license will be terminated upon receipt of a written request from Englewood Hospital. On February 16, 1998, X-Ray Equipment Co. notified Region I, of the receipt of the source and the depleted uranium at its facility in Mansfield, Texas.

ENCLOSURE P

Region II
Items of Interest
Week Ending February 20, 1998

Federal Emergency Management Agency

On February 17, 1998 the Regional Director, FEMA Region IV, visited the Regional Office and met with the Regional Administrator, and other select staff members, to discuss programmatic areas of mutual interest. FEMA IV includes all of the States within the Regional boundary, except for the Commonwealth of Virginia and the State of West Virginia.

Ground Engineering and Testing Service, Inc.

Representatives from Ground Engineering and Testing Service, Inc., were in the Regional Office on February 18 for an open Predecisional Enforcement Conference. Ground Engineering has a State of Kentucky license for use of portable moisture/density gauges containing licensed materials. Ground Engineering representatives discussed the causes and corrective actions taken for the apparent violation, which was for failure to obtain a general or specific license before using licensed material in NRC jurisdiction.

Southern Nuclear Operating Company, Inc.

Representatives from Southern Nuclear Operating Company, Inc. were in the Regional Office on February 18 to discuss plans for onsite dry cask storage at the Hatch facility. The licensee selected Holtec as the cask designer and will use either the Hi-Storm 100 or Hi-Star 100 system under a general license. These systems are dual-purpose storage canister/transportation containers. Pad pouring is scheduled from October through December 1998. Completion of the pad is scheduled for July 1999. The licensee anticipated loading its first cask in April 2000.

Carolina Power and Light Company - Robinson

On February 19, 1998, representatives from Carolina Power and Light Company were in the Regional Office for an open Predecisional Enforcement Conference. The licensee discussed a number of calculation deficiencies identified during the NRC Design Inspection and the potential inoperability of Safety Injection Pumps B and C due to insufficient net positive suction head resulting from a modification implemented in March 1988.

Tennessee Valley Authority - Sequoyah

On February 20, 1998, representatives from Tennessee Valley Authority met with Regional managers to discuss Operational Performance of the Sequoyah units. Items discussed included strengths and challenges in all functional areas. TVA described actions they have taken to improve plant material condition.

Taiwan Atomic Energy Council Visitors

Two Resident Inspectors from the Taiwan Atomic Energy Council visited Region II on February 19, 1998. The Region presented an overview of the Resident Inspector program and other technical inspection topics of interest. They also observed a predecisional enforcement conference. The visitors are currently attending the GE BWR/4 Advanced Technology Course series in the NRC Technical Training Center in Chattanooga, Tennessee.

ENCLOSURE P

Region III
Items of Interest
Week Ending February 20, 1998

Predecisional Enforcement Conference with U.S. Enrichment Corporation

On February 19, 1998, a Predecisional Enforcement Conference was conducted between management representatives of U.S. Enrichment Corporation and members of the NRC staff. The conference was conducted to discuss the corporation's apparent weak implementation of the nuclear criticality safety program at the Portsmouth Gaseous Diffusion Plant, located in Piketon, Ohio. This program establishes controls to ensure that, during operations, uranium remains subcritical. During an inspection in December and January, NRC inspectors found program inadequacies that included training, root cause evaluations and corrective actions. In addition, inspectors noted an apparent failure by plant staff to implement all the required controls for a non-operating cell that contained a deposit of enriched uranium greater than the minimum safe amount. NRC Regional A. Bill Beach participated in this conference.

ENCLOSURE P

Region IV
Items of Interest
Week Ending February 20, 1998

Management Meeting with Entergy Operations, Inc.

A predecisional enforcement conference was held with representatives of Arkansas Nuclear One, Units 1 and 2 on February 20, 1998, in the Region IV, Arlington, Texas, office. The purpose of the meeting, which was open to public observation, was to discuss three apparent violations concerning activities associated with the removal of the Unit 1 borated water storage tank vacuum relief valve which may have potentially rendered some emergency core cooling systems inoperable under design basis accident conditions.

ENCLOSURE R

Office of Congressional Affairs
Items of Interest
Week Ending February 20, 1998