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SECY 98-200

August 20, 1998

Contact:
M. Tschiltz, OEDO
415-1733

ENCLOSURE A

Office of Nuclear Reactor Regulation
Items of Interest
Week Ending August 14, 1998

Indian Point 2

On August 4, 1998, the staff approved Con Edison's relief request via 10 CFR 50.55a to perform a non-code repair on a non-isolatable portion on a mini flow test line in the RHR system. The repair was installed and the unit was heated up to 325 degrees. In addition, on August 7, 1998, members from NRC Headquarters and Region I held a public meeting with Con Edison to discuss the status of Con Ed's restart activities and their schedule for restart. The NRC Evaluation Team (NET) follow-up team was also on site from August 3 - 7, 1998, to close out open restart items and to oversee restart effort in the operations and corrective actions areas. The NET exit meeting was also held on August 7, 1998. Con Ed is establishing three teams to address concerns raised by the NET. The teams will focus on improvement in the operations area. The improvements include: (1) ensuring event free operations during startup, (2) reviewing the Shift Watch Supervisor's (SWS) administrative activities versus watch activities, and (3) moving the SWS's work station into the control room.

Catawba Nuclear Station

The TSs require the performance, every 10 years, of a pressure test of those portions of the fuel oil system associated with the emergency diesel generators (EDGs), designed to Section III, Subsection ND of the ASME Code. Contrary to that, the licensee found that testing of the fuel oil system had not been performed as required by TS. Instead, the surveillance prescribed by ASME Code Case N-498-1, which was previously authorized for use at Catawba by the NRC, was performed. Code Case N-498-1 permits the use of VT-2 visual examination, in conjunction with a system pressure test on Class 3 systems in lieu of hydrostatic testing. Thus, the wording of the TS 4.8.1.1.2.i.2 conflicts with that of TS 4.0.5, which requires that "Inservice Inspection of ASME Code Class 1, 2, and 3 components...shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(I)." On August 5, 1998, the licensee determined that the two Catawba Unit 1 EDGs were inoperable on the basis of noncompliance with TSs.

Upon the licensee's request, and after its own evaluation, the staff granted a Notice of Enforcement Discretion from the requirements of TS 4.8.1.1.2.i.2, to expire when the subject TS is amended on an exigent basis.

Oconee Nuclear Station Unit 1

On August 8, 1998, Unit 1 was shut down due to indications of an oil leak on Reactor Coolant Pump (RCP) 1B1 and a seal leak on RCP 1A2. There are indications that RCP 1B1 may also have a seal leak. Since the unit is expected to be in the cold shutdown condition for longer than

one week, the steam generator anomalies (crack indications in some steam generator tube extensions above the upper tube sheet) will be rolled to comply with an earlier commitment resulting from a Notice of Enforcement Discretion and amendment that were issued when the problem was first discovered on Unit 2 during the last refueling outage.

Browns Ferry

On August 10, 1998, the staff met with representatives of TVA to discuss the approach for resolution of outstanding issues relating to the Browns Ferry site Generic Letter 88-20 activities. On September 28, 1994, the staff issued its evaluation of the Browns Ferry IPE for single-unit operation of Unit 2 only. The staff concluded that TVA's IPE submittal was complete with the level of detail consistent with the information requested in NUREG-1334. However, the staff stated that closure of IPE activities for Browns Ferry was dependent upon the submittal of an acceptable PRA that considered multi unit operation. TVA submitted the Multi-Unit PRA (MUPRA) in April 1995, and addressed several containment performance issues as requested. This submittal closed out all open IPE issues for Unit 2.

In June 1997, the staff requested additional information as a result of its review of the MUPRA for applicability to Unit 3. TVA, however, declined to respond asserting that further staff review of the Browns Ferry site was unwarranted and that an adequate basis exists for closing out the IPE program at the site without the expenditure of more TVA and NRC resources. On May 20, 1998, the staff issued a brief summary evaluation of the GL 88-20 effort at Browns Ferry. This evaluation concluded that the staff is unable to conclude that the intent of GL 88-20 has been met at the Browns Ferry site, and cited five areas where information is incomplete.

In the August 10 meeting, TVA agreed to provide information regarding human reliability analysis modeling, residual heat removal system modeling, applicability of the Unit 2 containment model to Unit 3, verification of design and operating similarities between Unit 2 and 3, and verification that the containment performance improvements have been implemented. The staff agreed that this information should be sufficient to allow the staff to complete the GL 88-20 reviews for the Browns Ferry site, and that a Unit 3 IPE is not required.

Control Room Emergency Ventilation

On August 11, 1998, the staff informed TVA that its corrective actions for addressing certain control room emergency ventilation deficiencies are acceptable. As part of this review, TVA is committed to perform an analysis of the design basis loss of coolant accident to confirm compliance with General Design Criteria 19 (GDC-19) and offsite dose limits considering main steam isolation valve leakage and emergency core cooling system leakage. The results of this analysis will be submitted to the NRC for review and approval by March 31, 1999. Following NRC approval, any required modifications will be implemented during the refueling outages scheduled for Spring 2000 for Unit 3 and Spring 2001 for Unit 2. TVA will maintain the ability to monitor radiological conditions during emergencies and administer potassium-iodide to control room operators to maintain doses within GDC-19 guidelines. This ability will be maintained until the required modifications, if any, are complete.

This closes a 6 year old issue (under staff review since May 1992).

Comanche Peak Risk-informed Inservice Testing Program

The Safety Evaluation Report (SER) for the Comanche Peak risk-informed inservice testing program has been completed and approved. This program, submitted as part of a pilot plant initiative, will allow the licensee to utilize a risk-informed approach to determine inservice testing (IST) frequencies for certain valves and pumps that are categorized as low safety significance. In preparing the SER, the staff used the guidelines contained in the risk-informed regulatory guides (i.e., RG 1.174 and RG 1.175) and Standard Review Plans (i.e., SRP Chapter 19 and SRP Section 3.9.7). This Amendment was sent to the licensee on August 14, 1998.

Management Changes

On July 28, 1998, PECO Energy Company announced that Dickenson Smith, former President of PECO Energy Company, was named Chief Executive Officer of AmerGen Energy Company.

AmerGen is a joint venture of PECO Energy Company and British Energy Company of Edinburgh, Scotland, formed to purchase and operate nuclear plants in the United States. Proposed purchase of TMI 1 from GPU is the AmerGen's first venture initiative.

Dickenson Smith joined PECO Energy Company in 1987, after retiring from the U.S. Navy with the rank of rear admiral. He had been the Navy's chief of staff for Allied Atlantic Command.

ENCLOSURE B

Office of Nuclear Material Safety and Safeguards
Items of Interest
Week Ending August 14, 1998

Year 2000 Health Care Sector Meeting

On August 11, 1998, representatives from the Division of Industrial and Medical Nuclear Safety met with representatives of the Departments of Health and Human Services (DHHS), Commerce, Labor, Defense, Veterans Administration, and the Center for Disease Control on agencies' Y2K Outreach Plans for the Health Care Sector. DHHS is the lead agency for the Health Care Sector. Each agency discussed their outreach plans and the possible effects of the Y2K problem. The main emphasis of the discussions was on medical devices and billing and payment for health services. DHHS requested that each agency provide health care sector plans for the rest of the calendar year. The group will meet again in early September.

Pennsylvania to Suspend Low-Level Waste Disposal Facility Siting Efforts

On August 7, 1998, the Pennsylvania Department of Environmental Protection (DEP) announced that it was suspending the low-level radioactive waste disposal facility siting efforts of its contractor, Chem-Nuclear Systems, LLC. The state had announced in May its intention to take this action. DEP stated that the original factors that drove the need for such a facility have changed dramatically, and noted in particular that the annual volumes of low-level waste produced in Pennsylvania had dropped from more than 225,000 cubic feet in 1991 to less than 30,000 cubic feet in 1997. DEP also pointed out that Envirocare and Barnwell were providing the needed disposal capacity for the state and compact. The project will be suspended but not terminated, so that it can be expeditiously resumed if conditions warrant.

Nebraska Intends to Deny License for Boyd County Low-Level Waste Facility

On August 6, 1998, Nebraska regulators announced their intention to deny U.S. Ecology's license application for a low-level radioactive waste disposal facility in Boyd County, Nebraska. Nebraska is the host State for the Central Compact, which also includes Arkansas, Kansas, Louisiana, and Oklahoma. State officials identified seven specific issues that were the basis for their findings. In their announcement of the decision, they noted concerns with the proximity of the facility to the water table and the existing discharges of groundwater to the surface within the disposal site. They also stated that the proposed use of both engineered features and long-term active maintenance to compensate for these features of the site was not acceptable. Several other concerns were also identified. All relate to the license applicant's conformance with the Nebraska low-level radioactive waste disposal regulations which are compatible with 10 CFR Part 61.

It should be noted this decision is preliminary, and the public and U.S. Ecology will both have the opportunity to comment before a final decision is made by the state. Public hearings are scheduled for November.

ENCLOSURE C

Office of Nuclear Regulatory Research
Items of Interest
Week Ending August 14, 1998

Draft Regulatory Guides Issued

The following draft regulatory guides were issued recently for public comment.

Final Regulatory Guides Issued

Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis"

Meeting on Cooperative Research on LWR Spent Nuclear Fuel in Dry Storage

On July 31, RES/DET and NMSS/SFPO staff participated in a meeting at the Idaho National Environmental Engineering Laboratory (INEEL), with INEEL, Argonne National Laboratory - West (ANL - W), Electric Power Research Institute (EPRI), and the Department of Energy (DOE), to identify goals for cooperative research and associated tasks that could be funded under a cooperative research program with EPRI and DOE. The significance of this meeting relates to the existence of a unique opportunity at INEEL to evaluate the condition and integrity of the commercial spent nuclear fuel and dry cask storage systems using demonstration casks containing commercial spent fuel that have been housed at INEEL, some of which has been in dry storage for up to 19 years. Both INEEL and ANL - W have laboratory and hot cell facilities that could support the examination of the spent fuel and the casks. This data can be used to benchmark the predictions and models of spent fuel and cask system integrity over long term dry storage, and can be used to provide a technical basis for re-certification of dry storage spent fuel casks. The primary action resulting from the meeting is to use the information obtained in finalizing a response to a user need request from NMSS on dry cask storage issues.

1998 Piping and Pressure Vessel Conference

During July 26 through July 29, 3 staff members of DET (M. Mayfield, N. Chokshi, and J. Costello) attended the ASME/JSME Joint Pressure Vessel and Piping (PVP) Conference held in San Diego, California. There were some 750 attendees from more than 30 countries. About 770 technical paper were presented in 220 sessions. Technical sessions covered a broad spectrum of areas related to pressure vessel and piping (e.g., structures under extreme loading, codes and standards, fatigue, residual stress, aging and plant life management, risk assessment, and seismic engineering).

There were six sessions and a panel discussion on the subject of risk-informed methods, applications, standards, and regulation. Several sessions were devoted to risk-based ISI and IST. It is clear that there is a significant increase in interest and activity in this area. Other sessions of special interest to us included sessions related to ASME piping design criteria, pipe fracture, fatigue and ratcheting, and performance of structures and components under severe accident conditions.

Some papers were of special interest as ASME's Special Working Group - Seismic Rule (SWG-SR) continues to work on issues raised by NRC and others on the latest ASME piping seismic design rules. A study presented by an Italian researcher corroborated NRC's conclusion that new ASME seismic design criteria did not have sufficient margin in off-resonance regions.

In addition to attending meetings and chairing sessions, NRC participants also conducted meetings on several international cooperative programs as many of our collaborators were also attending the conference. This conference is very much focused on current issues of our interest and provides a good forum for exchange of information and ideas related to regulatory activities and supporting research.

ENCLOSURE F

Office of Administration
Items of Interest
Week Ending August 14, 1998

Contract Award

As a result of a competitive solicitation (RS-NMS-98-006) for multiple awards, five contract awards were made on August 12, 1998, for technical assistance in the "Update of Fuel Cycle Safety and Safeguards Regulatory Guidance Documents." These contracts awards were made to Science and Engineering Associates, Inc. ($643,567 for Physical Protection task area); 21st Century Industries, Inc. ($943,613 for Material Control and Accounting task area); Advanced Technologies and Laboratories International, Inc. (two awards - $548,035 for Criticality and Radiation Safety task area & $304,064 for Fire, Explosives and Chemical Safety task area); and Enercorp Federal Services Corp. ($558,919 for License Applications and Licensee Reporting task area.) The contracts are task ordering type contracts and have a five year period of performance. The following streamlining methods were utilized: (1) CBD synopsis waiver for technical assistance; (2) reduced SEP membership size; (3) award without discussions; and (4) simplified evaluation criteria.

Policy on Conduct of Adjudicatory Proceedings; Policy Statement

A document presenting the Commission's updated policy concerning the conduct of adjudicatory proceedings was published in the Federal Register on August 5, 1998 (63 FR 41872). The Commission reassessed its policy in view of the potential for a number of proceedings in the next few years concerning license renewal, restructuring in the electric utility industry, and waste storage facilities. The policy statement became effective August 5, 1998. The comment closing date on this matter is October 5, 1998.

Public Comment on the Integrated Review of the Assessment Process for Commercial Nuclear Power Plants

A document requesting public comment on integrated review of the assessment process for commercial nuclear power plants was published in the Federal Register on August 7, 1998 (63 FR 42439). The NRC is considering a new method for assessing licensee performance and is developing several new assessment tools that can be used as part of an integrated process. The NRC is soliciting public comment on the development of such an assessment process and the associated assessment tools. The comment closing period on this action is October 6, 1998.

Medical Use of Byproduct Material; Proposed Revision (Parts 20, 32, and 35)

A proposed rule that would revise the regulations governing the medical use of byproduct material was published in the Federal Register on August 13, 1998 (63 FR 43515). The proposed rule is one component of the Commission's overall program for revising its regulatory framework for medical use. The proposed rule is intended to focus NRC's regulations on those medical procedures that pose the highest risk to workers, patients, and the public and to structure the regulations to be risk-informed and performance-based. The comment period on the proposed rule closes November 12, 1998.

Medical Use of Byproduct Material; Draft Policy Statement

A document presenting proposed revisions to the Commission's policy statement on the medical use of byproduct material was published in the Federal Register on August 13, 1998 (63 FR 43580). The proposed revisions to the policy statement is one component of the Commission's overall program for revising its regulatory framework for medical use. The overall goals of this program are to focus NRC regulation of medical use on those medical procedures that pose the highest risk and to structure its regulations to be risk-informed and performance-based. The comment period on the draft policy statement closes November 13, 1998.

Security Guard Services at the White Flint Complex

On July 24, 1998, NRC terminated its contract with the former provider of guard services for the White Flint complex. Interim guard services are being provided by a GSA guard contractor. A new security guard services contract was awarded on August 13, 1998, to Wackenhut Services, Inc., with an effective date of August 14, 1998. DFS staff met with representatives of the new guard company to facilitate the transition beginning at 11:00 p.m. on August 14, 1998.

ENCLOSURE G

Chief Information Officer
Items of Interest
Week Ending August 14, 1998

Freedom of Information and Privacy Act Requests Received during the 5-Day Period of August 7, 1998 - August 13, 1998

IMPAC list. (FOIA/PA-98-308)

IMPAC list, personnel list and tenants for Region IV, on disk. (FOIA-98-309)

Florida Power & Light, Investigation re "blacklisting" claim filed with DOL, docs released in FOIA/PA 98-244. (FOIA/PA-98-310)

St. Mary's Medical Center, allegations (OI 3-97-022). (FOIA/PA-98-311)

Palisades, VSC-24 cask certificate of compliance, design and results of inspection for 1998. (FOIA/PA-98-312)

ORISE 92-K-39, "Confirmatory Radiological Survey Plan for Pathfinder Generating Station, Sioux Falls, South Dakota." (FOIA/PA-98-313)

ENCLOSURE I

Office of Human Resources
Items of Interest
Week Ending August 14, 1998

HRD Staff Member Attends Human Resource Development Council Policy and Legislative Committee Meeting

On August 12, 1998, Lillian van Santen of the Human Resources Development staff (HRD) attended the Human Resources Development Council Policy and Legislative Committee meeting. Items discussed included the Office of Personnel Management's initiatives on possible changes in training laws and guidance; reports on HRD Council, Legislative and Regulatory update; and HR/HRD initiatives throughout the Federal government.

*Deceased
**Expiration of Term Appt.

ENCLOSURE M

Office of Public Affairs
Items of Interest
Week Ending August 14, 1998

Media Interest

Chairman Jackson was interviewed by a reporter from Scholastic Publications.

The State newspaper (Columbia, SC) is printing an article about Barnwell's refusal to accept class C waste.

One reporter attended a public meeting regarding a new irradiator facility being built in Lynchburg, VA.

ENCLOSURE N

Office of International Programs
Items of Interest
Week Ending August 14, 1998

Visit of Dr. Junko Matsubara, Japan

Dr. Junko Matsubara, Commissioner of the Japan Nuclear Safety Commission, will visit the NRC on Thursday, August 20, to meet with the Chairman. She will also meet with the technical staff for overview discussions on the regulation of low- and high-level waste and nuclear power plant regulation.

ENCLOSURE O

Office of the Secretary
Items of Interest
Week Ending August 14, 1998

Commission Correspondence

1. Letter to Congress, dated August 4, 1998, provides the NRC's quarterly report on the nondisclosure of safeguards information

2. Letter to Admiral Frank L. Bowman, USN, dated August 4, 1998, extends congratulations on the 50th anniversary of the Naval Nuclear Propulsion Program

3. Letter to Representative Edward J. Markey, dated August 6, 1998, provides the results of the NRC's review of his concern that certain licensees may have used psychological testing to discourage employees from raising safety concerns

4. Letter to Westley C. Patrick, Center for Nuclear Waste Regulatory Analyses, dated August 6, 1998, concerns the selection by R&D Magazine of 3DSTRESS as one of the year's 100 most technologically significant products

5. Letter to Representative Kenneth E. Bentsen, Jr., dated August 7, 1998, concerns the proposed revisions to 10 CFR Part 35 (incoming of July 13, 1998, also released)

Federal Register Notices Issued

1. Advisory Committee on Reactor Safeguards; Meeting Notice for September 2-4, 1998

ENCLOSURE P

Region I
Items of Interest
Week Ending August 14, 1998

James A. FitzPatrick

W. Axelson, Region I Deputy Regional Administrator; R. Crlenjak, Deputy Director, Division of Reactor Projects; and S. Bajwa, Director, NRR Project Directorate I-1, conducted a site management visit at New York Power Authority's FitzPatrick Plant on August 11 and 12, 1998. The visit included plant tours and interviews with senior licensee management and plant staff.

Beaver Valley

The Beaver Valley Unit 1 reactor was made critical and the main generator was synchronized to the grid on August 11, 1998, following a 192-day outage. Subsequently, the reactor tripped from 24% reactor power, due to a steam generator (SG) steam flow/feedwater flow mismatch coincident with a low SG level reactor protection signal. Shortly prior to the trip, the bistables for one channel of the SG flow mismatch circuit had been placed in trip, in response to a failed steam flow channel. The SG experienced a level transient while feedwater flow control was transferred from the bypass feedwater regulating valve (FRV) to the main FRV. The normal SG level band during reactor startup is 33% to 44% narrow range level. Level reached the coincident 25% low SG level trip setpoint during the transfer, and the reactor tripped as designed. The plant responded to the trip as designed. The steam flow channel has been repaired and the failure was determined to be associated with an isolator between the safety and non-safety related circuits. Plant management concluded that the cause of the low steam generator level and subsequent reactor trip was an operator cognitive error regarding the SG level trip setpoint change due to the failed/tripped steam flow channel. Corrective actions are being taken, and plant restart is expected to occur late on August 13.

Prior to the August 11 startup, NRC inspection activities concluded that the licensee was ready to proceed with the startup based on reviews of the licensee's restart action plan, the restart checklist, operator workarounds, and control room deficiencies. The resident inspectors, supplemented by other regional inspectors had reviewed the restart action plan, observed the mode changes, approach to criticality and various surveillances. No significant adverse conditions or issues were identified. For the August 11 trip, the inspectors are continuing to monitor post-trip reviews and corrective actions, and plan to observe significant restart activities.

Special Projects

Millstone Unit 3 Shut Down to Repair a Small Leak on an Auxiliary Feedwater System Discharge

On August 12, 1998, Northeast Utilities commenced shutdown of Millstone Unit 3 from 100% power to repair a one-pint-per-minute body-to-bonnet leak on a 3-inch motor operated auxiliary feedwater (AFW) system discharge valve. This valve also serves as a containment isolation valve. The water is non-radioactive, resulting from back-leakage from the secondary side of the steam generator, and is being collected in a sump designed for collecting such leakage.

The current leakage does not exceed regulatory requirements, and the shutdown is not required by Technical Specifications. The valve is being repaired as a conservative precautionary measure since the valve performs a safety function and the APW system, though not currently in use, is a backup system for performing safe shutdown of the reactor in case on an emergency.

This outage to repair the valve is expected to last 7-10 days.

Update On RCS Decontamination At Connecticut Yankee's Haddam Neck Plant

On August 10, 1998, staff from Connecticut Yankee Atomic Power Company's (CYAPCo) Haddam Neck Plant initiated the second cycle (of a planned four) of its reactor coolant system (RCS) decontamination. A valve leak during the first decontamination cycle had resulted in a 1000-gallon leak to a sump. Inspections were conducted by NRC staff to confirm the licensee's readiness for commencement of cycle two. The licensee performed the chemical addition steps without any further problems and proceeded with the demineralizer cleanup steps in the process. However, near the end of the cleanup phase, a filter problem developed on one of the demineralizer beds, which caused the "C" demineralizer to be taken out of service. Following a review of the results of the first two cycles of RCS decontamination in removing radioactivity from the RCS piping and lowering radiation dose rates associated with the piping, Connecticut Yankee officials decided that no additional cycles of RCS decontamination were needed. NRC is continuing its review of the licensee's performance in RCS decontamination.

ENCLOSURE P

Region II
Items of Interest
Week Ending August 14, 1998

Virginia Electric and Power Company

On August 10, representatives from Virginia Electric and Power Company met in the Regional Office to discuss recent management changes and current items of interest pertaining to the company. The licensee discussed their strategic initiative action plans and schedules including improved Technical Specifications and license renewal.

Duke Energy Corporation - McGuire

Representatives from Duke Energy Corporation's McGuire Nuclear Station participated in a meeting with Region II management in the Regional Office on August 11. The purpose of the meeting was to discuss the licensee's actions in response to four problems occurring with their emergency diesel generators between the period May 19 through June 4, 1998. The problems included dropped and broken exhaust valve inserts, stuck inlet valve and a broken inlet valve outer spring in the cylinder head area. The licensee discussed the root causes of each problem and the corrective actions, which included improved vendor oversight for replacement work and continued engine diagnostic trend analysis.

Applied Radiant Energy Corporation

On August 12, the Division Director of Nuclear Materials Safety attended a public meeting in Lynchburg to discuss operational readiness of the new Applied Radiant Energy Corporation underwater irradiator. The licensee provided information on the status of construction and plans for finalizing construction and pre-operational testing. The licensee estimated receipt of sources in the latter part of September, 1998.

ENCLOSURE P

Region III
Items of Interest
Week Ending August 14, 1998

Management Meeting with Commonwealth Edison Company - Quad Cities

On August 13, 1998, a management meeting was conducted in the NRC Region III Office, Lisle, Illinois, between management representatives from Commonwealth Edison Company and members of the NRC staff. The meeting discussion focused on the status of the utility's resolution of issues in its fire protection program and other issues raised prior to the startup of Units 1 and 2 in May 1998. NRC Acting Regional Administrator James Caldwell participated in the meeting.

ENCLOSURE P

Region IV
Items of Interest
Week Ending August 14, 1998

Office of Management and Budget Visit

On August 11, 1998, Mr. John Pfeiffer, Office of Management and Budget, met with Region IV managers and staff to discuss regional processes and inspection responsibilities. Included in the discussions were: the Regional Administrator and Deputy Regional Administrator, the Deputy Director of the Division of Reactor Projects, the Director of the Division of Reactor Safety, a Senior Reactor Analyst, and Reactor Projects Branch Chiefs. From August 12-14, Mr. Pfeiffer visited the South Texas Project and San Onofre Nuclear Generating Station. While there, he participated in plant tours and interviews with licensee senior managers and the NRC senior resident inspectors.

Pre-Decisional Enforcement Conference with Nuclear Pharmacy of Idaho, Inc.

On August 11, 1998, the Regional Administrator and members of the Region IV staff conducted a pre-decisional enforcement conference with Nuclear Pharmacy of Idaho, Inc. During the conference, the licensee discussed the apparent violations described in NRC Inspection Report 030-32223/98-01.

Meeting with Portland General Electric (Trojan Nuclear Plant)

On August 12, 1998, the Regional Administrator and members of the Region IV staff met with Portland General Electric (PGE) managers to discuss the schedule of completion of dismantlement work at the Trojan site, the proposed time frame for the final radiological survey of the site, activities related to removal of the reactor vessel from containment and shipment to Hanford, Washington, for burial; the status of work related to dry cask storage of the spent fuel; and the status of the installation and testing of the modular spent fuel pool cooling and clean-up system.