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SECY 97-116

June 4, 1997

Contact:  M. Dapas, OEDO

ENCLOSURE A

Office of Nuclear Reactor Regulation
Items of Interest
Week Ending May 30, 1997

Maine Yankee

On May 27, 1997, the Board of Directors of Maine Yankee Atomic Power Company announced that it was taking immediate actions to reduce cost and place Maine Yankee in a preservation condition pending sale. It also stated that the current owners will not restart the facility. In remarks to the media, Mr. David Flanagan, Chairman of the Board, conceded that sale of Maine Yankee was not likely.

Representatives of PECO Energy are expected on site during the week of June 2, 1997, to begin a due diligence review in support of PECO's expressed interest in purchasing Maine Yankee. Maine Yankee officials expect the review to take 30 to 60 days.

Following the announcement, Maine Yankee released approximately 900 contractor personnel. However, the licensee is continuing work on several high profile projects to keep the restart option open. These projects include steam generator inspections, tube pulls and plugging, procurement of Cycle 16 fuel, and restoration of safety systems currently out of service for outage work. The licensee plans to proceed later this week to complete a full core offload. They have already offloaded 72 of 217 fuel bundles, but their efforts have been hampered by equipment and personnel problems, which the resident inspectors are following.

The licensee completed its steam generator (SG) eddy current (EC) inspections for the current refueling outage. MY is a Combustion Engineering (CE) plant with three model 67 SGs. The licensee plans to insitu pressure test tubes with the most limiting volumetric and axial indications based on sizing (voltage, length and depth) using the plus point probe. The licensee also plans to insitu pressure test the largest plus point indications that were not detected by the bobbin coil (NDD) since the bobbin coil was relied upon to a large extent as a screening tool.

Based on the initial pressure test results, MY expanded its insitu pressure testing plans and selected additional tubes for testing with emphasis on plus point estimated lengths and voltages rather than depths. The licensee is also reassessing its inspection scope to ensure adequate plus point coverage of the SG given the inconclusive pressure test results.

Salem Nuclear Generating Station, Units 1 and 2

Restart Schedule - By letter dated May 5, 1997, the licensee provided a revised schedule for Unit 2 restart. Initial criticality is scheduled for mid-July 1997, and full power, mid-August 1997. The Readiness Assessment Team Inspection is scheduled to begin June 9, 1997.

Memo to the Commission - A memo to the Commission prior to restart of Unit 2 is being prepared and is scheduled to be issued June 12, 1997. The Commission meeting is tentatively scheduled for 2:00 PM on June 25, 1997.

Restart Issues - On May 22, 1997, the staff and the licensee met at the Salem site to discuss each of the 25 actions that are needed to be resolved prior to restart. Similar meetings will be held approximately every other week to discuss the status of these items. The next meeting is scheduled for June 3, 1997.

The following are significant items that have to be resolved prior to restart.

Fire Protection - From April 14 through April 17, 1997, the staff conducted an inspection of Salem fire protection issues. By letter dated May 19, 1997, the licensee submitted a letter proposing a plan to address the inspection findings related to fire barriers. The plan consists of implementing fire watches as compensatory measures until the fire barrier issue is resolved. On May 27, 1997, the staff informed the licensee that the plan described in the licensee's letter did not contain sufficient detail or schedular information. The licensee will be providing additional information related to the plan for resolving the fire barrier issue.

Containment Fan Coil Units (CFCUs) - The modifications which have been implemented to preclude water hammer on loss of offsite power are being tested. The amendment increasing the CFCU initiation time from 45 to 60 seconds will include an evaluation of the modifications. The licensee will be providing additional information regarding the effects of cavitation in the service water piping. The amendment is on schedule to be issued prior to restart.

ECCS Switchover - In responding to a Region TIA, the staff raised two concerns related to the semi-automatic switchover of ECCS water source. These concerns are the inability of the Salem simulator to simulate all the manual steps and the licensee's consideration of human errors of omission and commission. In its LER dated May 19, 1997, and its letter dated May 27, 1997, the licensee provided a response to these concerns. The staff is reviewing these documents.

In addition, the following item is expected to be completed before restart:

Chilled Water System and HVAC System - By letter dated February 11, 1997, supplemented May 1, 1997, the licensee proposed a new Technical Specification section entitled "Chilled Water System". By letter dated May 1, 1997, the licensee proposed a new Technical Specification section entitled "Switchgear and Penetration Area Ventilation System."

NRC/ASME/NB Coordinating Committee Meeting

On May 15, 1997, Dr. Sheron and members of NRR and RES staff participated in the semi-annual meeting between NRC, ASME senior staff, and the National Board in New York City. The principal focus of this committee meeting was policy issues of mutual interest to ASME and NRC. Items of interest included:

• The Committee determined that a management briefing regarding progress and open issues by the Special Working Group (SWG) on Seismic Design should be made to Senior ASME and NRC managers in the near future. (This group was established in response to NRC management concerns (Beckjord/Russell letter of 5/24/95) regarding code criteria established in 1994 and found unacceptable to NRC.) The staff believes limited progress has been made by the SWG in resolving the identified issues.
  
  
• The ASME was advised of NRC concerns regarding interpretations that ASME committees may be making regarding GL 96-06 and the treatment of fluid trapped in isolated piping. The staff has not found the technical approach proposed by various members of industry & ASME (treat certain temperature-induced stresses as "self-relieving") to be acceptable.
  
  
• ASME is interested in approaches to accelerate the code change and rulemaking process. Staff actions relating to DSI-13 and the agency actions under PL104-113 on use of voluntary consensus-based standards were discussed.
  
  
• Other discussion items included steam generator issues, rulemaking and regulatory guides, risk-informed initiatives, procurement of replacement components, and generic communications.

Diablo Canyon, Unit 1

Steam Generator Tube Inspection Results

Pacific Gas & Electric Company (PG&E), the licensee for Diablo Canyon Unit 1 (DC-1), completed its steam generator (SG) eddy current (EC) inspections for the current refueling outage (end-of-cycle 8). DC-1 is a Westinghouse plant with four model 51 SGs.

PG&E performed full length bobbin coil EC inspections of 100% of the tube bundle. The licensee also performed specialized inspections using the plus point probe of the Row 1 and 2 Ubends, tube support plate (TSP) intersections, hot leg top of the tubesheet (TTS), and various bobbin coil indications. The licensee stated the thinning, wear, cracklike and volumetric indications found in the inspected areas did not challenge tube integrity. No insitu pressure testing or tube pulls were performed. PG&E plugged tubes with thinning or wear sized at depths greater than 40% throughwall and tubes with cracklike and volumetric indications.

Prior to the start of the outage, PG&E had reviewed SG EC data to identify suspected ligament cracking (SLC) locations in the TSP. Two hundred forty-one (241) SLCs were identified in DC-1. Approximately 70% of these anomalous EC signals were present since the preservice inspection; the remaining indications showed up within the next one or two cycles. The licensee performed secondary side visual inspections of 49 of the 241 suspected ligament calls (SLCs) during the current refueling outage. In all cases, the visual inspections revealed that the flow holes were drilled off center such that the flow hole and tube hole connected. Westinghouse is supporting PG&E's efforts to disposition this finding.

Severe Accident Management Demonstration

On May 29 and 30, 1997, David Desaulniers of HFFB attended a demonstration of severe accident management capabilities at the Comanche Peak Steam Electric Station in Granbury, Texas. The demonstration included the licensee's presentation concerning site-specific development and implementation efforts followed by two drills demonstrating the use of the severe accident management guidelines by members of the licensee's emergency response organization. The information obtained through this demonstration will be used in the development of a Temporary Instruction for evaluating licensee severe accident management programs. The demonstration was also attended by representatives from the Containment Systems and Severe Accident Branch, the Emergency Preparedness and Radiation Protection Branch, Region IV, NEI, and several other U.S. nuclear plant representatives.

Examination Writing Workshop

John Munro of HOLB was in the Region IV offices on May 29 - 30, 1997, to participate in a Region IV sponsored workshop on how to write NRC operator licensing examinations. The workshop was attended primarily by Region IV utility representatives.

Participation in the Four Party Nuclear Regulatory Authorities Meeting on Digital Systems

During the week of May 19, 1997, Jared Wermiel, Chief, Instrumentation and Controls Branch and Matthew Chiramal, Senior Level Advisor on Digital Technology met with the nuclear regulatory counterparts from Canada (Atomic Energy Control Board (AECB)), France (Direction de la Surete des Installations Nucleaire/Institut de Protection de la Surete Nucleaire (DSIN/IPSN)), and the United Kingdom (Nuclear Installations Inspectorate (NII)) in the AECB offices in Ottawa, Canada. This was the sixth of a continuing series of meetings to exchange information and experiences in the regulation of digital systems in nuclear power plants. During the meeting, the four parties agreed on the final changes to a draft of the consensus report on computer-based systems in nuclear power plants. The report documents the generally agreed upon high level criteria for acceptance of digital systems. A small group meeting is planned in the U. S. in September 1997 to complete the document. The final document will be made publicly available toward the end of 1997. The four parties also presented discussions of various issues they are currently dealing with in the implementation of digital systems, and the status of the efforts to develop the design of the boiler control system problem. The next four party meeting will be held in May 1998 in the NII offices in the U. K.

Advisory Committee On Reactor Safeguards Meeting of the Instrumentation and Controls Subcommittee

On May 28 and 29, 1997, the ACRS I&C subcommittee met with the NRR and RES staff to discuss the final version of the staff update to SRP Chapter 7 to incorporate digital system review guidance. The staff presented its disposition of the public comments on the draft SRP Chapter 7 update and the associated software quality regulatory guides, the disposition of the recommendations of the National Academy of Sciences study on the staff digital system review process and guidance, and provided discussions on several topics of interest to the ACRS including formal methods, software tools, defense-in-depth and diversity, commercial off-the-self software, and specific acceptance criteria for digital systems. The full ACRS meeting on this topic is scheduled for June 11, 1997. The staff is hopeful of receiving ACRS concurrence to proceed with issuance of the final SRP Chapter 7 update.

Inspection of Reactor Vessel Chemistry Data at Framatome Technologies, Inc.

The staff issued Generic Letter (GL) 92-01, Revision 1, Supplement 1 in May 1995 to require all licensees to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of that data on their RPV integrity analysis. Such data included the chemical composition (e.g., the concentration of copper and nickel) of the RPV. To assess industry activities in response to GL 92-01, Supplement 1, for B&W fabricated RPVs, the staff performed an inspection of Framatome Technologies, Incorporated (FTI) on May 19-21, 1997. During the inspection, the staff (1) traced the weld chemistry data to weld metal qualification tests (WMQs), chemistry laboratory work requests, and other fabrication records; (2) reviewed FTI's fabrication records to verify consistency with topical reports that have been submitted to the NRC; and (3) assessed the impact of including all available data in the best estimate chemistry determination.

During the inspection, additional chemistry data that had not been previously reported to the NRC was identified and provided by FTI. In addition, the NRC identified chemistry data that FTI did not have in their database. At the exit meeting, FTI agreed, in part, to compile all the remaining chemistry data, correct typographical errors for some of the data provided, and obtain references and establish traceability for several data points. In addition, FTI agreed to assess the chemistry data and notify any owners that were adversely affected by the additional data. Preliminary assessments of all the available chemistry data indicate that the chemistry estimates prior to the inspection were conservative for most heats of material. For the heats of material where the chemistry estimates were not conservative, the effects appear to be minimal. FTI agreed to supply the information identified during the exit meeting within 30 days. An inspection report documenting the results of the inspection will be prepared after reviewing the submitted information.

Failed Thermal Sleeves at the Oconee Nuclear Station

Oconee Unit 2 was shut down due to a weld crack that caused a leak on April 22, 1997, in the High Pressure Injection (HPI) system connection to the reactor coolant system (RCS). In addition, the thermal sleeve on this line was found to be loose and worn in the area where it protrudes into the RCS. The thermal sleeve is needed to protect the HPI piping (about 100^oF) from thermal stresses due to RCS temperature of about 550^oF. A review of site records revealed a gap in one thermal sleeve (3A1) in Unit 3. Subsequently, Unit 3 was shut down on May 3, 1997. Unit 1 has a different design for the thermal sleeve. Unit 1 will be shut down no later than June 14, 1997 to inspect the HPI system thermal sleeves. The basis for continued operation over the short-term is as follows: (1) the licensee has enhanced reactor coolant leakage detection measures; (2) examination of past inspection data indicated no mispositioning of thermal sleeves; (3) the licensee has instituted administrative controls to minimize thermal cycling by variations in the makeup flow; (4) there is higher makeup flow rate through Unit 1 thermal sleeves than that through those of the other two units; (5) the design of thermal sleeves in Unit 1 is different than those in Units 2 and 3 (This leads the licensee to conclude that these thermal sleeves are less susceptible to crack initiation); and (6) the licensee has instituted additional letdown storage tank level verification.

Oconee Unit 2 has been restarted and is operating at full power. Before restart, the failed thermal sleeve (2A1) and associated welds were replaced. Other Unit 2 sleeves were inspected and found to be satisfactory.

Oconee Unit 3 is expected to restart within the next week. The one thermal sleeve (3A1) that was of concern on Unit 3 has been replaced. All other thermal sleeves have been radiographed, and the welds have been ultrasonically inspected. Site records show that all thermal sleeves on this unit were repaired (hard rolled, etc.) in 1982, except 3A1.

ENCLOSURE B

Office of Nuclear Material Safety and Safeguards
Items of Interest
Week Ending May 30, 1997

Inspection of Department of Energy/Fort St. Vrain Spent Fuel Dry Storage Activities

On May 19-21, 1997, staff from the Spent Fuel Project Office (SFPO) completed an inspection of the Department of Energy's Idaho Operations Office (DOE-ID). The objective of the inspection was to assess the readiness of DOE-ID to manage and operate the Independent Spent Fuel Storage Installation (ISFSI) at Fort St. Vrain prior to license transfer from Public Service Company of Colorado to DOE-ID. The inspection was conducted in two phases: (1) at the Fort St. Vrain site on May 12-16, 1997; and (2) at DOE-ID, in Idaho Falls, Idaho, on May 19-21, 1997. The SFPO team reviewed the full range of programs planned for operation of the ISFSI. The team noted that DOE-ID's contractor, Lockheed Martin Idaho Technologies Co., developed and was scheduled to perform most of the operations activities, with limited DOE involvement.

The team made a number of findings and, consequently, the date originally requested by DOE-ID for the license transfer (July 1, 1997) may be delayed. DOE-ID will perform a comprehensive internal readiness audit and inform the Nuclear Regulatory Commission of the audit results prior to further licensing action.

Application for Certificate of Compliance from Westinghouse

On May 20, 1997, the Spent Fuel Project Office (SFPO) received an application from Westinghouse for a Certificate of Compliance for the transportation portion, (to be licensed under 10 CFR Part 71), of a Multi-Purpose Spent Fuel Storage and Transport Cask (MPC) System. The Storage application, (to be licensed under 10 CFR Part 72) is expected within the next few months. This is the sixth application for a Multi-Purpose system recently received by SFPO. The other applications received include the VECTRA MP-187, the Sierra Nuclear TRANSTOR, the Holtec HISTAR, the Nuclear Assurance Corporation, International (NAC) MPC, and the NAC Universal MPC System storage and transport systems.

Nuclear Materials Management Safeguards System Meeting

On May 22, 1997, Fuel Cycle Safety and Safeguards Division staff participated in a Nuclear Materials Management Safeguards System (NMMSS) meeting at the Department of Energy (DOE). Representatives from Nuclear Assurance Corporation (NAC), U.S. Enrichment Corporation, DOE Headquarters, and the DOE Oakland Operations Office also participated. The principal topic of discussion was the projected financial shortfall in NMMSS funding which could impact DOE and the Nuclear Regulatory Commission. DOE committed to provide information on available funds and a detailed breakdown of expenditures.

International Atomic Energy Agency Inspection

During May 17-20, 1997, the International Atomic Energy Agency (IAEA) performed a routine monthly inspection of the downblending of high enriched uranium from Kazakstan (Project Sapphire) at the Babcock and Wilcox Naval Nuclear Fuel Division Plant in Lynchburg, Virginia. The IAEA inspectors performed verification measurements and selected destructive analysis samples of the downblended product produced since the last inspection.

Assistance to the Department of Energy on Plutonium Storage

At the request of the Department of Energy (DOE), Nuclear Regulatory Commission staff members are providing limited technical assistance to DOE's Nuclear Materials Stabilization Task Group in conducting a trade off study on storage of plutonium (Pu) pending disposition. The DOE trade off study is scheduled to be completed by August 1997. The Task Group met during the week of May 26, 1997, with NRC participating as an observer under the existing interagency agreement for providing assistance to DOE on Pu disposition. The Task Group is attempting to determine how Pu should be stored at selected DOE sites until DOE can implement its disposition options for excess weapons Pu. The Task Group invited NRC to provide insights regarding: (1) relevant NRC regulatory requirements, and (2) NRC schedule requirements if Pu storage were subject to NRC licensing.

Notice of Intent to Prepare an Environmental Impact Statement

The Department of Energy (DOE ) has requested Nuclear Regulatory Commission views on its notice of intent to prepare a Surplus Plutonium Disposition (SPD) Environmental Impact Statement (EIS), including whether NRC will participate as a cooperating agency under an existing interagency reimbursable agreement. DOE published the notice of intent in the Federal Register on May 22, 1997 [62 FR 28009]. The scope of SPD EIS includes whether DOE should continue to pursue its dual-track approach of plutonium (Pu) immobilization and mixed uranium-plutonium oxide (MOX) fuel fabrication and, if so, what facilities should be used for pit conversion, Pu immobilization, and MOX fuel fabrication. DOE will prepare the SPD EIS based on the Plutonium Storage and Disposition Preliminary EIS, which was completed last December. DOE plans to assess 12 options in the SPD EIS, including the "no action" alternative. Half of the options involve processing at Hanford and half involve processing at the Savannah River Site. DOE plans to conduct scoping meetings in the vicinity of the sites under consideration for Pu conversion, immobilization, and MOX fuel fabrication during June and July 1997. NRC staff is presently evaluating DOE's request and notice of intent, and plans to consult with the Commission on the appropriate level of NRC involvement.

Meetings on U.S. Enrichment Corporation Privatization

On May 22, 1997, staff from the Office of Nuclear Material Safety and Safeguards and the Office of the General Counsel met with the U.S. Department of the Treasury to discuss issues affecting U. S. Enrichment Corporation (USEC) privatization. Treasury will consider the Nuclear Regulatory Commission's proposed approach and will meet again with the NRC to discuss Treasury's comments and future NRC/Treasury coordination in this matter.

On May 23, 1997, NRC staff and ICF, Inc., NRC's financial consultant contractor, met with USEC and J. P. Morgan, Inc., investment bankers working for USEC, to discuss USEC privatization. The financial evaluation procedures and criteria to be applied by J. P. Morgan, Inc., and the NRC; and the need to use compatible evaluation techniques (including the same data and general approach) were discussed.

Tank Waste Remediation Section Staff Visit Savannah River Site

On May 20-21, 1997, staff from the Tank Waste Remediation Section (TWRS) of the Special Projects Branch and from the Center for Nuclear Waste Regulatory Analyses (CNWRA) visited the Department of Energy's (DOE) Savannah River Site (SRS) in Aiken, South Carolina. The purpose of the visit was to familiarize staff with a vitrification facility for processing high-level radioactive waste. DOE conducted a tour of the H and S Areas that included the receiving basin for off-site fuel; H-Area tank farms; the pre-treatment processes; vitrification at the Defense Waste Processing Facility (DWPF); and the canister storage facility. DOE contractors briefed the staff on the waste characteristics and associated safety topics; the waste transfer system; extended sludge processing and in-tank precipitation; DWPF; and lessons learned from operating experience.

American Society for Nondestructive Testing, Inc.

On May 21, 1997, members from the Medical, Academic, and Commercial Use Safety Branch met with representatives of the American Society for Nondestructive Testing, Inc. (ASNT) to discuss ASNT's "application" requesting recognition as an independent certifying entity. The recent revision to 10 CFR Part 34 (Licenses for Radiography and Radiation Safety Requirements for Radiographic Operations) establishes new requirements which specify that, within two years, all individuals acting as radiographers must be certified by a certifying entity in accordance with specific criteria. ASNT's application describes how its certification program meets this criteria. Preliminary plans and procedures for review of the application were also discussed.

ENCLOSURE H

Chief Financial Officer
Items of Interest
Week Ending May 30, 1997

FY 1997 Final Fee Rule

On May 21, 1997, the CFO forwarded the FY 1997 final fee rule to the Federal Register for publication. The final rule, which was signed on May 12, 1997, establishes the licensing and annual fees to be assessed in order for NRC to recover approximately 100 percent of its FY 1997 budget authority.

ENCLOSURE I

Office of Personnel
Items of Interest
Week Ending May 30, 1997

National Academy of Public Administration (NAPA) Meeting Attended

On May 28, 1997, Eileen Mason, Chief, Organizational Development and Training, attended the NAPA quarterly meeting of the Competency Network. The purpose of the network is to share information about developing competency-based human resource systems that can be used to assess competencies and training needs for organizations. The Department of Transportation, Office of Human Resources Management, presented a model that was used to develop and assess competencies for its office; and a consultant from Washington Consulting Services and Technologies described a product under development that uses Government Performance and Results Act concepts to link strategic planning with performance management.

ENCLOSURE J

Office of Small Business & Civil Rights
Items of Interest
Week Ending May 30, 1997

White House Briefing on Affirmative Action Programs

On Thursday, May 29, 1997, Von Deloatch, Program Manager, Small Business Program attended a White House briefing on President Clinton's efforts to "mend but not end" affirmative action in Federal program procurement and in the Department of Transportation's (DOT ) grant programs. Secretary of Transportation Rodney Slater, as well as senior officials from the White House, Department of Justice and the Small Business Administration, participated in the briefing. The briefing focused on DOT's Supplemental Notice of Proposed Rulemaking to revise its decision, which impacts all Federal set-aside programs. The DOT program sets a nationwide goal that at least 10% of the amounts appropriated for highway, transit and airport assistance be expended with small business concerns owned and controlled by socially and economically disadvantaged individuals.

ENCLOSURE M

Office of Public Affairs
Items of Interest
Week Ending May 30, 1997

Media Interest

The public affairs officers at headquarters and in the regions have been contacted by a Wall Street Journal reporter who is preparing a story about the impact on the nuclear industry of NRC's 50.54f letters on plant design basis.

Region IV Administrator, Ellis W. Merschoff, conducted a news conference on May 29 at Waterford 3 to discuss recent problems there and NRC's creation of a team to monitor the plant.

The Walnut Creek public affairs officer attended a news conference on May 27, in San Francisco at which Federal and California agencies announced a $14 million settlement with Pacific Gas and Electric Co. over allegations that it had misreported data on fish larvae mortality rates at the Diablo Canyon Plant.

Reporter Martina Schmid, Florida Public Television in Tallahassee has contacted Region II about a documentary she intends to do about commercial nuclear power plants in Florida.

School Volunteers Program

Daniel Rom/NMSS attended a Science Expo at Fields Road Elementary School.

ENCLOSURE P

Region I
Items of Interest
Week Ending May 30, 1997

Meeting with Aberdeen Proving Ground Restoration Advisory Board

Two members of the DNMS staff, Anthony Dimitriadis and Marie Miller, represented NRC RI at the Aberdeen Proving Ground Restoration Advisory Board (APGRAB) meeting at the Edgewood (MD) Senior Center on May 29, 1997. This local organization requested NRC attendance to get a better understanding of the NRC decommissioning process for areas within the U.S. Army Aberdeen Proving Ground Installation. The APGRAB also discussed opportunities for public involvement in the restoration process.

ENCLOSURE P

Region II
Items of Interest
Week Ending May 30, 1997

Office of the Inspector General Visit to Region II

On May 30, 1997, the Inspector General (IG) and several representatives of the IG's Office held a "town meeting" with Region II managers and staff. The purpose of the meeting was to discuss the functions performed by the IG's Office and answer questions regarding the performance of those functions. One of the discussion topics was the process for closure of IG investigations and notification of affected parties.

Duke Power Company - Oconee

On May 30, 1997, Region II issued the Augmented Inspection Team (AIT) report, which documents the findings for NRC review of the degradation of the high pressure injection (HPI) system event. The event occurred on May 3,1997, while the licensee was cooling down reactor unit 3 at the site. The report concludes that the causes of the HPI degradation included a lack of redundancy in the level instrumentation system for the water supply to the HPI system, loss of inventory in the water supply and inadequate monitoring of the inventory.

Carolina Power and Light Company

The Regional Administrator and other Region II staff held a management meeting with representatives of the Carolina Power and Light Company on May 30, 1997. The purpose of the meeting was to discuss the status of engineering and reorganization for the licensee's nuclear reactor plants at Brunswick, Harris and Robinson.

Florida Power Corporation and Florida Power and Light

On May 27 and 28, 1997, Associate Director for Projects from the Office of Nuclear Reactor Regulation visited the St. Lucie and Crystal Nuclear Plants, respectively. The purpose of the visit was to meet with the resident inspectors, plant management, and tour each facility.

ENCLOSURE P

Region III
Items of Interest
Week Ending May 30, 1997

Advanced Medical Systems, Inc.

On May 27, 1997, NRC issued a license amendment to Advanced Medical Systems (AMS) Cleveland, Ohio, authorizing AMS to ship all of its dry, packaged radioactive waste to Barnwell, SC. This waste contains approximately 850 curies of cobalt-60, and is presently being stored in various restricted areas inside the AMS facility. The amendment also requires AMS to submit a revised Decommissioning Funding Plan based on the immediate dismantlement option no later than July 1, 1997.

Chemetron, Inc.

As of May 27, 1997, significant activities have begun which will accomplish final disposal of low-level radioactive waste on the Chemetron, Inc., Bert Avenue site in Cleveland, Ohio. NRC air monitoring stations are in service with sample collection by Cuyahoga County. An NRC inspector visited the site during the week of May 19, 1997, to verify work status, check the air monitors, and make arrangements for a site visit by the NRC Region III (Chicago) Office mobile laboratory. Land surveys, security arrangements, and construction of a decontamination station are all complete. Transfer of material from one half of the site to the other, for construction of an engineered disposal cell foundation, should begin on or about June 20, 1997.

The site is a deep ravine, encompassing about three acres, in a mixed residential and industrial area. It was used for many years as an uncontrolled landfill. Some wastes, which are contaminated by depleted uranium, will be removed to a licensed disposal facility, but most will be interred onsite. The NRC inspection plans through the 1997 construction season were discussed at a public meeting in Cleveland on April 4, 1997. NRC, the Ohio EPA, and the Cuyahoga County Health Department are cooperating in oversight of the project.

Illinois Power Company - Clinton

A. Bill Beach, Regional Administrator, Geoffrey Grant, Director, Division of Reactor Projects, Gail Marcus, Project Director, NRR, and members of the NRC staff met with Illinois Power Company officials on Wednesday May 28, 1997, at the Clinton Nuclear Power Plant. The meeting, one in a continuing series of restart readiness meetings, was to discuss current performance and progress related to the restart of the facility. Topics discussed included status of the Startup Readiness Action Plan items and selected technical issues including degraded voltage, breaker operability, and Emergency Core Cooling System suction strainers.

Commonwealth Edison Company - LaSalle

A. Bill Beach, Regional Administrator, Geoffrey Grant, Director, Division of Reactor Projects, Robert Capra, Project Director, NRR, and members of the NRC staff met with Commonwealth Edison officials from the LaSalle Nuclear Power Station on Wednesday May 28, 1997, at the Mazon Emergency Operations Facility, Mazon, Illinois. The meeting was held to discuss the status and effectiveness of the restart plan plant performance improvement actions. Topics discussed included status of the restart plan, system functional performance reviews and the licensee's high intensity training program. The meeting was one of a continuing series of monthly meetings with the licensee.

Northern States Power Company - Monticello

On May 27, 1997, a management meeting was conducted between management representatives from Northern States Power Company and members of the NRC staff at the Region III (Chicago) Office, Lisle, Illinois, to discuss recent operator performance issues at the Monticello Nuclear Power Plant. A number of operational errors within the last six months have resulted in a reactor scram, a rapid power reduction, and other abnormal conditions. In addition, during a recent operator requalification examination administered by Northern States Power, poor individual and crew performances resulted in a crew and several individuals failing the exam. Northern States Power management provided to NRC staff a description of the actions they had taken to address these concerns.

Special Inspection Team Dispatched to Byron

On May 27, 1997, Region III (Chicago) dispatched a special inspection team to the Byron Nuclear Power Station to examine the circumstances surrounding the utility's decision not to declare the Safety Injection System inoperable after apparently failing a surveillance test. Also, the team will review the failure by the utility to vent the Chemical Volume and Control System in accordance with the technical specifications.

ENCLOSURE P

Region IV
Items of Interest
Week Ending May 30, 1997

SALP Meeting at Wolf Creek Generating Station

On May 22, 1997, the Regional Administrator, Region IV, along with other Region IV and NRR staff, attended a public meeting at the Wolf Creek Generating Station to discuss the results of the latest Systematic Assessment of Licensee Performance.

Management Meeting and Press Briefing at Waterford 3

The Region IV Administrator and the Deputy Director, NRR, conducted a public meeting with Waterford Steam Electric Station management on May 29, 1997. This was one of a continuing series of bimonthly meetings to discuss safety performance improvements at the station. During the meeting, the licensee discussed actions taken to improve overall performance and the effectiveness of those actions. Following the meeting, the Regional Administrator conducted a quarterly press briefing.

WNP-2 Public Meeting in Arlington

The Region IV Administrator conducted a meeting open to the public on May 30, 1997, with the Washington Public Power Supply System (WNP-2 facility) in the Region IV office. This meeting was to discuss the reactor feedwater pump trip and subsequent manual reactor scram of March 27, 1997. The discussions included the results of the NRC's special inspection of the event. The second area of discussion was the licensee's Nuclear Safety Issues Program (employee concerns program) and the results of the NRC's review of the program. The Director, Office of Enforcement, participated in the meeting.

Region IV Licensee Workshop

The region sponsored a licensed operator examination workshop on May 29-30, 1997 in the RIV office. Staff from all RIV licensees attended. The purpose of the workshop was to provide guidance and lessons learned from recent examinations to enhance licensees' ability to develop operator licensing examinations that satisfy NRC expectations.

ENCLOSURE R

Office of Congressional Affairs
Items of Interest
Week Ending May 30, 1997