ML20244A467
| ML20244A467 | |
| Person / Time | |
|---|---|
| Issue date: | 06/07/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-890602, NUDOCS 8906120033 | |
| Download: ML20244A467 (39) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ GrTbR . ggg ] 1 l June 7, 1989 I For: The Commissioners From: James'L. Blaha, Assistant for Operations, Office'of the EDO l 1
Subject:
WEEKLY INFORMATION REPORT WEEK ENDING JUNE 2, 1989 I A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report. l Contents Enclosure q Nuclear Reactor Regulation 'A Nuclear Material Safety and Safeguards B j Nuclear Regulatory Research C Analysis and Evaluation of Operational Data D Governmental & Public Affairs E General Counsel F* Administration G Information Resources Management H l Controller I* Personnel J Small & Disadvantaged Business Utilization & Civil Rights K Enforcement L j Consolidation M Regional Offices N I Executive Director for Operations 0* Items Addressed by the Commission P _j Meeting Notices Q Proprietary or Other Sensitive Information (Not for R l externaldistribution)
- No input this week.
3 s906120033 % 0 ames L. Blaha, Assistant for Operations I PDR REPT PDC ffice of the Executive Director WEEKL for Operations
Contact:
James L. Blaha, OEDO 492-1703 )
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HIGHLIGHTS OF WEEKLY INFORMATION REPORT 3 WEEK ENDING JUNE 2, 1989 4 Thermal Fatigue Cracking in Piping Connected to the Reactor Coolant Systems The American Nuclear Insurers (ANI) sent a letter to the ED0 describing their independent review of current practices, NDE results and industry responses to NRC Bulletin 88-08 and its Supplements. The ANI agrees that the staff provided adequate guidance in Supplement' 2 regarding NDE.to detect thermal' The ANI review suggests that the-fatigue cracks'in large diameter piping. recommended enhanced ultrasonic testing techniques are not necessarily being utilfred to a great extent primarily because the recommendations provided by Supplement 2 are not mandatory. The American Nuclear Insurers is concerned that a thermal fatigue crack could be missed and result in a unisolable reactor coolant leak and, therefore, recommends that the NRC take action to make enhanced ultrasonic testing mandatory. The staff is preparing a. response to this letter. MemorandumofUnderstandine(M0U) staff members of the Division of Safeguards and' Transportation On May 25, 1989, 1 met with a representative of the Federal Bureau of Investigation (FBI) and discussed Nuclear Regulatory Conslission (NRC) comments on a revised NRC/ FBI-A review and Memorandum of Understanding (MOU) that was proposed by the FBI. revision of the MOU was proposed by the FBI to reflect new legal authorities and the ten years of operating experience that has occurred since the original NRC coments were provided by appropriate Headquarters MOU was published. offices and by the Regions which will be reflected in the revised MOU. Concurrence at the working level of both agencies will be achieved prior to The revised MOU will forwarding the MOU to senior management for concurrence., be formally adopted when signed by the Chairman and the Director of the FBI. Briefing on Department of Energy Fitness-For-Duty Rule OnFebruary2,198gtheDepartmentofEnergy(D0E)publishedaproposedrule which would require, among other things, aandatory drug testing of applicants for and individuals holding DOE and DOE contractor positions involving access transportation of, or protection of Category I quantities of special to, lear material. On June 1, members of the Division of Safeguards and nuc Transportation and the Office of Nuclear Regulatory Research were briefed The information will be used in by DOE staff on the status of rulemaking. assuring continuing comparability of DOE and NRC requirements for the protection of Category I material. Hearing f_or Approval of Second Building the Maryland National Capital Park and Planning On Thursday (, June 1, held a hearing to reconsider its 4/13/89 opinion Commission MNCPPC) i recommending approval, with conditions, of Two White Flint North. In response to substitute proposals from the applicant, White Flint North Partnership, and the government, GSA and NRC, the MNCPPC members reviewed their previous conditions and decided to change them in ways that would guareintee development local area of the site in accordance with Montgomery County zoning ordinances, d be review requirements and the Adequate Public Facilities Ordinance, an acceptable to both the appitcant and the Government.
_= i g 4 - e Office of Nuclear Reactor. Regulation, ' Items of Interest: ' Week Ending June ~2, 1989-3 Severe ~ Accident Issues - Limerick-NRR.has_ participated in-the development.cf a proposed plan..for dealing with severe accident issues for Limerick.' In particular, NRC has received a court. order to consider mitigation des gn a ternat ves including filtered vents and i l i core retention devices as a means to reduce environmental impacts.from severe accidents..RAB's role includes assessment for risk reductions associated with. s different design alternatives at Limerick. 'NRR will be providing: input to the staff's evaluation of Severe Accident. Mitigation Design' Alternative (SAMDA's) with respect to their utility in. reducing environmental impacts of severe. accidents. This staff's evaluation is' in. response to a court order to assess SANDA's for the Limerick Station. The NRR input.will be concerned with the dose involved with implementing:the-SANDA's and whether implementation of candidate design alternatives would be foreclosed by prior operation of the' plant. Thermal Fatigue Cracking in Piping Connected to the Reactor Coolant Systems The American Nuclear Insurers (ANI) sent a letter to the ED0 describing their independent review cf current practices, NDE results and industry responses to NRC Bulletin 88-08 and its Supplements. The ANI agrees that the staff provided adequate guidance.in Supplement-2 regarding NDE to detect thermal fatigue cracks in large diameter piping. The ANI review suggests that the recommended enhanced ultrasonic testing techniques are not necessarily being utilized to a great extent primarily because the recommendations provided by Supplement 2 are not mandatory. The' American Nuclear. Insurers is concerned that a thermal fatigue crack could be misses and result in a unisolable-reactor coolant leak and, therefore, recommends' that the NRC take action to make enhanced ultrasonic testing mandatory. The staff is preparing a response to this letter. Brunswick Diagnostic Evaluation Team Findings on the Service Water System NRR and Region'II met with the Brunswick diagnostic evaluation team (DET)'to discuss.the results of their findings on the service water system.- The team's basic conclusion was that the licensee did not have~an adequate understanding: of the= capability of the service water system to satisfy.its. licensing design basis. The DET identified several design and operational concerns with the. service water system. The primary concern was the potential diversion of service water flow to safety related equipment in the event of a failure in the single valve between the essential and nonessential' portions'of the' system to automatically close on receipt of an accident. signal. An additional problem concerns continuing overheating of the service water mmp motors. The licensee has performed further evaluations:and made stort term modifications to the system which~it was agreed have resolved questions of immediate-operability. However, additional modifications and technical specification change proposals will be made in the future in ordkr to reestablish the systemL capability per the design basis. Region II and the resident inspector are following the licensees efforts. The DET report is expected to be issued in approximately two weeks. JUNE 2, 1989 ' ENCLOSURE A
q >Y j 4 ' Office of Nuclea'r Material Safety'and Safeguards l Items of Interest- ' Week Ending June 2, 1989 - SAFEGUARDS.' International' ~ International Atomic Energy Agency (IAEA) Inspection at General Electric The International-Atomic Energy Agency initiated asshort notice random - i inspection at the General Electric Fuel Fabrication Plant-in Wilmington,. . North Carolina on May 31, 1989.' The scope of-the inspection will include an audit of'the facility accounting ledgers and measurement verification of fuel rods,. uranium dioxide pellets and uranium dioxide powder.- Domestic. - Memorandum of Understanding (MOU) On May 25, 1989, staff members of the Division of Safeguards and Transportation - met with a representative of the Federal Bureau of Investigation (FBI) and discussed Nuclear Regulatory Commission (NRC) connents on a; revised NRC/ FBI Memorandum of Understanding (MOU) that was proposed by the FBI. A review and revision of the MOU was proposed by the: FBI to reflect new legal authorities and the ten years of operating experience that has occurred since the original MOU was published. NRC comments were provided by appropriate Headquarters offices and by the Regions which will be reflected in:the revised MOU.- Concurrence at the working. level of both agencies.will be achieved prior to forwarding the MOU to' senior management for concurrence. The revised MOU will be formally adopted when signed by the Chairman and.the Director of the FBI. l Briefing on Department of Energy Fitness-For-Duty Rule On February 2, 1989 the Department of Energy (DOE) published a proposed rule-which would require, among other things, mandatory drug testing of applicants for and individuals holding DOE and DOE contractor positions involving access o to, transportation of, or protection of Category I quantities of special nuclear material. On June 1, members of the Division of Safeguards and q Transportation and the Office of Nuclear. Regulatory Research were briefed by DOE staff on the status of rulemaking. The information will be used in assuring continuing comparability of DOE and NRC' requirements for-the-J protection of Category I' material, i L Transportation. Meeting on Westinghouse Titan Spent Fuel Cask On May 25, 1989, Transportation Branch staff met with the Department of Energy ~ (DOE) and Westinghouse to discuss the Titan spent fuel shipping cask. ~ The-Titan is one of'a series of spent fuel truck casks being designed for DOE for l 1 JUNE 2, 1989 ENCLOSURE B.
l. .C I ] shipment under the Nuclear Waste Policy Act.. Preliminary design. calls for the LTitan cask bo@'to be' fabricated from a titanium alloy. Interchangeable fuel c baskets have a capacity of three pressurized water reactor (PWR) or 7 boiling ' water reactor (BWR) fuel assemblies. Additional meetings will be held to. .s discuss design details and material characteristics of the titanium alloy. Package Supplier Inspection Conducted On May 22-25,.1989, the'secondLinspection utilizing an~ analytical tree which I provides a systematic overview of major areas to be inspected was completed.. The inspection was conducted of Westinghouse Radiological Services at-their 'Moorestown, New Jersey. engineering facility.and at the container; maintenance facility located at Marlton, New Jersey by two. members of the' Transportation Branch supported by a Region I. inspector. The next package supplier' inspection is scheduled for June 19-23, 1989. INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety Monitored Retrievable Storage TheDepartmentofEnergy)(DOE)presenteditspositionontheneedforaMonitored RetrievableStorage(MRS facility to the MRS Review Commission on May 25,t1989.- DOE recommended that.a MRS facility be built, even with the present statutory. constraints, as an integral part of the federal waste management' system to better meet its objectives of. timely waste acceptance, schedule confidence, ~ system flexibility, and timely waste disposal. The MRS facility, as DOE currently would only be used to receive store, and stage shipments of' conceives it, fuel to the repository and would not include provision for rod intact spent consolidation or other spent fuel preparation for disposal since current studies indicate consolidation is not needed for the Yucca Mountain repository. DOE prefers that site selection for the MRS facility be accomplished through the use of a Nuclear Waste Negotiator, as opposed to' DOE-directed site screening, but there is not a currently -known volunteer state. DDE believes-that successful siting negotiations might lead to revisions in the statutory' constraints 'which { would allow the advantages of an MRS facility to be more fully realized. The MRS Commission is due to send their report and recommendations to Congress in November 1989. UNC Inc., Montville Connecticut On May 24, 1989, staff members of The Industrial and Medical Nuclear. Safety Division and Region I toured the'new facility addition to be used'for fabrication of naval reactor fuel. A.pending license amendment application 1 to authorize operations in the new facility was also discussed. The revised application was-received on May 30, 1989. UNC expects to be rea@ to p introduce fuel into' the facility on June 9,1989. 1 i l JUNE 2, 1989 ENCLOSURE B _-_ _ =_:__-_____
3 Combustion Engineering - Hematite, Missouri staff from the Fuel. Cycle Safety (CE) to discuss the statuaBranch and R On May 24, 1989, with representatives from Combustion Engineering and licensing issues.for CE's ongoing facility upgrade. In addition CE presented their supporting criticality safety analyses for the facility upgrade. il ) l JUNE 2, 1989 ENCLOSURE B l l
I 4 Office of Nuclear Regulatory Research Items of Interest 1 Week Ending June 2,1989 i l Resolving Safety Issues and Developing Regulations, l The staff has recently met with CRGR (May 24 and 25, 1989) on a number of l safety issue resolutions. Those include: proposed resolution of USI A-17 I (Electric' Power Reliability) and the final resolutions of USI A-47 (Safety' ) (Systems Interactions), proposed resolution of Generic Safety Issue 128 ImplicationsonControlSystems). The resolution packages for these issues are also undergoing review by the ACRS in their upcoming meetings. The staff further expects that these resolution packages will issue over the next several months. Prevention of Damace to Reactor Cores Semiannual 2D/3D Program Coordination Meeting A semiannual 2D/3D Program Coordination Meeting was held in Munich, Federal Republic of Germany, on May 16-19, 1989. Representatives from NRC/RES, Los Alamos National Laboratory (LANL), and MPR Associates, along with those from Germany and Japan participated in the meeting. Test results obtained or analyzed during the past 6 months were i presented and discussed. Major results are briefly discussed below. ] A test simulating nitrogen injection into the primary system at the end of the accumulator injection during a LOCA was conducted in the Upper Plenum Test Facility (UPTF). The test results showed'that there was a substantial surge of liquid level in the core as soon as nitrogen was injected into the cold legs, resulting in improved core cooling. This liquid level surge is a transient phenomenon brought on by a momentary pressurization of cold legs and upper downcomer as a result of reduced condensation. After this liquid level surge, the core cooling mode and the emergency core coolant (ECC) gen is vented to the containment returns to the usual pattern as nitro is supplied by the low pressure coolant injection (LPCI) system. In any case, the nitrogen injection has a positive effect on core cooling. This nitrogen effect was correctly predicted by the TRAC-PF1/ MODI code. Other interesting results were obtained from steam-water interaction tests in the UPTF. Typical LPCI flows injected into the cold legs caused water hammer to occur, however, the water hammer was not strong enough to cause any damage to the facility. The test conditions were i formulated based on typical and conservative combinations of steam and I water flows. UPTF testing is scheduled to be completed in September. JUNE 2, 1989 ENCLOSURE C
) 3 2 l -Containment Performance and Protection from Radiation Exposure Levels for Uranium Hexafluoride-J In response to a request from NMSS, a staff-authored tedhnical report, " Chemical Toxicity of Uranium Hexafluoride Related to Radiation Doses," was provided. The report derives exposure levels for uranium hexafluoride based on chemical toxicity that are equivalent to the ' accident radiation' i j dose levels used for' reactor siting evaluations in 10 CFR Part 100. i i Recently Published C,nntractor Reports A contractor report, " Atmospheric Dispersion of Uranium Hexafluoride," was j completed and provided to NMSS. The report provides a model for the dispersion of a release of uranium hexafluoride taking into account the exothermic reaction with water vapor that' contributes to plume buoyancy. The research was requested by NMSS. NUREG/CR-5351, "Models for Pulmonary Lethality and Morbidity After . Irradiation from Internal and External Sources,"'and NUREG/CR-5353, " Inhaled 147Pm and/or. Total Body Gamma Radiation: Early Mortality and ~I Morbidity in Rats," were published. These publications _ culminate a 10 year multi-laboratory research effort which. has provided the scientific basis j for development of models to predict the early effects of external and internal irradiation from reactor accidents. l i JUNE 2, 1989 ENCLOSURE C
j i - i Office for Analysis and Evaluation of Operational Data' Items of Interest Week Ending June 2,1989 ' Division of Operational A'ssessment. On May 30, the Perry Diagnostic Evaluation Team Report was transmitted to The Cleveland. Electric Illuminating Company by letter from the EDO. On May 30-June 2, the TTC staff members presented a special. Westinghouse' Technology Course for the Atomic Safety Licensing Board Panel (ASLBP) personnel.- Preliminary Notifications-The following Preliminary Notifications 'were. issued ~during-the past week, a a. PNS-I-89-07A, Philadelphia. Electric Company (Peach Bottom Atomic. Power: Station), Vehicle Bomb Threat - Update. b. PNS-I-89-08, UNC Naval Products -(DN 70-371), Contract Security . Organization _ Files.for Chapter 11 Bankruptcy. c. PNO-I-89-39, Northeast Nuclear Energy Company (Millstone Nuclear Station, - Unit 1), Shutdown Due to High RCS Leakage.f d. PNO-I-89-40,Syncor, Incorporated.(LN 20-21227-01MD),AccidentInvolving Vehicle Delivering Radiopharmaceuticals, e. PNO-I-89-41 Neutron Product. Incorporated (Agreement State. Licensee),. Electrical Fire at Licensed Facility. f. PNO-II-89-40,-SouthCarolinaElectric&GasCompany-(V.'C. Summer). Inadvertent Opening of Pressurire Safety Valve. -g. PNO-II-89-41, Chem-NuclearSystemsIncorporated(BarnwellLowLevelWaste Disposal Facility),' Apparent Pyrophoric Activity in Waste Shipment Received at the Barnwell Low Level Waste' Disposal Facility.-. h. PNO-II-89-41A, Chem-Nuclear Systems. Incorporated (Barnwell Low Level Waste - Disposal Facility), Apparent Pyrophoric Activity in Waste Shipment- -Received at the' Barnwell Low Level Waste-Disposal Facility - gUpdate). J l 1. PNO-III-89-37,' Illinois Power Company (Clinton), Recirculation Pump Seal Failure. l j.: PNO-IV-89-36 Public Service Company of Colorado (DN 50-267), Shooting Incident Offsite Involving FSV Security Officer..
- k.. PNO-IV-89-37-GulfStatesUtilities(RiverBendStation), Transformer Fire.
1. PNO-V-89-32,SouthernCaliforniaEdison(SongsUnit1),PlannedShutdown Due to Discrepant Steam Generator Level Indication. JUNE 2,zl989 ENCLOSURE D 1
Office.of Governmental.and Public' Affairs Items of Interest Week Ending June 2,1989' INTERNATIONAL PROGRAMS: i IAEA OSART Completes Byron NPP Review A three-week review of operational safety practices 'at Commonwealth Edison's Byron nuclear power plant was completed by an IAEA Operational Safety Review Team (0SART)onThursday. OSART Team Leader Ferdinand Franzen noted that-Byron was found to be "a good plant on its way to.becoming an excellent plant, managed by a group of individuals committed to safety, thoughtful, and responsive to unexpected developments'and new proposals." Copies of Franzen's three-page statement, containing the team's' broad findings, including areas of possibleimprovement,areavailableinGPA/IP(M.Mahy,x-20335). IAEA Meeting on International Waste Transactions -J NRC staff (GPA/IP, NMSS, OGC) attended a meeting at IAEA Headquarters in Vienna from May 22 to May 26 on the development of a " Code of. Practice" for inter-national shipments of radioactive wastes. A detailed report is being' prepared for the Commission. STATE. LOCAL AND INDIAN TRIBE PROGRAMS Meeting with Virginia Radiation Advisory Board Joel Lubenau, SLITP, and Richard Woodruff, Region II State Agreements Officer,. met with the Virginia Radiation Advisory Board, at the Board's request, on June 2, 1989 in Richmond, Virginia; The purpose of the meeting was to brief the Radiation Board on the Nk: Agreement State ~ Program.. There has been some State interest in pursuing Apteement State status. Meeting with IDNS Officials Fred Combs,-Assistant Director for Stats, local and Indian Relations, and NRC staff from NRR, 000, and Region III met with representatives from the Illinois Department of Nuclear Safety (IDNS) on June 2,1989 in Glen Ellyn, Illinois, i The purpose of the meeting was to discuss elements of the proposed Illinois resident engineer program and House Bill 2310. House Bill 2310, which passed -the House on May 22, 1989, proposes to provide IDNS with greater regulatory I powers "to reduce the possibility of nuclear accidents and to minimize the-I severity of such accidents at nuclear-facilities." The measure is now being considered by the Senate Energy and Environment Committee.. Ohio' Governor Submits Emergency Response Plan for FEMA ~ Approval Ohio Governor Richard Celeste has submitted "The Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities" to the Federal Emergency Management Agency for its review and approval under~44 CFR 350. The Ohio Plan applies to the Perry Nuclear Power Plant and the Davis-Besse Nuclear Power JUNE 2, 1989 ENCLOSURE E
1 2 Station and incorporates initiatives recommended by the Governor's Emergericy-Evacuation Review Team. Rancho Seco Referendum Set for June 6 Sacramento Municipal Utility District voters will decide in a referendum whether Rancho Seco should continue to. operate. The referendum is set for June 6, 1989. 1 I i l J i l l i i l JUNE 2, 1989 ENCLOSURE'E
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Office of' Administration-l ~ Items of Interest I Week Ending June 2, 1989 l 1 I Division of Contracts'and Property Management DCPM has begun installation of a 15_ ton air conditioner and six stabilizing transformers to support the Otis elevators and improve their operating efficiency. Division of Security The ED0 has approved the revised procedures for 145b security investigation '{ waivers which include enhanced reference checks, credit checks and fingerprint-checks. 1 Division'of Freedom'of Information and Publications Services I NUREG-1354, " Fitness for Duty in the Nuclear Power Industry: Responses to Public Comnents," has been printed for distribution.- Significant FOIA Recuests Received by the NRC for 4-Day Period May 26 - June 1,19E 9 Reauest for ccpics of all internal records or correspondence on quality assurance issues that were described in the December 28,:1983 order requiring j the applicant for the Comanche Peak nuclear power plant to file a plan for an independent design review and approving CASE's contention regarding design QA. (LynnConnor, Doc-SearchAssociates,FOIA-89-239) Request for a listing of all procurement offices. (Jana Donnell, Federal Consulting Forum, F01A-89-241) Request for records relating to the Uravan Uranium Mill site in Uravan, Colorado.(StevenBolotinofBivona& Cohen,FOIA-89-242)- Request for all records of meetings between the Regional Administrator, Deputy -l Regional Administrator, or Director of the Office of Nuclear Reactor Regulation 1 and management representatives of. Boston Edison Company for' the period January 1, 1986, to August 31, 1986, concerning the Pilgrim nuclear power plant. l (George Johnson of Swidler & Berlin, F01A-89-244) i 1 l -l JUNE 2, 1989 ENCLOSURE G
i Office of Information Resources Management Items of-Interest Week Ending June 2,1989
- 1.
New Archival Storage Contract l The. initial hearing on the complaint filed by Pace Data Systems regrrding { the new Archival Record Storage Contract, was held on May 25, 1989, in the -1 United States District Court for the Eastern District of Pennsylvania. ' At l the suggestion of the Federal judge hearing the case, the attorneys 3 1 representing NRC and the attorneys representing Pace Data Systems conferred for several hours on May 25, and a settlement was reached. In { short.-the MC agreed to eliminate any minimum requirement that the' storage j facility must be above ground, and NRC will reevaluate Pace's proposal witaout respect to any minimum requirement that the facility must be above ground;.however, the NRC will consider the above-ground status of the facility in accordance with 36 CFR 1228.222, " Facility Standards for Agency Record Centers," and give it whatever weight may be appropriate in 1 the circumstances. 2. Master Inspection Planninc System - Phase !! l The Physical Database Design for.this portion of the Inspection System is complete. Implementation in the Shared Data Test Environment is imminent. 3. Office of Personnel's ADP IRM staff met to discuss initiatives to improve the Office of Personnel's (0P) ADP and office automation capabilities and began drafting a proposal to submit to the Director OP. t l JUNE 2, 1989 ENCLOSURE H j
Office of Personnel Items of Interest' i Week Ending June 2, 1989 Arrivals The following employees reported this week: Lori Shield, Secretary (PFT),-IRM Timothy Carnes, Technical Intern (OPFT),'NRR ChrisDella-Penna,'TechnicalIntern(OPFT),NRR GidgetSmith,TechnicalIntern(OPFT),.NRR Shirley Day, Secretary, (PFT), OC ReginaldEwing,TechnicalIntern(OPFT),RIII Louis Carson, Health Physicist (PFT), RV i Departures The fellowing euiployees retired this week: GeorgeFetrow,AssistanttotheDirector(PFT),fromADM Virginia Prine, Secretary (Typing) (PFT), from NMSS Daniel Muller, Project Director, Project Directorate III-2 (PFT), NRR EdwardWilliams, Emergency.PreparednessSpecialist(PFT),fromNRR James Allan, Deputy Regional Director (PFT), from RI Phillip Stoddart, Sr. Radiation Specialist (PFT), from RII Stanley Lasuk, Sr. Radiation Specialist (PFT, from RIII i Buddy Brock, Fuel Facilities Inspector (PFT), from RV Other Departures: Daniel Pearlman, Law Clerk, ASLBP Pat.Starcher,SafeguardsAssistant(PFT),NRR (PFT),OGC StephenBergquist, Attorney (PFT),OGC William Briggs Solicitor Mary Chestnut, Secretary (Typing) ()PFT), RIII Thomas Olsen, Project Manager-(PFT, RIV JUNE 2, 1989 ENCLOSURE J
J 4 ] ) Office of Small and Disadvantaged Business Utilization i and Civil Rights Items'of Interest Week Ending June 2,1989 1 Civil Rights Program' The Office of Small and Disdavantaged Business Utilization and Civil Rights (OSDBU/CR) hosted'the agency's fifth Annual EED Counselors Training Conference ,j on May 8-9,1989. It was held at the Quality Inn College Conference Cer,ter in i Westminster, Maryland. The strong support of Chairman Zech and the EDO, Victor Stello, Jr., coupled with the direction provided by Bill Kerr, 4 Director, OSDBU/CR, and his staff, made the Conference an overwhelming l success. OSDBU/CR commends.the management of the various NRC offices for encouraging EE0 Counselors assigned to their unit to participate in the-Conference. Mr. Robert Maddox, President of Creative Cc:=unications Associates, was the primary instructor; Hi Barber, OSDBU/CR, was the-conference. facilitatory. Participation included counselors from NRR, NMSS, RES, AE0D, IRM, OC, GPA, ASLBP, ADM, and all five Regional offices. 1 l' J i l l l l l i JUNE 2, 1989 ENCLOSURE K l
.0ffice of Enforcement Items of Interest Week Ending June 2,1989 Significant Enforcement Action An Order Imposing Civil Penalties in the amount of $6,250 was issued on ney 30, 1989 to Advanced Medical Systems, Inc. The action was based on violations involving significant weaknesses in management contro1~of the radioactive protection program. (EN85-49A) Civil Penalty Paid Public Service Electric and Gas Company (Salem Units 1 and 2) paid the civil penalty in the amount of $50,000. The action was based on a violation of the equipment qualification requirements of 10 CFR 50.49..(EN89-41) l l t 1 JUNE 2, 1989 ENCLOSURE L.
Office of Consolidation Items of Interest Week Ending June 2,.1989 Hearing for Approval of Second Building: On Thursday (, June'1, the Maryland National' Capital Park and PlanningMNCPPC). Commission recommending approval, with1 conditions, of Two White Flint North. In. response. to substitute proposals from the applicant, White. Flint North Partnership, and the government, GSA and NRC. the MNCPPC' members leviewed their previous-conditions and decided to change Lhem in wayc-that would guarantee development local area. of the site-in accordance with Montgomery County. zoning ordinances d be review requirements and the Adequate Public Facilities Ordinance, an acceptable to both~the applicant and the Government.. Water Fountain Replacement As of Friday, June 2, 38 of the 41 new certified lead-free chilled Halsey - Taylor water fountains were installed and operational. However, before the-bottled water is removed from One White Flint North,- the drinking fountains will be tested. CONS expects the remaining fountains to be installed in the near future, and all the fountains to be tested beginning June.13. 1 l I t ' JUNE 2,.1989 ENCLOSURE M.
m j x Region Im . Items of InterestE Week Ending June 2,1989 ' 1. SUSQUEHANNA RER A Safeguards Regulatory Effectiveness Review (RER) is-scheduled for the- ~ Susque sanna Plant, Units 112, on June 19-23,11989.~ RER's are designed to' assure that the1 safeguards required by NRC's regulations, and imple-mented by the. licensee, provide-the-intended: level;of protection and'do not~ compromise safety of operations. ;The' review complements NRC's-licensing.and regional inspection functions..During.itsJon-site review,- the RER team compares the safeguards being. implemented at the' plant to NRC's regulatory fesign basis-threat.. The'RER team includes NRC reactori engineers and safeguards specialists:from HQ and Region I and individuals from the U.S.L Arnty Special Forces...The team is also: assisted by the NRC : resident inspector. 1 2. FITZPATRICK SSFI TEAM INSPECTION A Region I SSFI team inspection conducted during May at the Fitzpatrick . Station focused on' AC and DC Electrical Systems 'and the Emergency Diesel Generator (EDG) and its support systems. This inspection; identified deficiencies in'the EDG fuel system and EDG fuel. surveillance'which'could have potentially lead to interruptions of EDG operation.and a nonconserva-tive' quantity of fuel on site. A' design deficiency was observed in'the U lack of automatic-isolation capability. of the Reactor Building Closed; Cooling Water (RBCCW) system._. Discrepancies-were observed between as-built electrical. equipment ratings and e_lectrical drawings. lThe -) licensee initiated prompt' corrective action and'has committed to respond to outstanding items on an' appropriate schedule.. The~ team' concluded i that improvements could'be made in-the depth of. licensee engineering reviews for assuring the' reliability and adequacy =of safety related systems. 3. SALEM UNIT 1 LOSS OF RESIDUAL HEAT' REMOVAL (RHR) PUMPS DUE TO INADVERTENT NITROGEN INJECTION-On May 20, 1989, both RHR pumps at Salem Unit I were lost for about fifty minutes due to inadvertent injection of Nitrogen.into the reactor; coolant. system (RCS)fromthe' accumulator. .j A special NRC team' consisting _of'a supervisor,.a system specialist from. - NRR, a. senior operations' engineer and a resident inspector was dispatched 1 to investigate this incident.. Preliminary evaluation indicated thatithe'. 1 event was caused by _ operator error. ' Inadequate surveillance procedure, abnonnal operating: procedure and event classification guide were some of the other contributors. The licensee's immediate actions included j training lof operators, termination of accumulator check-valve' testing and revision of inadequate procedures;. NRCstaffisconsideringLissuance'of~ an'Information NoticeLto inform all licensees about this eventa ' Routine: a resident inspector coverage continues while the licensee is completing the . detailed investigation.' l i JUNE 2, 1989 ' ENC'LOSURE N' 'l i
1 2 4. REGION I - POWER REACTOR OPERATING LICENSING SEMINAR. l An operator licensing seminar was conducted by the Region I office on i May 31, 1989 for all power reactor licensees in Region I. The Region I Deputy Director of the Division of Reactor Safety, William V. Johnston, . welcomed 68' power reactor representatives plus Region I and NRR, Operator Licensing Branch, representatives to a meeting focused on discussing the group's combined experience with implementing the many changes to theThe operator licensing program that have been made over the past year. seminar was addressed by the Regional Administrator, William T. Russell, and Ken Perkins, Chief of the Operator Licensing Branch, NRR. Presenta-tions were made by facility and NRC representatives on the new initial exam format, the new requalification exam program and the national exam schedule along with frequent questions and answer sessions. Numerous comments received from seminar attendees indicated that this forum for interchange of experiences and comments serves to further strengthen the progressive steps being taken in the operator licensing area. { i 1 i i JUNE 2, 1989 ENCLOSURE N
l s. n -l A Region.II ] Items of-Interest- 'l Week.Ending June 2, 1989~ 1 1. International Visit' 1 On May 31, the Hangarian Deputy Minister of the Ministry of Industry, '1 accompanied by the President of the Hungarian _ National Bank, visited the ' Virginia Electric and Power Company's_ North Anna facility for a plant tour' l and to discuss construction costs, environmental concerns, relationship.. with regulatory agencies, and radwaste management associated with nuclear. ] . lant' operations._ -{ p 2.- Talks Proceed on Russian Exchange Program On ' June l',~ the Deputy Director of the Reactor Projects Division was at the Duke Power Company's Catawba Nuclear Power Station for a plant tour and.to, meet with the DeputyL Director of NRR and the. Resident Inspectors to _. discuss a future visit from Russian' delegates., The two Russian delegates' will arrive at Catawba in mid-July and'will. work with the Resident Inspec-tors for about seven weeks. The' purpose of'the visit is to improve Soviet-1 nuclear safety by living~ day to day with a good utility and Hesident-l . staff.- 3. VEPCO Elects New VP l Effective June 15, 1989, Virginia Electric and Power Company: elected. James P. 0'Hanlon to:the position of Vice President, Nuclear Services. This positinn will report directly to the Senior'Vice President -: Nuclear and will focus primarily on long-ters nuclear operations. support activi-ties.. Mr. O'Hanlon is current 1y' employed as,the Vice President of . Operations at Gilbert Associates,: Incorporated, in. Atlanta, Georgia, and was fomerly employed by_ INPO. 4. Board of Directors Votes to Cancel Grand Gulf Unit 2 System Energy Resources. Inc..- notified Ranion II 'on June 2,1989, that a decisionwasmadeon' June 1,1989,bythe'$oardsofDirectorsofSystem Energy Resources, Inc., and Entergy Corporation _(Mid-South Utilities)' to cancel Grand Gulf Unit 2. -The decision is subject to' approval by the-Public Ser71ce Commissions of Arkansas, Mississippi, Louisiana, and the City of tha Orleans. The utility will. not request cancellation _ of the Unit 2_ construction permit until this approval has'been received.
- 5. - - Pyrotronic. ' Inc.
On May 23, 1989, the Kennedy Space Center'(KSC) advised NRC Region II that-they had discovered radiological contamination on approximately_40.indus. ~ trial-type smoke ' detectors distributed by Pyrotronic, Inc.- (a New Jersey-based _ firm). KSC advised that this contamination was found after ser vicing' by the Pyrotronic distributor in Norcross, Georgia. Surveys
- JUNE 2, 1989-ENCLOSURE N.
2 4 conducted at the Norcross facility by State'of Georgia and NRC inspectors revealed the. presence of some contamination on industrial-type smo te detectors and limited contamination in the work place. NMSS and the Regions held three conference calls on this. issue between May 24 and - 'May 30, 1989. It was determined that further surveys were warranted at the Pyrotronic distribution centers. Surveys conducted at their centers in New Jersey and Michigan did not reveal any contamination. As a result of this information, Region I initiated action'with the licensee to have the. licensee evaluate the problem, issue instruction to distribution centers to adhere to established,' approved cleaning and maintenance procedures, and determine whether certain smoke detector sources were suitable for continued use. JUNE 2, 1989 ENCLOSURE N
Region III Items of Interest Week Ending June 2,1989 1. Monticello - On June 2,' 1989, Mr. A. Bert Davis, Regional Administrator, and members 'of the Region III staff conducted a SALP meeting with Ncrthern States Power at the Monticello Training Center. Prior to;the.SALP meeting, a management meeting was held in the Training Center to discuss the licensee's status;of improvements to the modification control process. The licensee will'also-brief the NRC on the scope of their upcoming refueling outage?in August 1989. 2. Byron The OSART at' Byron Station since' May 15, 1989, presented their inspection: conclusions in a management meeting on June 1, 1989.. NRC Region'III attendees were Dr. C. Paperiello, Deputy Regional' Administrator, E. Greenman,_ Director, DRP, and P. Brochman,. Senior Resident Inspector. The OSART conclusions regarding the eight areas which were reviewed were generally favorable. The areas reviewed were (1) Management, QA, andFireProtection,-(2)TrainingandQualification, IndustrialSafety(4) Maintenance (5) Technical Support,:(6) Radiation - (3) Operations' Protection, (7} Chemistry, and (8) Emergency. Preparedness. 3. Perry On May 31, 1989, the Region III Director of. Reactor Projects and the Perry Resident Inspector participated in the Perry periodic management meeting with NRR and the licensee Cleveland Electric Illuminating Company. 4. Clinton On June 1, 1989, the Illinois Power Company's Clinton Station experienced a loss of both seals fer the "B" recirculation pump and conc.urrent complications with a trip of the drywell chiller and the inability 'of the-feedwater regulating valve for the motor driven' feed pump to adequately control level..~The plant, passed through Unusual Event, Alert and Unusual Event. stages of their emergency plan and ultimately ended up with the plant in cold shutdown. A daily report (Event No.:15761), PN (PNO-III-89-37) andConfirmatoryActionLetter.(CAL-RIII-89-016)wereissued,andaspecial-inspection team consisting of the' Resident Inspectors, Specialists from RIII Division of Reactor Safety and a contractor from Brookhaven National' Laboratory was formed to followup.on the event. l S. Davis Besse On May.30, 1989,_a meeting was held at Davis Besse to present the SALP 7 results. The licensee had two Category 1 ratings (in Security and Emergency Preparedness) and five Category 2 ratings. There were no Category 3 ratings. JUNE 2, 1989 ENCLOSURE N
I 'o' 6. Point Beach. On June 2, 1989, an enforcement conference was conducted with Wisconsin Electric Power management on issues relating to station batteries at Point Beach. I ') 1 l l JUNE 2, 1989 ENCLOSURE N
Region IV' Items of. Interest-Week Ending June-2,1989-1. Houston Lighting & Power Company -W.Kinsey,PlantManager,SouthTexas' Project (STP),-andothermembersof STP staff met on,May 30, 1989, with members of the. Region ~IV staff in the Region IV office at the request of STP to discuss general operating -matters at'STP.
- 2.. ' Louisiana Power & Light Company Enforcement Conference R. P. Barkhurst,.Vice President for Nuclear Operations, of the LSuisiana Power & Light Company and members of his' staff met on JuneL 1,1989,71n the Region IV office for an enforcement conference to discussed potential:
violations associated with-the environmental qualification of' submerged splices and cables 'at Waterford Steam Electric Station, Unit 3. 3. -Atlas Mineral Enforcement Conference-An enforcement conference was held'on June 2, 1989, at the Uranium: Recovery Field Office with Region IV management and' Atlas Minerals' i management, a: Division of Atlas Corporation,;.to discuss an apparent violation of 10 CFR 20.106,-excessive release of radon-222 to an unrestricted area, at the Moab Mill site near Moab, Utah.EThe~ Deputy-Director, Division of-Radiation Safety and-Safeguards,. participated.in these discussions with the. Uranium Recovery Field Office Director and Staff. 4. Houston Lighting'and Power Company The Region IV Regional Administrator spoke briefly on June 2, 1989, on behalf of the NRC at a dedication ceremony for Unit 2 of the South Texas Project near Bay' City Texas. Other speakers on the program ~ included Rep. Greg Laughlin of the 14th Congressional District,~_in which the plant is located, and Don Jordan, chairman of Houston Lighting and Power Company. A videotaped message was presented from Energy Secretary James Watkins. Houston Lighting & Power Company (HL&P) has announced the ' appointment of' Robert W. Chewning as Vice President, Nuclear Assurance. Mr. Chewning. was the HL&P Nuclear Safety Review Board (NSRB), Chairman. Vice President,. Nuclear Assurance;is a newly created position within the HL&P1 organization. The NSRB Chairman and the General Manager, Nuclear Assurance, who formerly reported to the Group Vice President Nuclear (J. Goldberg) will report to the Vice President, Nuclear Assurance. g ~ JUNE 2, 1989 ENCLOSURE N~
s Region V . Items of Interest Week Ending June 2,1989 San Onofre Units 2 and 2 An enforcement conference will be held in the Region V Office at 9:30 a.m. .on June 2,1989-to discuss enforcement concerns associated with emergency chiller freon levels. The apparent violations involve the licensee's failure. to:-(1)reflectvendorcriteriaregardingfreonlevelsinplantoperating procedures and (2) take appropriate and timely corrective action when a low freon level.was observed. The type of enforcement to be taken will be deter- . mined following the enforcement conference. -i JUNE 2 1989 ENCLOSURE N
4 . ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JUNE 2, 1989 A. STAFF REQUIREMENTS ~ AFFIRMATION / DISCUSSION AND V0TE.'3:30 P.M., WEDNESDAY,- MAY 24, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) 'SECY to W. Parler, GC dated 6/2/89 Ccinihission Resnonse to Motion to Reconsider Seabrook ' Order I. (CLI-89-8) The Commission, by a 4-0 vote,* approved.an Order responding to a May.22,.1989 petition from the Massachusetts Attorney' General to reconsider.the decision in CLI-89-8 to deny. interveners' application for a stay of' issuance of the. Seabrook low power license. The Order denied the-motion to reconsider. Commissioner Curtiss did not participate in this matter. i.
- Section 201 of the Energy Reorganization Act, 42 U.S.C. Sec.
l 5841, provides that action of the Commission shall be' determined by'a " majority vote of the membars present." Chairman lZech was not present when this item was affirmed. Accordingly,'the formal vote of the. Commission was 3-0 in favor of the decision. Chairman Zech,uhowever, had previously. ~ indicated that'he would approve this paper and had he been present he would have affirmed his prior vote. -JUNE 2, 1989 ENCLOSURE P
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