ML20246E583
| ML20246E583 | |
| Person / Time | |
|---|---|
| Issue date: | 07/06/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-890630, NUDOCS 8907120296 | |
| Download: ML20246E583 (46) | |
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g July 6, 1989 For:
The Commissioners From:
James L. Blaha, Assistant for Operations, Office of.the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 30, 1989
. A sumary of key events is included as a convenience to those Commissioners
.who may prefer a condensed version of this report.
Contents Enclosure Nuclear Reactor Regulation A
Nuclear liaterial Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
Governmental & Public Affairs-E General Counsel F*
Administration G
Information Resources Management H
Controller I
Personnel J
Small & Disadvantaged Business Utilization & Civil Rights K
Enforcement L
Consolidation M*
Regional Offices N
Executive Director for Operations 0*
Items Addressed by the Comission P*
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
)
externaldistribution)
P' i
- No input this week.
s907120296 890630
,/ Jam's L. Blahs, Assistant for Operations COMMS NRCC e
PDR WEEKLYINFOREPT PDC EfficeoftheExecutiveDirector for Operations gdA James L. Bla V, OED0 492-1703
HIGHLIGHTS OF WEEKLY INFORMATION REPORT-WEEK ENDING JUNE 30, 1989 Seabrook - Completion of Low Power Testing On June 22, 1989, the Seabrook facility was manually scramed during the conduct of a natural circulation test. The circumstances of this even.t are being investigated by the licensee. The NRC is dispatching an Augmented Inspection Team (AIT), lead by Region I, to evaluate the event. The natural circulation test will be rescheduled as part of the power escalation test program.
PSNH informed the staff on June 26, 1989, that all low power testing, except the natural circulation test, has been completed and that the Seabrook facility will be cooled down to cold shutdown on June 27, 1989.
With the exception of the natural circulation test, all low power test program objectives were met. Based upon initial review, all reactor physics parameters were as expected. The licensee consumed about 20 mir.utes, of the 45 effective full power minutes allowed by the license (.75 EFPH).
l Meeting with Nuclear Management and Resources Council On June 26, 1989, representatives of the Nuclear Management and Resources Council (NUMARC) briefed the NRC staff on the content of a major industry petition to have specific comercial reactor waste streams designated as Below Regulatory Concern (BRC). The petition, which is being prepared on behalf of 54 nuclear utilities, is expected to be submitted to NRC in July or August 1989. NUMARC indicated that the potential BRC wastes considered in the petition represent 20 to 30 percent by volume and.018 percent by activity of low-level waste generated by comercial reactors. The various wastes addressed in this petition are considered as one large waste stream characterized by certain bounding physical and radioactive properties. NUMARC stated that the petition does not permit recycle of BRC wastes.
NRC Distinguished Service Medal Given to Chairman Zech At a farewell reception for Chairman Lando W. Zech, Jr., Commissioner Rogers, representing the Comission, presented the Chairman with NRC's Distinguished Service Award" in recognition of his exceptional leadership in strengthening the Comission's regulatory program and in motivating industry leaders to achieve excellence in the operation of nuclear power plants."
Commissioner Curtiss announced that the Comission had nominated Chairman Zech for the 1989 Enrico Fermi Award for his leadership and contribution to nuclear The Enrico safety and his exceptional achievement in scientific management.
Fermi Award winner will be selected later this year by a group of distinguished of scientists.
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Office of Nuclear Reactor Regulation Items of Interest Week Ending June 30, 1989 Arkansas Nuclear One, Reorganization (update)
On June 19, 1989, AP8L announced two new key management assignments in its Arkansas ' Nuclear One (ANO) Nuclear Operations organization. Mr. James Vandergrift was selected as the ANO Unit 1 Plant Manager (previously ANO Operations 14anager) and Mr. Robert Fenech was selected as the ANO-2 Plant j
' Manager-(previously Operations Superintendent at Palisades). Other position j
assignments were also announced as part of the ANO reorganization recently j
approved by NRR.
]
Seabrook - Completion of Low Power Testing On June 22, 1989, the Seabrook facility was nanually scrammed during the conduct of a natural circulation test. The circumstances of this event are being. investigated by the licensee. The NRC is dispatching an Augmented Inspection Team (AIT), lead by Region I, to evaluate the event. The natural circulation test will be rescheduled as part of the power escalation test program.
PSNH informed the staff on June 26, 1989, that all low power testing, except the natural circulation test, has been completed and that the Seabrook facility will be cooled down to cold shutdown on June 27, 1989.
With the exception of the natural circulation test, all low power test program objectives were met.
Based upon initial review, all reactor physics parameters were as expected. The licensee consumed about 20 minutes, of the 45 effective full power minutes allowed by the license (.75 EFPH).
Fort St. Vrain At 10:00 p.m. on June 22, 1909, the Fort St. Vrain Nuclear Generating Station exceeded its authorized power limit of 82 percent of full power.
The plant operated at approximately 83.6 percent of full power for about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The 82 percent power limit is based on the capability of the plant's long term decay heat renoval system. An error in programming the calculation of the plant's secondary heat balance led to a non-conservative power reading and exceeding the authorized limit. The licensee is reducing power to 65 percent of full power until all corrective actions are taken.
In July 1986, the Comission imposed a civil penalty of $75,000 after Fort St.
g Vrain exceeded its then authorized power limit (35%).
Pilgrim - Power Ascension Test Program The Region I Administrator signed a letter June 26, 1989, which approved reactor power operation up to fifty (50) percent of full power for the Pilgrim site.
The approval is in accordance with the Boston Edison Company's (BECo) Power Ascension Test Program and HRC Confirmatory Action Letter 86-10 and its supplements.
JUNE 30, 1989 ENCLOSURE A
t' The. staff.provided the Conmission information regarding the contemplated approval point release'on June 21, in accordance with SECY-88-346. The information included the plant status, adequacy of licensee's activities during the initial phase of operation, and the status of offsite emergency Preparedness _And progress being made.
The' licensee and the Commonwealth of Massachusetts were notified by telephone of the approval letter by the Regional Administrator. The NRC Restart' staff at Pilgrim resumed around-the-clock inspection coverage'on June 26.- The reactorpowerisbeingincreasedandtheunitwasatthirtyfive(35) percent power the morning of June 27.
NUMARC/NSAC Workshops on 50.59 Guiduice Document (NSAC-125)
The Technical Specifications Brrnch, participated in workshops sponsored NUMARC/NSAC on industry's guidelines for conducting 50.59 reviews (San Jose -
June 15/16; Baltimore - June 2;/23. Theguide(NSAC-125) incorporates
. connents made by the staff on earlier drafts of the' document.
Thestafflplansonwaiting(approximately6-months)togainexperienceusing NSAC-125, and to see how well utilities implement the 50.59 guidance document, before issuing a. Regulatory Guide that endorses NSAC-125. 'The staff is currently.considering alternatives and schedules for gaining experience with NSAC-125.
The. staff is preparing a memo to the Regional Administrators informing them of the trial use period and inviting key regional personnel to headquarters for one day.of briefing on the guide.
Hatch Units 1 and'2 - Record'Run
.In the early morning hours of Sunday, June 25, the Hatch plant achieved a total of 180 + days of continuous dual-unit operation, thus setting a new world's: record for continuous dual-unit operation by a GE BWR. The previous record of 180 days had been held by the Brunswick plant. Both Hatch units continue to operate smoothly with Unit I at 100% and Unit 2 at about 86% in a coastdown for refueling.
Hope Creek Generating Station and Salem Units 1 and 2 - Effects of the Delaware River Oil 5 pill i
At-the present time, Hope Creek is operating at 99% power, and Salem, Unit 2 is operating at 100% power. Salem, Unit 1 is at 20% power and increasing.
The utility, Public Service Electric and Gas, is continually assessing the situation with respect to Delaware River oil spill, and will shutdown the operating units if a significant amount of oil penetrates the service water it.take structure.
Most of the oil is on the west side of the river, and the units are located on the east side. A fossil fuel plant, 8 miles upriver, has detected some oil on J
the west side.
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'Some globules of oil 1-3 inches in diameter, have been detected on the surface of the north tip of Artificial Island, which is 21 miles from the units. No subsurface oil has been found. At this location, and at another, 1 mile north of the units, a net that goes all the way to 'the bottom is periodically dragged across the river. The sampling point 21 miles away should give the facility about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notice of an impending problem. The facility will also be dragging a net at a point 5 miles upriver to check the status of oil at the point.
Oil contamination control booms have been placed around the intake structures of the units to stop and divert oil from the surface down to a depth of it i
feet. Deep water fishing nets that go all the way to the bottom and have a mesh size of i inch have been acquired and are on standby to be placed across the intake structure to stop and divert subsurface oil If the oil reaches the service water intakes the facility is considering using just one service water pump to minimize contamination of the system. Most of the oil should not get through the traveling screens. The little that does get through should not have any significant effect on the operability of the system.
If service water is lost completely, the licensee plans to shut the units down, activate the EOF, and proceed with the requirements of E0Ps for the loss of service water.
Dresden Station i
Dresden Units 2 and 3 have restricted operation power to less than 70% so that environmental cooling lake temperature restriction are not exceeded. With all of Ceco's plants operational ~this has not been a problem. The high cooling lake temperature is the result of a combination of high area temperatures and humidity and lack of rain. Dresden is currently operating on a closed cycle (between lake and condenser to river) or an indirect cycle (river to condenser to lake to river). However, since there are environmental limitations on the number of hours Dresden can operate in each of those modes Ceco is waiting until a time when the additional power is needed to utilize these other options.
Palo Verde On June 21, 1989, INPO informed Arizona Nuclear Power Project, the licensee, that the accreditation of Palo Verde's entire training program with the exception of radiation protection, is being place on " probation" for 120 days due to programmatic deficiencies related primarily to initial and continuing training. The affected training programs include chemistry technician training, STA training, mechanical and electrical maintenance technician training, and licensed operator training to the extent that simulator fidelity deficiencies continue to exist.
In addition, INF0 stated that line management was not committed to and involved with training. The 120 day probationary period is to allow " signs of improvement" to become evident.
JUNE 30, 1989 ENCLOSURE A
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4 LThe NRC's SALP review of Palo Verde's training and qualification program identified a continuing decline in performance since early 1987. Similarly, 1-concerns of simulator fidelity and licensee's management attention to resolve.
i these concerns have persisted. NRC is most concerned with the apparent rift
- between Operations and Training due to ineffective communication between the two organizations and lack of confidence.in the accuracy of training material by the Operations organization. The licensee has since instituted exchange of each organizations needs, and taken steps to foster a more effective working environment.
JUNE.30, 1989 ENCLOSURE A
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1 Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending June 30, 1989 SAFEGUARDS International' Meeting with General Electric (GE) and International Atomic Energy Agency (IAEA)
Representatives On June 16, 1989, aSafeguardsInt'ernationalBranch(SGIB)representativemet
-with GE and IAEA representatives at Wilmington, NC to discuss arrangements for the Physical Inventory Verification (PIV) to be held at the GE facility during
,the week of August 21,1989. GE submitted a schedule and a list of inventory materials. Minor amendments to the arrangements were discussed and incorporated into the plan.
Physical Inventory Verification (PIV) at Babcock and Wilcox (B&W)
On June.19-20, 1989, a Division of Safeguards and Transportation representative observed the physical inventory taking at the B&W low enriched uranium fuel fabrication facility in Lynchburg, VA.. The inventory list was submitted to the International Atomic Energy Agency (IAEA) staff on the ever.ing of June 20.
During June 21-23, the IAEA staff audited the' facility ledger, made measurements on assemblies using the neutron collar, made rod measurements, sealed, weighed (using a load cell) and verified enrichment using a multi-channel analyzer with a germanium detector on UF cylinders, and weighed and sampled pellets and g
. powder. All of the IAEA PIV criteria were satisfactorily corpleted.
Transportation Package Supplier Inspection Conducted
'On June 19-22, 1989, the third inspection utilizing an analytical tree which provides a systematic overview of major areas to be inspected was completed.
.The inspection was conducted at Chem-Nuclear, Inc. at their Columbia, SC engineering and design facility and at the container maintenance facility located at Barnwell, SC..The inspection was conducted by two members of the Transportation Branch supported by a Region II inspector. There were no violations or items of nonconformance noted. The next package suppliers inspection is scheduled for July 10-14 INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety BAW Fuel Company (BWFC) Lynchburg, Virginia On June 21, 1989, representatives from BWFC and the Fuel Cycle Safety Branch met.to discuss BWFC's renewal application. Areas of discussion included radiation protection, nuclear criticality safety, environmental protection, and the organization and administration of the safety programs. As a result of-the meeting, BWFC agreed to submit a supplement to the renewal application.
JUNE 30, 1989 ENCLOSURE B j
Fansteel - Muskogee, OK, following a June 18, 1989, release of aboLt 90,000 gallons of untreated process waste containing low concentrations of uranium and thorfun into the Arkansas River as result of a leak in the liner of a settling pond, the licensee put in temporary dites to hold further leakage onsite. The licensee also constructed e diversion ditch to prevent any runoff from adjacent land adding to the licuid waste behind the temporary dikes.
At Fansteel's request, the staff issued a license amendment on June 23, 1989, for a change in process flow to allow continuing limited production (extraction of columbium and tantalum from ores) while concurrently removing the estimated or.e million gallons of liquid waste behind the dikes and three million gallons in the settling pond for treatment by neutralizing, settling, and clarification before discharge to the river. The process change involves the use of a filter press to remove solids from the process weste stream and drumming of the residues for temporary storage. The licensee also is taking steps to increase the capacity of the waste neutralization system to expedite the removal of the waste from the pond. Nevertheless, Fansteel estimates that it could take 50 days to remove and treat all of the liquid waste and gain access to the settling pond liner for subsequent repairs.
LOW-LEVEL WASTE MANAGEMENT Meeting with Nuclear Management and Resources Council On June 26, 1989, representatives of the Nuclear Management and Resources Council (NUMARC) briefed the NRC staff on the content of a major industry petition to have specific commercial reactor waste streams designated as Below Regulatory Concern (BRC). The petition, which is being prepared on behalf of 54 nuclear utilities, is expected to be submitted to NRC in July or August 1989. NUMARC indicated that the potential BRC wastes considered in the petition represent 20 to 30 percent by volume and.018 percent by activity of low-level waste generated by commercial reactors. The various wastes addressed in this petition are considered as one large waste stream characterized by certain bounding physical and radioactive properties, iUMARC stated that the petition does not permit recycle of BRC wastes.
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JUNE 30, 1989 ENCLOSURE B C-
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>.Y Office of Nuclear Regulatory Research Items of Interest Week Ending June 30, 1989 Integrity of Reactor Components Meeting to Discuss Low-Temperature, Low-Flux Embrittlement On Thursday, June 22, 1989, a meeting was held in Pittsburgh, PA, to discuss the results obtained from the Shippingport reactor shield tank investigation and their implications on low-temperature, low-flux embrittlement of reactor pressure vessel support structures. Members of the Materials Engineering Branch, Division of Engineering, and the Engineering Issues Branch, Division of Safety Issue Resolution, met with the cognizant staff from Westinghouse-Dettis, Argonne National Laboratory, Oak Ridge National Laboratory, and the National Institute for Standards and Technology (formerly NBS). The discussions centered on comparisons between the Shippingport shield tank investigation results and the results from the integrity assessment of the ORNL High Flux IsotopeReactor(HFIR). Preliminary results from the Shippingport study do not strongly support the HFIR results, but there are several areas of uncertainty in assessing the neutron danage for both the HFIR and the Shippingport shield tank.
The meeting resulted in several action items: providing detailed neutron energy spectra for both the HFIR and the Shi3pingport reactors; exchanging irradiated and unirradiated materials from tiese two reactors between ORNL and ANL; initiating a Materials Test Reactor irradiation of these and other typical support structure materials; assessing the efficiency of thermal neutrons in producing damage for low-temperature, low-flux irradiation when there is a large ratio of thermal-to-fast neutrons; and beginning work to understand the mechanisms that control low-temperature, low-flux irradiation damage, which will lead to an analytical model to
'redict irradiation damage. Overall, the a
meeting was successful, producing a >etter understanding of the differences and similarities between these two reactors, and of the data needed by the various researchers in evaluating the technical issue. Further meetings will Le planned on an ad hoc basis.
Confirming the Safety of High Level and Low Level Waste Disposal International Workshop on Validation of Ground-Water flow and Transport Models The 3rd INTRAVAL Workshop and 4th Coordinating Meeting was held June 12-16, 1989 in Helsinki, Finland. The Industrial Power Company Ltd., of Finland, TVO was the host. The INTRAVAL study, an international project organized by the Swedish Nuclear Power Inspectorate, examines validation of ground-water flow and transport models. These validation studies are a key element in the use of performance assessment methodology for evaluation of a HLW repository and LLW disposal sites.
INTPAVAL workshop participants consisted of technical specialists from 12 countries (i.e., Australia, Canada, Finland, France, 1
Germany, Japan, the Netherlands, Spein, Sweden, Switzerland, United Kingdom, j
United States, and OECD ) and included both NRC staff and contractors (i.e.,
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SNL, University of Arizona); DOE contractors (i.e., PNL); and Nevada contractors working in nuclear waste disposal assessments. High-level and low-level radioactive waste relevant test cases formulated to test and evaluate conceptual radionuclides migration models and codes were discussed in detail by both the experimentalist and the modeling project teams. The workshop focused on accomplished field and laboratcry research results, and numerical simulation studies for validating radionuclides transport models. Numerical siniulations of these studies by the various INTRAVAL project teams showed a great deal of progress since the last workshop in November 1988. The experimental data and simulation results covered various geologic media, hydrologic conditions, and spatial and temporal. scales related to radioactive waste disposal issues. Of particular interest to the NRC staff were the presentations and technical feedback on the unsaturated zone test cases (i.e., Apache Leap Tuff Site, and LasCrucesTrenchexperiments),aswellas}.thefractureflowcontaminant studies (e.g., Finnsjon and Stripa studies The workshop included recent field and laboratory studies being conducted by the University of Arizona for l
1 validating unsaturated flow and transport models for fractured media. New results were presented from various modeling and analysis efforts by NRC staff (T. McCartin, RES and R. Codell, NMSS) and contractors (S. Neuman, Univ. of Arizona).
Copies of the recently publised "INTRAVAL Progress Report 3 November 1988 -
February 1989" which outlines the project objectives, test cases, and accomplishments are available from the RES contact.
RES contact is Thomas J. Nicholson at EXT 2-3856.
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Office for Analysis and Evaluation of Operational Data Items of Interest i
Week Ending June 30, 1989
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Division of Safety Programs
.This week, the 1988 AE0D Annual Report was published. The report is published in two parts. NUREG-1272, Vol. 3, No. 1, covers Power Reactors and presents an overview of the operating experience of the nuclear power industry, including
.1 comments about the trends of some key performance measures. The report also i
. includes the principal findings and issues identified in AE00 studies over the past year, and summarizes.information from Licensee Event Reports, Diagnostic.
Evaluations'and reports to the'NRC's Operations Center. NUREG-1272, Vol. 3, No. 2., covers Nonreactors and presents a review of the nonreactor events in 1988 and.a brief synopsis of AE0D studies published in 1988.
AE00 participated in an INP0. task group meeting to discuss the expansion in -
scope of the NPRDS to include additional balance of plant equipment. Decision on the scope of the expansion is expected later this summer.
Division of Operational Assessment On June 26-30, IRB met with the five regional Emergency Response Coordinators in a special workshop to standardize the Regional Supplements to NUREG-0045, the procedure for the NRC Incident Response Plan. This effort will allow for easy transition of response team members responding to events in other regions.
The Training Advisory Group (TAG) had a very productive meeting at the Technical TrainingCenter(TTC)on 6/28-29/89. All regions plus NRR, NHSS, RES, AE00, and OP were represented at the meeting. A number of training issues were discussed including the following: technical training of various NRC technical groups (mandated by NRC Inspection Manual Chapter 1245, Examiner Standards, and headquarters office letters); consolidation of the training curriculum for reactor, materials, and fuel facility radiation specialists; the simulator upgrade plan for NRC controlled simulators at the TTC; Combustion Engineering simulator training; high technology training enhancements for reactor technology training; Operator License Examiner techniques training; new cross training series in Babcock & Wilcox and Combustion Engineering technology; Incident Investigation Team training and accident / investigation seminars in regions; Site Access Training and Site Access Refresher Training; Emergency Operating Procedure (EOP) simulator training as refresher training for inspectors; OSHA training of NRC staff; security training; shifting to a risk based culture for NRC technical training; and severe accident training plans.
Preliminary Notifications The following Preliminary Notifications were issued during the past week.
a.
PNS-I-89-10A,ConsolidatedEdisonCompany(IndianPointNuclear Generating Station), Security Threat - Update.
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b.
PNS-I-89-108, Consolidate Edison Company (Indian Point Nuclear Generating Station), Security Threat - Closecut.
c.
PNO-III-89-40, Commonwealth Edison Company (Zion Unit 2), Loss of Control Room Annunciators.
d.
PNO-III-89-41, Illinois Power Company, (Clinton), Loss of Main Transformer Causes Reactor Trip.
e.
PN0-I-89-46, Duquesne Light Company (Beaver Valley Power Station Unit 2),
Unusual Event Due to Primary to Secondary Leak.
f.
PN0-1-89-47, Rochester Gas and Electric Company (R.E.Ginna Nuclear Plant),
Forced Plant Shutdown Due to Two Inoperable Safety Injection Pumps.
g.
PN0-1-89-48, Public Service of New Hampshire (Seabrook, Unit 1), Manual Reactor Trip During Natural Circulation Testing.
h.
PNO-I-89-48A, Public Service of New Hampshire (Seabrook, Unit 1), Update on June 22, 1989 Manual Reactor Trip Event - Issuance of Confirmatory Action Letter.
1.
PNO-I-89-48B, Public Service of New Hampshire (Seabrook, Unit 1), Update on June 22, 1989, Manus 1 Reactor Trip Event - Formation of Augmented Inspection Team.
J.
PH0-I-89-49, Boston Edison Company (Pilgrim Nuclear Power Station), Release for Operation up to 50 Percent Power.
k.
PN0-I-89-50, Philadelphia Electric Company (PEco) (Peach Bottom Atomic Power Station Units 2 and 3), Agreement Reached Between PECo and Pennsylvania.
1.
PN0-I-89-51, Rochester Gas & Electric Co. (R.E.Ginna), Requalification Examination Results.
PN0-I-89-52,PhiladelphiaElectricCompany(PECo)(PeachBottomAtomic i
m.
i Power Station, Unit 2), Peach Bottom Authorized to Proceed to 70 Percent Power.
n.
PNO-I-89-53 Long Island Lighting Company (Shoreham Nuclear Power Station), LILCO Shareholders Approve Agreement to Close Shoreham.
o.
PNO-I-89-54, Syncor Corporation, Reported Loss of Radiopharmaceutical
- Vehicle, p.
PN0-II-89-46(A), Florida Power and Light Company (Turkey Point Units 3 and 4), Drug Testing (Update).
(ReferencePN0-II-89-46 dated 6/15/89.)
q.
PNO-IV-89-39, Private Citizen, Lenapah, Oklahoma, Radioactive Material in Uncontrolled Area.
JUNE 30, 1989 ENCLOSURE D
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PNO-IV-89-40,PublicServiceCompanyofColorado(FortSt.Vrain),
_ r..
Operation Above' Authorized Power Level, s.
.PNO-IV-89-43,GulfStatesUtilities(RiverBendStation), Personnel
. Contamination.
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PNO-IV-89-44,PublicServiceCompanyofColorado(FortSt.Vrain),
Unplanned' Release.
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PNO-V-89-37, Arizona Nuclear Power Project (Palo Verde Unit 2), Palo Verde Unit 2 Restart.
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JUNE'30, 1989 ENCLOSURE D
'4 Office of Governmental' and Public Affairs Items of Interest Week Ending June 30, 1989 INTERNATIONAL' PROGRAMS:
International-Visitors i
'On Tuesday Dr. Giuseppe Verri, Head of the Information Systems Division, Directorate for Nuclear Safety and Health Protection (DISP), National.
Comittee for Research and Development of Nuclear Energy and Alternative Energy (ENEA), met with staff from AE0D to discuss NRC and non-NRC data base for. event analysis.
IAEA Signs Memorandum of Understanding with WANO l
l The International Atomic Energy Agency (IAEA) and the World Association of Nuclear Operators (WANO) signed a Memorandum of Understanding on June 6, 1989 aimed at complementing the work _ of each organization in improving nuclear safety. 'Under the agreement there will be an exchange of information between IAEA and WANO covering, for example, technical reports and reviews of' i
operational experience, as well as invitations to workshops and meetings.
Export / Import
- During the week ending June 30, 1989, two applications for export licenses were received from Energy Fuels Nuclear, Inc. and Manufacturing Sciences Corporation.
A license was issued to the-latter applicant and to Westinghouse Electric Corporation.
IAEA Vacancies Following is a list of vacancies for positions at the International Atomic Energy Agency:
P-3 Nuclear Physicist, Nuclear Data Section, Division c? Physical and Chemical Sciences, Department of Resecrch and Isotopes P-5 Unit Leader, Section for Data Processing Development, Division of Safe-i guards Information Treatment, Department of Safeguards P-2 Systems Programmer, Section for Data Processing Systems, Division of Safeguards Information Treatment, Department of Safeguards i
P-3 Translator, Russian Translation Section, Division of Languages, Department of Administration P-5 Section Head, Personnel Management Section, Division of Personnel, Department of Administration P-5 Support Programmes Officer, Division of Development and Technical Support, Department of Safeguards JUNE 30, 1989 ENCLOSURE E
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P-5 Group Leader, Division of Operations B, Department of Safeguards P-4 Risk Management Specialist, Safety Assessment Section, Division of Nuclear' Safety, Department of Nuclear Energy and Safety P-5 Section Head, Staff Administration Section, Division of Personnel, Department of Administration P-2 Marine Bio / Geochemist, Radioecology Section, International Laboratory of Marine Radioactivity at Monaco, Department of Research and Isotopes STATE, LOCAL AND INDIAN TRIBE PROGRAMS Illinois Senate Passes Nuclear Safety Legislation The Illinois Senate passed H. B. 2310, the Illinois Nuclear Facility Safety Act, as amended, by a vote of 55-1 on June 23, 1989. The Senate version of the legislation differs substantially from the House version and includes the following language.
"It is the intent of the General Assembly that this Act should be construed consistently with federal law to maximize the role of the State in contributing to safety at nuclear facilities in Illinois. It is the' intent of the General Assembly that the Illinois Department of Nuclear Safety should not 'take any actions which are preempted by federal law or engage in dual regulation of nuclear facilities, unless dual regulation is allowed by federal law and policies of the Nuclear Regulatory Consnission.
In implementing its responsibilities under this Act, the Illinois Department of Nuclear Safety shall not take any action which interferes with the safe operhtton of a nuclear facility."
The measure must now go back to the House for its consideration of the differences from the House-passed version. The Illinois General Assembly is scheduled to adjourn on June 30, 1989. The Office of General Counsel is reviewing the Senate version of the legislation.
Health Physics Society Annual Meeting Vandy Miller, Assistant Director for State Agreements, attended the Health Physics Society 34th Annual Meeting which was held in Albuquerque, New Mexico from June 25-29,1989. The meeting covered a wide range of health physics issues including external dosimetry, waste management, emergency planning and management and environmental radiation. Mr. Miller made a presentation entitled " Accidental Radioactive Contamination of Metal Products".
JUNE 30, 1989 ENCLOSURE E
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J Meeting with New York Public Service Comission Staff-j l -:
Staff from the New York Public Service Comission met with Region I ' staff.on June 27, 1989 in King.of Prussia, Pennsylvania. The purpose of the meeting -
.was to discuss the NRC process for oversight of licensee self-assessments.
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Office of Administration Items of Interest Week Ending June 30 1989 Office of the Licensing Support System Administrator Construction has been comp 1e'ted on.the 5th floor of the East / West Towers building for the Office of the Licensing. Support System Administrator. The space has been made ready for occupancy on Monday, July 3.
Protest A:recent protest filed with the General Services Board of Contract Appeals related to NRC's contract with Applied Management Systems, Inc. for ADP systems development and maintenance services was withdrawn by the protester on June 28, 1989.
High Wind Conditions An. anemometer,-an instrument for measuring and indicating the speed of wind, has been installed at the One White Flint North building. This device is part of the new procedures which have been added to the One White Flint North Emergency Protection Plan to r.otify employees when high wind conditions exist.
Privacy Act The Division of Freedom of Information and Publications Services is currently reviewing all. systems of records maintained by the NRC pursuant to the Privacy Act.
Significant FOIA Requests Received by the NRC For-5-Day Period of June 23,1989 - June 27,""7989 Request for a copy of license No. 34-19854 issued to Atom Mechanical of Ohio.(DonnaEly,AdvancedMedicalSystems,Inc.,F01A-89-278)
Request for copies of any pre-solicitation announcements and an awarded proposal..(B. W. Linville', FOIA-89-279)
Request for copies of the transcripts of the first three Comission meetings on the status of operating reactors and fuel facilities. (Colleen Amoruso, STS Incorporated, F01A-09-280)
Request for six categories of records relating to RFP RS-ARM-89-137.
(Sherry McBride, Telos, FOIA-89-261)
JUNE 30, 1989 ENCLOSURE G
9 Request for copies of minutes of meetings between NRC staff and utilities on evaluation of design and construction adequacy of the LaSalle, Grand Gulf, andSusquehannanuclearpowerplants.(MichaelO'Mealia, Doc-SearchAssociates, F01A-89-283)
Request for records not already in the PDR related to the shutdown of the Peach Bottom nuclear power plant, the post-shutdown investigations, or the bases for the shutdown and post-shutdown investigations. (Nancy Jones of Shaw,Pittman,Potts&Trowbridge,F01A-89-284)
Request for co)ies of internal NRC correspondence involving the licensing and operation of t1e Grand Gulf Unit 1 nuclear power plant during the years 1982 through1984.(LynnConnor, Doc-SearchAssociates,F01A-89-286) 1 1
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Office of Information Resources Management Items of Interest Week Ending June 30, 1989 1.
Cullinet Federal Advisory Group On June 28, 1989, the Cullinet Federal Advisory Group met at the offices of the Comptroller of the Currency. The issue addressed was the merger between Cullinet Software, Inc. and Computer Associates.
(Cullinet,our i
IDMS/R vendor is merging with Computer Associates, the largest independent software company in the world on August 16,1989.)
Bob Weiler, President of Cullinet addressed the group. Mr. Weiler, who is handling the merger from the Cullinet side, explained the details of' the transaction. Based on his personal interactions with Charles Wang, Chairman of Computer Associates, Mr. Weiler expressed his opinion on the changes that NRC can expect as a result of the merger. A white paper discussing, in detail, Mr. Weiler's presentation is being prepared by IRM.
2.
Computer Facility Operations The new computer facility operations contract under Statistica began on June 19, 1989. After the planned transition / training period of four days, the new operations-team took over the operational responsibility on June 23, 1989 when the Kenrob contract expired on June 22, 1989. Proper security heasures (e.g. changing system passwords) were taken and the transition went very smoothly.
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JUNE 30, 1989 ENCLOSURE H
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Office of the Controller Items of Interest Week Ending June 30, 1989 l
NRC's FY 1990 Appropriation l
On Wednesday, June 28, 1989, the House of Representatives passed the FY 1990 4
Energy and Water Development Appropriation Bill (H.R. 2696). There were no 1
amendments to H.R. 2696 that would directly affect NRC. Thus, H.R. 2696 would reduce the NRC's FY 1990 budget request of $475 million by $30 million.
1 Information Digest The pocket reference edition of the NRC Information Digest was distributed to all NRC offices.
If you do not have a copy available to you, and you need one, contact the Distribution Services Unit on extension 27333.
JUNE 30, 1989 ENCLOSURE I
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Office of Personnel Items of Interest Week Ending June 30, 1989 NRC Distinguished Service Medal Given to Chairman Zech i
At a farewell reception for Chairman Lando W. Zech, Jr., Commissioner Rogers, representing the Comission, presented the Chairman with NRC's Distinguished Service Award" in recognition of his exceptional leadership in strengthening the Comission's regulatory program and in motivating industry leaders to achieve excellence in the operation of nuclear power plants."
Commissioner Curtiss announced that the Comission had nominated Chairman Zech for the 1989 Enrico Fermi Award for his leadership and contribution to nuclear safety and his exceptional achievement in scientific management. The Enrico Fermi Award winner will be selected later this year by a group of distinguished scientists.
Farewell Reception for Chairman Zech Held at Headquarters Three receptions were held to honor Chairman Lando W. Zech, Jr., who completed his term as Chairman on June 30, 1989, and retired from government after 47 years of military and civilian service. Hundreds of employees, friends, ano guests wished the Chairman well, and greetings and best wishes were conveyed from all of the Regions.
Arrivah The 'ollowing employees reported this week:
Jeffrey Harold, General Engineer (PFT), NRR Darrell Roberts, General Engineer (PFT), NRR DavidBeaulieu,ReactorEngineer(PFT),RI JosephD' Antonio,ReactorEngineer(PFT),RI Departures John Schneider, Space Management Specialist (PFT), retired from ADM.
RumualdLipinski,SeniorMechanical/StructuralEngineer(PTT), retired from NRR.
Reba Diggs, Facilities Program Coordinator (PFT), retired from OC.
Dale Smith, Director, Uranium Recovery Field Office (PFT), retired from RIV.
Other Departures:
Vivianheid, Secretary (Typing)(PFT),NRR Andrenna Inman, Secretary (PFT), OGC JUNE 30, 1989 ENCLOSURE J
Office of Small and Disadvantaged Business Utilization and Civil Rights Items of Interest Week Ending: June 30, 1989 Federal Women's Program The Federal Women's Program (FWP) Manager held the third quarter teleconference with the five Regional FWP Coordinators on June 12, 1989. The i
l teleconference served as a forum for a discussion of the current women concerns in the regions, the FWP activities presented during this quarter, tentative pre-planning for the upcoming FWP Conference, and NRC employee participation in the Federally Employed Women's National Training Conference
.in Memp11s, Tennessee. Christine O'Rourke, Region I FWP Coordinator, and Toye Sinsons, Region III FWP Coordinator, agreed to co-coordinate the 1989 NRC FWP Conference to be held at a Headquarters location in October. Peggy Shaw, Region II, the 1988 FWP Conference Coordinator, will join Era Marshall and this year's Conference Co-coordinators in planning this event.
JUNE 30, 1989 ENCLOSURE K
Office of Enforcement Items of Interest Week Ending June 30, 1989 The following Significant Enforcement Actions were taken the week of June 26, 1989.
An Order Imposing A Civil Penalty in the amount of $50,000 was issued on June 26, 1989 to Carolina Power and Light Company (Brunswick Units 1 and 2).
The action was based on violations involving the failure to meet the equipment qualification requirements of 10 CFR 50.49.
(EN88-35A)
A Hotice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued on June 28, 1989 to Louisiana Power and Light Company (Waterford3). The action was based on a failure to properly evaluate ASME Section XI test results for the B High Pressure Safety Injection (HPSI) pump.
(EN89-65)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $28,500 was issued on June 28, 1989 to Isomedix, Inc., Whippany, New Jersey.
The action was based on three separate deliberate violations involving bypass of the radiation monitor interlock system and a violation involving bypass of a safety system designed to protect individuals from radiation-produced toxic gases. The mitigation / escalation factors in the Enforcement Policy were considered and the base civil penalty for one violation was increased 25 percent because of prior notice, while another was mitigated 50 percent when the licensee's good past performance was balanced against multiple examples.
(EN89-64)
The following Civil Penalty Paid the week of June 26, 1989.
Niagara of Wisconsin Paper Corporation, Niagara, Wisconsin paid the civil penalty in the amount of $750. The action was based on two violations which involved:
(1) failure to,have licensed individual perform the removal of a enerally-licensed radioactive gauge from its installed location and
- 2) transfer of a radioactive gauge to an unlicensed metal salvcge yard.
EA89-65).
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JUNE 30, 1989 ENCLOSURE L j
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Region I Items of Interest Week Ending June 30, 1989 1.:
R. EL GINNA - REQUALIFICATION EXAMINATION RESULTS L
During the week of June 19. 1989, the NRC' administered requalification
-examinations.to twelve licensed operators at the R. E. Ginna. Station..
Preliminary results of the simulator and' walk through portions of the.
examination indicate that five operators failed.. NRC and facility parallel grading are in agreement on those results. Facility grading of the written examination has identified one additional failure. NRC grading of the written examination is in progress.
Based on the preliminary resultis, the-Ginna requalification program is evaluated as unsatisfactory.
A management. meeting to_ discuss the requalification examination results and licensee proposed correction actions is scheduled for Friday, June 30', 1989, in Region I.
2.
SHOREHAM NUCLEAR POWER STATION On June 28, 1989,'about 95% of the Shoreham~ shareholders' voted to approve the sale of the plant.to the Long Island Power Authority of the State of New York for ' decommissioning. The vote.is considered valid, but must be confirmed by an independent auditor, which should take' about' two weeks. The shareholder vote. is the final step of licensee approval of the agreement with the State.of New York.
There will be a licensee meeting with NRR and Region I in the Region I office on June 30 to discuss short-term plans for the plant.
3.
MEETING BETWEEN NRC AND FEMA Dr. Halcolm R. Knapp, Director, Division of Radiation Safety and Safeguards, and Dr. Ronald R. -Be11any, Chief, Facilities Radiological Safety and-Safeguards Branch, met with Mr. Paul Giordano, Director, FEMA Region III, on Thursday, June 29, 1989, in the FEMA III Philadelphia office. The meeting is intended to provide a forum for the discussion of the interface between the NRC and FEMA.
- 4.-
PEACH BOTTOM UNIT 2 As of 8:00 a.m. on June 29, 1989, Unit 2'is at 45% power and 411 MWe.
During the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the licensee received permission from the NRC to operate up to and at 70% power. Reactor power was increased to 45%
for feedwater control loop stability testing. There were two ENS calls during the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to the loss of the Emergency Notification System to the NRC Operations Center. At this time the ENS line is still out of service. Backup communications are in place.
- JUNE 30, 1989 ENCLOSURE N
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PILGR1H NUCLEAR POWER STATION-As of 7:30 a.m. on June;29, 1989, the reactor is at 35% power with the turbine generator synchronized to the grid. The' licensee is preparing for performance of the " shutdown from outside.the control room" (SDOCR) test which is planned to begin this afternoon. -The plant will be
-manually scrammed and brought to' hot shutdown using alternate shutdown-panels located in the process buildings. The NRC restart. staff is in
.i 24-hour shift coverage and will provide augmented inspection coverage of the SDOCR test.
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Region II Items of Interest Week Ending June 30, 1989 1.
VEPCO'S CEO and Chairman of the Board Visit On June 28, J. Rhodes, President and CEO, and W. Berry, Chairman of the Board, Virginia Electric and Power Company, visited the Regional Adminis-trator to discuss their assessment of the root causes for the Surry problems, their rationale for actions that have been taken, and their thoughts on future actions.
2.
Enforcement Conference With Florida Power Corporation On June 28, representatives of the Florida Power Corporation were in the j
Region II Office to attend an Enforcement Conference regarding EQ issues at their Crystal River Nuclear Power Station. The licensee recogized there were substantial deficiencies in their EQ program and described an extensive effort to reverify compliance with the EQ rule through walk-downs, technical reviews, and training.
3.
Licensed Operator Requalification Examination at Farley On June 29, the Regional Administrator, the Reactor Safety Division Director, and other selected members of the Regional staff were at the Alabama Power Company's Farley site to attend the operator requalification examination exit. Preliminary results indicate weaknesses in the areas of event classification and use of certain E0Ps by the crews in the simu-lator.
4.
Turkey Point Drug Testing Status Florida Power and Light is continuing their drug testing activities at the Turkey Point Plant. As of June 30, 1989, a total of 1312 persons have been tested,1270 passed, 2 tested positive for cocaine, and one refused to be tested. Random testing of bargaining unit personnel was initiated on June 28, 1989, and 136 personnel have been tested. Results of these tests are not yet available, j
5.
Crystal River Loss of Offsite Power i
With Unit 3 in mode 3 and cooling down, a loss of offsite power occurred on June 29, 1989, when Unit 3 startup transformer breakers 1691 and 1692 l
opened due to a lightning strike. The "A" emergency diesel generator
/
started and loaded the "A" ES bus. Because of the "B" diesel generator being out of service for repairs, the "B" ES bus had to be manually 1
aligned to Units 1 and 2 startup transfonner. Natural circulation was initiated and continued until approximately 10:00 p.m when Unit 3 startup transformer was returned to service and two RCPs started. The unit had earlier declared an unusual event due to the Technical Specifications required shutdown because of the inoperable energency diesel generator. A I
JUNE 30, 1989 ENCLOSURE N
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meeting will be conducted in Region II on July 5, 1989, with Florida Power Corporation to discuss the licensee's action prior to the unit startup.
' 6.
Surry Unit Commences Heatup Unit'l entered node 4 (above 200 degrees F) at' 6:50 a.m. on June 30, 1989, following satisfactory completion of the control room bottle air test.
The licensee received indications of loose parts in the reactor vessel, and will have B&W evaluate the monitor indications. Criticality is scheduled for July 2.
JUNE 30, 1989 ENCLOSURE N
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Region III
' Items of Interest Week Ending June 30, 1989 1..
Point Beach Nuclear Power Station The Regional Administrator, Director, Division of Reactor Projects, and other regional staff members met with Wisconsin Electric Power Company on June 27,1989,'to discuss the Systematic Assessment of Licensee Performance (SALP). Based on discussions at the meeting, Region III will conduct periodic meetings with the licensee to improve communications.
l 2.
Quad Cities Unit 1 i
In early June, the licensee noticed an increase in seal cavity pressure for the IB Reactor Recirculation pump. Normal cavity pressure is 500 psig, current pressure is approximately 690 psig depending on reactor pressure. The licensee developed and is implementing a procedure to monitor and trend seal pressure, temperature and drywell leakage. This procedure was developed at the request of Region III. The SRI and regional management are closely monitoring the performance of the degraded seal.
3.
Monticello C. E. Norelius and other representatives from Region III and NRR 1
Headquarters staff met with Northern States Power Com)any management on June 26, 1989, in the Region III offices to discuss tie ifcensee's progress in resolving security problens at the Monticello site.
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1 JUNE 30, 1989 ENCLOSURE N
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i Region IV
. Items of Interest I
Week Ending June 30, 1989
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University of Oklahoma
.An' enforcement conference was. held in Region IV on June 26, 1989.'The Region IV management met.with the Provost of the University-of Oklahoma
-and his Assistant for Administrative Affairs, the Dean of the. College of.
' Pharmacy, the Director of Nuclear Pharracy, and the Radiation Safety Officer.with the Health Sciences' Center' to discuss the licensee's activities.related to unauthorized manufacturing and distribution of radiopharmaceuticals.
u 2.
State of Utah The Director'of the state of Utah, Bureau of Radiation Control, met June 27,L1989, in the RIV office with NRC staff from the Uranium Recovery Field Office and the Regional Office. The meeting focused on the regulatory interface between the state of Utah (an agreement state)
-and the NRC in matters concerning source and byproduct materials transported into Utah for processing or disposal.
' 3..
Arkansas Nuclear One The.licenseeatArkansasNuclearOne(AN0), Unit 2,conducteda controlled unit shutdown on June 23, 1989 because of increased unidentified reactor coolant system (RCS), leakage. Following repairs to a' low-temperature overpressure isolation valve and a reactor head vent line flange, the unit was brought to operating temperature and pressure on June 27, 1989. On June 27, 1989, at.7 a.m. (CDT), RCS leakage' increased to approximately 7 GPM and.the licensee began returning the unit to culd shutdown. The reactor head vent line flange was found
-to be leaking again. The licensee is investigating the cause of the leak.
The unit will remain shut down for repairs for 2-3 days. The resident inspectors are monitoring licensee actions, i
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Region V Items of Interest Week Ending June 30, 1989 1.-
San Onofre Units 1. 2 and 3 L
A management meeting between NRC and licensee personnel was held at the-
. San Onofre site on June 27, 1989. The senior representatives from the two organizations were J. Martin, Regional Administrator, and
-Dr. L. Papay, Senior Vice President. The meeting focused on recent L
licensee efforts to consolidate, relocate, and improve the. design engineering and quality oversight functions, with the expectation that--
this will lead to observable improvement in these' areas by the end of.
1989. As a result of other discussion during the meeting,:the licensee-also' plans to evaluate improvements in the root cause assessment program; 2.
Washington Public Power Supply System (WNP-2)
An enforcement conference was held with Supply System representatives in
.the Region V. office on June 28, 1989, to discuss potential escalated enforcement issues involving environmental-qualification (EQ) and commercial grade procurement. The intended course'of action regarding EQ is being discussed.among Region V, the Vendor Inspection Branch, and.the-
~ Office of Enforcement. The commercial grade procurement issue was held open pending inspection efforts to obtain additional information from the L
L licensee. Licensee actions'in response to the numerous shutdown cooling' isolations experienced during the 1989 refueling outage were also discussed following the enforcement. conference.
3.
Palo Verde Unit 2 Restart On June 29, 1989, Palo Verde Unit 2 reactor was restarted following a 105 day outage. No problems were experienced by the licensee during restart..The Unit 2 reactor was shutdown on March 15,-1989, as a result
- of a number of concerns arising from the investigation of the March 3, 1989, reactor trip event at Palo. Verde Unit 3.. The Unit 2 reactor had been required to be maintained.in a shutdown condition under the provisions of a Confirmatory Action Letter issued by the NRC on March 28 1989. The restart of the reactor was witnessed by NRC personnel onsite.
The plant is currently operating at 3 percent power. Units 1 and 3 both remain in refueling outages and require NRC concurrence prior'to restart.
4.
Veterans Administration Medical Center. Palo Alto On Monday, June 26,-1989, Robert Pate, Chief, NMSS Branch, Michael Blume, Regional Attorney and Frank Pang, Radiation Specialist held an l
enforcement conference with James Dentro, Director of the Palo Alto l:
VeteransAdministrationMedicalCenter(VAMC),andhisstafftodiscuss the violations (including three repeat violations) identified during a recent NRC inspection. The discussion centered on needed Palo Alto VAMC program improvements to prevent recurring violations.
' JUNE 30, 1989 ENCLOSURE N
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5.
Management Meeting - Washington State University
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.A management meeting was held on June 29, 1989, in Pullman, Washington between,the NRC staff, State of Washington, Office of Radiation Protection staff.and Washington State University. The meeting involved discussion of recent NRC and State inspection findings regarding I
management involvement at the Washington State University Nuclear
.i Radiation Center.
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JUNE 30, 1989 ENCLOSURE N 1
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ITEMS ADDRESSED BY THE COMMISSION - Week Ending June 30, 1989 A.
SECY-89-143/COMLZ-89 AMENDMENT TO 10 CFR 50 RELATED TO MAINTENANCE OF NUCLEAR POWER PLANTS - SECY to V. Stello, Jr., dated 6/26/89 The Commission has been impressed by the tremendous teamwork effort put forth by the NRC staff to develop, on the Commission's accelerated schedule, the final rule on Maintenance of-Nuclear Power Plants and the accompanying regulatory guide.
NRC's rulemaking initiative immediately served to increase industry attention on this important aspect of nuclear power plant safety.
During recent visits to nuclear power plants, Commissioners have seen the evidence of the industry's commitment to improving plant maintenance.
Moreover, based upon recent NRC analyses of industry performance in the area of maintenance, including the results of the maintenance team inspections, the AEOD Special Study Report (AEOD/S901, Revision 1), performance indicators, SALP ratings, and other similar measures, it is evident that progress has been made over the past four years in the area of nuclear power plant maintenance.
As the AEOD report points out, j
this is particularly true for the latter part of 1987 and 1988.
Nevertheless, there is a widely held view that further improvements are necessary, especially with regard to effective j
implementation of maintenance programs.
1 Because maintenance plays such an important and integral role i
with plant operations in assuring public safety, the Commission
)
is convinced that continued improvement in maintenance is needed; i
not only for improved maintenance today, but to ensure the continued proper performance of maintenance in the future.
Therefore it is appropriate for this agency to pursue its interest in seeking to improve maintenance.
The Commission also I
believes that industry participation in developing a standard for maintenance would be extremely valuable; without the industry's expert involvement in developing such a standard, the draft Regulatory Guide might not be as good as it can or should be.
Accordingly, the Commission (with all Commissioners agreeing) has approved the following actions related to maintenance at nuclear power plants:
1.
The Commission has agreed to hold the final draft rule on maintenance in abeyance for an 18-month period from the effective date of a revised policy statement (see Item 2 below) while closely monitoring industry's maintenance progress.
At the end of the 18-month period, the staff should report back to the Commission on the progress that the industry has made in improving maintenance and provide recommendations on the need, if any, for additional regulatory action.
The Commission will review the industry's improvement in maintenance based upon inspections and relevant performance indicators to determine what, if any, additional regulatory action is warranted.
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2.
The staff should prepare for commission review and approval a revised Maintenance Policy Statement.
The revised Maintenance Policy Statement should retain the basic elements of NRC's current policy trith appropriate revisions based on the staff's efforts to date, acknowledge the industry progress to date and commitment to continued improvement in maintenance performance, and encompass the following additional elements:
a.
State the Commission's intention to grant the industry a set period of time, (18 months) during l
which the Commission would monitor the industry's initiatives in the area of maintenance; and announce the Commission's intention to hold the draft final rule in abeyance during this period of time.
b.
Emphasize the need for continued improvement in maintenance of nuclear power plants and the importance of well executed and documented maintenance programs to plant life extension; c.
Encourage expanded industry use of and participation in the Nuclear Plant Reliability Data System (NPRDS);
d.
Indicate the commission's intention that the staff continue to refine its draft maintenance standard.
NRC should encourage the assistance of the jndustry and the public in this task.
NRC should also encourage voluntary industry adoption of the maintenance standard; e.
Encourage the further development and use of maintenance performance indicators by the nuclear industry such that the Commission and the industry may closely monitor the progress of industry improvement initiatives; f.
Indicate the Commission's intention to issue plant specific orders or to take other approp'riate enforcement action where the NRC detects poor or declining maintenance performance; and g.
Identify the principal elements that are essential to an acceptable maintenance program (these are set forth in large part in the existing policy Statement, but may need to be supplemented).
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JUNE 30, 1989 ENCLOSURE P l
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3.
The staff'should publish the draft regulatory guideLfor
' comment ~so that-a' final. regulatory guide with the:
s benefit'of feedback,from maintenance-inspections and input from'the industry can be. ready for final' issuance-with a maintenance rule at'a later date:if necessary.-
(see Itemile above)" The notice requesting comments on-the guide-should; provide adequate-background-information-for those seeking to comment on;the' guide without publishing the' draft final-rule..
4.
Totassist the Commission.in monitoring industry improvement _ initiatives, the staff should proceed;with-validation-and implementation of its maintenance effectiveness indicator on an' expedited basis.
As a -
first' step, the staff should invite the voluntary participation of licensees in a small, NRC-utilities,
. demonstration projevc to identify' quantitative' indicators-for the evaluation of the performance of maintenance programs._ This project should_begin-
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immediately and would have.theiobjective of developing a product suitable for use on a trial-basis within one year.- Following the~ identification of a mutually agreed upon set of indicators, a testing period (of adequate: duration)1of their use should begin.
5.
The staff'in coordination with OGC should establish criteria to be used to determine'when a plant specific order or'other appropriate enforcement action should be j
taken under the revised Maintenance Policy.
In this regard, the staff and OGC should examine lour authority to issue orders or to'take enforcement action for balance:of plant systems'and components.
If the 1
current regulations on this matter are unclear, the
'l staff should identify;those changes in the regulations I
that-would be necessary to permit-the Commission ~to-issue such orders or take_other appropriate enforcement action.
The criteria should be forwarded for~
Commission review and approval.
6.
Staff should continue to coordinate with ACRS so that ACRS views can be incorporated.into the revised policy-statement and reflected in future staff activities ~in this area.
Commissioners Roberts and Curtiss believe that tha staff should
- identify, based upon the results of' maintenance team inspections, for' utilities where maintenance improvements are considered l-necessary so that individual utilities can direct their efforts 1
accordingly.
The articulation of improvements should be in terms
-of and results, not the process.
Commissioner. Roberts believes (in addition to the above items) that in order not to dilute staff and' licensee resources, staff should identify, in terms of function, those BOP systems and
.i components that have an importance to safe operation of the plant..
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STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 11:30'A.M.,
THURSDAY,-JUNE 22, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to W. C. Parler, GC-dated 6/28/89 I.
SECY-89-189 - Motion for Protective Order bv'Joseoh J.
Macktal The Commission, by a 5-0 vote, approved an order responding to a June 13, 1989, " Motion for Protective Order" filed by Mr.
Joseph J. Macktal.
The motion _ requested that the Commission modify an earlier subpoena and.(1) move his interview to l
Washington, D.C., (2) grant.Mr, Macktal confidentiality, and (3) provide 30' days notice of che interview.
The order denied the' motion but. modified the subpoena to be returned on July 6, 1989, at 9:00 a.m.,
C.D.T..at the NRC Region IV, OI office in Arlington, Texas.
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