ML20006D670
| ML20006D670 | |
| Person / Time | |
|---|---|
| Issue date: | 02/07/1990 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-900202, NUDOCS 9002140214 | |
| Download: ML20006D670 (44) | |
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February 7, 1990 M:
The Comissioners From:
James L. Blaha, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING FEBR'JARY 2, 1990 4
A sumary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure A
Nuclear Reactor Regulation Nuclear Material 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-1*
Personnel J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Enforcement L
Consolidation M
Regional Offices N
Executive Director for Operations 0*
l Items Addressed by the Comission P
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
externaldistribution)
- No input this week.
~s pgg21ggg4ygggo7' aha, ssistant for Operations t
WEEKLYINFOREPT PDC fice of the Executive Director for Operations q
Contact:
p James L. Blaha, OEDO I'{i 492-1703 I
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j WEEK ENDlhG FEBRUARY 2, 1990
' L i ce' see. C ert i f i ca tion :. Insleneata ti on. of. FFD.Au la l
e Letters certifying implementation of-the Fitness-for-Duty rule have been received from all except p t of the power reactor licensees. The one exception has confirmed that the cert (fication letter has been forwarded. Of the responses received, 27 sites did not report more stringent measures than i
required by the rule, and 46 sites implemented more stringent cutoff levels and/or are testing for additional substances.
i Diablo Canyon has responded that they are in compliance as far as the temporary j
restraining order pertaining to random testing will allow.
QNB. Review of Fitness.fer Duty Rule l
TheOfficeofManagementandBudget(OMB)hasnotgrantedaclearancefor i
the information collection requirements contained in 10 CFR 26, ' Fitness An interagency meeting involving the National Institutes of Health, Health and Human Services, National Institute on Drug Abuse, the for Duty."
Office of Management and Budget, and NRC is being scheduled to seek resolution of OMB's issues.
l Meeting.with. Governor.of.0hio A. Bert Davis, Region III Administrator, and Region III staff met with Ohio Governor Richard Celeste and members of his staff on January 30, 1990 in Columbus, Ohio. The purpose of the meeting was to discuss the i
recent series of gaseous releases as a result of loop seal failures in the off-gas system at the Perry Nuclear Power Plant and other issues of interest.
Second Buildino. Status The General Services Administration (GSA) solicited expressions of interest for development of alternate sites along the Red Line between Grosvenor Station and Rockville Station for NRC's second building after it appeared that the negotiations for construction of Two White Flint North were breaking GSA received several proposals, at least one of which is receiving serious consideration. At the same time, negotiations are continuing between down.
GSA and the White Flint North developer concerning the site adjacent to One White Flint North (OWFN).
On January 29, the Director, Office of Consolidation, met with staffs of the Montgomery County Department of Economic Development and the Montgomery Count The discussions covered Planning Board to brief them on recent developments.
GSA/NRC alternatives and potential actions for achieving consolidation of the NRC headquarters in light of difficulttes encountered in concluding negotiations for construction of the second building on the lot adjar.ent to OWFN.
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I Office of Nuclear Reactor Regulation Items of Interest Week Ending February 2,1990 CALVERT CLIFFS UNITS 1.AND.2 l
Pending final resolution of outstanding special team inspection / confirmatory action letter (STI/ CAL) and other start commitments, BG&E believes it will be ready to begin startup on 02/22/90 (Mode 4) with the plant in Mode 1 by
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03/08.
In addition to completing all outstanding STI/ CAL issues and other restart commitments, major work to be completed prior to Unit I restart includes-Instrument Air modifications, MOV refurbishment, evaluation of the flow adequacy for the SDC heat exchangers, resolution of low temperature over-pressure protection (LTOP) concerns, completion of many restart-related work requests and resolution of several nonconformance reports (NCRs).
An enforcement conference was held on 01/18/90 in Region I to discuss multiple omissions, deficiencies and errors by BG&E in assuring adequate reactor vessel LTOP at Calvert Cliffs 1/2. This issue is discussed in a combined Special
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Inspection Report dated 01/03/90.
l A meeting was held on 01/23/90 in Headquarters to discuss BG&E's request to license an independent spent fuel storage installation (ISFSI) at its Calvert Cliffs plant site. The request is in accordance with 10 CFR Part 72. Technical Specification changes associated with the Part 50 license will be required for the SFP crane and SFP boration during fuel transfer. These changes will be requested in the latter part of this year.
BG&E provided an Event Notification on 01/30/90 related to shutdown cooling heat exchanger tube rattling problems. BG&E is assessing the problem and preparing a 50.59 safety evaluation. The impact on Unit I restart is not known at this time.
PEACH. BOTTOM.. UNITS.2.AND.3 On January 28, 1990, the operators rapidly reduccd power on Unit 3 from 100 percent power due to a fluid leak in the electrohydraulic control.(EHC) system for the main turbines. The reactor was manually scrammed from about 50 percent power when efforts to makeup the EHC fluid reservoir failed to restore EHC fluid level. Following the reactor scram, a primary containment isolation system group II/III actuation occurred when reactor water level decreased below zero inches. Per procedure, two feedwater pumps were manually tripped. When the third feedwater pump tripped on high reactor water level, the operators used RCIC and HPCI to control reactor level. Due to the imminent loss of EHC, the operators worked to reduce reactor pressure using the turbine bypass valves. As a result of the transient caused by the initial power reduction to 50 percent, the reactor scram, and reactor depressurization, two additional group II/III actuations occurred due to reactor water level fluctuations. The l
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FEBRUARY 2, 1990 ENCLOSURE A
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reactor was depressurized to about 600 psig using the main condenser as the heat sink, prior to removing the EHC system from service. The EHC leak was repaired and the decay heat removal path to the main condenser was reestablished within a few hours after the reactor scram.
Unit 2 had been shutdown from 100 percent power on January 27 to repair a leak ontheoneinch"B"feedwaterpumpdischargeflowinstrumentline. As of 6:00 a.m. on January 31, the licensee has completed necessary repairs and restarted both units with Unit 2 at about 65 percent power and Unit 3 in the i
startup mode at about 3 percent power. The resident inspectors are monitoring l
licensee corrective actions.
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In response to the Unit 3 event notification, a team of AEOD staff members and contractors plans to visit the site from January 31 thru February 2,1990 to
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evaluate human factors considerations in the operators' response to the i
event. This is part of a generic NRC evaluation sponsored by AEOD which will include about a dozen plant events. An NRR representative is planning to accompany the team.
Tennessee Valley Authority the Associate Director for Special Projects issued with the j
On February 1 concurrenceoftheCommission,aSeverityLevelIIINoticeofViolationto TVA. The subject of the NOV was a series of material false statements made by Mr. Herbert Sanger, then General Counsel to TVA, to the Commission in a March 1986 meeting and to 01 investigators shortly thereafter.
No civil penalty was assessed because TVA implemented extensive remedial action, Mr. Sanger has since left TVA and his responses were not discussed or concurred in by other TVA executives.
Licensee Certification:. implementation.of.FFD. Rule Letters certifying implementation of the Fitness-for-Duty rule have been received from all except one of the power reactor licensees. The one exception has confirmed that the certification letter has been forwarded. Of the responses received. 27 sites did not report more stringent measures than required by the rule, and 46 sites implemented more stringent cutoff levels and/or are testing for additional substances.
Diablo Canyon has responded that they are in compliance as far as the temporary restraining order pertaining to random testing will allow.
Canadian Visit to. Discuss.Darlington CANDU NRR staff is meeting this week with the Canadian AECB and consultants to discuss the delay in licensing of the Darlington CANDU Plant due to computer software issues. Darlington uses computers on all protection and control systems.
FEBRUARY 2, 1990 ENCLOSURE A
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NTOL AND RESTART SCHEDULE 2/2/90 1.
Schedule for NTOL plants:
INITIAL FULL PLANT LOW POWER CRITI-COMMISSION POWER I
AUTHORZTW CALITY.
BRIEFING..
AUTHORZTW COMANCHE PEAK 1 2/90E 2/90E 3/90E 4/90E SEABROOK 5/26/89C 6/13/89C 1/18/900 2/90E II. Schedule for RESTART plants:
COMMISSION NRC STATUS RESTART PLANT-S_HUTDOWN BRIEFIWG -.
DECISION PLANT. RESTART BROWNS FERRY 2 P.'; 5/84C 4/90E 5/90E 5/90E NINE MILE POINT 1 12/19/87C 3/90E 4/90E 4/90E l
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FEBRUARY 2, 1990 ENCLOSURE A l^^
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Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending February 2,1990 SAFEGUAROJ International Uranium Recovery. Project.at. General. Electric (GE).. Wilmington.. North Carolina The International Atomic Energy Agency (IAEA) was informed of plans by GE to recover uranium from on-site lagoons that had been previously discarded as waste.
IAEA agreement with a proposed procedure for returning the recovered uranium to the facility's ledger has been requested.
Transportation Package. Supplier Inspection On January 22-25, 1990, a quality assurance inspection was conducted at the General Electric Co., Vallecitos Nuclear Center in Pleasanton, CA, by members of the Transportation Branch supported by two inspectors and a radiography specialist from Idaho National Engineering Laboratory. The inspection focused I
on quality assurance in the fabrication, materials control, maintenance and repair of transportation casks with certificates of compliance issued by the NRC. A number of nonconformances with 10 CFR 71 requirements were identified by the inspection team.
INDUSTRIAL AND.HEDICAL.WUCLEAR. SAFETY Materials Licensing Installation and. Operation.of.the.Second. Thermal.Weutron. Activation.(TWA).
Explosive Detection. Device at. Miami InternetionaL Airport On January 29,1990, Pan American World Airways began operational scanning of international checked baggage with the Science Applications International Corporation (SAIC) TNA device, Model EDS-3, at the ramp level of the Miami International Airport in Miami, FL.
Several legal concet u from Pan l
American delayed the installation of the device almost five months after it l
wasdeliveredfromtheFederalAvlationAdministration(FAA), Pan American l
finally obtained full liability protection regarding future radiation lawsuits l
from the manufacturer, SAIC. The E05-3 device will screen checked luggage onto approximartely 20 flights a day from Miami to London.
Fuel. Cycle Safety Atomic. Vapor Laser Isotope. Separation.( AVLIS). Program. Briefing On January 25, 1990, the Department of Energy and Lawrence Livermore National Laboratory program managers for the uranium Atomic Vapor Laser Isotope Separation (AVLIS) project briefed the Nuclear Material Safety and Safeguards Director and staff on the plan for demonstration, transition, and deployment of FEBRUARY 2, 1990 ENCLOSURE B
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AVLIS technology. The plan, which is intended to lead to lower cost production of enriched uranium, had just been submitted to Congress by the Secretary of J
Energy. In the briefing, the program managers emphasized features of the plan i
that would involve NRC licensing of an AYLIS production facility, which they believe will be mandated by Congress. The licensing-related schedule appeared to be optimistic, particularly in view of the need for conducting site selection and environmental review activities prior to submitting a license application in about one year.
Duke. Power License.for. Dry. Storage.of. Spent. Fuel.Under.10.CFR.Part.72 l
On January 29, 1990, the Nuclear Regulatory Commission issued a license for dry storage of spent fuel under 10 CFR Part 72 to Duke Power Company for an independentspentfuelstorageinstallation(ISFSI)locatedatitsOconee Nuclear Station site. The ISFS1 is a concrete module and stainless steel system. A total of 88 modules containing 2112 pressurized water reactor spent fuel assemblies is authorized.
West. Valley. Demonstration. Project TheDepartmentofEnergy(DOE)hasdecidedtobuildaninterceptiontrench i
adjacent to the old reprocessing facility burial ground at West Valley, NY, 1
to prevent buried reprocessing solvent from reaching a nearby creek. During the period when the reprocessing plant operated, from 1966 to 1972, the operator disposed of dearaded solvent (basically kerosene with some additives) by pouring it in tanks ?illed with sorbeit material and burying the tanks.
Twenty-two tanks are known to have been buried in eight locations in the burial ground.
Solvent was first detected leaking from the burial ground in 1983.
In response, DOE exhumed the tanks from two of the eight locations, and found closed and mostly empty. Funds from the West them to have been inadequately (WVDP) were used for the exhumation.
Valley Demonstration Project In 1988 solvent was detected in a monitoring well on a different side of the burial ground.
In November 1989 solvent was detected anew in the area of the 1983 leak. On January 9,1990 DOE informed us that they will use WVDP funds to build an interception trench between the burial ground and the nearest cm aks.
New York State, the site owner, has agreed that this should be done. The L
parties have not agreed on the larger remedial actions that should be taken to prevent future solvent leakage.
The NRC staff has reviewed DOE's pitas for the interception trench, and has agreed that the trench is an apprepinte way to stop the spread of leaking solvent. A letter was sent to DOE stating our support for their hetion. The staff will visit West Valley during the stage of trench construction when the main features of the trench will be most accessible for examination.
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FEBRUARY 2, 1990 ENCLOSURE 8 i
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Office of Nuclear Regulatory Research Items of Interest Week Ending February 2,1990 Integrity.of. Reactor Components ACRS. Structural. Engineering. Subcommittee. Meeting On January 24 and 25,1990 the ACRS Structural Engineering Subcommittee reviewed Structural and Seismic Engineering Branch (SSEB) research programs related to containment performance and building response. The meeting was held in Albuquerque, NM. Dr. James Costello and Roger Kenneally represented the SSEB, The meeting began at 1:00 PM on January 24. The afternoon of the 24th and morning of the 25th were devoted to presentations of aspects of the Containment Performance Research Program. After introductory remarks by J. Costello, Dr. M. Amin, Sargent and Lundy, summarized the results of an analytical study l
of the resistance of containment structures to seismic loads beyond design basis. A summary of the test to failure of a model of the Sizewell "B" 1
containment, performed in the UK by the Central Electricity Generating Board, was then provided. Mr. R. Dameron, ANATECH Corporation, described the i
analytical prediction and dr. D. Horschel, SNL, described the test model and procedure. Dr. M.B. Parks, SNL, summarized the results of a series of test programs on penetration failure modes and outlined plans for the latest program on bellows failure modes.
In the area of building response two programs were reviewed: Seismic Category I Structures Program (FIN A7221), and Assessment of the Effects of Structural ResponseonPlantRiskandMargins(FINA1851).
C. Farrar, LANL, described the results of tests performed on models of building segments during the past 4 years. Unlike the data from earlier tests (1980 - 1985) which rep (orted thatapproximate structural stiffness was much lower than analytical predictions 25% of theory) data from the recent tests are within 70 - 100% of theory. A report on the last phase of these tests will be distributed for staff review in i
February. The ACRS questioned if these results will be fattved into the review of advanced reactor designs. Current analytical methods do not require an enveloping analysis to cover the reported differences in stiffness. NRR was advised of the ACRS coment. The ACRS was also informed that these test data i
l are being used by the American Society of Civil Engineers (ASCE) working group
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on structural stif fness to develop new analysis procedures.
C. Farrar and R.
Kenneally are members of the working group.
M. Bohn, SNL, described how the differences in structural response effected deterministic (design-like) and probabilistic calculations. The evaluation was I
made using the Peach Bottom NUREG-1150 analysis.
Basically, core damage frequency estimates from PRA results increased 60% (from 7.66 E-05 to 1.24 E-04 per year); design loads (shear and bending moment) increased 16 - 30% due to the reduction in building stiffness. Two more plants will be evaluated: Zion j
and possibly Maine Yankee. The ACRS supported this effort and requested a i
briefing after the other analyses are completed.
i All presentations were well received by the subcomittee. No further actions were requested of the staff.
FEBRUARY 2, 1990 ENCLOSURE C i
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i Resolving. Safety. issues.and. Developing. Regulations The. Probability.of Liner. Failure.in. Mark LContainment An approach using a probabilistic framework for resolving the BWR Mark I containment liner meltthrough issue was developed for the NRC by professor T. G. Theofanous of the University of California, Santa Barbara. Using hi:-
probabilistic framework, Professor Theofanous estimated the containment liner meltthrough probability for the flooded drywell case to be approx. I x 10-3 (conditional on core melt). For dry case the probability of failing the linee is almost 1 (conditional oh core melt). A draft NUREG/CR-5423 report has been issued for broad peer review.
A briefing for the Nuclear Safety Research Review Comittee is scheduled on February 13, 1990, at the Guest Quarters Hotel in Bethesda, Md. We-are also planning to brief the ACRS Severe Accident subcomittee and the full comittee, if desirable, following the completion of the peer review. After factoring the peer review and ACRS coments we will make any necessary final recommendations to the Comission on the Mark I liner meltthrough issue.
Meetina.with.Technogram On January 25, 1990, representatives from the Office of Research (Beckjord, Wilson, and Caron) and NRR (Scaletti and Yoshida) met with Michel Rozenhole and Jean Paul Crette of Technogram. Technogram has been hired by ElectricitedeFrance(EDF)toinvestigatevarioustechniquesanddesigns that could possibly be implemented in the nuclear power plants which EDF will build around the year 2000. The discussions focused on our licensing procedures for design certification and our review of the Advanced Boiling Water Reactor and the Simplified Boiling Water Reactor.
Meeting.with NHB. Technical. Associates On January 30, 1990, representativesfromtheOfficeofResearch(Williams, King, Landry, and Flack) met with Greg Minor and Ricnard Hubberd of MHB 1
i Technical Associates. MHB has been hired by the Union of Concerned Scientists to perform a study of selected advanced reactor designs (MHTGR, PRISM, and AP600). The discussion focused on the staff's draft SERs on MHTGR cnd PRISM.
i Also present at the meeting was Brent Sadauskas from Bechtel-Gaithersburg, representing the MHTGR community.
j TN!-Vessel. integrity. Program RES, in cooperation with the OECD/NEA, is removing metal samples from the TMI Unit 2 reactor vessel bottom head for metallurgical examination and analysis.
The 30-day work window inside the TH1 Unit 2 containment for cample removal began Tuesday, January 30. The contractor, MPR Associater., is to r cove a minimum of 8 samples from the inside surface of the TMI-2 reactor vessel. The samples are being cut from the vessel by electric discharge machining process.
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3-Initial cutting problems have been experienced involving the electrical system, the flush water system to the cutting electrodes, and the plant air supply system that vibrates the electrodes to make and break the arc. The existing electrical contact between the vessel and the power equipment was not sufficient to permit the equipment to work properly. The ground return was reestablished via an intact incore instrument nozzle in the lower head of the vessel, and several aeditional electrical fixes were made to correct these problems.
j Problems with the flush water, traced to fittings incorrectly tightened, have been corrected. The plant air supply system was blown down and found to contain a large quantity of water. The system has been cleaned out and air dryer equipment installed.
Cutting resumed at 6:30 a.m., February 5, 1990. The contractor estimates that it will take 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> to remove the first sample.
9 The TMI vessel integrity work is jointly funded by the U.S. and ten partner countries under the auspices of the OECD/NEA.
Recently Issued. Documents 1.
Medical Use.of Byproduct. Material:. Proposed. Amendments-and.Oraft Regulatory Gulde The NRC has proposed amendments to 10 CFR Part 35, " Medical Use of Byproduct Material," that would require medical use licensees to establish and implement a basic quality assurance program and that would modify the reporting and recordkeeping requirements. The NRC is developing Draf t Regul6 tory Guide OG-8001, "Dasic Quality Assurance Program for Medical Use," for guidance on the proposed i
Section 35.35.
Contact:
A. Tse, RES (492-3797) 2.
Draft. Regulatory Guide.DG-3002
" Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning under 10 CFR Parts 30, 40, 70, and 72" Comments requested by March 30, 1990.
Contact:
K. Steyer, RES (492-3824) 1 l
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ENCLOSURE C FEBRUARY 2, 1990 1
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Office for Analysis and Evaluation of Operational Data Items of Interest I
keek Ending February 2,1990 j
l Division.of. Operational. Assessment.(00A) i On February 1, a staff member from IRB attended a meeting of the Ad hoc Subcommittee of the Federal Radiological Emergency Response Plan (FRERP)
Revision Work Group to discuss revisions to the FRERP.
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The first three workstations for the Emergency Response Date. System (ERDS) were
- 11vered to the Operations Center this week and have been installed. The coainder of the system is scheduled for deliver in April 1990. Thus far, we have had 14 licensees, comprising of 38 units, volunteer for the ERDS program.
Initial data transmission tests have been successfully completed with the contractor for Palisades and with Oyster Creek.
On January 30-31, the Training Advisory Group (TAG) had an extremely productive meeting at the TTC. All regions plus NRR, HMSS, RES, AEOD, OP, and GPA were represented at the meeting. A number of training issues were discussed including the following:
recommended interim changes to the NRC Inspection Manual Chapter 1245 training requirements for reactor inspectors; the need for and timing of a meeting in the short-term to discuss the job requirements of reactor inspectors and associated; detailed training requirements; more detailed look at the training requirements for Headquarters technical positions; the simulator upgrade project; increasing risk-based specialized technical training updates; incident response training issues; the health physics # curriculum; Combustion Engineering simulator training; long-range plans for inspection team training; and long-range plans for human factors research.
Preliminary Notification The following Prelimir.vy Notifications were issued during the past week.
PNO-I-90-07, Public Service Company of New Hampshire (Seabrook Station),
a.
Fitness for Duty Suspension From Work.
b.
PNO-III-90-06, Solar Testing Laboratories Licensee Emergency Inc., Stolen Moisture-Density Gauge.
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FEBRUARY 2, 1990 ENCLOSURE D
9 Items of Interest Office of Governmental end Public Affairs Week Ending February 2,1990 State. Programs 1111 nots. Radiation. Control. Program Review l
B. J. Holt, Region III State Agreements Officer, began a review of the i
Illinois Radiation Control Program on January 29, 1990 in Springfield, l
1111nois. Vendy Miller, Assistant Director, State Agreements Program, will assist Ms. Holt on a portion of the review and the exit meeting.
The review is scheduled to continue through February 9,1990.
Meeting.with. Governor-of.0hio A. Bert Davis, Region III Administrator, and Region III staff met with Ohio Governor Richard Celeste and members of his staff on January 30, 1990 in Columbus, Ohio. The purpose of the meeting was to discuss the recent series of gaseous releases as a result of loop seal failures in the off-gas system at the Perry Nuclear Power Plant and other issues of interest.
Technical. Training. Center. Advisor _v. Group.Meettna Vendy Miller, Assistant Director for State Agreements Program, attended the Technical Training Center Advisory Group meeting on January 30-31, 1990 in Chattanooga, Tennessee. Th purpose of the meeting was to discuss and coordinate NRC and Agreement State training needs.
North Carolina. Review Visit.on.LLW Program l
R. L. Wuodruff, Region II State Agreements Officer, conducted a review visit of the North Carolina LLW program on January 30-31, 1990 in Raleigh, North Carolina. The purpose of a review visit is to assess the status of the State's program and to assist the State in preparing for a J
routine review.
Meeting with Vermont. State-Liaison.0fficer Marie Hiller, Region I State Liaison Officer, met with William Sherman, nuclear engineer with the State of Vermont and State Liaison Officer designee, on January 31, 1990 in Montpelier, Vermont. The purpose of the meeting was to discuss the status of Vermont's activities with regard to Vermont Yonkee.- Ms. Miller also toured the LLW storage facility at i
Vermont Yankee. The Vermont Yankee SALP l'anagement meeting was held in Vernon, Vermont on January 31, 1990, FEBRUARY 2, 1990 ENCLOSURE E 4
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l Neeting.with.New. Hampshire State Liaison Officer Marie Miller, Region I State Liaison Officer, met with Georga Iverson, Director of the New Hampshire Office of Emergency Management and State Liaison Officer, on February 1, 1990 in Concord, New Hampshire. The purpose of the meeting was to discuss HRC concerns with the New Hampshire Agreement State program, State /NRC communications and organization and future State observations at Seabrook. Geoffrey Huntington, Assistant Attorney General, also participated in the discussions.
I South. Carolina. Governing Board.Neetino Robert Trojanowski, Director of Region II State and Government Affairs Staff, attended the Governing Board of the South Carolina Department of Health and Environmental Control meeting on February 1,1990 in Columbia, South Carolina. The Board received a recommendation from Department staff on States found not to be in compliance with the 1990 milestone of the low-Level Radioactive Waste Policy Amendments Act of 1985. The Board accepted the DHEC staff recommendation that Vermont, New Hampshire, Rhode Island, Puerto Rico and the District of Columbia were not in compliance.
This action results in denial of access to the Barnwell LLW disposal facility. At present, LLW generators in New Hampshire (except Seabrook) and the District of Columbia dispose of their waste at the Beatty LLW disposal facility under contract with the Rocky Mountain LLW Board. A contract with Rhode Island for access requires approval by the Rocky Mountain LLW Board. Vermont and Puerto Rico have been denied access to the three disposal sites since 1988 for not being in compliance with the 1988 milestone.
A contract between Vermont and the Rocky Mountain LLW Board for access to Beatty through 1992 awaits approval by the Vermont legislature.
Meeting.with Massachusetts.LLW.0ff tetal 54arie Miller, Region I State Liaison Officer, met with Carol Amick, l
Executive Director of the Massschusetts LLRW Management Board, on February 2,1990-in Boston, Massachusetts. The purpose of the meeting t
was to discuss the status of LLW issues in Massachusetts.
International. Programs Commission Visit On Friday, Dr. Kunihiro Uematsu, Director General of the Organization for Economic Cooperation and Development's Nuclear Energy Agency, met with Chairman Carr, Commissioners Rogers and Remick, GPA Director H. Denton, and NRR Director T. Murley to discuss NRC's participation in NEA safety activities.
FEBRUARY 2, 1990 ENCLOSURE E
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Office of Administration Items of Interest Week Ending February 2,1990 Significant.FO!A.ReQuehts. Received by.the.WRC.for.5-Day Period January 26 - February... 1990 Request for a copy of the proposal in response to solicitation
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No. RS-IRM-90-191. (Michael Briers, C&P Telephone Company F01A-90-38)
Request for four categories of records related to SECY-89-248, "Rulemaking on Sequestration of Witness Interviewed under Subpoena / Exclusion of Attorneys,"
and two categories of records related to the OIG report regarding Roger Fortuna.
(Susan Bevill of Balch & Bingham, F01A-90-40)
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j Office of Information Resources Manegement Items of Interest Week Ending February 2,1990 I
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Workload Information and Scheduling Program-(WISP)
The second part of the IRM/NRR walkthrough of the Schedule Module for WISP was completed on January 25, 1990. Once the changes derived from the walkthrough are documented, the requirements for the Schedule Module will be complete.
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2.
NUDOCS/AD.Trainion l
On January 30, 1990, a meeting was held to discuss the issues and status l
of NUDOCS/AD training.
In attendance were representatives from the Document Control Branch, Informetion Technology Services Branch, the ITS Training Laboratory contractor, the Office of Personnel and the NUDOCS contractor (Statistica). The discussion covered the ITS Training Laboratory /Statistica interf ace in preparing suitable instruction material and support. We anticipate access to the s l
able by February 2, in the form of six (6) ystem by the ITS to be avail-dial up ports that will not be subject to time-outs. The training will use an abbreviated, demonstration database to assure minimal effect of potentially heavy traffic. Based on the meeting, it is anticipated that pilot training (with ten users) will be conducted on February 7.
Full implementation of the ITS Training schedule should commence within three weeks.
3.
NUDOCS/AD. Implementation l
As a result of a disk drive failure, NUDOCS/AD ex >erienced an unexpected period of dowa-cime over the last week. During t11s period, NUDOCS dato was loaded into the system, and two enhancements to the system were implemented that should improve response time. Additional processor L
memory and an additional central processing unit (CPU) board were added to I
the Data General MV/20000 computer system.
4.
IRM Survey.
On January 25. the first mailing of the IRM survey to randomly selected NRC employees began. A total of 600 questionnaires were raalled to employees from every office. Responses are due to be mailed back to IRM by February 5; 165 have already been returned. The survey is designed to determine NRC staff awareness of IRM services, assess the level of user satisfaction, and identify potential areas for improvement.
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DNB. Review.of Fitness.for. Duty Rule The Office of Management and Budget (DMB) has not granted a clearance for the information collection requirements contained in 10 CFR 26, " Fitness for Duty." An interagency meeting involving the National Institutes of Health Health and Human Services, National Institute on Drug Abuse, the Office of Management and Budget, and NRC is being scheduled to seek resolution of OMB's issues.
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Office of Enforcement Items of Interest Week Ending February 2,1990 l
i Significant. Enforcement Action A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $30,000 was issued on January 25, 1990 toTVElectric(ComanchePeak). The
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action was based on multiple violations identified by an AIT after the applicant experienced a backflow event through Auxiliary Feedwater system checkvalves on April 23, 1989. The violations involved two instances of operator failure to follow system lineup procedures during hot functional testing and four examples of inadequate corrective actions for identified deficiencies. Had these incidents occurred during plant operation, they would likely have constituted a significant problem relating to the operability of the auxiliary feedwater system.
- However, because substantial construction activities were still underway during the conduct of the hot functional testing, it was concluded that these events should be judged against the examples in Supplement II, Part 50 Facility Construction, of the Enforcement Policy. The violations cited do not appear, even in the aggregate, to fit the examples for a Severity Level III issued under Supplenent II, but are clearly of more than minor safety significance. Therefore, the violations have been characterized as Severity Level IVs, with a proposed civil penalty due to the applicants prior history of procedural violations and weaknesses with their corrective action. No escalation or mitigation was applied, as these factors were considered in proposing the civil penalties.
(EN90-008)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $75,000 was issued on January 26, 1990 to Carolina Power and Light Company (Brunswick Units 1 and 2). The action was based on failures to promptly identify and correct deficiencies in the service water system involving over temperatures of pump motors and diversion of flow to nonsafety-related loads.
The failure to correct the overtemperature problem resulted in the failure of one of the nuclear service water pump motors and the failure to correct the flow diversion problem may have resulted in not being able to provide adequate cooling to the diesel generators. The escalation and mitigation factors of the Enforcement Policy were considered and the civil penalty in this case was escalated 50% because the licensee failed to recognize the safety significance of the issue and initiate prompt corrective action until the DET questioned the licensee's evaluation and corrective action.
(EN90-009)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $100,000 was issued on Janu6ry 31,1990 to Coninonwealth Edison Company (Zion). The action was based on ttt. failure to properly consider the role of the Emergency Diesel Generator (EDG) ventilation support system, which is required by the FSAR but not directly included in technical specifications, when making EDG operability determinations. The civil penalty was escalated because the NRC 1dentified the failure of the licensee to consider the room cooling function of the EDG ventilation system prior to disabling it on all EDGs for over one month. The civil penalty was further escalated for prior notice and poor past performance. The licensee had raised specific questions concerning the ventilation system and had prior opportunity to resolve the issue, but failed to do so. The licensee was also previously cited for past A 50% mitigation was failures in maintaining FSAR referenced safety (functions.EN90-010) applied for the proposed corrective actions.
FEBRUARY 2, 1990 ENCLOSURE L
2 Civil. Penalty Paid Yale New Haven Hospital, New Haven, Connecticut paid the civil penalty in the enount of $1,250. The action was based on an NRC inspection in which violations involving the improper disposal of a brachytherapy source, as well as failures to perform adequate inventories or surveys which could have prevented the improper disposal, were identified.
(EA89-119)
Mayaquez Medical Center, Mayaquez, Puerto Rico paid the civil penalty in the amount of $500. The action was based on numerous violations that, in the aggregate, were considered to represent a significant breakdown in management control of licensed activities.
(EA89-33)
Iowa Electric Light & Power Company (Duane Arnold) paid the civil penalty in the amount of $50,000. The action was based on the licensee's failure to take adequate corrective actions for previously identified environmental qualifica-tion (EQ) violations for which the licensee was given a civil penalty and for a number of other EQ violations that were identified.
(EA89-215)
Correction in the Weekly dated January 19, 1990 it was stated that Veterans Administration Medical Center, Brooklyn, New York paid the civil penalty in the amount of
$8,750. That is incorrect. They responded to the Notice of Violation and Proposed Imposition of Civil Penalty.
(EN89-107) i FEBRUARY 2, 1990 ENCLOSURE L
I Office of Consolidation Items of Interest Week Ending February 2,1990 Second Building Status The General Services Administration (GSA) solicited expressions of interest for development of alt *rnate sites along the Red Line between Grosvenor i
Station and Rockville Station for NRC's second building after it appeared
+
that the negotiations for construction of Two White Flint North were breaking down. GSA received several proposals, at least one of which is receiving serious consideration. At the same time, negotiations are continuing between i
GSA and the White Flint North developer concerning the site adjacent to One White Flint North (OWFN).
On January 29, the Director, Office of Consolidation, met with staffs of the h ntgomery County Department of Economic Development and the Montgomery County Planning Board to brief them on recent developments. The discussions covered GSA/NRC alternatives and potential actions for achieving consolidation of the NRC headquarters in light of difficulttes encountered in concluding negotiations for construction of the second building on the lot adjacent to OWFN.
OWFN. Cafeteria Work on the cafeteria is approximately 50% complete with the installation last week of drywall, kitchen grill exhaust hood, and the beginning of floor tile installation. The revised plan for the cafeteria calls for installation of i
equipment that will make it possible to provide a selection of grilled, fried and other hot foods in addition to pizza, hot dogs, soups, salads, I
yogurt, made-to-order sandwiches, packaged sandwiches, desserts, snacks and beverages.
l l-FEBRUARY 2, 1990 ENCLOSURE M l
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Region !
Items of Interest Week Ending February 2,1990 1.
CinttchemcInc.
On December 12, 1989,.Cintichem, Inc., Tuxedo, New York, reported the disci,very, on November 28, 1989, of singhtly contaminated water in an onsite storm drain. No releases to offsite environs were identified.
Cintichem produces radioactive isotopes for the pharmaceutical industry.
Following a Region I inspection of the licensee's actions and analytical results, the licensee issued a letter dated December 28, 1989 which confirmed commitments to investigate the source of the contamination and identify corrective actions. An informational meeting involving NRC and the State of New York was held at the Tuxedo site on January 2,1990 to discuss potential sources of the contamination, actions taken to verify.
and/or correct these sources, a plan of action for continuad corrective measures, and identification of the licensee skills and resources needed to accomplish the planned actions.
Another informational meeting was held by NRC and New York State representatives on January 25, 1990 with the Tuxedo New York, Town Board. Board members were informed of the roles of New York State and the NRC in the contamination problem and of actions by NRC to follow the licensee's investigation. NRC agreed to keep the Town officials informed relative to the contamination problem.
Review of recent analytical data indicated that there continues to be no evidence of offsite releases from the facility. The licensee informed the NRC on January 31 that the source of the contamination may have been identified and efforts to confirm this are underway.
2.
Susquehanna.Requalification. Examination First " Alternative.B" In_ Region 1 InaccordancewiththeCommissionapprovedstaffpaper(SECY89-55)on four alternatives for reducing the level of examiner resources necessary for conducting requalification examinations under 10 CFR 55, the approved
" Alternative B" (i.e., one examiner evaluating two candidates on selected portionsoftheexamination)wasusedfortherequalificationexamination conducted at Susquehanna during the January 22, 1990 week. This requali-fication examination is the first in Region ! using Alternative B.
This examinationalsoevaluatedthelargestnumber(20)ofcandidatesinRegion I f or a one-week requalification examination. The results indicate that this alternative is a viable method for reducing the examiner resources.
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j Region I Items of Interest Week Ending February 2,1990 i
3.
Calvert Citffs A supplement to the Confirmatory Action Letter under which Calvert Cliffs is restrained from restart was issued February 1,1990, by the Regional Administrator, Region I.
The licensee has agreed to conduct an assessment of the status of completion of several prior licensing commitments as a result of having failed to implement six associated with a 1978 Low Temperature Overpressure Protection program and to report results prior to restart.
4 Seabrook On Tuesday,1/30/90, Mr. Fred Anderson, Jr., President of ideas and Information, Inc., Exeter, New Hampshire, provided, in response to an NRC subpoena, copies of 202 tapes he made of control room transmissions in 1989 and 1990. The Region I staff is reviewing the contents of these tapes for any possible safety or security problems. Arrangements are being made to make transcripts of these tapes.
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Items of Interest Region II Week Ending: February 2,1990 i
1.
Duke. Power. Company On January 30 and 31, the Regional Administrator, acccmpanied by i
Region II and NRR staff, was at the McGuire and Catawba Nuclear Power Stations, respectively, to present the SALP assessment findings to Duke power Company representatives.
1 On January 31, the Regional Administrator, accompanied by the Director, Office of Enforcement, and the Region II and NRR staffs, was at the Catawba Nuclear Power Station to meet with Dulo Power Company representatives to discuss the recently issued proposed escalated enforcement action which addresses a number of security
)
violations at each of Duke's plants.
2.
Florida. Power. Corpora tig3 On February 1, representatives of the Florida Power Corporation were in the Region II Office to attend an Enforcement Conference regarding the issues associated with the Crystal River Unit 3 high pressure safety injection system flow instrumentation, i
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Region III Items of Interest Week Ending February 2,1990 1
.1.
Perry Nuclear. Power Station A. Bert Davis, Regional Administrator, members of the regional staff, and the Senior Resident Inspector mot January 30,1990, with Governor Richard Celeste of Ohio in Columbes, Ohio, to review recent off-gas system release problems at the Perry Nuclear Power Station. Also attending the meeting were the Ohio Disaster Services Agency State Liaison Officer and the Ohio Public Utilities Commission Chairman, Region III offered to meet with the Governor after he expressed concerns about the off-gas releases.
2.
Duane Arnold.Eperny Center Mr. Richard W. McGaughy, Vice President - Production, Iowa Electric Light and Power Company, met with the Regional Administrator in the regional i
office on February 1, 1990, to discuss general topics related to the status of the Duane Arnold facility. The raeeting was held at Mr. McGaughy's request.
l 3.
American Radioiabeled. Chemical Region 111 ceceived a Petition for Limited Modification of Order Suspending Licenses. The petition requested that the licensee be permitted on an interim basis to purchase prepackaged materials from other licensed vendors for reshi) ment to their customers. This petition is currently being reviewed >y the Region til and Headquarters staffs. 'The licensee also requested a hearing on the Order.
4.
VA Medical Center.. Des.Noines.10wa On January 30, 1990, C. J. Paperiello, Deputy Regional Administrator, and members of the Region III staff conducted an Enforcement Conference to discuss: (1) eleven procedural violations identified durin inspection, (2) the licensee's corrective actions, ar.d (3)g a recent NRC enforcement i
options available.
l FEBRUARY 2, 1990 ENCLOSURE N
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Zion.Wuclear Power Station 1
On January 30,1990, enforcement discretion was granted by Region Ill, with NRR concurrence allowing a 40-hour extension to an action statement requirement prescribed by a February 29, 1980, Confirestory Oroer. That l
portion of the Order stipulates allowable diesel generator outage times 1
dependent on the number of diesel generator failures in the prior 100 i
tests. The Unit 1 diesel generators had experienced four failures which corresponded to an allowable outage time of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />. The Unit 1, 16 Diesel Generator was declared inoperable due to a failure of the air start system. This was the fourth failure in 100 tests, which would require
/
after the expiration of the 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> that the unit be brought to hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in cold shutdown within the i
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Relief was requested to complete the repair to the air start system and to perform the recuired operability run of the IB Diesel Generator in order to avoid seb;ecting the unit to an unnecessary i
s transient. This relief was based on the adoittonal knowledge of and changes in the regulatory position concerning diesel generator j
surveillance testing and reliability reflected in the Standard Technical Specifications and Generic Letter GL 84-15.
In cddition, each ESF bus is J
cepable of being powered from the System Auxiliary Transformer supplied i
by the off site distribution system, the Unit Auxiliary Transformer powered by the main generator or offsite power when in backfeed configuaration, a reserve feed from the opposite units 4 kv bus, and the diesel generator assigned to the associated ESF bus. Also, during the requested extenion, two diesel generators for Unit I and three diesel generators for Unit 2 will remain operable.
6.
Davis Besse Nuclear. Plant On January 26, 1990, at 8:46 am (EST), Davis-Besse tripped from 72 percent i
power after the reactor protection system (RPS) detected the loss of a reactor cochnt pump (RCP) due to a spurious signal caused during surveillance testing. All systems operated as required except two main i
steam safety valves (MSSV)RCS) letdown valve (MU-26) that would not reopen that failed to properly seat after lifting and a reactor coolant system L following the reactor trip. Regarding the MSSV, the operators promptly responded lowering secondary pressure by approximately 30 psig to reseat the two safeties. The RCS letdown valve was found to have a stem that separated from the valve disc. The plant is currently shut down and will 1
be commencing their four month refueling outage. Major activities planned for the refueling outage will be:
reactor vessel inspection; eddy current 1
inspection of the steam generator; main steam safety valve refurbishment; j
RCP motor overhauls; appendix R modifications; RCP seal modification; and control room human factor modifications.
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FEBRUARY 2, 1990 ENCLOSURE N 4
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Clinton Pedr. Station On January 26, 1990, Mr. A. Bert Davis, Regional Administrator, Mr. Edward G. Greenman, Director, Division of Reactor Projects, Mr. John Craig, NRR Project Directorate III-3, and members of the Region III and NRR staffs, met with Mr. Wendell Kelley, CEO of Illinois Power Company and members of his staff to discuss the results of.the Clinton Power Station SALP 9.
The licensee provided considerable comments as each functional area was discussed resulting in an effective dialogue between the NRC and Illinois Power Company. Members of the public and news media were present and interviews were conducted with both the NRC'and Illinois Power following the meeting.
r 8.-
'Duane.Arnolo Energy. Center On January 30, 1990, Mr. John A. Zwolinski,' Assistant Director for Region III reactors, NRR, Mr. H. J. Miller, Director, Division of Reactor Safety, Region III, Mr. R. Knop, Chief, Branch 3, Division of Reacter Projects, and other NRC staff members met with representatives of Iowa Electric Light and Power Company at headquarters.
Items discussed were the Duane Arnold engineering &pr.rtment reorganization, the extent of silting problems associated with the Cedar River and status of their HPCI improvement plan.
9.
Division.of.Reaftor. Projects i.
The section chief of Section 2B, Division of Reactor Projects Region
.III, traveled to the University of Wisconsin in Madison, Wisconsin for the purpose of interviewing 12 graduating seniors as prospective employees for Region III.
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R'gion IV
' Items of Interest >
Week.Ending' February 2,1990.
~ 1..- Mr. Thomas Roundtree of ICF Kaiser Engineers will be in the Region IV--
office on behalf of EPA Region VI to review the Fensteel docket file.
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-ICF Kaiser Engineers is a superfund contracter of EPA.
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Region-V Items of Interest Week Ending February 2,1990 l
1.
Ariruna. Nuclear Power.Rroject Commissioner Curtiss visited Palo Verde February 1, accompanied by Deputy Regional Administrator Bobby Faulkenberry. On February 2 the Commissioner visited San Onofre, where discussions focused on reliability centered maintenance.
2.
University.of.Wawait On January 26,1990, a management meeting was held by telephone conference with the University of Hawaii to discuss several deficiencies in their radiation safety program relating to the security of nuclear materials, monthly surveys of material use.. areas, and contamination of work surfaces.
The licensee was encouraged to take more effective corrective action and make more effective use of the audits by the Radiation Safety Officer.
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FEBRUARY 2. '990 ENCLOSURE N 1
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ITEMS ADDRESSED'BY THE COMMISSION - WEEK'ENDING-FEBRUARY 2, 1990 f
T l
k STAFF RE UIREMENTS'- BRIEFING ON NRC ACTIONS FOR CLEANUP OF CONTAMINATED UNDER NR ISDICTION, 2:00 P.M., THUR5 DAY, DECEMBER El,1989, COMMISSIONER 5' LL-CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC i
LN ATTENDANCE) SECY Memo topmes M. Taylor dated 1/31/90 l
1
'The Commission was briefed by the staff on its proposed strategy for cleanup of contaminated materials sites under NRC jurisdiction.
l The Commission requested the staff to:
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Submit a preliminary analysis of any implications of the BEIR-V report with respect to the Commission Policy l
Statement on Exemption from Regulatory Control.
The 4
analysis should also include recommendations on the need for further analysis of the BEIR-V report with respect to other Commission actions (e.g., Part 20, Clean Air Act).
.(Subsequent to the meeting, the staff submitted an analysis on January 10, 1990.)
L 2.
Submit a list of contaminated sites in order of priority including the name and location of the site, name of responsible. party,-condition of the site, schedule and description of the next step in site cleanup, and other pertinent information.
The list should be accompanied by l
a discucsion of criteria used to rank gggh site, i.
3.
Submit to the Commission any proposal to terminate a license at a site with significant. contamination within this coming year or where a site with such contamination has been cleaned for unrestricted release.
4.
Submit an estimate of the minimum time required to promulgate NRC requirements on residual radioactivity criteria.
Staff should expedite this rulemaking because the' requirements, once final, will provide licensees with an_ incentive to' complete site decommissioning rather than-
-the current situation which may encourage licensees to defer decommissioning pending issuance of NRC require-ments.
As part of the Federal Register Notice for this rulemakir.J, NRC staff should provide general notice to licensees that additional cleanup may be'necessary to comply with standards promulgated at a futura date by EPA.
In the interim before NRC requirements are in place, staff should provide notice to licensees that terminated licenses may be recalled and additional cleanup required if.forth-coming NRC requirements indicate a need for further-decontamination.
Once NRC requirements are in place, NRC should not needlessly raise uncertainties at the time of each license termination about the potential need for V
licensees to conduct additional decontamination to' meet future standards.
Unless additional decontamination is shown in the future to be necessary to protect human health and the environment, NRC decisions to terminat9 licenses are considered final agency actions as Ibng as licensees comply with all applicable standards in effect at the time of' termination.
FEBRUARY 2, 1990 ENCLOSURE P
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e consistent with this approach, the Commission directs.the.
staff-not to develop procedures to. provide notice to licensees'that' licenses terminated in accordance with NRC requirements may be recalled _if forthcoming _ EPA regulations indicate a need for: further decontamination.- In the event
-that EPA should develop residual radioactivity standards, staffashould emphasize to EPA the need either to grandfather f
those sites whose licenses have-already been terminated in accordance with NRC requirements prior to issuance of such standards or to demonstrate that EPA's standards result ~in' significant and justifiable improvement in protecting human health and the environment.
With respect to_the-possibility of forthcoming EPA standards, Commissioner-Curtiss expressed the-following view:
In lieu of the approach recommended by-the staff (i.e. to develop procedures to notify the-licensees that' terminated licenses may be recalled if the forthcoming EPA residual radioactivity standards indicate a need for further decontamination)
Commission Curtiss would direct the staff to provide that if a licensee complies with all applicable standards in effect at the time, the license should be terminated with a statement to that effect. - This approach will serve to expedite site decommissioning by giving the licensees an incentive to move forward with decommissioning, rather, than encouraging the licensee to defer action pending the issuance of final-EPA standards.
In the event that EPA should develop residual radioactivity standards, the staff should emphasize to EPA:that for.the sake of admin-istrative finality, provision should be made to grandfather sites for which licenses have already been terminated.
.5.
Establish a timeliness criterion (e.g., 3 years) for the completion of decontamination and cleanup activities after l-cessation'of operations.
As a first step staff should submit a plan for promulgating a. timeliness criterion.
The criterion'should be accompanied by a provision for a licenses to seek a variance for timing of cleanup based on a demonstration that compliance with the timeliness I
criterion-(1) is not necessary to ensure protection of My public health and safety or the environment; (2) is not technically achievable; or (3) would likely cause greater environmental or public harm than deferred cleanup.
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.The Commission rejected-the staff's recommendation to pursue discussions with the Environmental Protection Agency. (EPA): on the development of a protocol' governing the application of Superfund to contaminated sites..
Instead,-the staff should first consult with the Commission i
in.the'. event that-the need arises to consider the application of Superfund for any particular site.
At such-time,.the staff should submit a detailed discussion of the circum-stances at the'given site, the reason (s) that existing NRC regulatory. authority is inadequate, and theJobjectives that would.be served by the. application of Superfund to the given site.
The discussion should also include an analysis of (1) _the cleanup standard that would apply under Superfund and the difference between that standard and the Atomic Energy Act standard; (2) the rights'and authorities that the state would have if Superfund were extended to the site; and (3) the rights and authorities that private citizens would have to sue the Federal-government or the licensee (s) using~the citizens' suit provision of'Superfund.
B.
STAFF REQUIREMENTS 'IMMEDIATE EFFECTIVENESS REVIEW BRIEFING - SEABROOK, 9:00 A.M., THURSDAY, JANUARY 18, 1990 COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) Memo from SECY-to Taylordated 1/31/90 The Commission *-was briefed by the representatives of the New Hampshire: Yankee (NHY) Division of Public Service.of New Hampshire (PSNH) (Seabrook), the Commonwealth of Massachusetts, l~
the Seacoast Anti-Pollution League, the New England Coalition on Nuclear Pollution, and the NRC staff on the readiness of the y
Seabrook Nuclear Power Plant, Unit 1 to operate at full power.
l Representing PSNH were:
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- Edward A. Brown, President and CEO, NHY l-
- Ted Feigenbaum, Senior Vice President and l
Chief Operating Officer, NHY l-l
- Bruce Drawbridge y
Executive Director for Nuclear Production, NHY
- George Gram, Executive Director of Emergency ll Preparedness and Community Relations, NHY Representing the Commonwealth of Massachusetts was:
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- John Traficonte, Chief Nuclear Safety Unit Department of the Attorney General
- commissioners Curtiss and Remick were not present.
FEBRUARY 2, 1990-ENCLOSURE P
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l_B._. cont'ch-Representing Seacoast Anti-Pollution League was:
- Robert A. Backus Representing'New-England Coalition on Nuclear Pollution was:
- Diane' Curran u
Chairman Carr. requested that PSNH provide the Commission with the age of the oldest maintenance item in the corrective maintenance backlog and that the staff advise the Commission on J
when they plan to do a maintenance team inspection at Seabrook.
(Subsequently on January 23, 1990, the staff forwarded responses to Chairman.carr's questions.)
Chairman carr thanked the participants and indicated that he expected that the Commission would conclude its immediate-effectiveness review-and reach a decision on the pending
- adjudicatory matters-within two to three weeks.
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Congression'al Affairs CONGRESSIONAL HEARINGS SCHEDULE (CA).
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0CA DATE TIME' WITNESS SUBJECT COMMITTEE j ASSIGimENT F Combs 02/05/90 10:00 Non-NRC Nomination of Bartlett Senators Johnston/McClure to be Dir., Offc of_
Senate Energy & Natural Resources Civilian Radioactive g
Waste Mgent o
Gerke 02/07/90 TBA Markup H.R. 743, Negotiated Reps. Frank /Sensennbrenner Rulemaking Act Madden 02/08/90 9:45 Cosumission NRC's FY91 Authori-Reps. Udall/Har.sen zation Subc on Energy & the Environment House Interior & Insular Affairs Cos6s 02/22/90 9:30 Sec. Watkins DOE's Civilian Nuclear ' Senators Johnston/McClure Waste Program Senate Energy & Natural Resources.
Gerke 02/21/90 9:30 Mon-NRC S. 1742, Paperwork Senators Glenn/Roth Reduction Act
' Senate Governmental Affairs 02/22/90 Gerke 02/2//90 1BA Non-NRC Equal Opportunity Civil Service (Sikorski/Morella)-
Complaint Pro-House Post Offc & Civil Service cessing Empi Opportunities (Martinez /Gunderson)'
House Education & Labor Combs 03/08/90 9:30 Non-NRC DOE's Plan to Open Senators Johnston/McClure WIPP Senate Energy & Natural Resources 9 Combs 03/08/90 10:00 Mon-NRC DOE's Nuclear Waste, Reps. Bevill/Myers Uranium Enrichment Energy & Water Development P
Appropriations FY91 House Appropriations-y
" Callahan 03/20/90 TBA Jim Taylor Advanced Reactors Reps. Lloyd/Morrison x
Energy Research 8 Development House Science, Space & Technology i
Madden 03/21/90 10:00 Cossnission NRC's FY91 Budget Reps. Bevill/Myers Su':c en Energy & Water Development.
House Appropriations
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NRR MEETING NOTICES
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. 3j February 5,1990 APPLICANT /,
.yjDATE/ TIME
'MUMBER LOCATION PURPOSE ATTENDEES NRR' CONTACT' 2/7/90 White Flint Bldg.
Review and' discuss information NRC/GE-S. ?!ewberry-9:00-11:30 Room 108-11 presented by BWROG regarding Neutron Flux monitoring capability and plans for implementation of instrumentation that conforms to Regulatory Guide 1,97.
2h8/90 50-395 White Flint Bldg.
Discuss the inspections NRC/SCE8G-J. Hayes.
8:30-10:30 Room 148-11 associated with the implementation of Bulletins 79-02.and 79-14 V. C. Sumer Nuclear Station.
2/8/90 50-269/
Hatch Nuclear Plant Discuss the status of'various NRC/GPCo L. Wiens 8:30-4:00 270 licensing activities and safety Duke Power Co.
initiatives at Duke Power Company's and Georgia Power Company's nuclear stations included in PDII-3 area of responsibility.
2/9/90 White Flint' Bldg.
Discuss Appendix A of Chapter 1 NRC/EPRI/BNL T.:Kenyon 9:00-4:00
' Room 10B-11 of the EPRI Requirements Document, E2 "PRA Key Assumptions and Ground-P rules," that was submitted on
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July 3, 1989.
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- Copies of summaries of these meetings will be made ' publicly available and placed in the respective docket file (s) in the NRC and local public document rooms.
A listing of these meeting notices can be obtained by calling 492-7424.-
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NRR MEETING NOTICES c.
E February 5,1990
.i APPLICANT /
g g.DATE/ TIME NUMBER
' LOCATION PURPOSE:
ATTENDEES NRR CONTACT 2/8/90 White Flint Bldg.
-Discuss the results of recent MRC/Mortheast
.G.~Vissing 10:00-3:00
' Room 14B-13 steam generator tube inspection for Millstone Unit 2.
2/13/90 White Flint Bldg.
Discuss new control rod design.
NRC/GE S. Wu-8:30-12:00 Room 138 2/13/90 50-271 White Flint Bldg.
Routine discussion of scheduling NRC/ Vermont M. Fairtile 9:30-11:00 Room 14D-7 and prioritization of licensing Yankee Nuclear actions.
Power Corp.
2/14/90 White Flint Bldg.
Discuss the following items (1)
NRC/GE G. Thomas 9:30-12:00 Room 88-11 results of strategies with and without water level lowered to top of active fuel; (2) effects of power / flow / level oscillations on operator actions and fuel integrity; (3) pros and cons of i
revised heat capacity temperature limit (HCTL) for ATWS mitigation; (4) analytical capability needed to accurately model ATWS; (5)
E uncertainty in existing analyses.
P h2/15/90 50-390 Waits Bar Site The NRC staff will discuss with NRC/TVA R. Auluck g 1:30-5:00
. Spring City, Tenn.
TVA representatives, the staff's.
preliminary assessment of TVA's evaluation of the cable damage-c j,
e issue.
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APPLICANT /
NRR CONTACT:
1, DATE/ TIME
. NUMBER LOCATION PURPOSE
-ATTENDEES __
2/28/90 50-335/
White Flint Bldg..
' Discuss St. Lucie 1 and 2
. NRC/FP&L
. J. Norris.
1:00
. 389 Room 16B-11
. safeguards issues.
3/15/90
.50-269/
McGuire Nuclear: Plant.
Discuss the status.of various NRC/GPCo L. Wiens 8:30-4:00 270 licensing activies and safety
- Duke Pow'er Co.
initiatives at Duke Power Company's and Georgia Power Company's nuclear stations included in PDII-3' area of responsibility.
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l-February [2,.1990'
.n 2E WSS. Meeting Notices g
7 Division-of Safeguards-and Transportation g
e Docket
-Attendees /
Date/ Time Number Location Purpose Applicant NRC-CAstactj 2/14-16
. San Onofre, CA Briefing at the NMSS J. Higdon Western Association
. Meeting, SG Log Analysis Program 2/21-22 Lexington, KY Participate in 19955 E. Easton-Transportation DOE Contractors Coordination Group meeting, Office.of Civilian Radioactive Waste Management, DOE Division af.High-Level Waste Management Docket Attendees /
~
Date/ Time Number Location Purpose Applicant NRC Costact 2/6-7 Las Vegas, NV
- To discuss preliminary NMSS K. Stablein Yucca Mt., NV results of investi-
'RES ~
E gation on silica veins State of. Nevada P
DOE 1
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Djvision.of. Industrial.and Nedical.Muclear Safety
- :o Si Docket
' Attendees / -
?E.Date/ Time Numbec Location Purpose Applicant
'NRC Costact-2/2 OWFN Initial discuss Wq of
. MSS -
J. Swift-.
E 3-5 p.m.
-DOE plans for future DOE 8
- work on monitored NY State Officials-retrievable storage 2/6 Project West Valley, NY-Examine construction of MSS-D. Hurt-M-32 Interception trench at DOE
-West Valley buriali ground 2/6 Project Baton Rouge, LA Brief Louisiana Dept.
MMSS P. Loysen-M-45 of Environment Quality RIV~
Officials on LES LA Official et al.
Project and Uranium Hexafluoride 2/7 70-1193 OWFN To review status of MSS C. Sjoblom-12-3 p.m.70-925 6B-11 decommissioning on OGC-Crescent and Cushing RIV Oklahoma sites 2/7 OWFN Discuss licensing MSS T. Huffert 6B-13 requirements for source OGC materials with Heritage RI Minerals, Inc. & Nord Ilmenite Corporation mME 2/7-9 70-1113 Wilmington, NC To discuss license NMSS'
'R. Wilson-3 E
application at GE E
Wilmington.
.o 2/8 70-135 OWFN Review' licensing issues MSS
'P.'Loysen with Babcock & Wilcox B&h' Pennsylvania Muclear Service 0perations-4
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Docket Attendees /
[
Date/ Time q
Number Location irpose' Applicant-
- NRC. Contact' N
2/15 OWFN-Sub.ntttal of license NMSS S. Ruffin:
application for storage -PSC
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of. spent fuel under Part 72' at Putlic Service Co. of Colorado's
. (PSC) Fort St.'Vrain nuclear power plant site Division-of Low, Level Waste Management-and Decommissioning Docket Attendees /
Date/ Time Numbec Location'
- Purpose Applicant.
NRC.Costact 1/29-2/9 Raleigh, NC To participate in MSS J. Shaffner-Agreement States
- Program Reviews-2/1-2 Springfield, IL IDMS Agreement State NMSS
- J. Shaffner.
Review 2/5-7 Salt Lake City, UT Agreement State Review NMSS J. Shaffner.
2/25-3/01 Tucson, AZ Waste Management MSS L. Pittiglio 90 Conference
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- Docket Purpose.
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. MRC.
Contact:
s 5 'Date/ Time.
Musber Location.
m Director!s.0ffice
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Nuclear Safety.Research. Review Cossaittee-(NSRRC). Meetings
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2/13/90 Guest Quarters NSRRC Subcommittee meeting R. Shepard i'
Bethesda, MD (with Chairman Carr in attendance) 492-3723 i
Division.of. Engineering J. Vora 3/20-21/90 Bethesda Ramada Inn Nuclear Plant Aging
' 492-3854 Bethesda, MD Research (NPAR): Research Review Group Meeting a
i Division.of Systems.Research 2/15/90 NL/S 013 Analysis / Eval. of 2D/3D D. Ross~et al.
- G. Rhee-9:00 AM Program Test Results 492-3564 M. Cunningham.
3/8-9/90 Washington, DC LAttend MUREG-1150 Peer J. Murphy &
'~ 492-3 % 5
- Area Review Committee Meeting K. Cunningham n
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- February.2g 1990.~'
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di~ lE Region. I.i4eeting. Notices
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~ Docket Attendees /
i
?
-Date/ Time Namber
- Location Purpose ~
Applicant
.NRC. Contact 8 02/20/90 50-57 RI Office Management Meeting Licensee-'and Selected McCabe~
e-
'1:00 pm SUNY Buffalo RI Staff Members
~-
02/27/90 50-317 RI Office Requal Exam Meeting Licensee'and Selected-Cowgill:
1:00 pm.
50-318 BG&EC
-Calvert Cliffs RI Staff Members
^
03/06/90 50-244 RI Office Management Meeting ~
Licensee and Selected McCabe 9:00 am RG&EC - Ginna' RI Staff Members l
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Ell NEETING. NOTICE
.:g ATTENDEES /
E DOCKET.'
. PURPOSE-APPLICANT NRC. CONTACT-
[ DATE/ TIME NUblBER LOCATION ~
W$
02/15/90 RII Office Enforcement Conference Licensee DRA and selected Milhoan 10:00.a.m.
CP&L - Harris facility RII staff members 02/20/90 New Hill, NC, SALP Presentation - CP&L Licensee, RA, and selected Ebneter Harris facility RII and resident staff 02/21/90 RII Office Management Meeting Licensee, RA, and selected Ebneter.
10:30 a.m.
VEPCO RII staff 02/22/90 Hartsville, SC Chairman will~ visit Chairman, Tech. Asst.,
M11hoan Robinson facility for Deputy RA, and Residents site familiarization l
02/27/90 RII Office Enforcement Conference Licensee, RA and selected
.Ebneter 10:30 a.m.
VEPC0 - N. Anna facility l
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Docket Attendees Date/ Time Number Location Purpose Applicant
- NRC. Contact' G
02/07/90 50-346 Headquarters Toledo Edisori Company, Licensee, Deputy Regional.
Greenman g 1:00 pm Davis-Besse - Management Administrator and selected Meeting members of RIII Staff 02/08/90 50-461 Region III Illinois Power Company, Licensee, Regional Davis 9:00 am Clinton - Management Administrator and selected Meeting members of RIII Staff 02/09/90 50 440 Perry Plant Detroit Edison Company, Licensee.and selected Greenman 1:00 pm 50-441 Fermi Slanagement members of.RIII Staff Meeting 02/13/90 Headquarters Illinois Department of IDMS, EDO, GPA, Regional-Lickus 1:30 pm Nuclear Safety -
Administrator and selected Management Meeting members of RIII Staff
+
2/13/90 50-255 Palisades Plant Consumers Power Company Licensee and selected Greenman Palisades - Quarterly members of RIII Staff 1
Management Meeting 02/14/90 50-341 Fermi Plant Detroit' Edison Company, Licensee, Deputy Regional Norelius Fermi - Emergency Administrator and selected Prepare 4 mess Exercise members of RIII Staff 02/22/90 50-254 Quad Cities Plant Comunonwealth Edison Licensee, Deputy Regieral Greenman M
<;. 50-265 Company, Quad Cities Administratcr and selected m
G Systematic Assessment members of RIII Staff.
of Licensee Perfor1sence EN c,
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. Region IV Meeting. Notice-
-E Febrsary 2',1990 -
' si
~ 4 Docke't Attendees /.
- p'Date Nus6eg Location Purpose'
- Applicant..
RIV.Costact-
~
G 30-05965' RIV Firestone Tire & Rubber Company FT&R Mnget.
BBeach, LYandell, 8~ 2/02/90 (1:00) 35-13617 Enforcement Conference to discuss -
weaknesses in.their management of FT&R's radiation safety program.
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