ML20011E627

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Weekly Info Rept for Wk Ending 900202
ML20011E627
Person / Time
Issue date: 02/07/1990
From: Blaha J
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-900202-01, WIR-900202-1, NUDOCS 9002220046
Download: ML20011E627 (47)


Text

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i UNITED STATES l

NUCLEAR REGULATORY COMMISSION l

WASHINGTON, D. C,20sss

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INFORMATION REPORT-February 7, 1990 SECY-90-043 For:

The Commissioners j

From:

James L. Blaha, Assistant for Operations. Office of the EDO l

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 2, 1990 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

j Contents Enclosure Nutlear Reactor Regulation A

1 Nuclear Material Safety and Safeguaros B

Nuclear Regulatory Research C

Analysis and Evaluation of Operational Data D

Governmental & Public Affairs E

l General Counsel F*

3 Administration G

Information Resources Management H

Controller' s

Personnel J'

Small & Disadvantaged Business Utilization & Civil Rights K*

Enforcement L

Consolidation M

N Regional Offices r

Executive Director for Operations 0*

j ltems Addressed by the Commission P

Meeting Notices Q

Proprietary or Other Sensitive Information (Not for R

external distribution) l

  • No input this week.

DISTRIBUTION:

i Commissioners GPA M

OGC REG OFFICES res L. Blaha, ssistant for Operations

'OIG EDO

.fice of +.he Executive Director LSS ACRS for Operations pir'd 1

Contact:

ACNw I

James L. Blaha, OEDO ASLBP UOTE:

TO BE MADE PUBLICLY

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492-1703 ASLAP AVAILABLE IN 10 UORKING 9002220046 900207 SECY DAYS FROM THE DATE OF

$KL THIS PAPER NFOR PDR J

HIGHLIGHTS OF WEEKLY IWFORMA. ION REPORT T

'o WEEK ENDING FEBRUARY 2, 1990 a*

Licensee Certif f cation:.!mplementation.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 i

responses received, 27 sites did not report more stringent measures than j

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

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restraining order pertaining to random testing will allow.

ONB. Review of Fitness.for Outy Rule The Office of Management and Budget (OMB) has not granted a clearance for the information collection requirements contained in 10 CFR 26,

  • Fitness An interagency meeting involving the National Institutes of for Duty."

1 Health. Health and Human Services, National Institute on Drug Abuse, the Office of Management and Budget, and NRC is being scheduled to seek i

resolution of OMB's issues, Meeting with. Governor..of.0hio j

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l A. Bert Davis, bgion Ill Administrator, and Region !!! staff met with j

l Ohio Governor Richard Celeste and' members of his staff on January 30, j

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 l

interest.

Second Building Status TheGeneralServicesAdministration(GSA)solicitedexpressionsofinterest 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 down.

serious consideration. At the same time, negotiations are continuing between GSA and the White Flint North developer concerning the site adjacent to One White Flint Ncrth (0WFN).

On January 29, the Director, Office of Consolidation, met with staffs of the Montgomery County Department of Economic Development and the Montgomery Co The discussions covered l_

Planning Board to brief them on recent developments.

GSA/NRC alternatives and potential actions for achieving consolidation of the t

NRC heedquarters in light of difficulties encountered in concluding negotiations for construction of the second building on the lot adjacent to OWFN.

I FEBRUARY 2, 1990

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.o-i Office of Nuclear Reactor Regulation items of Interest Week Ending February 2,1990 CALVERT CLIFFS UNITS 1 AND.2 Pending final resolution of outstanding special team inspection / confirmatory

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action letter (ST!/ 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 03/08.

J In addition to completing all outstanding STI/ CAL issues and other restart s

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 1 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 Inspection Report dated 01/03/90.

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' letter 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.BOTT0!!, UulTS 2 AND 3 On January 28, 1990, the operators rapidly reduced 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 w u 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 11/111 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 11/111 actuations occurred due to reactor water level fluctuations. The 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 startup mode at about 3 percent power. The resident inspectors are monitoring licensee corrective actions.

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 evaluate human factors considerations in the operators' response to the 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 On February 1, the Associate Director for Special Projects issued, with the concurrence of the Commission, 4 Severity Level 111 Notice of Violation to 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 i

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 confirmea that the certification 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 dnd/or are testing for additional substances.

Diablo Canyon has responded that they are in compliance as f ar as the temporary restraining order pertaining to random testing will allow.

Canadian Visit to Discuss.Darlinoton.CANDU L

NRR staff is meeting this week with the Canadian AECB and consultants to l

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

.o NTOL AND RESTART SCHEDULE 2/2/90 I.

Schedule for NTOL plants:

INITIAL FULL PLANT LOW POWER CRITI-COMMISSION POWER AUTHORZTN CALITY.

BRIEFING..

AUTHORZ3 COMANCHE PEAK 1 2/90E 2/90E 3/90E 4/90E SEABROOK 5/26/890 6/13/890 1/18/900 2/90E i

11. Schedule ft.r RESTART plants:

COMMISSION NRC STATUS RESTART PLANT SHUTDOWN BRIEFING DECISION PLANT. RESTART BROWNS FERRY 2 9/15/84C 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

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s Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending February 2,1990 1

l SAFEGUARDS International Uranium Recovery Project.at. General Electric (GE).

  • Wilmington.. Worth. Carolina TheInternationalAtomicEnergyAgency(IAEA)wasinformedofplansbyGEto recover uranium from on-site lagoons that had been previously discarded as t

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

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specialist f rom Idaho National Engineering Laboratory. The inspection focused-on quality assurance in the f abrication, materials control, maintenance and repair of transportation casks with certificates of compliance issued by the e

NRC. A number of nonconformances with 10 CFR 71 requirements were identified by the inspection team.

INDUSTRIAL AND MEDICAL. NUCLEAR. SAFETY Materials Licensing f

Installation.and. Operation.of.the Second. Thermal.Weutron Activation.(TNA).

l Explosive Detection Device atSiami International Airport On January 29, 1990 Pan American World Airways began operational scanning of international checked baggage with the Science Applications International l

Corporation (SAIC) TNA device, Model EDS-3, at the ramp level of the Miami l

International Airport in Miami, FL.

Several legal concerns from Pan l

American delcyed the installation of the device almost five months after it was delivered from the Federal Aviation Administration (FAA).

Pan American finally obtained full liability protection regarding future radiation lawsuits from the manufacturer, SAIC. The EDS-3 device will screen checked luggage l

onto approximately 20 flights a day from Miami to London.

l Fuel. Cycle Safety Atomic. Vapor Laser Isotope Separation.(AVLIS) Program. Briefing I

On January 25, 1990, the Department of Energy and Lawrence Livermore National Laboratory progrem managers f or the uranium Atomic Vapor Laser Isotope Separation ( AVLIS) project briefed the Neclear Material Safety and Safeguards Director and staff on the plan for demonstration, transition, and deployment of FEBRUARY 2, 1990 ENCLOSURE B l

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AYLIS 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

Energy, in the briefing, the program managers emphasized features of the plan that would involve NRC licensing of an AVLIS 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.

Du ke. Powe r L i ce n se f or. D ry. S to ra ge. of. S pen t Fue l.Under.10. C FR. P e rt. 72.

On January 29, 1990, the Nuclear Regulatory Commission issued a' license for dry storage of spent fuel under 10 crR Part 72 to Duke Power Company for an independent spent fuel storage installation (ISFSI) located at its Oconee Nuclear Station site. The ISFSI is a concrete module and stainless steel system. A total of 88 modules containing 2112 pressurized water reactor spent fuel assemblies is authorized.

West Vallev Demonstration. Project The Department of Energy (DOE) has decided to build an interception trench adjacent to the old reprocessing facility burial ground at West Valley, NY, l'

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 degraded solvent (basically kerosene with some additives) by pouring it in tanks filled with sorbent material and burying the tanks.

Twenty-two tanks are known to have been buried in eight locations in the burial ground.

Solvent was first detecteo leaking f rom the burial ground in 1983.

In response, DOE exhumed the tanks from two of the eight locations, and found them to have been inadequately closed and mostly empty.

Funds from the West i

Valley Demonstration Project (WVDP) were used for the exhumation.

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 creeks.

l New York State, the site owner, has agreed that this should be done. The parties have not agreed on the larger remedial actions that should be taken to prevent future solvent leakage.

l The NRC staff has reviewed DOE's plans for the interception trench, and has agreed that the trench is an appropriate way to stop the spread of leaking solvent. A letter was sent to DOE stating our support for their action. The staff will visit West Valley during the stage of trench construction when the j

main features of the trench will be most accessible for examination.

FEBRUARY 2. 1990 ENCLOSURE B 1

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Office of Nuclear Regulatory Research Items of Interest j

Week Ending February 2,1990 Integrity-of. Reactor Components ACRS. Structural Engineertoo. Subcommittee. Meeting j

Cn January 24 and 25,1990 the ACRS Structural Engineering Subcomittee reviewed Structural and Seismic Engineering Branch (SSEB) research programs related to containment performance and building response. The meeting was held in i

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 j

morning of the 25th were devoted to presentations of aspects of the Containment

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Performance Research Program. Af ter introductory remarks by J. Costello, Dr. M. Amin, Sargent and Lundy, summarized the results of an analytical study of the resistance of containment structures to seismic loads beyond design i

basis. A summary of the test to f ailure of a model of the Sizewell "B" containment, performed in the UK by the Central Electricity Generating Board, was then provided. Mr. R. Dameron ANATECH Corporation, described the analytical prediction and Mr. 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), end Assessment of the Eff ects of Structural l

Response'on Plant' Risk and Margins (FIN A1851).

C. Farrar, LANL, cescribed the results of tests performed on models of building segments during the past 4 years. Un11ke the data from earlier tests (1980 - 1985) which reported that structural stiffness was much lower than analytical predictions (approximately 1

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 February. The ACRS questioned if these results will be factored into the i

l review of edvanced reactor designs.

Current analytical methods do not require l

an enveloping analysis to cover the reported differences in stiffness. NRR was I

advised of the ACRS comment. The ACRS was also informed that these test data are being used by the American Society of Civil Engineers (ASCE) working group l

on structural stif fness to develop new analysis procedures.

C. Farrar and R.

Kenneally are members of the working group.

l-M. Bohn, SNL, described how the differences in structural response effected i

deterministic (design-like) and probabilistic calculations. The evaluation was made using the Peach Bottom NUREG-1150 analysis.

Basically, core damage-f requency estimates f rom PRA results increased 60% (f rom 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 and possibly Meine Yankee. The ACRS supported this effort and requested a briefing after the other analyses are completed.

All presentetions were well received by the subcommittee.

No further actions were requested of the staff.

FEBRUARY 2, 1990 ENCLOSURE C

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Resolving Safety Issues.and Developing. Regulations The' Probability. of Liner. Failure. in. Mark. L Ccntainment 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 his probabilistic framework, Professor Theofanous estimated the containment liner meltthrough probaLility for the flooded drywell case to be approx.1 x 10-3 (conditional on core melt). For dry case the probability of failing the liner is almost 1 (conditional on core melt). A draft NUREG/CR-5423 report has been issued for broad peer review.

A briefing for the Nuclear Safety Research Review Committee is scheduled on February 13, 1990, at the Guest Quarters Hotel in Bethesda, Md. We are also planning to brief the ACRS Severe Accident subcommittee and the full committee, if oesirable, following the completion of the peer review. After factoring the peer review ano ACRS connents we will make any necessary final recommendations to the Commission on the Mark I liner meltthrough issue.

Meeting with Technogram On January 25, 1990, representatives from the Office of Research (Beckjord, Wilson, and Caron) and NRR (Scaletti and Yoshida) met with Michel Ruzenhole and Jean Paul Crette of Technogram. Technogram has been hired by Electricite de France (EDF) to investigate various techniques and designs that could poss?bly 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 Re' actor end the Simplified Boiling Water Reactor.

Meeting-with MHB Technical. Associates On January 30, 1990, representatives from the Office of Research (Williams, King, Londry, and Flack) met with Greg Minor and Richard Hubbard of MHB Technical Associates. MHB has been hired by the Union of Concerned Scientists to perf orm a study of selected advanced reactor designs (MHTGR, PRISM, and AP600). The discussion focused on the staff's draft SERs on MHTGR and PRISM.

Also present at the meeting was Brent Sadauskas from Bechtel-Gaithersburg, representing the MHTGR community.

1 TM1-Vessel Integrity. Program RES, in cooperation with the OECD/NEA, is removing metal samples from the TM1 Unit 2 reactor vessel bottom head for metallurgical examination and analysis.

The 30-day work window inside the THI Unit 2 containment for sample removal began Tuesday, January 30. The contractor, MPR Associates, is to remove 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.

FEBRUARY 2, 1990 ENCLOSURE C

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initial cutting problems have been experienced involving the electrical system, the flush water system to the cutting electrodes, and the plant air supply l

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 aoditional electrical fixes were made to correct these problems.

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Problems with the flush water, traced to fittings incorrectly tightened, have been corrected. The plent 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 i

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.

The TMI vessel integrity work is jointly funded by the U.S. and ten partner countries under the auspices of the OECD/NEA.

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Recently 1ssued. Documents 1.

Medical Use.of. Byproduct. Material:. Proposed. Amendments ~and.Draf t Regulatory Guide 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 Regulatory Guide DG-8001,

" Basic Quality Assurance Program for Medical Use," for guidance on the proposed Section 35.35.

Contact:

A. Tse, RES (492-3797) 2.

Draf t. Regulatory Guide.DG-3002

" Standard Format and Content of Financial Assurance Mechanisms Required for t

Decommissioning under 10 CFR Parts 30, 40, 70, and 72" Comments requested by March 30, 1990.

Contact:

K.Steyer,RES(492-3824) l.

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l ENCLOSURE C FEBRUARY 2, 1990

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Office for Analysis and Evaluation of Operational Data j

ltems of Interest i

Week Ending February 2, 1990 l

Division of.0perational Assessment.(DOA)

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.

The first three workstations for the Emergency Response Data System (ERDS) were delivered to the Operations Center this week and have been installed. The 3

remainder 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,14 MSS, RES, AE0D, 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 tjotification The following Preliminary Notifications were issued during the past week.

a.

Pt10-1-90-07, Public Service Company of New Hampshire (Seabrook Station),

Fitness for Duty Suspension From Work, b.

PN0-Ill-90-06, Solar Testing Laboratories Licensee Emergency Inc., Stolen Moisture-Density Gauge.

FEBRUARY 2, 1990 ENCLOSURE D

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'c1 Items of Interest Office of Governmental and Public Affairs Week Ending February 2,1990 t

_ State. Programs 0

1111oots Radiation Control Program Review B. J. Holt, Region 111 State Agreements Officer, began a review of the Illinois Radiation Control Program on January 29, 1990 in Springfield, Illinois.

Vandy 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.0 bio A. Bert Davis, Region 111 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.

Technicol. Training. Center Advisory. Group Meeting l

Vandy Miller, Assistent Director for State Agreements Program, attended the Technical Training Center Advisory Group meeting on January 30-31, 1990 in Chattanooga, Tennessee. The purpose of the meeting was to discuss and coordinate NRC and Agreement State training needs.

North Carolina Review Visit.on LLW Program R. L. Woodruff, Region 11 State Agreements Officer, conducted a review visit of the North Carolina LLW program on January 30-31, 1990 in Raleigh, North Carolino. 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 routine review.

Meeting with Vermont. State. Liaison.0fficer Marie Miller, Region 1 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 Ydnkee. Ms. Miller also toured the LLW storage facility at l

Vermont iankee. The Vermont Yankee SALP Management meeting was held in Vernon, Vermont on January 31, 1990.

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Meeting.with New Hampshire State Liaison Officer Marie Miller, Region 1 State Liaison Officer, met with George Iverson, Director of the New Hampshire Office of Emergency Management and State Liaison Officer, on February 1,1990 in Concord, New Hampshire. The i

purpose of the meeting was to discuss NRC concerns with the New Hampshire 3

Agreement State program, State /NRC communications and organization.and future State observations at Seabrook. Geoffrey Huntington, Assistant Attorney General, also participated in the discussions.

South. Carolina. Governing Board Neeting Robert Trojanowski, Director of Region 11 State and Government Affairs i

Staff, attended the Governing Board of the South Carolina Department of Health and Environmental Control meeting on February 1,1990 in Columbia, 1

South Carolina. The Board received a recommendotion 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 f acility 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.Messachusetts.LLW Official Marie Miller, Region 1 State Liaison Officer, met with Carol Amick, Executive Director of the Massachusetts LLRW Management Board, on February 2,1990 in Boston, Massachusetts. The purpose of the meeting 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

Office of Administration t

items of Interest week Ending February 2,1990 Significant.FOIA. Requests. Received by the.WRC f or.5-Day. Period January 26 - February-1 1990 6

Request for a copy of the proposal in response to solicitation 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 OlG report regarding Roger Fortuna.

(Susan Bev111 of Balch & Bingham, F01A-90-40) l

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,6 Office of Information Resources Management Items of Interest Week Ending February 2,1990 r

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Workload Information and Scheduling Program (WISP) i 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 i

E will be complete.

2.

NUDOCS/AD. Training On January 30, 1990, a meeting was held to discuss the issues and status of NUDOCS/AD training.

In attendance were representatives from the Document Control Branch, Information Technology Services Branch, the 1

ITS Training Laboratory contractor, the Office of Personnel and the NUDOCS contractor (Statistica). The discussion covered the ITS Training Laboratory /Statistica interface in preparing suitable instruction material able by February ?, in the form of six (6) ystem by the ITS to be avail-and support. We anticipate access to the sdial 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 conqueted on February 7.

Full implementation of the ITS Training schedule should comme'nce within three weeks.

3.

NUDOCS/AD Implementation As a result of a disk drive failure, NUDOCS/AD experienced an unexpected period of down-time over the last week. During this period, NUDOCS data was loaded into the system, and two enhancements to the system were implemented that should improve response time. Additional processor memory and an additional central processing unit (CPU) board were added to 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 mailed 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.

FEBRUARY 2, 1990 ENCLOSURE H

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ONB. Review of Fitnecs for Duty Rule The Office of Management and Budget (OMB) 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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FEBRUARY 2, 1990 ENCLOSURE H l

I Office of Enforcement Items of Interest i

Week Ending February 2,1990 j

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Significant Enforcement Action A Notice of Violation and Proposed Imposition of Civil Penalty in the amount I

of $30,000 was issued on January 25, 1990 to TV Electric (Comanche Peak). The 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 111 issued under Supplement 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) l A Notice of Violation and Proposed Imposition of Civil Penalty in the amount l

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 toentify 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 l

the Enforcement Policy were considered and the civil penalty in this case was l

escalated 50% because the licensee failed to recognize the safety significance of the issue and initiate prompt corrective action until the DET questioned the l

licensee's evaluation and corrective action.

(EN 90-009) l A Notice of Violation ano Proposed Imposition of Civil Penalty in the amount-of $100,000 was issued on January 31, 1990 to Commonwealth Edison Company (Zion). The action was based on the 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, l

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 l

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.

Tne licensee was also previously cited for past A 50% mitigation was failures in maintaining FSAR referenced safety (functions.EN 90-010) applied for the proposed corrective actions.

FEBRUARY 2, 1990 ENCLOSURE L

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' Civil. Penalty Paid Yale New Haven Hospital, New Haven, Connecticut paid the civil penalty in the amount 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 j

improper disposci, were identified.

(CA89-119) l i

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 r

aggregate, were considered to represent a significant breakdown in management I

control of licensed activities.

(EA89-33)

Iowa Electric Light & Power Company (Duane Arnold) paid the civil penalty in i

the amount of $50,000. The action was based on the licensee's failure to take i

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 dateo 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.

(EN 89-107)

I h

l FEBRUARY 2, 1990 ENCLOSURE L

a i

Office of Consolidation Items of Interest t

Week Ending February 2,1990 Second Building Status TheGeneralServicesAdministration(GSA)solicitedexpressionsofinterest 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 down. GSA received several proposals, at least one of which is receiving serious consideration. At the same time, negotiations are continuing between GSA and the White Flint North developer concerning the site adjacent to One White' Flint North (0WFN).

On January 29, the Director Office of Consolidation, met with staff s of the Montgomery 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 difficulties encountereo in concluding negotiations for construction of the second building on the lot adjacent to OWFN.

0WFN Cafeteria Work on the cafeteria is approximately 50% complete with the installation last week of crywall, kitchen grill exhaust hood, and the beginning of floor tile installation. The revised plan for the cafeteria calls for installation of 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, yogurt, made-to-order sandwiches, packaged sandwiches, desserts, snacks and beverages.

FEBRUARY 2, 1990 ENCLOSURE M

I

.o I

'I Region I Items of Interest i

Week Ending February 2,1990

(

l 1.

Cintichem. Inc.

On December 12, 1989 Cintichem, Inc., Tuxedo, New York, reported the discovery, on November 28, 1989, of slightly contaminated water in an onsite storm drain. No releases to offsite environs were identified.

Cintichem produces radioactive isotopes for the pharmaceutical industry.

l 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 continued corrective i

measures, and identification of the licensee skills and resources needed to accomplish the planned actions.

[

t 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 investigotion. NRC agreed to keep the Town officials informed l

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 l

NRC on January 31 that the source of the contamination may have been identified ano efforts to confirm this are underway.

2.

Susquehanna Requalification. Examination First "Altern6tive 5" in Region I in accordance with the Commission approved staff paper (SECY 89-55) 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 portions of the examination) was used for the requalification examination conducted at Susquehanna during the January 22, 1990 week. This requali-i fication examination is the first in Region I usin This examination also evaluated the largest number (20)g Alternative B.

of candidates in Region I for a one-week requalification examination. The results indicate that this alternative is a viable method for reducing the examiner resources.

FEBRUARY 2, 1990 ENCLOSURE N

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Region !

Items of Interest Week Ending February 2,1990 I

l 3.

Calvert Cliff s

\\

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 i

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 gabrook On Tuescay,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.

FEBRUARY 2, 1990 ENCLOSURE N

r t

e Items of Interest Region 11 Week Ending:

February 2,1990 1.

Du ke. Power. Company t

On January 30 and 31, the Regional Administrator, accompanied by Region 11 and NRR staff, was at the McGuire and Catawba Nuclear Power Stations, respectively, to present the SALP assessment i

findings to Duke Power Company representatives.

On January 31, the Regional Aaministrator, accompanied by the Director, Office of Enforcement, and the Region 11 and NRR staffs, was at the Catawba Nuc1 car Power Station to neet with Duke Power Company representatives to discuss the recently issuea proposed escalated enforcement action which addresses a number of security violations at each of Duke's plants.

2.

Florida. Power. Corporation On February 1, representatives of the Florida Power Corporation

[

were in the Region 11 Office to attend on Enforcement Conference

~

regarding the issues associated with the Crystal River Unit 3 high pressure safety injection system flow instrumentation.

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FEBRUARY 2, 1990 ENCLOSURE N A

)

Region Ill items of Interest Week Ending February 2,1990 f

1.

Perry Nuclear Power Station A. Bert Davis, Regional Administrator, members of the regional staff, and the Senior Resident inspector met January 30, 1990, with Governor Richard l

Celeste of Ohio in Columbus, 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 111 offered to meet with the Governor after he expressed concerns about the off-gas releases.

2.

Duane Arnold Energy Center Mr. Richard W. McGaughy, Vice President - Production, Iowa Electric Light and Power Company, met with the Regional Administrator in the regional office on February 1, 1990, to discuss general topics related to the status of the Duane Arnold facility. The meeting was held at Mr. McGaugby's request.

3.

American Radiolabeled Cbemical Region 111 received a Petition for Limited Modification of Order Suspending l

Licenses. The petition requested that the licensee be permitted on an interim basis to purchase prepackaged materials from other licensed vendors for reshipment to their customers. This petition is currently being reviewed by the Region Ill and Headquarters staffs. The licensee also i

requested a hearing on the Order.

4 VA Medical Center

. Des.Moines. Iowa On January 30, 1990, C. J. Paperiello, Deputy Regional Administrator, and members of the Region til staff conducted an Enforcement Conference to discuss: (1) eleven procedural violations identified durin inspection, (2) the 11censee's corrective actions, and (3)g a recent NRC enforcement options available.

FEBRUARY 2, 1990 ENCLOSURE N

5.

Zion. Nuclear Power Station i

l On January 30, 1990, enforcement discretion was granted by Region III, with NRR concurrence allowing a 40-hour extension to an action statement requirement prescribed by a February 29, 1980, Confirmatory Order. That portion of the Order stipulates allowable diesel generator outage times dependent on the number of diesel generator failures in the prior 100 tests. The Unit I 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, 1B

)

Diesel Generator was declared inoperable due to a failure of the air start l

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 i

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 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 i

air start system and to perform the required operability run of the IB i

Diesel Generator in order to avoid subjecting the unit to an unnecessary r

transient. This relief was based on the adoit1onal knowledge of and changes in the regulatory position concerning diesel generator surveillance testing and reliability reflected in the Standard Technical Specificottons ona Generic Letter GL 84-15.

In addition, each ESF bus is capable of being powered f rom the System Auxiliary Transformer supplied by the off site distribution system, the Unit Auxiliary Transformer powered by the main generator or offsite power when in backfeed configueration, a reserve feed from the opposite units 4 kv bus, and the diesel generator assigned to the associateo ESF bus.

Also, during the requested extenion, two diesel generators for Unit 1 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 power after the reactor protection system (RPS) detected the loss of a reactor coolant pump (RCP) due to a spurious signal caused during All systems operated as required except two main surveillance testing (.MSSV) that failed to properly seat after lifting and steam safety valves a reactor coolant system (RCS) letoown valve (MU-26) that would not reopen j

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 be commencing their four month refueling outage. Major activities planned for the refueling outage will be:

reactor vessel inspection; eddy current inspection of the steam generator; main steam safety valve refurbishment; l

RCP motor overhauls; appendix R modifications; RCP seal modification; and control room human factor modifications.

1' l

l FEBRUARY 2, 1990 ENCLOSURE N l:

i I

L 7.

Clinton Power-Station On January 26, 1990, Mr. A. Bert Davis, Regional Administratur, Mr. Edward G. Greenman, Director, Division of Reactor Projects, Mr. John Craig, NRR Project Directorate 111-3, and members of the Region 111 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 i

public and news media were present and interviews were conducted with both the NRC and Illinois Power following the meeting.

8..

Duane Arnolo.Eneroy. Center On January 30, 1990, Mr. John A. Zwolinski, Assistent Director for Region 111 reactors, NRR, Mr. H. J. Miller, Director, Division of Reactor Safety, Region Ill, Mr. R. Knop, Chief, Branch 3, Division of Reactor Projects, ano other NRC staff members met with representatives of Iowa Electric Light and Power Company at headquarters.

Items discussed were the Duane Arnold engineering department reorganization, the extent of silting problems associated with the Cedar River and status of their HPCI improvement plan.

9.

Division.of. Reactor. Projects The section chief of Section 2B, Division of Reactor Projects, Region III, traveled to the Universtty of Wisconsin in Madison, Wisconsin for the, purpose of interviewing 12 graduating seniors as prospective employees for Region 111.

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l FEBRUARY 2, 1990 ENCLOSURE N

G' Region IV Items of Interest i

Week Ending February 2,1990 P

i 1.

Mr. Thomas Rounatree of ICF Kaiser Engineers will be in the Region ly office on behalf of EPA Region VI to review the Fansteel docket file.

ICF Kaiser Engineers is a superfitnd contractor of EPA.

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FEBRUARY 2, 1990 ENCLOSURE N

,s,-

iE.

l Region Y l

l Items of Interest j

Week Ending February 2,1990 1.

Arirvoa. Nuclear Power. Project

)

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 l

centered maintenance, i

2.

University.of Hawaii

?

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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l FEBRUARY'2, 1990 ENCLOSURE N

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" ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING FEBRUARY 2, 1990 A. : STAFF REQUIREMENTS-- BRIEFING ON NRC ACTIONS FOR CLEANUP OF ' CONTAMINATED SITES UNDER NRC JURISDICTION, 2:00 P.M., THURSDAY, DECEMBER 21, 1989, COMMISSIONERS' L

[,

~ CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC-ATTENDANCE) SECY Memo to James M. Taylor dated 1/31/90-I The commission was briefed by the staff.on its proposed strategy for cleanup of contaminated materials sites under NRC jurisdiction.

~

The commission requested _the staff to:

1.

SubmitJa preliminary r.nalysis of any implications of the BEIR-V report with respect to the Commission Policy Statement _on Exemption from Regulatory Control.. The 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.)

2.

Submit a list.offcontaminated 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 a discussion of criteria used to rank gagh site.

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 rulemaking, NRC staf f should provide general notice to licensees that. additional cleanup may be necessary to comply with standards promulgated at a future 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 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 terminate licenses are considered final agency actions as long as licensees comply with all applicable standards in effect at the time of termination.

ENCLOSURE P FEBRUARY 2, 1990

'2 -

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Gi; A.

4.,conOd.

Consistant with this approach, the Commission directs the 4

staff-not to develop proceduros 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, staff should emphasize to EPA the need either to grandfather 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 viewr 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 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 licensee to seek a variance for timing of cleanup based on a demonstration that compliance with the timeliness criterion (1) is not necessary to ensure protection of 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.

1 I

FEBRUARY 2, 1990 ENCLOSURE P

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'4:

.c 1

,g A.,

cont'd.

16.

.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, i

E Insterd, the staff should'first: consult with the Commission in the svent that the need arises to consider the application l

[

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.

l regulatory authority is inadequate, and-the. objectives l

that would be scrved by the application of Superfund to L

the'given~ sit' The discussion should also include an~

L analysis of (2, the' cleanup standard that would apply.

p under Superfund and the difference between that standard; and the Atomic' Energy Act standard; (2) the rights and i

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.

i 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 l

~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, the Seacoast Anti-Pollution League, the New England Coalition E

on Nuclear Pollution, and.the NRC staff on the readiness of the Seabrook Nuclear Power Plant, Unit 1 to operate at full power.

Representing PSNH were:

- Edward-A. Brown, President and CEO, NHY

?

- Ted Feigenbaum, Senior Vice President and

[

Chief Operating Officer, NHY l

- Bruce Drawbridge f

Executive Director for Nuclear Production, NHY

\\

E

- George Gram, Executive Director of Emergency l.

Preparedness and Community Relations, NHY l

Representing the Commonwealth of Massachusetts was:

L

- John Traficonte, Chief Nuclear Safety Unit Department of the Attorney General L

L

  • Commissioners Curtiss and Remick were not present.

-FEBRUARY 2, 1990 ENCLOSURE P

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.4 2

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B.. cont'd.

1

' Representing Seacoast Anti-Pollution League was:

- Robert A.

Backus l

' Representing New England Coalition on Nuclear Pollution was:.

i

- Diane curran Chairman Carr requested that PSNH provide the Commission'with the age'of the oldest maintenance item in the corrective x

1 J

maintenance backlog and that the staff advise the Commission on

~

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.

1

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.l FEBRUARY 2, 1990 ENCLOSURE P

W Congressional' Affairs h!-

CONGRESSIONAL-IIEARINGS SCllEDULE (CA)

EE OCA

-DATE TIME WITNESS SilBJECT -

COMMITTEE 3j-ASSIGNMENT

!* 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 ff Waste Mgmnt o

Gerke 02/07/90 TBA Markup II.R. 743, Negotiated Reps. Frank /Sensennbrenner Rulemaking Act Madden 02/08/90 9:45' Comnission NRC's TY91 Authnri-Reps. Udall/Hansen-ration Subc on Energy 81the Environment House Interior & Insular Affairs I

Combs 02/22/90 9:30 Sec. Watkins DOE's Civilian Nuclear Senators Johnston/McClure Waste Program Senate Energy & Matural Resources Gerke 02/21/90 9:30 Non-NRC S. 1742, Paperwork Senators Glenn/Roth 02/22/90 Reduction Act Senate Governmental Affairs Gerke 02/27/90 TBA Non-NRC Equal Opportunity Civil Service (Sikorski/Morella)

Complaint Pro-House Post Of fc & 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 E2 Combs 03/08/90 10:00 Non-NRC DOE's Nuclear Waste, Reps. Bevill/Myers Uranium Enrichment Energy.& Water Development l

P S?

Appropriations FY91 House Appropriations E

Callahan 03/20/90 TBA Jim Taylor Advanced Reactors Reps. Lloyd/Morrison Energy Research & Development l

House Science, Space & Technelogy Madden 03/21/90 10:00 Conesission NRC's FY91 Budget Reps. Bevill/Myers' Subc on Energy & Water Development flouse Appropriations l

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NRR' MEETING ~ NOTICES ES ~

lSE February 5,' 1990 F

APPLICANT /

((DATE/ TIME NUMBER LOCATION PURPOSE' ATTENDEES NRR CONTACT..

-2/7/90 White Flint Bldg.

. Review and discuss information NRC/GE 5.'flewberry.

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.

2/8/90 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. Summer 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-f2 rules," that was submitted on S?

July 3,1989.

' t Ei m

  • Copies of summaries of these meetings will be made publicly available and
  1. 3 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

$5 February 5,1990 N

L-APPLICAtlT/'

!!DATE/ TIME NUMBER LOCATION

~ PURPOSE

. ATTENDEES NRR CONTACT; 2/8/90 White Flint Bldg.

Discuss the results of.recent-NRC/t!ortheast G. Vissing, 10:00-3:00 Room 148-13 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 138-9 l

2/13/90 50-271 White Flint Bldg.

Routine discussion of scheduling NRC/Vernont M. Fairtile

?:30-11:00 Room 14D-7 and prioritization of licensing Yankee Nuclear actions.

.Ihower Corp.

2/14/90 White Flint Bldg.

Discuss the following items (1)

NRC/GE G. Thones.

9:30-12:00 Room 8B-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 revised heat capacity temperature limit (HCTL) for.ATWS mitigation; (4) analytical capability needed to accurately model ATWS; (5) uncertainty in existing analyses.

mz o,_

S$ 2/15/90 50-390 Watts.Bar Site The NRC staff will discuss with NRC/TVA R. Auluck E 1:30-5:00 Spring City, Tenn. -

TVA representatives,tthe. staff's:

((

preliminary assessment of _ TVA's evaluation of the cable damage issue.

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'NRR NEETING NOTICES

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February 5,1990 -

APPLICAtlT/

~

.gDATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES i:RR CONTACT 2/28/90 50-335/

White Flint Bldg.

Discuss. St. Lucie' I and '2' NRC/FP&L

.J. Norris 1:00 389 Room 16B-11

-safeguards issues.

licGuire 'uclear Plant Discuss the status of various NRC/GPCo

L.-Wiens-3/15/90 50-269/

N 8:30-4:00 270 licensing activies 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.

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T lh EE NMSS. Meeting. Notices

.E 93 Division.of' Safeguards and Transportation 8

-Docket

-Attendees /

Date/ Time Number Location Purpose

. Applicant.

NRC Contact.

2/14-16 San Onofre, CA Briefing at the NMSS J. Higdon Western Association tleeting,- SG Log Analysis Program 2/21-22 Lexington, KY Participate in NMSS E. Easton Transportation DOE Contractors Coordination Group meeting, Office of Civilian Radioactive

Waste Management, DOE Division of High-Level Waste. Management i

Docket Attendees /

t Date/ Time Number Location Purpose Applicant NRC. Contact.

2/6-7 Las Vegas, HV To discuss preliminary NMSS K. Stablein Yucca Mt., NV results of investi-RES E2 gation on silica veins State of Nevada E?

DOE 8

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Docket Attendees /.

3. Date/ Time Number Location Purpose Applicant ~'

NRC

Contact:

2/2 OWFN-Initial discussion of-

'NMSS "J. Swift

.G 3-5 p.m.

-6B-11

~ DOE plans for-future DOE 8-work on monitored.

NY State Officials

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retrievable storage' 2/6 Project West Valley, NY Examine construction of -NMSS D.. Hurt-M-32

. Interception. trench at ~ DOE West Valley burial ground-2/6 Project ' Baton Rouge, LA Brief Louisiana Dept..

NMSS

.P..Loysen-M-45 of Environment Quality RIV Officials on LES LA Official'et al.

Project and Uranium i

llexafluoride 2/7 70-1193 OWFN To review status of NMSS G. Sjoblom:-

12-3 p.m.70-925 6B-11 deconsnissioning on OGC Crescent and Cushing RIV-Oklahoma sites 2/7 OWFN Discuss licensing NMSS T. Huffert 6B-13 requirements for source-- OGC materials with Heritage RI Minerals, Inc. & Nord Ilmenite Corporation mz S 2/7-9 70-1113 Wilmington, NC To discuss license' NMSS R. Wilson E

application at GE

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2/8 70-135 OWFN Review licensing. issues NMSS P.'Loysen with Babcock & Wilcox B&W Pennsylvania Nuclear Service.0perations 1

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q Date/ Time Number Location Purpose-

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2/15 OWFN Submittal of license NMSS '-

S.'Ruffin.

g application.for storage PSC g

of-spent fuel under" Part 72 at Public Service.Co. of Colorado's (PSC) Fort St. Vrain nuclear power plant site Division of. Low-Level. Waste.Madagement and. Decommissioning Docket

. Attendees /

Date/ Time Number Location Purpose Applicant NRC Contact 1/29-2/9 Raleigh, NC To participate in NMSS-J. Shaffner-Agreement States Program Reviews 2/1-2 Springfield, IL IDNS 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 NMSS.

L. Pittiglio.-

90 Conference

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RES. Meeting Notices m'j Docket Attendees /.

Date/ Time Number Location Purpose Applicant <

NEC.Cor tact ro Director!s_ Office o

t$g Nuclear Safety Research Review Committee (NSRRC). Meetings 2/13/90 Guest Quarters

.NSRRC Subcommittee. meeting

.R._ Shepard Bethesda, MD

'(with Chairman'Carr'in attendance) 492-3723.

Division.of Engineering Nuclear Plant A J. Vera' Research (NPAR)ging 3/20-21/90 Bethesda Ramada Inn

Research 492-3854 Bethesda, MD Review Group Meeting 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 3/8-9/90 Washington, DC' Attend NUREG-1150 Peer J. Murphy 8-M. Cunningham Area Review Committee Meeting M. Cunningham

. 492-3965 9

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' Region-I Meeting Notices-E' 4

Docket Attendees /-

Date/ Time Number Location Purpose Applicant.

NRC Contact m

Q 8

02/20/90 50-57 RI' Office Management Meeting.

Licensee and Selected' McCabe 1:00 pm SUNY Buffalo RI Staff Members 02/27/90 50-317

'RI Office' Requal Exam Meeting Licensee and Selected-Cowgilij 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 P

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February 2,f 990.,-

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.RII MEETING. NOTICE E

E DOCKET ATTENDEES /

DATE/ TIME NUf4BER LOCATION PURPOSE APPLICANT.

NRC. CONTACT 02/15/90 RII Office Enforcement Conference Licensee, DRA and selected Milhoan CP&L Harris' facility RII. staff members 10:00 a.m.

02/20/90 New 11111, NC SALP Presentation - CP&L Licensee, RA, and selected-Ebneter Itarris facility P.II and resident' staff 02/21/90 RII Office Management Meeting Licensee, RA, and. selected Ebneter 10:30 a.m.

VEPC0 RII staff 02/22/90 Hartsville, SC Chairman will visit Chairman, Tech. Asst.,

Milhoan!

Robinson facility for Deputy RA, and Residents site familiarization 02/27/90 RII Office Enforcement Conference Licensee, RA and selected Ebneter VEPC0 - N. Anna facility 10:30 a.m.

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L Region III Meeting Notices l

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Date/ Time Number.

Location Purpose Applicant NRC. Contact i

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^ Greenman G

02/07/90 50-346 Headquarters Toledo Edison Company, Licensee, Deputy Regional l

g; 1:00 pm Davis-Besse - Management Administrator and selected fleeting 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 - Management members of RIII Staff Meeting 02/13/90 Headquarters Illinois Department of IDNS, 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 Management Meeting 02/14/90 50-341 Fermi Plant Detroit Edison Company, Licensee, Deputy Regional Norelius Fermi - Emergency Administrator and selected Preparedness Exercise members of RIII Staff

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02/22/90 50-254 Quad Cities Plant Commonwealth Edison Licensee, Deputy Regional Greenman

's 50-265 Company, Quad Cities Administrator =and selected m

5 Systematic Assessment

. members of RIII Staff of Licensee Performance E"'

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Region.IV. Meeting. Notice

~5 February.2, 1990

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Docket-Attendees /'

to ~Date Number Location Purpose Applicant.

RIV. Contact G

8 2/02/90 30-05965 RIV Firestone Tire & Rubber Company.

FT&P, Mngmt.

BBeach, LYandell, (1:00) 35-13617 Enforcement Conference to discuss weaknesses in their managemenet of '

FT&R's 'rddiation safety program.

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