ML20138F159
| ML20138F159 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851206, NUDOCS 8512160029 | |
| Download: ML20138F159 (38) | |
Text
DN December 11, 1985 For:
The Commissioners From:
T. A. Rehm.. Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING DECEMBER 6, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
Executive Legal Director F*
Interna'ional Programs G
State Programs H
Resource Management I*
Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Reg'ional Offices L
CRGR Monthly Report M*
Executive Director for Operations N*
Items Addressed by the Commission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
T. A. Rehm, sistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, ED0 851216o029 estatt 492-7781 PDR COMMS NRCC WEEKLYINFO EPT PDR 7
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING DECEMBER 6, 1985 i
Shoreham The Long Island Lighting Company has scheduled a special shareholders meeting for December 12, 1985, to elect a new Board of Directors.
Mr. John Matthews, who was a candidate for Nassau County Executive earlier this year, forced the meeting after buying 100 shares of LILC0 preferred stock. Because LILC0 has failed to pay 4 quarterly prefePred stock dividends, the preferred stockholders have the right to elect a majority of the Board of Directors. The licensee has recomended a slate of directors to oppose those nominated by Mr. Matthews, who has declared himself to be opposed to the operation of Shoreham and in favor of a public power authority to replace LILCO.
Clinton Power Station i
On November 27, 1985, Illinois Power Company released a news Bullitin which stated that construction of Clinton Power Station would'be~
essentially complete by the end of December 1985. However, as stated in the Bulletin, because of delays in completing systems for testing it is anticipated that fuel loading will occur between late February and late March T986.
f Hope Creek Generating Station By letter dated November 29, 1985, Public Service Electric & Gas Company announced that the fuel load date for Hope Creek has slipped to February 1986. This date is based on a recently completed assessment of the status of work activities necessary to support fuel loading and
~
low power testing. Based on a June 1985 Caseload Management Team visit to the site, both NRR and Region I believe a February 1986 fuel load date is possible.
Catawba, Unit 2 On December 5 Duke Power Company informed us that the Catawba Unit 2 current schedule for fuel load is January 22, 1986. The licensee previous date was January 15, 1986. The delay was caused by the recent main bearing failure in one of the TDI diesel generators.
Establishment of International Nuclear Technology Liaison Office (INTLO)
This past October the Department of State established the International Nuclear Technology Liaison Office (INTLO) in an effort to improve U.S.
support for the IAEA's Technical Cooperation Program.
In addition to improving the overall planning, implementation and evaluation of U.S.
support for IAEA technical cooperation activities INTLO will provide background information and briefing materials to U.S. officials routinely involved in formulating overall U.S. policy regarding the IAEA. The office receives direction and guidance from an inter-agency l
Steering Comittee headed by the Department of State and consisting of representatives from several offices in the Departments of State and Energy, the U.S. Arms Control and Disarmament Agency and the NRC. The l
Steering Comittee held its first meeting on Wednesday, December 4, at the Department of State.
DEC 6 1985
OFFICE OF ADMINISTRATION Week Ending December 6, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1984 179 23 Received, 1985 795 41 Granted 624 31 Denied 182 18 Pending 168 15 ACTIONS THIS WEEK Received Steven C. Sholly, Requests records related to the UKAEA/NRC meeting held MHB Technical on October 15, 1985, and the Germany /NRC meeting on Associates October 16-18, 1985; all papers presented at a (85-784) recent LWR meeting; all records generated as a result of the recent meeting of the Society of Exploration Geophysicists attended by Dr. E. Zurflueh; SECY-85-283 and copies of slides / handouts used by NRC staff at the Commission meeting on September 9, 1985, and the ACRS meeting on October 31, 1985, on earthquakes as related to emergency preparedness.
Dave Skripol, Requests a list of organizations licensed to machine AMCA International magnesium-thorium source material.
Corporation (85-785)
Louis L. Robein, Requests copies of records concerning drug use, drug Gardner, Robein screening, or urinalysis of individuals covered under and Healey NRC's authority.
(85-786)
Timothy Nusser Requests a record identifying since 1982 how many (85-787) individuals at the Goodyear Atomic Energy Corporation Uranium Enrichment Facility in Piketon, Ohio, have l
received cumulative or single event expo.iure to radiation beyond that level allowed by the safety regulations.
(NRCemployee)
Requests all records regarding an EE0 matter.
(85-788)
(NRCemployee)
Requests all records regarding an EE0 matter.
(85-789)
CONTACT: Donnie H. Grimsley ENCLOSURE A 492-7211 DEC 61985 l
2 Received, Cont'd Steven C. Sholly, Requests all comment records on NUREG-0956, NUREG-1037, MHB Technical and NUREG-1079 and all NRC staff memoranda concerning Associates the American Physical Society's report reviewing the NRC t
(85-790) source term reassessment program.
Lindsay Audin Requests copies of three categories of records regarding (85-791) the MH-1A and GE-700 spent fuel shipping casks, and minutes of all meetings of the DOE /NRC transportation safety group between February 1,1985, and December 1, 1985.
(An individual Requests records in the NRC on herself.
requesting information about herself)
(85-792)
Andrew Plunkett, Requests records provided to Kathiann Kowalski under Paul, Weiss, F01A-85-375.
Rifkind, Wharton
& Garrison i
(85-793)
Billie P. Garde, Requests all records developed by the License Fee Government Management staff about the cost of the operating Accountability licensing review of the Comanche Peak nuclear power Project plant from June 24, 1984, to the present.
(85-794)
Robert J. Huber, Requests copies of all records supplied to NRC by Exxon Fabyanske, Svoboda Corporation (or Exxon Minerals Company, U.S.A.)
and Westra concerning the Highland Uranium Operation in Converse (85-795)
County, Wyoming.
Granted l
Steven Aftergood, In response to a request for copies of four categories Committee to of records related to the University of Michigan Ford Bridge the Gap nuclear reactor and its conversion from highly enriched (85-587) uranium fuel to low enriched uranium fuel, made available 10 records.
Informed the requester that six additional records subject to this request are already available at the PDR.
4 1
i James 7. Lawless, In response to a request for a list related to the l
The ' lain Dealer 10 CFR 50.55(e) items which appear in the SALP 5 (85-658)
Report for the Perry nuclear power plant, made available a copy of the requested list and the related excerpt from the SALP report.
Charles Barnes In response to a request for a listing of certain Docket (85-752) 40 files retired before 1974, made available records identifying the subject docket 40 files, from which those docket 40 licenses used for export / import of ENCLOSURE A source materials have been excluded.
DEC 6 1985
~ -.
3 Granted, Cont'd In response to a request for all AEC records in the Charles Barnes (85-755)
NRC's possession relating to transportation incidents 111-69-03 of March 5,1969, and III-70-04 of May 16, 1970, related to the United Nuclear Corporation and Kerr-McGee's Cimarron Facility, informed the requester that the NRC has no records subject to this request.
Suggested that he contact the 00E.
In re.sponse to a request for registrations by six listed Francis J. Kreysa, Informed companies, made available five records.
Neutron Products the req ester that one listed company is located in (85-758)
New York, an agreement state, and suggested that the requester contact the Bureau of Nuclear Operation in New York for records on the company.
In response to a request for a copy of the successful Robin Kimling, proposal submitted in response to Solicitation RFP No.
Micro Mart, Inc.
RS-0RM-85-334 entitled "On Call Maintenance for NRC (P5-762)
Microcomputers and Related Equipment," informed the requester that the Solicitation RFP was issued as a sealed bid, for which a technical proposal was not required.
In response to a request, on behalf of an individual, Jim Ruppenthal, for medical records and the background investigation Disabled American report regarding the individual's security clearance, Veterans (85-779) informed the requester that the NRC has no records on the individual.
Denied 4
j Ann Cross Eschenbach, In response to a request for certain records regarding 1
alleged acts of non-compliance by University Nuclear Attorney-At-Law (85-35)
Systems, Inc., at Washington Public Power Supply Systems 1
Units 1 and 4, made available 185 records.
Informed the requester that additional records subject to this request
,'i I
are already available at the PDR. Denied two records in their entirety containing predecisional information which constitutes advice, opinions and recommendations of the staff. Denied two records in their entirety and portions of 71 records containing the names of individuals and personal identifiers the disclosure of which would constitute an unwarranted invasion of personal privacy.
Steven Aftergood, In response to a request for copies of three categories of documents related to the proposed rule for limiting Committee to the use of highly enriched uranium (HEU) in research and Bridge the Gap test reactors, made available 21 records.
Informed the (85-379) requester that additional records subject to this request are already available at the PDR. Denied 15 records in their entirety containing the predecisional advice, opinions, and recommendations of the staff on the proposal to withdraw the proposed rule.
ENCLOSURE A i
i DEC 6 E'
4 Denied, Cont'd Nina Bell, In response to a request for three categories of Nuclear Information records relating to seismic hazards, made available and Resource 41 records. Denied portions of cne report, release (85-535) of which could cause substantial economic harm to the Electric Power Research Institute (EPRI).
Steven Aftergood, In response to a request for copies of (1) SECY-85-152, Committee to entitled " Disposition of Application for Award of Bridge the Gap Attorney Fees Under Equal Access to Justice Act by (85-636)
Business and Professional People for the Public Interest; (2) the Application for Award of Attorney Fees addressed in SECY-85-152; and (3) the Order approved by the Commission disposing of the Application, informed the requester that item 2, which is Attachment 1 to the SECY paper, and item 3 are already available at the PDR.
Denied portions of the SECY paper, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
ENCLOSURE A DEC 6 1585
1 WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING DECEMBER 6, 1985 L
i 3
RFP ISSUED t
RFP No.: RS-NRR-86-052
Title:
" Safety Review of Advanced Reactors"
==
Description:==
The objective of this project is to provide technical assistance l
to the NRC in the review of three advanced reactor conceptual designs; one high temperature gas cooled reactor concept and two liquid metal reactor concepts.
t Period of Performance: Two years Sponsor: Office of Nuclear Reactor Regulation Status: RFP issued on December 2, 1985. Proposals due January 3, 1986.
RFP No.: RS-NRR-86-055
Title:
" Assessment and Application of Thermal-Hydraulic Phenomena for j
Severe _ Accident Decisions"
==
Description:==
Generic Assessment of thermal hydraulic issues associated with severe accidents, review all LWR designs to determine the specific applicability of results of the generic assessment of thermal-l hydraulic issues, and provide support for implementation of NRC's severe accident policy, review of probablistic risk assessments j
and prioritization of generic issues.
Period of Performance: 30 months Sponsor: Office of Nuclear Reactor Regulation Status: RFP issued on December 5, 1985. Proposals due January 6, 1986.
PROPOSALS UNDER EVALUATION l
RFP. No'. : 'RGI-86-311
Title:
" Technical Support for Non-Destructive Examination Van"
==
Description:==
On a task order basis, the Contractor shall provide personnel
~
with expertise in the field of non-destructive examination and a radiographic isotope source to perform field non-destructive examinations at nuclear power plants under construction or in i
operation anywhere in the United States.
l Period of Performance: 24 months i
Sponsor: Region I, Division of Reactor Safety Status: RFP closed on December 2, 1985. Proposals forwarded to Source Evaluators for review on December 2, 1985.
RFP No.: RS-01E-85-156
Title:
" Technical Assistance in Developing and Implementing Programs and Procedures for Inspection of Operating Reactors During Major Outages"
==
Description:==
The objective of this project is to provide technical assistance to the NRC for activities pertaining to planned outages of operating reactors. This includes the development of standardized t
inspection procedures for planned outages as well as providing assistance to the regional offices for conducting inspections during planned outages of operating reactors.
Period of Performance: Three years Sponsor: Office of Inspection and Enforcement Status: Best and Final offers are due on December 12, 1985.
ENCLOSURE A l
DEC 6 E25 l
- _ - _.. -. _ _. _ ~ _. -. -. _ _, _. _, _ _. _. -
Weekly Information Report Division of Contracts CONTRACT AWARDED IFB No.: RS-0IE-86-171
Title:
" Graphic Services"
==
Description:==
Provide graphic / photographic services to the Technical Training Center for use in instructional material.
Period of Performance: December 2, 1985 through December 1, 1987.
Sponsor: Office of Inspection and Enforcement Status: Fixed Price Requirements Contract No. NRC-05-86-171 awarded to Robert Moles & Associates in the amount of $105,992.50 effective December 2, 1985.
l l
f ENCLOSURE A 6$6 i
I
I 0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending December 6, 1985 Diablo Canyon Power Plant, Unit 1 With the plant at about 0.5% power, the reactor tripped on steam flow / feed flow mismatch coincident with steam generator low-level signal. The flow mismatch was a momentary upset caused by opening the turbine stop valves in the process of latching the turbine. With one steam generator level bistable tripped because the channel was out of service, the coincident mismatch signal made up the logic for the
_ Trip breaker Train A opened but trip breaker Train B did reactor trip.
not open. Botn breakers have the shunt trip attachment installed.
The licensee's review of the sequence of events indicated the trip signal duration was for one cycle, or 15 milliseconds.
Subsequent testing indicates that about 70 to 80 milliseconds are required for the breakers to actuate. Why the Trair. A breaker opened in light of this finding is still under investigation. The licensee has verified the operability of the breakers, including the testing of the undervoltage trip attachment, and additional review of the event is still underway.
Shoreham The Long Island Lighting Company has scheduled a special shareholders meeting for December 12, 1985, to elect a new Board of Directors.
Mr. John Matthews, who was a candidate for Nassau County Executive earlier this year, forced the meeting after buying 100 shares of LILC0 preferred stock. Because LILC0 has failed to pay 4 quarterly preferred stock dividends, the preferred stockholders have the right to elect a majority of the Board of Directors. The licensee has recommended a slate of directors to oppose those nominated by Mr. Matthews, who has declared himself to be opposed to the operation of Shoreham and in favor of a public power authority to replace LILCO.
River Bend i
At 10:47 p.m. on November 26, 1985, the licensee declared an unusual l
event when a low level indication was received by the River Berd Division III ECCS. The low level indication activated the HPCS, injecting water into the reactor vessel for about 12 seconds until operator action returned HPCS to the standby mode. The low level indication was the result of a failure by a licensee instrumentation and control technician to physically isolate the level transmitter prior to filling its common reference leg.
At the time of the event, the plant was at rated temperature and l
pressure in the start-up mode (about 4% power) with the ECCS on standby. The licensee informs us that the actual water level remained ENCLOSURE B l
at or above the normal operating band during the event.
DEC 61985
Clinton Power Station On November 27, 1985, Illinois Power Company released a news Bulletin which stated that construction of Clinton Power Station would be essentially complete by the end of December 1985. However, as stated in the Bulletin, because of delays in completing systems for testing it is anticiaated that fuel loading will occur between late February and late Marc 1 1986.
Hope Creek Generating Station By letter dated November 29, 1985, Public Service Electric & Gas Company announced that the fuel load date for Hope Creek has slipped to February 1986. This date is based on a recently completed assessment of the status of work activities necessary to support fuel loading and low power testing. Based on a June 1985 Caseload Management Team visit to the site, both NRR and Region I believe a February 1986 fuel load date is possible.
Palisades Plant Palisades Plant shut down at midnight on November 30, 1985 for a refueling outage, replacing the remaining components that are not qualified for post-accident environment, and completing the remote panel and isolation switch installation for alternative safe shutdown capability per Appendix R.
Early in the morning of December 2, 1985, the plant staff observed wave action was eroding the beach area of the site and had washed away the sand under an extensive length of security fencing leaving about a three foot vertical gap between the bottom of the fence and the sand. This resulted from 40 mph winds from the west and an unusually high lake level. The only plant components that were threatened were two water storage tanks with low level contaminated water. The plant staff backfilled and installed rip rap around the tanks to prevent them being undermined. During this activity, the front end loader being used slipped down the eroded beach and flattened 50 feet of security fence. Another 100 feet of security fence is undermined and leaning at a 45* angle toward the lake. Two security guards were posted along the damaged fence line. By the morning of December 3, 1985, the winds had died down, erosion had stopped and the plant staff is repairing the damage and continuing the backfilling.
Catawba, Unit 2 I
On December 5 Duke Power Company informed us that the Catawba Unit 2 current schedule for fuel load is January 22, 1986. The licensee previous date was January 15, 1986. The delay was caused by the recent main bearing failure in one of the TDI diesel generators.
ENCLOSURE B i
l DEC 6 1985
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At 3:44 a.m. CST, on December 3, 1985, River Bead Station (RBS)...
synchronized their turbi(e generator vith the utility, power grid for the first time. At that time, RBS was at 7% rqted power at opetating pressure and temperature. At 4:20 a.m., while operating at 10%' power, RBS experienced a turbinc: trip due to an appar.elet'?reversa power,
condition on the. generator: The licensee doc.o not believe an actual s
reverse power situation Occurred,4 but believes <the problem is in relay i.
circuitry. Region,IV it f ollowing.4p. RB5 is now proceeding with SRL' h.'
1, and turbine trip testing.
h On November 29, 1985, RBS experienced asturbipe trip caused by a high 7 intermediate range monitor reading. Subsequently, a reactor scram occurred as a result of a cold water slua c3used by feed water 3
fluctuations. During this scram, the fuse ~ far the backup scram valves' blew. This problem was'duii'to a wiring errcT, which failed to observe the correct polarity for the electr? cal system of the backup scram valves. The licensee believes the Wirirg error accurred during maintenance, subseque'nt to acceptance'ter.t for'the backup scram n
system. Region IV is folloy,ing up.
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ENCLOSURE B DEC 6 1985 w
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1 NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS WEEK ENDING DECEMBER 6, 1985 1.
DEFUELING On December 4,1985, the licensee completed cutting the tangled and i
damaged fuel rods and rod-bundles on top of the debris bed. The licensee plans to load this material into special debris buckets and then place the' loaded buckets into the fuel canisters. This effort should improve fuel loading efficiency and increase the amount of fuel loaded into a canister. On December 5,1985, the licensee surveyed the debris bed and made debris height measurements. These actions were performed to locate and count damaged endfittings _for future planning and identify appropriate locations to place debris loading buckets.
On December 5, 1985, a small fire occurred when an unsecured light bulb at the railing of the defueling platform tool slot ignited paper towel material wrapped around the bulb. The light bulb was deenergized and the fire was extinguished in less than one minute. There were no personnel contaminations or increases in airborne activity in the building. NRC personnel at the defueling coordination center observed that the i
licensee's actions were appropriate. Precautions to prevent a recurrence l
have been taken by the licensee.
1 Beginning December 9,1985, defueling activity will be increased to three team entries from two team entries per day. During the past week, in-reactor building defueling time was increased to almost 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per entry team from the previous average of about 3 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
In part, l
this increase was due to the elimination of respirator requirements (see Weekly Status Report of November 25 - November 30,1985). Since the occupational dose due to transits remains the same per entry, the increase in defueling time per team should result in an overall man-rem savings.
l 2.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel..
The plenum is on its storage stand in the deep end of the fuel
-transfer canal. A dam has been installed between the deep and shallow ends of the fuel. transfer canal. The deep end is filled with water to a depth of about 20. feet (about 5 feet above the top of the plenum).
DEC 6 1985 ENCLOSURE B l
.. -.. ~ -..-
r The modified internals indexing fixture is installed on the reactor vessel flange and is floeded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the internals indexing fixture for defueling.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat foss to.the reactor building ambient atmosphere.
Incore thermocouple readings range from 69*F to 94 F with an average of 83*F.
The average reactor building temperature is 56 F.
The reactor building airborre activity at the Westinghouse platform is 1.1 E-7 uCi/cc Tritium and 6.4 E-10 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over the fuel c'snister storage racks.
3.
WASTE MANAGEMENT Backwashing of the Defueling Water Cleanup Syst,em (DWCS) filters was unsuccessful in producing any useful extension of the filter life.
The cause of the filter plugging is believed 4 to be very finely divided particulate contamination consisting mainly of iron compounds that blind the sintered metal filter media. The licensee is evaluating the use of a filter precoat material to alleviate the problem.
The kill of algae by addition of hydrogen peroxide in the spent fuel pool was successful in reducing turb/dity.
Hydrogen peroxide was added~ to the fuel transfer canal thh week. Additional hydrogen peroxide additions to both the spent fuel pool and the fuel transfer canal are being evaluated.
Submerged Demineralizer, System (SDS) is temporarily shutdown.
EPICOR II is temporarily shutdown while changing out liners.
Total volume processed through SDS to date is 3~,598,397 gallons, and, the total volume processed through EPICOR II is 2,700,737 gallons.
The licensee has begun construction of a Unit 2 Solid Waste Handling Facility within the Unit 2 owner controlled area &-
The facility technical evaluation report is being reviewed by the TMICPD.
Completion is expected in sumer 1986.
The facility will prepare waste for movement to the shipping / storage facility (Interim Solid Waste Storage Facility) and will store no waste. The facility will house di$ assembly and cutting equipment for shipment preparation of large equipment pieces. A barrel compactor will be located in the facility. Non-compactible waste will be loaded into barrels or boxes.
The facility will also-house, an equipment decontamination facility to complement the temporary decontamination facility in the Unit 2 Auxiliary Building. Liquid radwaste solidification will be performed in the' Unit 2 Fuel Handling Buildin' using the newly installed cement and barrel g
tumbling unit.
/."
4.
RADI0 ACTIVE MATERIAL / WASTE SHIPMENTS November 1 - Unit 2, EPICOR II dewatered resin liner shipment to Hanford, WA.
November 1 - Unit 2 radioactive samples sent to Rockville, MD.
November 5 - Unit 2 laundry shipment of 69 drums ano 3 boxes of protective clothing to Royersford, PA.
November 6 - Unit 2 reactor coolant system samples sent to Oak Ridge, TN.
November 7 - Unit 2 radioactive samples sent to Rockville, MD.
November 12 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
November 13 - Unit 2 laundry shipment of 44 drums and 3 boxes of protective clothing to Royersford, PA.
November 13 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, PA.
November 14 - Unit 2 liquid radioactive sample sent to Rockville, MD.
November 15 - Unit I liquid radioactive sample sent to Rockville, MD.
November 18 - Unit 2 EPICOR II dewatered resii liner shipment to Hanford, WA.
November 19 - Unit 2 laundry shipment of 61 drums and 1 box of protective clothing to Royersford, PA.
November 22 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
November 22 - Unit I liquid radioactive sample sent to Rockville, MD.
November 25 - Unit 1 one solidified evaporator bottoms liners and two dewatered resin liners to Barnwell, SC.
November 27 - Unit 2 check source sent to Forked River, NJ.
November 27 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
5.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles is in progress.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
Decontamination of the pressurizer and "A" D-ring is in progress.
ENCLOSURE B c
l DEC 61985
6.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 16 through November 23, 1985. A gama scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from November 17 through November 23, 1985. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between November 27 and December 5, 1985.
No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
7.
REACTOR BUILDING ACTIVITIES The initial phase of defueling the reactor core is in progress.
Installation of the vacuum defueling system is in progress.
8.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.
Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
9.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
- 10. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for December 12, 1985, at the Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to 10:00 PM.
DEC 6 1985 ENCLOSURE B
5-At that meeting GPUN will provide a status of defueling activities and Mr. and Mrs. Aamodt will provide information regarding their health effects evaluations.
Persons desiring the opportunity to speak before the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
1 4
ENCLOSURE B DEC 6 1985
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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending December 6, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Section:
141(b) of NWPA:
Submittal of MRS Proposal Status:
The staff has been informed by DOE that the formal submittal of its MRS proposal to the Commission and EPA for review and comment, in accordance with the NWPA, will be delayed until about December 15 (previous schedule was December 2). The staff understands that the delay is related to DOE considera-tion of comments by Tennessee State review groups on the pro-posed MRS.
Action:
NRC staff will review the MRS proposal and provide comments to the Commission for approval and transmittal to DOE.
The comments will be submitted with the MRS proposal to Congress.
Section:
121(a) of NWPA:
EPA Final High-Level Waste Standards Status:
EPA final rule for Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste became effective November 18, 1985 (50 FR 4003).
Action:
Staff is currently preparing revisions to 10 CFR Part 60 for conformance to EPA standards, and will provide a proposed rule to the E00 and the Commission in January,1986.
Section:
114(e) of NWPA:
Project Decision Schedule (PDS)
Status:
In the draft PDS, DOE requested that all affected Federal agencies l
review Section 10 - Compliance with Federal Statutes, Regulations, and Permits, and submit a report to DOE by January 1,1986.
l Action:
The requested report has been prepared by ELD and is currently under review by NMSS for submittal to DOE.
l l
EitCLOSURE C DEC G1985 l
l
.m
Table S-3 Rulemaking The EDO agreed, by memorandum dated November 29, 1985 with NMSS recommendation, to drop the planned rulemaking to add a narrative explanation to Table S-3, the
" Table of Uranium Fuel Cycle Environmental Data" in 10 CFR Part 51.51, and to incorporate new values for Rn-222 and Tc-99.
The principal reason for dropping the rulemaking is that there are no reactor licensing cases which are still open for which we need, for hearing purposes, the narrative explanation of Table S-3 or the new values for Rn-222 and Tc-99. A Commission Paper on the proposal to drop the Table S-3 rulemaking action will be prepared. Work will continue in RES on the environmental assessment of the fuel cycle environmental effects of high burnup in LWR fuels and the applicability of Table S-3 in reviewing proposed license amendments to authorize going to high burnup.
Exxon Nuclear Company, Inc. (ENC)
On November 4-8, 1985, a member of NMSS accompanied a Region V Inspector during an inspection of ENC. The uranium hexafluoride dry conversion process equipment was observed prior to issuance of a license amendment authorizing operation with enriched uranium.
Dry Storage of Spent Fuel A meeting between Foster Wheeler Company (FW) and General Electric Company (GEC) of the United Kingdom (UK) and NMSS staff was held on November 25, 1985.
FW and GEC presented a design concept for dry storage of spent fuel - the MVDS (Modular Vault Dry Store).
A system similar to it is being used at the Wylfa power plant in the UK. Fuel assemblies are proposed to be stored in sealed tubes in an air atmosphere at a maximum fuel rod cladding temperature of about 150*C. A topical report is expected to be submitted to NRC in July 1986.
NFS-Erwin Strike by OCAW members continues.
There has been some negotiating between the Union and NFS within the last eight weeks but no resolution has been reached.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities.
No problem with site operations has arisen to date.
l ENCLOSURE C 6M
1 i.
Items of Interest Week Ending December 6, 1985 i
4 1.
The following Significant Enforcement Actions were taken during the past week:
i a.
EN 85-78, Proposed Imposition of Civil Penalty in the amount of $500 was issued November 27, 1985 to DelMonte Corporation (Walnut Creek,
]
CA). This action is based on the unauthorized removal and improper disposal of a generally licensed Filtec gauge containing 100 milli-curies of americium-241.
b.
EN 85-79, Proposed Imposition of Civil Penalty in the amount of l
$5,000 was issued December 5, 1985 to Exam Company (Tulsa, OK). This action is based on the failure to perfonn surveys after each radio-graphic exposure and the failure to follow operating and emergency procedures.
2.
The following IE Preliminary Notifications were issued during the past week:
'a.
PNO-IIT-85-2B, Southern California Edison Company (San Onofre Unit 1),
Status Report from NRC Incident Investigation Team, b.
PNO-I-85-90, Pennsylvania Power & Light Company (Susquehanna Units 1
& 2), Both Susquehanna Units Trip.
c.-
PNO-I-85-91, Yale University (New Haven, CT), Disposal of Phosphorous-32 l-In A Landfill.
l d.
PN0-II-85-113, Bryan W. Whitfield Memorial Hospital (Demopolis, AL),
Inadvertent Incinceration of Radioactive Material.
l e.
PNO-II-85-113A, Bryan W. Whitfield Memorial Hospital (Demopolis, AL),
Inadvertent Incineration of Radioactive Material (Update).
f.
PNO-II-85-114, Florida Power Corporation (Crystal River Unit 3),
Unscheduled Shutdown Greater Than 48 Hours.
i g.
PNO-III-85-95A, Detroit Edison Company (Fermi 2 Nuclear Power Plant),
Damage to Diesel Generator During Testing (Update).
r h.
PNO-III-85-100, Consumers-Power Company (Palisades' Nuclear Power l
Station), Lake Water Threatens Plant Site.
i.
PNO-IV-85-60, Basin Industrial X-Ray, Inc. (Midland, TX), Radiography Source Disconnect Resulting In An Overexposure.
j.
PNO-V-85-80, Pacific Gas & Electric Company (Diablo Canyon Unit 2),
Unexpected Partial Reactor Trip.
ENCLOSURE D DEC 01985 l'
i
k.
PN0-V-85-81, Pacific Gas & Electric Company (Diablo Canyon Unit 2),
Reactor Trip During Load Rejection Test.
1.
PN0-V-85-82, Pacific Gas & Electric Company (Diablo Canyon Unit 2),
Unit 2 Reactor Trip and. Safety Injection (Shutdown to Exceed 48 Hours).
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
a.
IE Information Notice 85-92, Surveys of Wastes Before Disposal From Nuclear Reactor Facilities, was issued December 2,1985 to all pro-duction and utilization facilities, including nuclear power reactors and research and test reactors, holding an operating license or construction permit.
4.
Other Items a.
Part 21 Notifications (1) Carolina Power & Light Company on 12 of 16 ADS and MSIV accumu-lator valves produced by Rockwell Edward (Part 21 #85-444).
(2) Transamerica Delval on standby diesel intake and exhaust valve springs produced by Betts Srping Company (Part 21#85-448).
(3) Paul Monroe on pipe snubber brackets at Beaver Valley (Part 21
- 85-450).
(4) Arizona Nuclear Power on steam traps in a Texas steam turbine (Part21#85-460).
b.
Civil Penalties Paid (1) EA 85-95 issued December 2, 1985, Commonwealth Edison (LaSalle),
$125,000.
(2) EA 85-47 issued December 4, 1985, American Can Company, $250.
c.
Management Meeting IE Director attended a Senior Management Meeting in Region I December 5, 6, 1985.
d.
Inspection Accompaniment A representative of the Operating Reactor Programs Branch, Division of Inspection, participated in a special week-long team safeguards inspection at Rancho Seco. Another representative of this branch accompanied a physical security inspection at Georgia Tech's nonpower reactor.
ENCLOSURE D DEC 6 1985
e.
Outage Inspection Representatives of the Reactor Construction Programs Branch, Division of Inspection, and the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, began an outage design inspection at Dresden 3.
f.
Materials Interface Chief, Safeguards Materials Programs Branch, Division of Inspection, other branch representatives, and a Program Support and Analysis Staff representative attended the Materials Interface meeting in Region IV.
g.
High Level Waste Repository Program Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, participated with NMSS and DOE in a public meeting on December 4, 5, 1985 about the High Level Waste Repository Program.
h.
Equipment Qualification Management and representatives of the Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs met with regional managers on December 3 to discuss IE's program for equipment qualification inspections.
1.
ASME Committee Meeting Director, Division of Emergency Preparedness and Engineering Response, attended a meeting of ASME's Committee on Operation and Maintenance in St. Petersburg, FL. A representative of the Events Analysis Branch attended the concurrent meeting of ASME's Valves and Pumps Subcommittee.
i i
ENCLOSURE D DEC 6 1985
m OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending December 6,1985 Semiscale An unsuccessful attempt to run Semiscale Test S-NH-2 was made on November 26, 1985. This is a simulated 2.1 percent cold-leg break in a 4-loop pressurized water reactor (PWR) without high pressure safety coolant injection. Failures in the accumulator system resulted in coolant injection at higher than design pressure and excessively high flow rates throughout the injection period due to failure to valve out the nitrogen source to the accumulators. This test will provide data for code ansessment regarding the effectiveness of operator recovery actions.
x;iother attempt to perform the test is expected on December 4,1985.
Uncertainty Study A study is being done at the Brookhaven National Laboratories (BNL) to determine quantitatively the uncertainty in the source terms.
On Thursday, November 21, 1985, a peer review meeting was held in Bethesda, Maryland, to critique the methodology that is proposed by the BNL staff for this study.
Fifteen people were at the meeting:
6 revicwors; 2 NRC project managers; and several observers.
Organizations represented by the review group were the NRC, the IDCOR Program, the Battelle Columbus Laboratories and the Sandia National Laboratories.
The meeting consisted of presentations by the BNL staff, discussions by all attendees and comments by the reviewers.
The reviewers were requested to provide written comments by December 6, 1985. The comments will be used to refine the methodology and identify issues likely to arise when the results are presented.
ENCLOSURE o DEC f ihE
. HYDROCOIN Workshop on Ground-Water Modeling for Waste Management The third Hydrologic Code Intercomparison.(HYDROCOIN) workshop and coordination meeting was held at the OECD/ Nuclear Energy Agency offices in Paris, France, from November 18, 1985, through November 20, 1985.
The NRC was represented by Thomas J. Nicholson, RES/DRPES/ESB, and Paul The purpose of the workshop was to review and discuss Davis of Sandia.
the comparison of computer simulation results for previously defined ground-water flow problems associated with generic high and low-level The workshop participants were from Western European waste sites.(Britain, France, Germany, the Netherlands, Sweden, Norway, countries Switzerland) Canada, Japan, and the United States (both Finland, and NRC and DOE). Computer simulation results for validation exercises on various waste management problems were presented and compared. Specific topics discussed were ground-water flow in bedded salt and unsaturated zone systems, and comparisons of particle tracking techniques. The capabilities and difficulties of specific computer programs used in the discussed. Future problems for ground-water flow simulations were also validation of models using field experimental data were reviewed and Discussions of proposals for the next level of formally identified.
work for sensitivity and uncertainty analyses resulted in tentative agreements on the types of problems to be chosen and the simulation outputs to be used for comparisons. The next HYDROCOIN meeting will be in Japan in May of 1986.
I Recently Issued Publications Draft Regulatory Guide and Value/ Impact Statement: Design of an Independent Spent Fuel Storage Installation (Dry Storage), Task CE 410-4. Comments requested by February 7,1986.
Contact:
F. Cardile (301) 443-7815.
Reg. Guide 1.82, Rev.1
" Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident", November 1985.
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DEC 61985 I
RES Rulemaking Activities Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors (Part 50) (Appendix J)
The proposed rule would update and revise the 1973 criteria for preoperational and periodic pressure testing for leakage of primary and secondary containment boundaries of water-cooled power reactors. The revision is needed to resolve continuing conflicts between licensees and NRC inspectors over interpretations, current regulatory practice which is no longer being reflected accurately by the existing rule, and endorsement in the existing regulation of an obsolete national standard that was replaced in 1981.
Interoffice concurrence has been completed and minor editorial coments on the rule are being incorporated prior to going forward to the EDO for concurrence and forwarding to the Comission for permission to submit a Federal Register notice requesting public comment.
Licensing Recuirements for the Storage of Spent Fuel and High-Level Radioactive haste (Part 72)
The proposed rule is intended to include within existing regulations for the storage of spent fuel in an independent spent fuel storage installation regulations for the storage of spent nuclear fuel and high-level radioactive waste in a monitored retrievable storage installation, as required by the Nuclear Waste Policy Act of 1982.
The proposed rule package was forwarded from the ED0 to the Comission on November 25, 1985, as SECY-85-374 for notation vote on the staff's recommendation that the Comission approve publication of the notice of proposed rulemaking allowing 90 days for public comments.
Standards for Protection Against Radiation (Part 20)
Radiation protection philosophy and technology have changed markedly since the present Part 20 was promulgated nearly 30 years ago. Because the present Part 20 has beccme outdated, most radiation protection actions occur through licensing actions independent of Part 20. A complete revision is necessary to l
provide better assurance of protection against radiation; establish a clear health protection basis for the limits; reflect current information on health risk, dosimetry, and radiation protection practices and experience; provide NRC l
with a health protection base from which it may consider other regulatory I
actions taken to protect public health; be consistent with recommendations of world authorities (ICRP); and apply to all licensees in a consistent manner.
The Federal Register notice of proposed rulemaking for 10 CFR Part 20 was provided to DRR, ADM, on November 29, 1985.
DRR will incorporate coments from Chairman Palladino and Comissioner Asselstine into the preamble. The staff will publish the notice in the Federal Register within the next week or two for a 120-day public coment period.
ENCLOSURE E DEC 6 1985
i ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 6, 1985 j
Interacency Task Force Meeting The Interagency Task Force for Nuclear Exports held its monthly meeting on November 26 at the Department of Commerce. Members of the Task Force are interested in meeting with representatives from RES to discuss possible future research cooperation between Yugoslav nuclear institutes and the NRC. A status report was also presented regarding a proposed Joint Indonesia-U.S.A. Industry / Government Nuclear Energy Seminar which is now scheduled to take place April 21-23, 1986 in Jakarta, Indonesia.
NRC will receive a letter of invitation to participate in this seminar.
Establishment of International Nuclear Technology Liaison Office (INTLO)
This past October the Department of State established the International Nuclear Technology Liaison Office (INTLO) in an effort to improve U.S.
support for the IAEA's Technical Cooperation Program.
In addition to improving the overall planning, implementation and evaluation of U.S.
support for IAEA technical cooperation activities, INTL 0 will provide background infonnation and briefing materials to U.S. officials routinely involved in formulating overall U.S. policy regarding the IAEA. The office receives direction and guidance from an inter-agency Steering Committee headed by the Department of State and consisting of representatives from several offices in the Departments of State and Energy, the U.S. Arms Control and Disannament Agency and the NRC. The Steering Committee held its first meeting on Wednesday, December 4, at i
the Department of State.
International Meet h I
The announcements of the following international meetings supplement those previously announced:
December 9-11, 1985, Vienna, Austria - IAEA Experts Meeting to Plan an International Conference on Radiation Protection in Nuclear Energy December 16-19, 1985, Vienna, Austria - IAEA Consultants Meeting on the Question of Accident Prevention and Management for Water Reactors December 16-20, 1985, Vienna, Austria - IAEA Meeting for Final Preparation of an IAEA Safety Series Document on Derived Intervention i
Levels for Radiation Protection l
February 10-14, 1985, Vienna, Austria - IAEA Seventh Meeting of the Technical Review Committee on Underground Disposal of Radioactive Waste ENCLOSURE G DEC 6 1985 l
l l
f 2
Foreign Visitors On Monday Mr. Shin Won-Ky of the Nuclear Safety Center of the Korean Advanced Energy Research Institute toured the NRC Operations Center and met representatives of the IE Incident Response and Development Branch to discuss the functional capabilities of the center.
Foreign Trip Reports Milton Vagins, DET, NRR; Gery Wilkowski, Battelle Columbus Laboratory; and Dr. Shafik Iskander, ORNL March 3-22, 1985; Visited the UK, France, Belgium, Finland, Sweden, the FRG, Switzerland, Italy, and Spain:
The object of this trip was to convince most Western European nations to join a cooperative pipe fracture research program that the NRC is developing. The program entitled " International Piping Integrity Research Group (IPIRG)" was discussed in eight countries.
M. E. Mayfield, MEB, NRR September 8-21, 1985; Visited Japan:
The purpose of this trip was to invite the Japanese to participate in the IPIRG program. They committed to join IPIRG.
Phili) W. Robinson, SGMT, NMSS Novem)er 11-19, 1985; Visited Austria:
Mr. Robinson attended the U.S.-IAEA Technical Working Group Meeting on Accounting and Reporting. This working group was convened to review the status of U.S. reporting of safeguards information to the IAEA.
ENCLOSURE G 1
DEC 6 1985
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING DECEMBER 6, 1985 State Program Reviews The New York Department of Environmental Conservation radiation control program will be reviewed December 9-13, 1985 and the Mississippi radiation control program will be reviewed December 16-20, 1985.
t I
DEC 6 1935 ENCLOSURE H
. =. -
..... = _.._. -.
i REGION III.
STATUS REPORT i
DAVIS-BESSE LOSS OF FEEDWATER EVENT DECEMBER 5, 1985 i
i Plant Status The plant remains in cold shutdown. The circulating water canal is drained.
Decay heat loop No. 2 is drained and out of service for maintenance.
1 i
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i ENCLOSURE L i
i DEC 6 1985 l
E, c
Region III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS-MEMO OF AUGUST 5, 1985 c) 78 EE 1.
Item: Adequacy of the licensee's management:and maintenance activities ACTION STATUS / COMMENTS (b) Evaluate and take action on the Region III is observing maintenance activities and
++
licensee's response to findings evaluating LER's, DVR's and other items as they relate to concerning management practices the control of maintenance. A maintenance survey team (e.g., control of maintenance inspection conducted on September 16-20, 1985 confirmed programs and post-trip reviews).
previous concerns identified by Region III. An IE/NRR inspection team will assess maintenance and management practices prior to restart. This inspection is currently planned for mid-January 1986.
6.
Item: Reliability of the AFW containment isolation valves and other safety-related valves ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble-Troubleshooting activities related to containment isolation shooting activities valves AF599 and AF608 are complete. Region III specialists are evaluating and monitoring M0 VATS testing on other safety-related motor operated valves. Of a total of 167 valves, 105 have been completed.
17 valves will require retest.
i (e) Determine that the procedures for Limitorque operators for valves AF599 and AF608 have been adjustments of the AFW isolation adjusted and the valves have been tested under dp valves such as torque switch bypass conditions. Procedure reviews and evaluations of the switches are clear and proper, and training program will be completed prior to restart.
that associated training programs are Confirmatory testing will be performed during startup.
adequate. Confirm that adjustment settings are consistent with plant procedures.
ni 2
h2 4
S si m
r-
TE co ll 8.
Item: Reliability of AFW pump turbines to EE ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble-Troubleshooting activities are complete. Region III shooting activities including will monitor confirmatory testing during plant startup possible hot plant operation to as part of startup test activities.
confirm failure mode.
(d) Verify that the AFW system has been Results of test review group meetings have culminated adequately tested to confirm system in the development of a charter outlining test review group configuration involved with design responsibilities and activities. AFW testing will be basis events, included as part of the testing review team effort.
(e) Review the implementation of the The licensee is developing a training program on resetting operator training program to assure of the trip throttle valve. This training will include proper operator actions, such as resetting of trip mechanism at operating conditions, resetting of trip throttle valve.
therefore, the training will be completed during plant restart.
9.
Item: Reliability of the PORY ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble-Troubleshooting activities have been completed.
shooting activities.
Confirmatory testing will be conducted at operating temperature and pressure. Testing of an equivalent valve indicated a lower flow condition than expected. Testing of a modified PORY completed at the Marshall Steam Station facility on November 15, 1985, demonstrated an acceptable flow rate.
E P8 i
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Other Activities Installation of the new electric motor driven startup feedwater pump is complete. Testing of the motor (uncoupled from the pump) was completed on November 14, 1985. Calibration of the assuciated instrumentation is in progress.
Evaluations and inspections of safety system piping supports are continuing.++
Nonconformance Reports (NCRs) have been written against 2185 of 2387 pipe i
supports inspected so far. Rework is required on 171 of the 838 supports that have had NCRs dispositioned (earlier status reports had reported the number evaluated, an interim stage of the disposition process) by the licensee's staff. Rework has been completed on 64 supports.
M0 VATS testing continues on the 167 safety-related motor-operated valves onsite. Of the 105 valves completed,17 will require rete' sting due to maintenance activities. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
On December 1,1985, the licensee has begun three shift coverage for all ++
work activities.
The service water structure will require ventilation improvements before startup. This modification work appears to be a critical path item. The licensee has not yet performed testing required to allow completion of the design of the ventilation improvements.
The NRC test review team continues to provide weekly coverage of licensee ++
testing activities. Presently, there are very few tests ready for performance.
The testing schedule has been delayed due to the implementation of Facility Change Requests (FCRs) and is expected to accelerate by the end of December.
In the meantime, the test review team is focusing on the review of individual test procedures. The licensee has recently completed and approved a System Review Package for each system under review. The licensee's schedule presently indicates that the test program will be complete by February 12, 1986.
The test review group concludes that completion in early March,1986 is more realistic.
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DEC 6 1935 ENCLOSURE L 4
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I I
ITEMS ADDRESSED BY 'THE ~ COP 9tISSION ' ' WEEK'ENDING ' DECEMBER'6, '1985 A.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION ~AND' VOTE,'4f00'P.M.. TUESDAY, NOVEMBER 26, 1985o wmI55IONER5' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE? Memo SECY to W.~Dircks and H. Plaine dated 12/5/85 I.
SECY-85-370 - Environmental Qualification (EQ). Extension of the November 30, 1985 Deadline for the Fort St. Vrain Nuclear Generating Station The Commission, by a 5-0 vote, approved an order extending the deadline for environmental qualification at the Fort St. Vrain Nuclear G3nerating Station-from November 30, 1985 to May 31, 1986....The Commission also authorized the Director of NRR to authorize operation of Fort St. Vrain at up to 35 percent of l '
full power through May 31, 1986 contingent on a finding that the confirmatory submittals from the licensee are acceptable.
I (Subsequently, on November 26, 1985 the Secretary signed the Order.)
II.
SECY-85-338A - Revised Environmental Qualification (EQ)
Extension Request Post-November 30, 1985 for the Pilgrim Nuclear Power Station The Commission, by a 3-2 vote (with Chairman Palladino and commissioners Bernthal and Asselstine agreeing), approved l
issuing an order denying a request from Boston Edison Company to extend the EQ deadline from November 30, 1985 to February 8,
.1986.
Commissioners Roberts and Zech would have granted the extension to allow documentation of test results to be i
completed.
Commissioner Zech would also have granted an l
extension to allow completion of testing on one piece of equipment.
I (Subsequently, on November 27, 1985 the Secretary signed the Order.)
4 ENCLOSUURE O DEC 61985
E, r
NRR MEETING NOTICES
- DECEMBER 6, 1985 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/9/85 50-346 P-422 Discuss status of Davis-Besse Toledo Edison A. De Agazio 1:00 pm Bethesda restart efforts l
12/9/85 P-118 To discuss IDCOR's plan &
IDCOR Z. Rosztoczy 1:00 pm Bett.esda schedule for analysis of severe accident uncertainties and recent changes in the SARP 1
approach to uncertainty analysis l
12/9/85 50-327 Wi11ste Bldg To discuss Physical Security Plan TVA T. Kenyon 1:00 r5 50-328 7915 Eastern Ave 50-390 Silver Spring, MD 50-391 4
50-259 50-260 50-296 50-438 50-439 12/10/85 B&W Offices To discuss B&W Owners Group B&W Owners Group W. Paulson 3:00 pm 7910 Woodmont technical specification program Bethesda i
l 12/10/85 50-213 Haddam Neck Site To discuss licensee's requests Northeast Utilities F. Akstulewicz i
9:00 am East Hampton, CT for additional exemptions from Southern Co. Serv.
the fire protection requirements Comex of Appendix R Stone & Webster
- Copies of summaries of these meetings will be made publicly avaliable and placed in the respective docket file (s) in the NRC and local public document rooms SP8 4
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E c) o rd NRR MEETING NOTICES
- 31 DECEMBER 6, 1985 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/11/85 50-219 Oyster Creek Site To review the status of GPU Nuclear J. Donahew 9:00 am licensin, actions for Oyster Creek with Plant Personnel i
12/12/85 General Electric To discuss the program for BWR Owners Group J. Stefano 9:00 pm Bethesda, Md.
the elimination of BWR plant suppression pool temperature limit requirement and related schedules.
12/12/85 50-259, Phillips Bldg.
TVA regarding responses to TVA J. Youngblood 1:00 pm 260, 296, Room P-118 September 17, 1985 50.54(f) i 390, 391, 7920 Norfolk Ave.
letter.
438, and Bethesda, MD 439 1
12/12/85 50-275 San Francisco, To discuss theoretical Pacific Gas & Elec.
H. Schierling 9:30 PM 50-323 Calif.
numerical ground motion LLL Advisory Board i
modelling efforts - Diablo Canyon 12/12/85 P-422 To discuss reactor trip breaker B&W Owners Group W. Paulson i
9:00 am Bethesda test interval j
12/17/85 P-118 Reactor coolant pump seal Westinghouse J. Jackson 10:00AM failures Owners Group 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.
m E5 b
c, E3 NMSS MEETING NOTICES FOR WEEK ENDING:
12/6/85 Division of Fuel Cycle and Material Safety c=
G EE DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 12/6-7/85 40-6940
- Reading, Accompany 0RAU on confirmatory D. Cool (FC)
Cool PA survey of KBI Reading fac,ility.
12/10-11/85 40-2061 Glen Site visit to Kress Creek (Kerr-D. Cool (FC)
Cool
- Ellyn, McGee).
IL 12/17-19/85 40-8027 Fort Hearing on Sequoyah Fuels Corp.
E. Shum (FC)
Shum CANCELLED
- Smith, License Amendment for UF to M. Horn (FC) 6 NOW SCHEDULED FOR AK UF Conversion.
D. Cool (FC) 4 1/7-9/86 Division of Safeguards 12/12/85 8th Floor Conf.
SG staff will brief the INMM Committee Baker 9:00 a.m.
Room Willste Bldg.
INMN Safeguards Committee Members RE: Current SG Rules &
SG Staff Amendments Division of Waste Management 12/16-17 Chicago, Illinois Meet with Illinois REBrowning SRomano Department of Nuclear SARomano Safety for the 2nd 4
Annual LLW Generators Conference 12/18 Chicago, Illinois Meet with Illinois RJStarmer RJStarmer Department of Nuclear n,
is Safety and present E;
paper for Technical g;
Advisory, Panel on Alternative LLW g;
Disposal Systers i
HMSS MEETING NOTICES-FOR WEEK ENDING:
12/6/85 Division of Fuel Cycle and Material Safety h
DOCKET ATTENDEES /
DATE/TIPE NUPSER LOCATION PURPOSE APPLICANT NRC CONTACT 12/6-7/85
,40-6940 Reading.
Accompany ORAU on confirmatory D. Cool (FC)
Cool PA survey of KBI Reading facility.
12/10-11/85 40-2061 Glen Site visit to Kress Creek (Kerr-D. Cool (FC)
Cool
- Ellyn, McGee).
IL 12/17-19/85 40-8027 Fort Hearing on Sequoyah Fuels Corp.
E. Shum (FC)
Shum to M. Horn (FC)
CANCELLED
- Smith, License Amendment for UF6 NOW SCHEDULED FOR AK UF4 Conversion.
D. Cool (FC) 1/7-9/86 Division of Safeguards l
12/12/85 8th Floor Conf.
SG staff will brief the INPf1 Comittee Baker 9:00 a.m.
Room Willste Bldg.
INtti Safeguards Committee Members RE: Current SG Rules &
SG Staff Amendments Division of Waste Management 12/16-17 Chicago, Illinois Meet with Illinois REBrowning
- SRomano Department of Nuclear SARomano Safety for the 2nd Annual LLW Generators
'e Conference 12/18 Chicago, Illinois Meet with Illinois RJStarmer RJStarmer Department of Nuclear E
Safety and present P
paper for Technical 8
Advisory Panel on E
Alternative LLW
[
Disposal Systems
E OSP MEETING NOTICES December 6, 1985 m
w DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 12/19/8S Region III Offices, Discuss. transfer of files SP & Reg. III JLubenau 10AM Glen Ellyn, Ill.
and other aspects of 274b staff; OSP Agreement with Iowa D. Flater, Iowa; x29887 B. Hokel, Iowa I
9 P
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December 6, 1985 fh
[*
RII MEETING NOTICE 3$
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 12/10/85 RII Office Meeting with TVA repre-Licensee and Selected Grace 10:00 am sentatives to introduce RII Staff Members new TVA management team to Regional Administrator 12/10/85 Princeton, WVA Enforcement Conference Licensee and Stohr 2
10:00 am Bluestone Paving Co.
Selected RII Staff Members 12/13/85 Region II Meeting with MP&L Licensee, Selected Walker 10:30 am Representatives to discuss RII, NRR & IE Staff recent overspeed event at Members Grand Gulf Unit 1 Diesel Generator i
P S
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