ML20137X790

Weekly Info Rept for Wk Ending 851129

ML20137X790
Person / Time
Issue date:	12/04/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-851129, NUDOCS 8512100630
Download: ML20137X790 (39)

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I December 4, 1985 l

For: The Commissioners

( Frm: T. A. Rehm. Assistant for Operations Office of the EDO I

Subject:

WEEKLY INF0PMATION REPORT - WEEK ENDING NOVEMBER 29, 1985 l A sumary of key events is included as a convenience to those Comissioners 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*

International Programs G State Programs H*

Resource Management I*

Analysis and Evaluation of Operational Data J*

_ Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L l

CRGR Monthly Report M*

Executive Director for Operations N*

Items Addressed by the Comission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)

• No input this week.

lA.Reh, L, stant for Operations Office of the Executive Director for Operations

Contact:

l f92f78ghm.EDO e512100630 851204 PDR COMMS NRCC WEEKLYINFOREPT PDR t _-- _ _ . _ _ _ _ _ _ _ _ _.

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o HIGHLIGHTS OF WEEKLY INFORMATI0fl REPORT WEEK ENDING NOVEMBER 29,1985 San Onofre Unit 1 (50NGS-1) f l

At 5:00 a.m. on November 21, 1985 50NGS-1 had a failure of auxiliary )

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transformer C which de-energized safety bus IC. The operators then l l

tripped the reactor which resulted in the loss of power to the other- i

- safety bus. Both diesel generators started but are not designed to .'i j

automatically assume safety bus loads in such situations. The operators restored offsite power by backfeeding through the main i

transformer in about 4 minutes. The operators then restarted the main

! feedwater pungs, which are driven by electric motors. These pumps are

! thought to have caused a water-hammer event which ruptured a  !

check-valve gasket in the 8 steam generator feedwater bypass line (4" diameter). The resulting leak could not be manually isolated due to

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the high temperature steam environment in the area. The operators fed l

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- all stear generators with auxiliary feedwater and began to cool down

) the pl. ant. The primary-to-secondary leak rate was less than 3 l gallons / day so the leak did not pose a radiological hazard. After '

cooling down to about 280*F, the operators switched over to RNR to i j

continue the cocidown. At about 10:00 a.m., 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after it began, the leak was manually isolated.

i 1 The plant is now in cold shutdown and the licensee is evaluting the ,

i damage done ey the water hansner event. The Cycle 9 refueling outage is

- scheduled to begin on November 30,1985. An NRC Incident Investigation '

Team has been sent to evaluate the event.

' i Peach Bottom Atomic Power Station Unit 3 .

On November 25, 1985, thePeachBottomSeniorResidentInspectori?

l informed the NRR PM that four bolts connecting the steam separator.4 i

I assembly to the shroud head were determined by the licensee to have-cracks. At least one bolt was found to be cracked in half. These i

bolts are 2 inches in diameter by 18 feet long and made out of Inconel '

600 steel. The licensee's preliminary indications are that the defects are the result of intergranular stress corrosion cracking (IGSCC). The r

licensee has taken steps to replace all 48 bolts prior tp Unit 3 1 i start-up. The Region is following up on the generic implications of l

ths event. The Resident Inspectors also indicate concern over the

- disposal of the replaced bolts. The NRR PM has informed the i Engineering Branch of D8L of these findings. j I Niacara Mohawk Power Corporation. Nine Mile Point Nuclear Station. Unit 2 On November 27, 1985, Niagara Mohawk Power Corporation was issued Materials i

License No. $NM-1895 for Nine Mile Point Nuclear Station, Unit 2, authorizing 1 the receipt, possession, inspection and storage of uranium enriched in U-235 isotope contained in fuel assemblies. The Station previously had been a'uthorized l

to receive, store, install and perform preoperational tests of neutron detectors containing uranium enriched in the U-235 isotope. All materials are for eventual

! use at Nine Mile Point Nuclear Station, Unit 2.

NOV 2 91985 l

l OFFICE OF ADMINISTRATION l

Week Ending November 29, 1985 l

ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received 1985 783 41 Granted 615 30 Denied 177 18

- Pending 170 16 ACTIONS THIS WEEK Received i Blair Childs, Requests a list of SES employees in the NRC.

Senior Executives Association (85-768)

Steven C. Sholly, Requests records subsequent to FOIA-85-669 regarding MHB Technical the most recent Seabrook 1 Caseload Forecast Panel Associates meeting; the NRC Resident Inspector's handbook or (85-769) similarly-titled guidance; all coment letters on draft NUREG-0956; and all records regarding the NRC-sponsored Risk Methodology Integration and Evaluation Program at Sandia National Laboratories.

Thomas Devine, Requests all records related to OIA's investigation into Government charges that the NRC staff responded improperly to Accountability allegations by whistleblowers at the Diablo Canyon Project nuclear power plant, including the OIA report.

(85-770)

Thomas C. Houghton, Requests Reactor Operator / Senior Reactor Operator exam KMC, Inc. questions and answer keys for specified exams at Hatch.

(85-771) Farley, Millstone, and Peach Bottom nuclear power plants.

Steven C. Sholly, Requests copies of all containment analyses and source MHB Technical term estimates for the Shoreham nuclear power plant and Associates all records concerning the " Source Tenn Code Package" (85-772) related to NUREG-0956.

Leslie R. Axelrod, Requests copies of Berthold's license 37-21226-02G and Kay-Ray Inc. supporting documentation.

(85-773)

CONTACT: nn . Grimsley ENCLOSURE A NOV 2 91985

2 Received. Cont'd Mark Robinowitz, Requests copies of the contents of all docket files on Health & Energy specified licenses for three listed fims and any other Institute licenses for finns irradiating either medical instruments (85-774) or food.

James T. Lawless, Requests a copy of enclosure 1 to a Novecher 4, 1985 The Plain Dealer letter from C. Norelius to M. Edelman of Cleveland (85-775) Illuminating Company regarding allegations about improper work done by Metaweld Inc.

Sister Barbara Bacci, Requests three categories of records regarding land-Sisters Servants, surveying records on the Fermi nuclear power plant.

of the Imaculate Heart of Mary

. (85-776)

Robert' Guild, Requests copias of all records related to inspection Business and Report 50-456/85-21/50-457/85-22 regarding the Braidwood Professional People nuclear power plant.

. for the Public Interest (85-777)

Stephen H. Hanauer, Requests copies of each Daily Report for January 11 Technical Analysis through February 17,1982.

Corporation (85-778)

James T. Ruppenthal, Requests, on behalf of an individual, records of medical Disabled American and/or psychological exams, and the background Veterans investigation report, concerning the individual's security (85-179) clearance.

Albert E. Levy, Requests records concerning the Susquehanna nuclear power Attorney-At-Law plant.

(85-780)

Steven C. Sholly, Requests copies of all NRC and National Laboratory MHB Technical coment:: concerning American Nuclear Society's Associates report on source terms, reports by the IDCOR program on (85-781) source terms, and the EPRI report on a source term analysis of the Surry nuclear power plant.

Daurice C. Morrow, Requests seven categories of records relating to Fried, Frank, hydrodynamic loads in pressure suppression containments Harris, Shriver & associated with BWRs.

Jacobson (85-782)

(NRCemployee) Requests all records regarding Vacancy Announcement No.

(85-783) 84-2556-4.

ENCLOSURE A NOV 2 91985

3 Granted (NRC e:nployee) In response to a request for the names and addresses (85-751) of persons contacted during his security clearance investigation, informed the requester that the FBI would respond directly to him.

Tab Wilkins, In response to a request for a listingg of project New York State abstracts and firms who applied to the NRC for Phase Science and I or Phase II funding under the Small Business Innovation Technology Research Program (SBIR) during FY85, informed the (85-757) requester that the NRC is not in possession of the requested list. However, we made available the SBIR Phase I and II project sunnaries.

(Anindividual In response to a request for records pertaining to

_ requesting himself that are maintained by the NRC, informed the information about requester the NRC has no records pertaining to him in himself) its radiation exposure, document control, or the (85-760) security systems of records.

(NRCemployee) In response to a request for specified weekly summary (85-761) reports on work assignments, made available the requested reports.

James J. Myron, In response to a request for a listing of the names and The Applied Radiant addresses of companies or institutions that operate Energy Corp. radioactive isotope irradiators categorized by the (85-764) designation 03521, made available a computer printout.

Denied J. Patrick Hickey. In response to an APPEAL TO THE COM ISSION for the -

Shaw, Pittman, release of five denied records regarding mis-

- Potts & Trowbridge administration reports for the second, third and (85-A-31-85-372 fourth quarters of 1984 pertaining to 18 specified hospitals, made available one record. Continued to deny the four records which are investigatory records compiled for law enforcement purposes.

ENCLOSURE A NOV 2 91935

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• WEEKLY INFORMATION REPORT  !

DIVISION OF CONTRACTS l l WEEK ENDING NOVEMBER 29, 1985

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i PROPOSALS UNDER EVALUATION  !

RFP No.: RC-MMS-86-002 l 4

Title:

"The Need for Spent Fuel Storage Capability"

Description:

Technical Assistance to the NRC in determining spent fuel inventory

and storage capacity projections through calendar year 2000, i Period of Performance

21 months l Sponsor Office of Nuclear Material Safety and Safeguards  !

Status RFP closed on November 26, 1985. Proposals forwarded to Source Evaluation L Panel for review on November 26, 1985. i

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( RFP Nog: RS-01E-85-167 l'

Title:

L" General Course in Non-Destructive Examination Technology and Codes"  !

i' Description The purpose of this project is to provide NRC personnel the detailed technical training in non-destructive examination (NDE) and the  !

appilcable codes necessary to enable them to conduct in-depth l

inspection of NRC licensed facilities under construction or

modification.  !

Period of Performance Three years i i Sponsor Office of Inspection & Enforcement Status Best and Final offers are due on December 9,1985. l I

RFP No. : RS-SEC-86-201 i

Title:

" Stenographic Reporting Services"

Description:

Contractor will provide stenographic reporting services for NRC

{g Commission meetings held in the Washington, D.C. Metropolitan Area.

Period of Performance

Two years with an option to extend one additional year.

i Sponsor Office of the Secretary is - Status

Best and Final offers. received.on November 26, 1985 and forwarded to

Source Evaluation Panel for review on November 26, 1985.

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1 ENCLOSURE A  :

NOV 2 S 1985

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OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending November 29, 1985 San Onofre Unit 1 (SONGS-1)

At 5:00 a.m. on November 21, 1985 SONGS-1 had a failure of auxiliary transformer C which de-energized safety bus IC. The operators then tripped the reactor which resulted in the loss of power to the other

. safety bus. Both diesel generators started but are not designed to automatically assume safety bus loads in such situations. The operator's restored offsite power by backfeeding through the main transformer in about 4 minutes. The operators then restarted the main feedwater pumps, which are driven by electric motors. These pumps are thought to have caused a water-hemmer event which ruptured a check-valve gasket in the B steam gc,<rator feedwater bypass line (4" diameter). The resulting leak ce ld iot be manually isolated due to the high temperature steam environment in the area. The operators fed all steam generators with auxiliary feedwater and began to cool down the plant. The >rimary-to-secondary leak rate was less than 3 gallons / day so tie leak did not pose a radiological hazard. After cooling down to about 280*F, the operators switched over to RHR to continue the cooldown. At about 10:00 a.m., 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after it began, the leak was manually isolated.

The plant is now in cold shutdown and the licensee is evaluting the damage done by the water hammer event. The Cycle 9 refueling outage is scheduled to begin on November 30, 1985. An NRC Incident Investigation Team has been sent to evaluate the event.

Catawba Units 1 & 2 On November 21, 1985, the Atomic Safety and Licensing Appeal Board (ASLAB) issued ALAB-825 affirming the remaining part of the Licensing Board's operating license author <zation that permits Duke Power Company to receive and store at the Catawba Nuclear Station spent fuel generated at Duke's Oconee and McGuire facilities.

This decision completes the ASLAB consideration of the Licensing Board's

authorization of the issuance of full power operating licenses for the i

Catawba facility.

l ENCLOSURE B NOV 2 91985 L _

Trojan A design deficiency has been identified in the Trojan Residual Heat Removal (RHR) System. Should an RHR pump fail on demand such that the motor breaker closes but the pump fails to provide flow (e.g., sheared shaft), its associated mini-flow recirculation valve would open and provide an alternate flow path from the redundant RHR train and starve some of the flow to the reactor coolant system. Thus, less water would be aumped into the reactor coolant system than intended during the injection plase of a large break loss of coolant accident. It is our understanding that this design deficiency may also exist in other Westinghouse plants.

The licensee, Portland General Electric, has evaluated the deficiency. The licensee's evaluation concludes that there is a margin of approximately 1050 gam per pump. No more than approximately 625 gpm would be diverted througi the recirculation line. Thus, the margin of flow would be about 425 gpm under this scenario. The licensee's vendor, Westinghouse, will provtde a more indepth evaluation.

The resident inspector identified the design deficiency. The unit is currently operating. The staff is presently pursuing the generic implication of this deficiency.

Crystal River Unit No. 1 On Friday, November 22, 1985 Crystal River Unit 3 dropped a control rod and the unit was being shut down to repair the stator. As power was reduced below 50%,

the main feedwater valve was closed and the steam generators were being fed through the 6" startup feed control valves and the 10" low load control valves.

' Low load control is normally used in the 15-50% power range and startup feed

- control in the 0-15% range. Because of previously known control problems on the 6" valve on one steam generator, it and its block valve were closed at about 20% power, and level control shifted to the 10" low load control valve.

This is a slow-acting valve and was unable to respond quickly enough to prevent reduction in that SG level to the EFIC trip point, actuating the AFW system.

Both the electric and steam driven AFW pumps started automatically. To avoid a possible overcooling transient, the operators tripped the electric AFW pump and after several unsuccessful attempts to close the steam admission valve on the steam driven AFW pump finally secured that pump and reset EFIC. Apparently it was expected that the low load control valve would provide satisfactory control.

However, the cold AFW caused a power increase to about 26%, and a high pressure reactor trip resulted.

In an attempt to avoid the trip, the operators had o)ened the PORY but there was no indication that it had actually opened. The 20RV block valve was.then closed.

l ENCLOSURE B NOV 2 01985

l 3-i About three minutes after the trip, the steam admission valve on the AFW pump ,

opened spuriously. (At the time there is no indication of an EFIC or other actuating signal). With the low load control valve at least partly open and (

full AFW flow from one pump SG 1evel increased to 50-70" before the operators were able to secure the AFW pump. No overcooling resulted outside of the normal post-trip envelope. At no time during the entire transient did an j engineering safeguards signal occur.

Separately, on November 23, while the reactor was in Mode 3 and steam generator level transmitters were being calibrated, a false signal again initiated  !

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auxiliary feedwater. This was the second spurious AFW initiation caused by l EFIC transmitter sensitivity. The licensee is examining electrical or i mechanical time delay to eliminate such events.

n The plant was restarted on Sunday, November 24, 1985.

River Bend At 3:00 p.m. CST November 25, 1985, River Bend Station bepan o>erating for the L

< first time in excess of 55 rated power. The Office of Nuc ear teactor Regulation issued a full power operating license for River Bend Station on November 20, 1985.

l Gulf States filed an application for an operating license on April 22, 1981. ,

The low power license was issued on August 29, 1985. The unit went critical on October 31, 1985. The Comission authorized issuance of the full power license on November 15, 1985.

h Peach Bottom Atomic Power Station, Unit 3

- On November 25, 1985, the Peach Bottom Senior Resident inspector ,

informed the NRR PM that four bolts connecting the steam separator l i

assembly to the shroud head were determined by the licensee to have <

cracks. At least one bolt was found to be cracked in half. These l

bolts are 2 inches in diameter by 18 feet long and made out of Inconel

600 steel. The licensee's preliminary indications are that the defects are the result of intergranular stress corrosion cracking (!GSCC). The

) licensee has taken steps to replace all 48 bolts prior tp Unit 3 t

start-up. The Region is following up on the generic implications of ths event. The Resident Inspectors also indicate concern over the disposal of the replaced bolts. The NRR PM has informed the .

Engineering Branch of DBL of these findings. 1 i

Millstone Nuclear Power Station. Unit 3 Operating License No. NPF-44 was issued to Northeast Nuclear Energy Company on Monday, November 25, 1985. The license permits operat'on of i Millstone 3 at power levels up to five percent of rated power. Fuel load was initiated at 11:26 p.m. on Tuesday, November 26, 1985.

Region I estimates fuel load may be complete by Monday, December 2, ENCLOSURE B 1985.

NOV 2 91985

NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR WEEK ENDING NOVEMBER 29, 1985

1. DEFUELING The changeout of hydraulic fluid in the defueling tools hydraulic system was completed on November 25. The new type of borated hydraulic fluid should alleviate the boron precipitation problem experienced during the previous week. Defueling operations resumed on November 25 and 26th.

The licensee had continued success in cutting substantial quantities of broken and tangled fuel rods with a hydraulic shear tool. The cutting is going to continue next week prior to loading the debris into defueling

, canisters.

On November 25, the licensee determined that respirators for this phase of defueling operations would no longer be necessary. This determination was made after air sample analyses and radiation surveys of nearly one month of defueling entries. In general, airborne particulate composite concentration at the defueling work platform has been less than one-tenth of the Maximum Permissible Concentration. The removal of respirator requirements is expected to increase work efficiency and should result in overall occupational exposure reduction.

2. PLANT STATt;S

- 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 and of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep and is filled with water to a depth of about 20 feet (about 5 feet above the top oftheplenum).

- *ihe modified internals indexing fixture is installed on the reactor l

l ENCLOSURE B NOV 2 01985

- vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the Internal Indexing Fixture for defueling.

- Calculated reactor decay heat is less than 12 kilowatts.

- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 73'F to 95'F with an average of 83*F.

- The average reactor building temperature is 57.5'F. The reactor building airborne activity at the Westinghouse platform is 2.7 E-8 uC1/cc Tritium and 1.2 E-10 uti/cc particulate, predominantly Cesium 137.

- Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister storage racks.

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3. WASTE MANAGEMENT

$ After approval of the procedure, the filters on the Defueling Water Cleanup System (DWCS) were backwashed. Both trains of the reactor vessel filtration portions of DWCS will be started to determine the success of the backwash in reducing the filter differential pressure.

- Submerged Demineralizer System (SDS) processing of batch 126 was completed, Fuel Transfer Canal recycle through both Trains and "B" cation sand filter. A total of 406,435 gallons was processed in batch 126.

- The Spent Fuel Pool (SFP) and Fuel Transfer Canal experienced an algae bloom after the filling of the Spent Fuel Pool. A swiming pool filter has been used to reduce turbidity. Studies have indicated that the bloom was due to euglena present in the Spent Fuel Pool before filling. A kill of the euglena is planned ay addition of hydrogen peroxide to SFP to a concentration of 300 ppm.

- 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.

4. 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.

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5. ENVIRONMENTAL MONITORING

- USEnvironmentalProtectionAgency(EPA)sampleanalysisresul'ts show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and tho City of Lancaster Agreement.

ENCLOSURE B NOV 2 01985

- TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 9 through November 16, 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 10 through November 16, 1985. A gamma scan detected no reactor related radioactivity.

- The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between November 20 and November 27, 1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

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6. REACTOR BUILDING ACTIVITIES

- Concrete Core samples were obtained from interior basement walls at two feet and eight feet from the basement floor (281 foot elevation) by a Robot-like vehicle. These samples will be used to characterize the contamination of basement walls. The information will be used to plan decontamination activities of the basement walls.

- The initial phase of defueling the reactor core is in progress.

- Installation of the vacuum defueling system is in progress.

7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES

- Installation of the balance DWCS continued.

- Spent Fuel Pool has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).

8. NRC EVALUATIONS IN PROGRESS

- Technical Specification Change Request number 49.

- Recovery Operations Plan Change number 31.

- SDS Technical Evaluation and System Descriptio i l'pdata.

- 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.

9. PUDLIC HEETING 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.

At that meeting GPUN will provide a status of defueling activities and Mr. and Mrs. Aamodt will provide information regarding their health effects evaluations.

ENCLOSURE B NOV 2 0198!

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- . 4 Persons desiring the oppo'rtunity 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.

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ENCLOSURE B NOV 2 91985

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending November 29, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 141(b) of NWPA: Submittal of MRS Proposal Status: DOE will submit to Congress a proposal containing a " detailed study of the need for and feasibility of" a monitored retrievable storage facility.

ActioVi: According to the draft Project Cecision Schedule, DOE had planned to submit the MRS proposal to NRC for review and comment on December 2, 1985. Current schedules now indicate that this date will be December 15, 1985. DOE still plans on submitting the proposal to Congress with NRC comments on January 15, 1986. The Environmental Assessment (preliminary information) for the MRS has been submitted to the State of Tennessee as of November 8, 1985.

Section: 141(d) of NWPA: Licensing of MRS Status: NRC is currently developing revisions to 10'CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by

, Congress.

Action: The proposed rule on 10 CFR Part 72 was submitted to the Commission otrNovember 25, 1985 for approval, which is expected in January 1986.

The final rule will be proposed after Congress authorizes the MRS, if it does so.

J Section: 114(e) of NWPA: Project Decision Schedule (PDS)

Status: In the draft PDS, DOE requested that all affected Federal agencies review and revise Section 10 - Compliance with Federal Statutes, Regulations, and Permits, and submit a report to DOE by January 1, 1986. i Toe report should include the Federal agency action required by the '

statute, regulation or permit, and the amount of time which should be scheduled to permit agency action.

Action: The requested report has been prepared by ELD and is currently being reviewed by NMSS for submittal to DOE.

ENCLOSURE C NOV 2 91985

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f Near-Term NRC Actions Under the Nuclear Waste Policy Act (cont'd) y Section: 134 of NWPA: Final Rule on Hybrid Hearings Status: The final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel was published in the Federal Register on Tuesday, October 15, 1985 (50 FR 41662).

Action: The final rule on Hybrid Hearings became effective on November 14, 1985.

l Status of NRC/ EPA Interface Efforts Mill Tailings: NRC and EPA staff are working to develop alternate concentra-tion. limit (ACL) guidance which can be used by the NRC in making ACL determina-

tion (;. Staff exchanged and commented on preliminary guidance documents in August. As part of the development of their guidance, EPA is preparing nine site studies, including one for the Riverton remedial action site. NRC staff is currently reviewing the first two site studies and expects to receive the Riverton study for review in December.

LLW: The first study identifying the non-radioactive hazardous components in LLW has just been completed and the report on management options is due to be  ;

completed by the end of December. NRC staff will provide EPA and other interested parties with copies of the final documents and plans to meet with EPA to discuss them.

HLW: Staff continues to work on the rulemaking to confo m NRC regulations to

._the EPA standards and expects to submit a rulemaking package to the Commission by January 1986. The package will include a description of how staff plans to implement the EPA standard.

Niagara Mohawk Power Corporation, Nine Mile Point Nuclear Station, Unit 2 On November 27, 1985, Niagara Mohawk Power Corporation was issued Materials t License No. SNM-1895 for Nine Mile Point Nuclear Station, Unit 2, authorizing the receipt, possession, inspection and storage of uranium enriched in U-235 isotope contained in fuel assemblies. The Station previously had been authorized to receive, store, install and perform preoperational tests of neutron detectors containing uranium enriched in the U-235 isotope. All materials are for eventual use at Nine Mile Point Nuclear Station, Unit 2.

Babcock & Wilcox, Apollo and Parks Township 4

On November 21, 1985, members of the staff (ELD, Region I, NMSS) met with a group of concerned citizens representing the Kiski Valley Coalition (KVC) to discuss Babcock & Wilcox's (B&W) Pennsylvania operations. Included in the group was the Mayor Elect of Apollo, Pennsylvania. The KVC is concerned about past and future operations of B&W's Apollo and Parks Township plants.

l ENCLOSURE C l NOV 2 91985 l

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4 Items of Interest Week Ending November 29, 1985

1. The following Significant Enforcement Actions were taken during the past week:

EN 85-14A, Imposition of Civil Penalty in the amount of $15,000 was issued November 27, 1985 to Nuclear Fuel Services, Inc. (Erwin, TN). The licensee responded to the Notice of Violation and Proposed Imposition of Civil Penalty (EN 85-14, dtd Feb 15,1985) in the amount of $20,000 in the letter dated May 22, 1985. After careful consideration of the licensee's response, the staff has concluded that the violation did occur as set

- forth in the Notice of Violation and Proposed Imposition of Civil Penalty.

The original proposed civil penalty has been reduced by 25%, because of the licer.see's extensive and comprehensive corrective actions.

EN 85-56A, Proposed Imposition of Civil Penalty in the amount of $5,000

- was issued November 26, 1985 to Astrotech, Inc. (Harrisburg, PA). The licensee responded to the Notice of Violation and Proposed Imposition of Civil Penalty (EN 85-56 dtd August 15,1985) in letters dated September 10 and 16, 1985. After careful consideration of the licensee's response, the staff has concluded that the violations did occur as set forth in the Notice.

2. The following IE Preliminary Notifications were issued during the past week:

~a. PNO-I-85-88, Northeast Utility Energy Company (Millstone Point Unit 1), Short Loss of All AC During Refueling Outage.

b. PNO-II-85-110A, Florida Power and Light Company (Turkey Point Units 1 & 2), and Florida Power Corporation (Crystal River Unit 3),

Actions in Response to Hurricane Kate (Update).

c. PNO-II-85-112, Florida Power and Light Company (Turkey Point Unit 4),

Shutdown to Check Valve Motors.

d. PNO-III-85-2A, Southern California Edison Company (San Onofre Unit 1),-Status Report from NRC Incident investigation Team, e.- PNO-V-85-78, Southern California Edison Company (San Onofre Unit 1),

Plant Trip and Rapid Cooldown Due to Steam Leak In The Feedwater System.

3. The following IE Information Notices and IE Bulletins were issued during the past week:

IE Information Notice 85-91, Load Sequences for Energency Diesel Generators, was issued to all Nuclear Power Reactor Facilities holding an operating license or a construction permit.

ENCLOSURE D NOV 2 91985

4. Other Items

a. Incident Response The Chief, Incident Response Branch, Division of Emergency Preparedness and Engineering Response (DEPER) and staff member attended the FRPCC Subcommittee Meeting on Federal Response on November 26, 1985. The meeting discussed upcoming FEMA exercises, the Relocation Tabletop Exercise to be held in December, Mighty Derringer, and the next Federal Field Exercise (FFE).

i

b. Quality Assurance A representative of the Quality Assurance Branch, Division of Quality Assurance Vendor and Technical Training Center Programs (DQAVT), attended a

- meeting on Vogtle Readiness Review in Region II with Georgia Power re.presentatives this week.

c. Inter Grannular Stress Corrosion Cracking (IGSCC)

Representative of Engineering and Generic Communications Branch, Division of Emergency Preparendess and Engineering Response (DEPER), was at the EPRI NDE Center, Charlotte, NC on November 21-22, 1985 to review requalification testing of ITL, GC and TVA Retest NDEresults Personnel in IGSCC of CMT, CE and NES detection with automated UT systems.

were reviewed.

d. B&W Navy Chief, Safeguards Material Program Branch, Division of Inspection Programs was in Atlanta, GA this week to participate in SALP board meeting on B&W -

Navy.

3

e. Independent Design Verification Program (IDVP)

Representatives of 6he Quality Assurance Branch, 18-22, 1985DQAVT, visited Sargent &

to inspect Lundy offices in Chicago, Illinois November corrective actions resulting from Byron 1 IDVP and Clinton IDVP.

ENCLOSURE D NOV 2 91985

OFFICE OF NUCLEAR REGULATOP,Y RESEARCH Items of Interest

Week Ending November 29, 1985 RES Rulemaking Activities Severe Accident Risk Assessment The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being used to support NRR's review of IDCOR submittals. In addition, it will support the staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, con'tainment performance, source terms, and risk in making severe accident decisions.

The viability and effectiveness of containment venting is important to the likelihood and mitigation of consequences of core melt accidents at BWRs.

Examples of possible problems that could effect viability would be the j environment in which the operator must work to perfonn the venting, the integrity of downstream ductwork, and the consequences of venting on the torus.

4 A visit to the Peach Bottom plant (Mark I containment) to assess the viability of containment venting was successfully completed on November 20, 1985. The engineering problems that were anticipated were indeed found, but it is possible that most could be resolved with rather minor plant changes. However, the evaluation of the problem is far from complete. The utility thought the visit was well worthwhile from their standpoint also and commented that the visit was l well planned and professionally executed.

I A two-day retreat was held at Harpers Ferry by selected DRA0 and contractor staff to discuss the content and format of NUREG-1150 and its technical appendices. The meeting was successful, an initial draft detailed outline will be prepared by mid-December 1985, and a revised draft will be issued for comment outside of DRA0 in early January 1986. Preliminary writing assignments

! have been made.

Shipping Cask Response to Severe Transportation Accidents--Modal Study l

l The purpose of this study is to determine the performance of licensed casks under various types of realistic accidents that might occur during shipments of

, spent fuel. This purpose is being accomplished by assessing the performance when subjected to severe transportation accident environments, as well as by assessing the likely frequency of such eavironments. A final report is schedu;ted to be completed by mid-December 1985.

l A draft of Sections 1 and 2 of the final Engineering Report had been received previously from LLNL. Comments on the latter section were sent to LLNL on November 21, 1985. The submission of other sections of this report is currently 2 weeks behind schedule because of extensive comments generated in internal LLNL reviews. A meeting is planned in early December to assure that applicable coments are included in the report in the most expeditious and j applicable manner. ENCLOSURE E NOV 2 81985

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING NOVEMBER 29, 1985 International Meetings The announcements of the following international meetings supplement those previously announced:

December 2-6, 1985, Vienna, Austria - IAEA Consultants Meeting to Assess the Impact of Sea Dumping of Nuclear Wastes on Living Marine Resources

~

December 10-13, 1985, Budapest, Hungary - IAEA Technical Comittee Meeting on Research Reactor Activities in Support of National Nuclear Programes January 27-31, 1986, Vienna, Austria - IAEA Technical Comittee Meeting 1 on Status, Experience and Future Prospects for the Development of Probabilistic Safety Criteria January 27-31, 1986, Vienna, Austria - IAEA Advisory Group Meeting on Waste Acceptance Criteria for Disposal of Radioactive Wastes in Deep Geological Fonnations March 11-14, 1986, Kalpakkam, India - IAEA Technical Comittee on Fast Breeder Reactor Development--19th Annual Meeting of the International Working Group on Fast Reactors September 15-19, 1986, Stockholm, Sweden - IAEA International Symposium

_. on Improvements in Water Reactor Fuel Technology and Utilization International Organization Vacancy Notices The following vacancy notices from the International Atomic Energy Agency located in Vienna, Austria have been posted on NRC bulletin boards:

P-5 Head, Field Procurement Section, Division of Technical Assistance and Cooperation, Department of Technical Cooperation P-5 Earth and Nuclear Scientist / Engineer, Waste Management Section, Division of Nuclear Fuel Cycle, Department of Nuclear Energy P-5 Group Leader, Division of Operations A, Department of Safeguards P-4 Contracts Officer, Experts Section, Division of Technical Assistance and Cooperation, Department of Technical Cooperation ENCLOSURE G NOV 2 91985 i

2 Foreign Trip Reports T. S. Kress, NRC/DAE Program Manager, ORNL October 7-8, 1985; Visited France:

The purpose of this foreign travel was to participate in the fourth and final meeting of the CSNI Special Task Force on Source Terms.

Donald A. Cool, Ph.D., Uranium Fuel Licensing Branch, NMSS October 7-11, 1985; Visited Austria:

Mr. Cool participated in the IAEA advisory group meeting in Vienna on the application of the principles of radiation protection to sources of 4

i . potential exposure, with special reference to radioactive waste rdpositories, d

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ENCLOSURE G NOV 2 91985 1

REGION I TMI-1 STATUS REPORT FOR THE PERIOD NOVEMBER 22-29, 1985

1. Plant Status As of 8:00 a.m. on November 29, 1985, TMI-1 was at 75% power.

2. Test Program Status

- The licensee's planned test program and current status for restart of 4 TMI-1 are shown on the attached Figure 1. As of 1:30 a.m. on November 23, 1985, the licensee completed the required 30 days of operation at the 48%

power testing plateau. After release was granted by the Region I Admin-

- istrator from the 48% hold point, the licensee slowly increased power until reaching the 75% testing plateau at 5:00 p.m. on November 23, 1985.

r During this power escalation, stops were made at 60% and 65% of rated power for integrated control system (ICS) tuning and turbine control valve testing.

Initial testing at the 75% power plateau included routine steady-state tests (facility performance data review, heat balance calculation, and ICS tuning).on November 24 and two automatic reductions to 60% of rated power (runback) tests on November 25, 1985. The first runback test was  ;

initiated by an indicated (not actual) asynnetric control rod position and the second by the planned stopping of one of two main feediater pumps.

The tests appear to be successful based on the licensee's preliminary review of data. The licensee still plans to remain at 75% power until late December 1985.

3. Facility Operations Summary ,

Steady-state operation at 48% power continued until power was increased

" to 75% on November 23, 1985. Except during the runback tests on November 25, 1985,-the plant operated at the 75% power testing plateau for the remainder of the period.

4. Items of Special Interest .

4 NRC Notifications As has been the case in prior periods, the licensee determined that there were no events that required notification of NRC.. There are, however, two items of interest and they are discussed below.

Maximum Power Operating Limitation During the power escalation program, the licensee has trended steam.

generator steady-state water levels versus reactor power and their preliminary conclusion is that the plant will not be able to achieve 100%

of rated power. The nuclear steam system supplier, Babcock and Wilcox

! (B&W), has provided a high steam generator. level limit of 82% on the ENCLOSURE L NOV 2 91965

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4 2

L operating range (0-100%) to assure proper feedwater heating in the downcomer region of the steam gererators. This is an operational limit and not a technical specification limit. The current limit on steam generator level correlates to a projected reactor power of.approximately 82%. B&W plans to perform additional analyses which may result in raising the steam generator high level limit to about 92% as has been done for other B&W plants. This limit would correlate to a reactor power for TMI-1 of about 90% of rated power.

The. rise of steady-state steam generator level with time for a given reactor power is not unique to TMI-1 since other B&W facilities are 1 similarly limited in power output. The problem is apparently due to fouling of heat transfer surfaces and/or flow passages in the steam generator with time. Consequently, a higher steam generatar level is

- needed to transfer the same amount of heat. Power escalation above 75%

power is.not expected to occur until the end of. December 1985. The licensee is working with B&W and other licensees to develop a generic

. solution to the problem.

Reactor Coolant System Leakage Measurements

.Throughout the past.two months of the testing program, the licensee and

-NRC have been monitoring the results of periodic reactor coolant system

(RCS)leakagemeasurements. The calculated values of unidentified RCS leakage through all possible leakage paths and the specific measurements of RCS leakage through the steam generator tubes have remained very low and much below applicable regulatory limits. The unidentified RCS leakage

-remains at approximately -0.15 to -0.25 gallons per minute (gpm) after applying certain correction factors as permitted by the Technical Speci-

- fications. Without these correction factors, the unidentified leakage is

- about 0 to 0.1 gpm as compared with the limit of one gpm. The leakage through steam generator tubes has been about 0.001 to 0.003 gpm (or 0.06 to 0.18 gallons per hour) in recent weeks. Trending results for both unidentified RCS leakage and steam generator tube leakage indicate no increase in leakage after the recent escalation to '75% of. rated power.

The TMI-1 Restart-Staff will continue to monitor these parameters closely as the testing program progresses.

5. NRC Thermoluminescent Dosimeter (TLD) Special Monitoring Program for TMI The special NRC TLDs for TMI for the period November 13 - 25, 1985, were processed at the Region I TLD laboratory. The TLD readings are provided in the attached Table A. The monitoring results indicate that the radiation levels at these monitoring locations remain at natural background levels. These readings can be expected to vary slightly from period to period due to variations in natural background, independent of releases from the plants.

i l E m 0ERE L 4

NOV 2 S 1985 l l

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6. TMI-1 Restart Staff Status During the Period The TMI-1 Restart Staff ecntinued 16-hour shift coverage until 1:30 a.m.

on November 23, 1985, when continuous coverage was initiated of the esca-lation to the 75% power testing plateau. At 5:30 p.m. on that day, the staff began 12-hour shift coverage of steady-state plant operation. This coverage was augmented by region-based inspectors during the turbine runback testing. The shifts were manned by NRC personnel from Region I and by reactor operator examiners from EG8G Idaho, Inc., an NRC contractor.

A Region I project engineer, a reactor engineer, and two startup inspectors were on site during portions of the period to augment the resident inspection staff.

The staff's inspection plan for this period covered the primary functional arsas of operations, maintenance, surveillance, and restart testing with the division of responsibility as noted in previous status reports. The staff continued to evaluate the performance of licensee personnel and the

plant to determine whether the licensee should be permitted to proceed beyond the hold point at 48% power. At 1

54 a.m. on November 23, the licensee was released from that hold point. The decision was based in part on a recommendation from the TMI-I Restart Staff as documented in a memorandum dated November 26, 1985, from W. F. Kane to T. E. Murley.

Contact from the press and public was minimal throughout the period. We continued to maintain daily contact with representatives of the Commonwealth of Pennsylvania during this period.

The TMI-1 Restart Staff issued four daily highlight reports for the Execu-tive' Director for Operations on November 22, 25, 26, and 27, 1985, regar-ding the escalation to 75% of rated power, preliminary results of initial

- tests at that plateau, and the steam generator operating level limitations.

The seventh weekly status report for the period November 15 - 22, 1985, was issued on November 22, 1985.

-7. TMI-1 Restart Staff Composition During Period The THI-1 Restart Staff was comprised of the following personnel during the period:

W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-I Restart Manager D. R. Haverkamps Technical Assistant F. I. Young, Resident Inspector, TMI-1 W. H. Baunack, Project Engineer R. J. Urban, Reactor Engineer N. J. Blumberg, Startup Inspector P. C. Wen, Startup Inspector M. A. King, Shift Inspector, CG&G Idaho, Inc.

T. L. Morgan, Shift Inspector, EG&G Idaho, Inc.

C. .P. Hix, Secretary L. M. Prough, Secretary ENCLOSURE L NOV 2 91985

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9 TABLE A TMI SPECIAL TLD MONITORING RESULTS Station Distance Direction Baseline Field Exposure 11/13/85-11/25/85 (miles) mR/ day mR/ day (Mean s.d.) (Mean s.d.; total uncertainty)

Control #1 - 0.16 + 0.01; 0.02 Control #2 - 0.12 T 0.00; 0.02 2 3.9 101 0.19 + 0.02 0.20 I 0.00; 0.03

~

3 .s 2.7 109 0.16 T 0.02 0.18 I 0.03; 0.03 43 1.8 163 0.16 I 0.02 0.18 I 0.01; 0.03 5 2.2 161 0.18 T 0.02 0.17 T 0.01; 0.03 6 1.0 150 0.17 7 0.03 0.18 T 0.01; 0.03 7 0.6 136 0.17 T 0.02 0.16 T 0.02; 0.02-8 0.4 83 0.16 T 0.03 0.16 T 0.01; 0.02 9 0.5 60 0.16 T 0.02 0.17 T 0.01; 0.03 10 1.7 1 0.14 7 0.02 0.17 I 0.00; 0.03 11 0.9 25 0.16 T 0.01 0.16 T 0.00; 0.02 12 2.8 46 0.16 I 0.02 0.17 I 0.00; 0.03 14 2.5 358 0.14 T 0.02 0.17 T 0.01; 0.03 16 3.1 0 0.14 T 0.02 0.16 7 0.00; 0.02 18 3.5 349 0.17 T 0.03 0.16 T 0.01; 0.02 19 3.2 343 0.17 T 0.02 0.19 T 0.02; 0.03 20 5.0 318 0.16 7 0.01 0.16 I 0.01; 0.02 21 1.3 348 0.13 T 0.01 0.15 T 0.00; 0.02

'22 3.1 17 0.17 I 0.02 0.18 T 0.01; 0.03

_ 23 3.8 64 0.13 T 0.01 0.17 T 0.01; 0.03 24 3.6 44 0.17 I 0.01 0.18 I 0.00; 0.03 34 2.3 267 0.17 T 0.01 0.20 T 0.02; 0.02 35 1.8 299 0.17 I 0.01 0.18 I 0.01; 0.03 36 1.2 267 0.12 T 0.02 0.14 T 0.00; 0.02 37 1.4 256 0.14 7 0.01 0.15 T 0.00; 0.02 38 1.9 225 0.18 T 0.02 0.19 T 0.01; 0.03 39 2.1 200 0.13 T 0.01 0.16 T 0.01; 0.02 40 2.5 204 0.16 7 0.02 0.16 T 0.01; 0.02 46 3.0 177 0.14 I 0.02 0.16 T 0.00; 0.02 50 4.9 145 0.1410.04 0.1810.01;0.03 Abbreviations:

mR = millirem s.d. = standard deviation REMARKS:

Twenty-nine environmental (offsite) locations are monitored on a two-week exchange cycle using special TLDs for the TMI site. Two control TLDs were stored in a 1/2" thick lead shield at the NRC TMI Office for two weeks. The baseline data for the environmental monitoring were calculated using the past naSuhSfb$ckg0ou$0"ra0NEfoEINefs. # " $C URE L NOV 2 91985

REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT NOVEMBER 26, 1985 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.

v Ef! CLOSURE L

~ NOV 2 91985'

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I

! Region'III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO OF AUGUST 5, 1985 to

1. Item: Adequacy of_the licensee's management and maintenance activities -

on ,

' STATUS / COMMENTS ACTION (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 l

j (e.g., control'of maintenance inspection conducted on Septenber 16-20, 1985 confirmed programs and post-trip reviews). previous concerns identified by Region III. An IE

- inspection team will assess maintenance and management practices prior to restart.

! 6. Item: Reliability of the AFW containment isolation valves and other safety-related valves i

ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting activities related to containment isolation ++

4 shooting activities valves AF599 and AF608 are complete. Region III specialists are evaluating and monitoring MOVATS testing on other safety-related motor operated valves. Of a total of 167 valves, 105 have been completed. 17 valves will require retest.

Limitorque operators for valves AF599 and AF608 have been (e) Determine that the procedures for 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.

i adequate. Confirm that adjustment .

settings are consistent with plant procedures.

El P

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z SE 8. Item: Reliability of AFW pump turbines b ACTION STATUS / COMMENTS U$ i 28 (a) Monitor the licensee's trouble- l 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 inv01ved 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.

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I' i

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 associated instrumentation is in progress.

4 Evaluations and inspections of safety system piping supports are continuing. ++

Nonconformance Reports (NCRs) have been written against 2185 of 2387 pipe supports inspected so far. Rework is required on 163 of the 820 supports that l have had NCRs dispositioned (earlier status reports had reported the number P

evaluated, an interim stage of the disposition process) by the licensce's staff. Rework has been completed on 45 supports.

M0 VATS testing continues on the 167 safety-related motor-operated valves ++

onsite. Of the 105 valves completed, 17 will require retesting due to maintenance activities. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.

The licensee has discovered leakage from inspection covers on both steam ++

generators. The licensee plans to drain the reactor coolant system (RCS) to repair the leaks. Draining the RCS may lead to a requirerent to rebuild some of the reactor coolant pump seals.

f The licensee is planning to begin 24-hour, three shift coverage for all work ++

activities on December 1, 1985.

The service water structure will require ventilation system improvements ++-

. before startup. This modification work appears to be a critical path item.

. The licensee has not yet performed the testing required to allow completion of.the design of the ventilation system 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 review team believes that the testing schedule will accelerate by the first week in December and in the meantime is focusing on the review of individual test procedures. The licensee's schedules presently indicate that the test program will be complete by February 2, 1986. The test review group has assessed the licensee's schedule and concluded that completion in early March, 1986 is more realistic.

During the review of the Control Room Emergency Ventilation System as part of

.the SRTP, the licensee determined that existing system tests did not adequately address the operability of the system cooling function. Region III is evaluating the significance of this matter.

i ENCLOSURE L HOV 2 9 E85' 3

ITEMS ADDRESSED BY THE' COMMISSION ' WEEK'ENDING' NOVEMBER'29,'1985 4 A. STAFF REQUIREMENTS ~ - 00ARTERLY ' SOURCE ' TERM '. BRIEFING, ~ 10 t 00 ' A.M. , ' MONDAY, NOVEMBER 4, 1985, CO MISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO

~ PUBLIC ATTENDANCE) Mamo SECY to W. Dircks dated 11/22/85 The commission met with the staff for staff's quarterly briefing on the source term.

Commissioner Asselstine requested that staff provide to the Commission the interim paper on staff's source term effort. He

! would like the interim report to address how the staff proposes j to implement the source term work, what the outstanding technical issues are, how the staff proposes to resolve those issues and

= whether prior to the resolution of the techr.ical issues the staff'can make implementation decisions.

(NRR/RES) (SECY Suspense: 1/3/86)

-Commissioner zech believes that the source term effort is important and should not lose focus or momentum. The dis-solution of the Accident Source Term Program Office and delegation of responsibility to two senior managers appears to defocus the effort. Commissioner zech recommends that the delegation of authority and responsibility be vested in one i senior manager who has the time and resources at his disposal to effectively bring the work to a scientifically defensible and timely closure.

B. STAFF REQUIREMENTS MEMORANDUM ' AFFIRMATION / DISCUSSION AND V0TE, 4:30 P.M.,

- TUESDAY, NOVEMBER 19, 1985o COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE? Memo SECY to H. H. E. Plaine dated 11/25/85

! I. SECY-85-330A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Point Beach l

Nuclear Plant, Units 1 and 2 The commission, by a 5-0 vote, approved an order extending the November 30, 1985 deadline for environmental qualification at the Point Beach Nuclear Plant, Units 1 and 2 until December 31, 1985 for Unit 2 and until the Spring 1986 refueling outage but not later than May 25, 1986 for Unit 1.

(Subsequently, on November 20, 1985 the Secretary signed the Order.)

ENCLOSURE O NOV 2 91985

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B. CONTINUED II. SECY-85-337A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Haddam Neck Nuclear Plant The Commission, by a 5-0 vote, approved an order extending the November 30, 1985 deadline for environmental qualification at the Haddam Neck Nuclear Plant until the January 1986 refueling outage, but no later than January 4, 1986.

(subsequently, on November 20, 1985 the Secretary signed the Order.)

III. SECY-85-335A - Order Regarding Environmental Qualifi-cation Ektension of the November 30, 1985 Deadline for Siquoyah Nuclear Plant, Units 1 and 2

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The Commission, by a 5-0 vote, approved an order denying the requested extension of the November 30, 1985 deadline for environmental qualification at the Sequoyah Nuclear Plant, Units 1 and 2.

l (Subsequently, on November 20, 1985 the Secretary signed the Order.)

IV. SECY-85-339A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Donald C.

Cook Nuclear Plant, Unit 2 1

.The Commission (with Commissioner Asselstine disapproving) approved an order extending the November 30, 1985 deadline for environmental qualification at the D.C. Cook Nuclear Plant, Unit 2 until the February 1986 refueling outage, but no later than February 28, 1986. Commissioner Asselstine provided l

separate comments to be attached to the order.

(Subsequently, on November 20, 1985 the Secretary signed the Order.)

V. SECY-85-345A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Millstone Nuclear Power Station, Unit 1 The Commission (with Chairman Palladino and Commissioner Asselstine disapproving) approved an order extending the November 30, 1985 deadline for environmental qualification at i

the Millstone Nuclear Power Station, Unit 1 until the next outage that occurs after that staff has made a determination on whether an exemption to Section 50.49 can be granted and that is of sufficient duration to replace the equipment in question, l

l ENCLOSURE O

! NOV 2 91985

B. CONTINUED but in any event no later than the next refueling outage for Millstone Unit 1 scheduled for mid-1987 or August 30, 1987, whichever occurs first. Chairman Palladino and Commissioner Asselstine provided separate comments to be attached to the order.

(Subsequently, on November 20, 1985 the Secretary signed the Order.)

C. STAFF REQUIREMENTS - DISCUSSION /POSSIBLE VOTE ON FULL POWER OPERATING LICENSE

' FOR RIVER BEND, 10:00 A.M., FRIDAY, NOVEMBER 15, 1985, COPfiISSIONERS'

' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks dated 11/29/85 The Commission met to discuss the issuance of a full power license for the River Bend Nuclear Power Plant, Unit 1.

The Commission voted 5-0 to authorize the staff to issue a full power license for River Bend, Unit 1.

Chairman Palladino and Commissioner Each requested that staff provide to the Commission the results of a proposed survey of all operating plants and the next few FTOL's to determine what percentage, if any, of shift technical advisors (STA's) do not possess degrees. The staff should additionally provide a proposal or recommendation, if warranted, with respect to its findings.

(NRR) i ENCLOSURE O NOV 2 91985

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hco NRR MEETING NOTICES" DOCKET APPLI'C4NT/

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/3/85 B&W Offices To discuss issues of current B&W Ownsrs Group W. Paulson 9:00 am 7910 Woodmont interest between the B&W Bethesda Owners Group Analysis Committee and the NRC Staff 12/4/85 MNBB-6110 ' Survey presentation of the NRC Staff T. Chang 8:30 am Bethesda March 3rd Chile Earthquake 12/4/85 50-247 P-110 To discuss status of detailed Consolidated Edison M. Slosson 9:00 am Bethesda control room design review 12/4/85 50-315 P-422 To discuss steam generator Indiana & Michigan D. Wigginton 9:00 am 50-316 Bethesda tube leaks, tube plugging & Elec. Co.

corrosion rate for surveillance requirements in Unit 2 12/4/85 50-400 P-118 To discuss Fire Protection Carolina Power & B. Buckley 10:30 am Bethesda issues Light 12/5/85 50-275 MNBB-6507 To discuss proposed spent fuel Pacific Gas & H. Schierling 9:00 am 50-323 Bethesda pool reracking Elec.

12/5/85 50-315 P-422 To discuss hydrogen control Indiana & Michigan D. Wigginton 9:00 am 50-316 Bethesda inside containment and efforts Elec. Co.

to meet 10 CFR 50.44 for D.C.

Cook 1&2 Ccpies of summaries of these meetings will be made publicly available and placed in the respective docket flie(s) in the NRC and local.public document rooms.

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I NRR MEETING NOTICES * ,

.- NOVEMBER 29, 1985 gg

, DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/3/85 50-443 P-110 PSNH Presentation on Seabrook's Public Serv. Co. of V. Nerses 1:00 pm 50-444 Bethesda Cable Tray Testing and Quali- New Hampshire fication Program 12/3/85 50-454 MNBB-6110 To discuss results of review Commonwealth Edison L. 01shan 9:00 am 50-455 Bethesda of Byron LCO Relaxation Program BNL Westinghouse ,

l 12/3/85 50-272 P-442 To discuss RVLIS tech specs Public Serv. Elec. D. Fischer ,

10:00 am 50-311 Bethesda and commitment regarding core & Gas Co.

exit thermocouples 12/3/85 50-259/260/ P-110 To brief staff reviewers on TVA W. Long 9:30 am 296 Bethesda revised Appendix R plan for Browns Ferry 12/3/85 P-422 Quarterly Meeting of EPRI EPRI D. Moran l 1:30 pm Bethesda Light Water Reactor Steering AIF Committee and NRC Policy

! Committee to assess progress and i provide guidance for the EPRI Advanced LWR Program

• Ccpies 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

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_. NRR MEETING NOTICES * '

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DATE/ TIME NUMBER LOCATION PURPOSE ' ATTENDEES NRR CONTACT 1 12/9/85 50-346 P-422 Discuss status of Davis-Besse Toledo Edison A. De Agazio 1 no pm Bethesda restart efforts 12/9/85 P-118 To discuss IDCOR's plan & IDCOR 7. Rosztoczy 1:00 pm Bethesda schedule for analysis of severe accidewnt uncertainties and recent changes in the SARP approach to uncertainty analysis 12/10/85 B&W Offices To discuss B&W Owners Group B&W Owners Group W. Paulson 3:00 pm 7910 Wcodmont technical specification program Bethesda 12/10/85 50-213 Haddam Neck Site To discuss licensee's requests Northeast Utilities F. Akstulewicz 9:00 am East Hampton, CT for additional exemptions from the fire protection requirements of Appendix R 12/11/85 50-424 P-114 To discuss applicant's response Georgia Power Co. M. Miller 9:00 cm 50-425 Bethesda to staff questions on its EALs Southern Co. Serv.

Comex Stone & Webster 12/12/85 50-275 San Francisco, To discuss theoretical Pacific Gas & Elec. H. Schierling 9:30 cm 50-323 Calif. numerical ground motion LLL Advisory Board modelling efforts - Diablo Canyon 12/12/85 P-422 To discuss reactor trip breaker B&W Owners Group W. Paulson 9:00 cm Bethesda test interval Ccpies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in th2 NRC and local public document rooms.

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NMSS MEETING NOTICES FOR WEEK ENDING: 11/29/85 Division of Fuel Cycle and Material Safety .

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E DOCKET ATTENDEES /

PURPOSE APPLICANT NRC CONTACT

$ DATE/ TIE NUpWER LOCATION ,

ill m 40-2061 Chicago, To meet with ANL to discuss supple- M. Horn (FC) Horn 12/2/85 IL mental EIS on Kerr-McGee. W. Nixon (FC)

Reps of ANL 12/10/85 Willste One-quarter scale model' tests for F. Falci (D0E) Chappell 9:00-12:00 Sth floor waste package. Reps of Sandia conf room National Lab R. Chappell (FC) .

12/10-12/85 40-6563 St. Louis, Mallinckrodt - accompany Oak Ridge M. Horn (FC) Shum MD Environmental Assessment Team on site E. Shum (FC) visit and to answer questions. Reps of ORNL 12/11/85 Gaithersburg, Materials Technology Seminar for C. MacDonald (FC) MacDonald 9:00-12:00 MD (NBS) Shipping Casks at the National Bureau of Standards.

12/12/85 Willste To discuss proposed environmental Dr. Hannun (DOE /WV) Clark 2:30 assessment for low-level waste Mr. Blickwedhi (DOE /WV) disposal at West Valley. L. Rouse (FC)

R. E. Cunningham (FC)

T. Clark (FC)

N. Davison (FC)

R. Browning (WM)

T. Nicholson (RES) 12/17-19/85 40-8027 Fort Smith, Hearing on Sequoyah Fuels Corp. E. Shum (FC) Shum AK License Amendment for UF6 to UF4 M. Horn (FC)

Conversion. D. Cool (FC) m a

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LOCATION PURPOSE ATTENDEES CONTACT 4

12/17/85 Chicago, Illinois To meet with Illinois Compacts REBrowning SRomano and talk to generators group SRomano .

DIVISION OF SAFEGUARDS None t

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N:vember 29. 1985' E IE MEETING NOTICES E

DOCKET  ; ATTENDEES /.

DATE/ TIME Nt#BER LOCATION'  ; PURPOSE . APPLICANT .NRC CONTACT 12/2/85 Washington, DC To meet with EPA staff to E. Jordan and E. Jordan discuss implementation of' EPA Incident Response rulemaking on reportable Branch staff members quantities of hazardous materials. F covered by Superfund activities' and its possible effect on reporting requirements of NRC licensees.

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RES MEETING NOTICES November. 29,1985 -

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• DOCKET  : ATTENDEES /

NUPBER LOCATION PURPOSE- APPLICANT NRC CONTACT DATE/ TIME 8th floor Contractor briefing (Sandia) " Locks: Sandia K. Jamgochian-12/5/85 Willste In Physical Protection Systems" RES (Final Draft Report) NMSS IE NRR P-422 Management meeting - Reference Plant F. Gillespie 12/9/85 8:30- Risk Analysis 10:30 AM

Purpose:

To present the results to date' fmm Surry, Peach Bottom and Sequoyah analyses.

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w i RII MEETING NOTICE

• i DOCKET ATTENDEES /

APPLICANT NRC CONTACT NUMBER LOCATION  ! PURPOSE DATE/ TIME ,

Port Gibson, MS Full-scale Emergency Selected RII Stohr 12/3/85 and contractor Exercise at Grand Gulf representatives Quarterly Regional Meeting All Resident Inspectors Walker I:00 pm RII Office' of Resident Inspectors and selected HQs representatives 2

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