ML20137R758

Weekly Info Rept for Wk Ending 851122

ML20137R758
Person / Time
Issue date:	11/27/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-851122, NUDOCS 8512060066
Download: ML20137R758 (43)

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November 27, 1985 For: The Comissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 22, 1985 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 CRGR Monthly Report M*

Executive Director for Operations N*

Items Addressed by the Comission 0 Meeting Notices P Proprietary or Other Sensitive Information (flot for Q external distribution)

• No input this week. _

, 8512060066 851127

/T. A. Re ,

4 sistant for Operations Office of the Execu;ive Director

$hKL ORE PDR for Operations l

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Contact:

! T. A. Rehm, ED0 492-7781

> HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING NOVEMBER 22, 1985 South Texas Project Units 1 and 2 1 The owners of the South Texas Project have announced a delay in the-projected fuel load for Unit 1 from December 1986 to "sumer,1987." They have characterized the delay as being of "approximately six months." No _

significant impact on the construction schedule for Unit 2 was announced, with completion scheduled "in 1989." It was noted that a comprehensive cost and schedule review is now underway to be completed by November 20, 1985.

NUREG-0956 MANAGEMENT ,

The authors of the NUREG-0956 report on source terms met on November 14, .

1985 with six former members of the American Physical Society study group to receive their individual comments. Among their most important coments were the following: (1) the science, apart ilege the numerical techniques, of the numerous source term computer codes should be widely published to permit a broader peer review; (2) the computer codes are not well vali-dated against experimental data, and more should be done to perform and I document such comparisons; (3) notwithstanding their shortcomings, the [

new source term codes should be used for decision making because the

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presentbasisfordecisionmaking(viz., TID-14844)iswrong;(4)the conclusions in draft NUREG-0956 as stated by the staff are too~opti-mistic; (5) the NRC's two-tier code strategy (detailed mechanist 4c codes .

andintegratedcodes)isappropriate;(6)Uncertaintiesneedmorestudy so that an uncertainty range can be given for all results; (7) an impediment to further pro failure analyses; and (8)gressthe riskisperspective the inability to do good conta.inment in NUREG-0956 should be deleted. The meeting was open to the public.

) Oriain-Swaps Involving U.S.-Supplied Materia' i

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in late October, staff members from IP, NMSS, and ELD met with representatives from DOE and State, at the request of State, to discuss the implications of " origin-swaps" which have the effect of changing the national origin of the feed components for uranium inventories. The implications of origin-swapping were discussed in a report to the Comission in August 1979 (SECY-79-58A), in which the staff concluded that origin-swaps involve no proliferation concerns. Domestic l

origin-swaps occur with some regularity but transactions including swaps across national boundaries occur, on the average, only about once each year. Department of State requested a discussion of the origin-swap l process because of its concerns that the U.S. might lose control rights, such as retransfer and reprocessing approval rights, over U.S.-supplied materials when swaps occur. State is continuing to review the matter to '

ensure that U.S. understandings regarding U.S. control rights continue to be shared by our trading partners. Future requests for swaps wQ1 continue to be coordinated with the Executive Branch prior to approyal.

Incident Response On November 19, 1985, the Chief. Incident Response Branch, i Division of Emergency Preparedness and Engineering Response and staff member attended a meeting with FEMA and NRC to discuss the ground rules for NRC participation in the Shoreham ,

exercise. )

, NOV 2 21985 1

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> s 0FFICE OF ADMINISTRATION 1

Week Ending November 22, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 767 41 Granted 603 30 Denied 176 17 Pending 167 17 ACTIONS THIS WEE 6 Received Patty Day, Requests a copy of SECY-85-288, "NRC's Approach to NUS Corporation Training Evaluation Based on Policy Statement on (85-756) Training and Qualification of Nuclear Power Plant Personnel."

Tab Wilkins, Requests a list of project abstracts and firms who New York State applied to NRC for FY85 S8IR funding.

Science & Technology Foundation (85-757)

Francis J. Kreysa, Requests copies of all registrations by six listed Neutron Products firms.

Inc.

(85-758) 1 Diane Curran, Requests three categories of records related to Harmon, Weiss the backfit rule published in the Federal Register

& Jordan on August 8,1985, and any propose 7 or draft versions of (85-759) the rule.

(Anindividual Requests records in the NRC on himself.

requesting information about himself)

(85-760)

(NRCemployee) Requests specified weekly summary reports on work (85-761) assignments.

CONTACT: Connie H. Grimsley 492-7211 ENCLOSURE A NOV 2 21965 I

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> , g Received, Cont'd Pobin Kimling, Requests a copy of the winning proposal submitted in Micro Mart, Inc. response to RFP RS-0RM-85-334.

(85-762)

Bobby G. Hardwick, Requests, on behalf of his client, records concerning McClure, Brannan his client's exposure to radiation at the Clinton nuclear

& Hardwick power plant.

(85-763)

James J. Myron, Requests a list of names and addresses of organizations The Applied that operate radioactive isotope irradiators categorized Radiant Energy by the designation 03521.

Corp. ,

(85-764) ,

Laurie Fowler, Requests records regarding allegations, findings and Law Offices of orders that Pullman Power Product employees intimidated Brian Spears and harrassed quality control inspectors at nuclear  ;

(85-765) facilities.

Laurie Fowler, Requests copies of all records regarding an NRC  ;

Law Offices of investigation by OIA or others of an NRC employee.

Brian Spears (85-766) [

Dana Bottorff, Requests a copy of the draft report of the November 9, Ottaway News 1985, meeting of the ACRS concerning Palo Verde.

Service (85-767) .

Granted Nina Bell, In response to a request for all records regarding a Nuclear Performance Appraisal Team inspection conducted at the Information and San Onofre nuclear power plant starting the week of Resource Service March 1,1985, and fire protection deficiencies at (85-425) San Onofre, made available 46 records.

Jim Pedro, In response to a request for a copy of SECY-85-120, NUS Corporation made available a copy of the requested paper.

(85-717)

Peter Rathje, In response to a request for copies of specified monthly Doc-Search operation reports for the Haddam Neck nuclear power e Associates plant, made available 12 reports. Irformed the requester (85-723) that two additional reports are already available at the .

PDR.

(Anindividual In response to a request for records related to the requesting license issued to Kelly Air Force Base, Texas, information about made available one record.

himself)

ENCLOSURE A NOV 2 21985

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3 Granted, Cont'2d Joel M. Kaplan, In response to a request for copies of procedures, Karlin & Fleisher rules, and regulations in effect in 1973, 1974, 1975, (85-734) and 1976 with respect to radiation exposure of persons working at the Zion nuclear power plant, made available six records.

Ellen M. Neering, In response to a request for records in the possession of Barris, Sott, the ACRS relating to Dr. Jorj Osterberg's compensation Denn & Driker for work performed for the ACRS, informed the requester (85-743) that no records were found subject to this request.

William R. Pearce In response to a request for a copy of the transcript of (85-746) the ACRS Grand Gulf Subcommittee meeting held on January 18, 1974, informed the requester that the transcript is already available at the PDR.

Kenneth T. White In response to a request for a list with five categories (85-749) of information regarding manufacturers who install sealed sources requiring leak testing into devices with registered designs for distribution to licensees, made available a printout furnishing this information.

Denied Mozart G. Ratner, In response to a request for copies of 33 specified Attorney-At-Law records regarding the General Electric facility in (85-554) Wilmington, North Carolina, made available five records.

Denied portions of 22 records containing information which identifies procedures for safeguarding licensed special nuclear material at the licensed facility.

(NRCemployee) In response to a request for records regarding an (85-568) allegation of the employee's misconduct, made available three records. Denied portions of nine records, release of which would constitute an unwarranted invasion of personal privacy.

Joyce Miller Nelson, In response to a request for a copy of SECY-85-279, TCP, Inc. denied this paper in its entirety, release of which would (85-716) tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

i Mozart Ratner, In response to an APPEAL TO THE COMMISSION for the Attorney-At-Law release of a draft handwritten note from Neil Jensen, (85-A-40-85-542) OGC, to the General Counsel and an attached draft handwritten letter from N. Jensen to M. Ratner, continued to deny portions of this record, release of which would tend to inhibit the open and frank exchange of ideas and free flow of advice essential to the l

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deliberative process and would interfere with an j attorney's work-product privilege.

I ENCLOSURE A NOV 2 21985 i

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WEEKLY INFORMATION REPORT  !

DIVISION OF CONTRACTS WEEK ENDING NOVEMBER 22, 1985 RFP ISSUED RFP No.: RS-0RM-85-336

Title:

"ADP Information Technology Support Center Contract"

Description:

End user computing support services for users of NRC microcomputers and NRC users of the NIH computer facility.

Period of Performance: Two years Sponsor: Office of Resource Management Status: Closing date has been extended to December 6, 1985.

PROPOSAL UNDER EVALUATION RFP No.: RS-SEC-86-201

Title:

" Stenographic Reporting Services"

Description:

Contractor will provide stenographic reporting services for NRC Commission meetings held in the Washington, D.C. Metropolitan Area.

Period of Performance: Two years with an option to extend one additional year.

Sponsor: Office of the Secretary Status: Negotiations completed on November 19, 1985. Best and Final offers due on November 26, 1985.

CONTRACT AWARDED RFP No.: RS-ADM-86-235 Titic: "NRC Translation Services"

Description:

The contractor will be required to furnish translation services for reports and other related material provided by NRC when issued by a formal work order.

Period of Performance: Two years Sponsor: Office of Administration / Technical Information & Document Co.ntrol Status: Fixed Price Requirements Contract No. NRC-10-86-235 awarded to SCITRAN, Santa Barbara, California, in the estimated amount of $230,716.00, effective November 18, 1985.

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! EtlCLOSURE A l NOV 2 21985 l

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1 OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST

, Week Ending November 22, 1985 Kewaunee Plant - Plant Trip On November 13, 1985 at 23:29 CST a steam flow / feed flow mismatch resulted in a low steam generator level which in turn caused a reactor trip. Both main

! trip breakers functioned properly.. One of these breakers had failed a bench test on November 7, 1965, a test required by IEB 85-02. The "A" steam generator main feedwater regulating valve was found with its operator sitting 20* from vertical, two of four bolts holding operator to yoke broken and the operator shaft bent. The plant came down normally after the trip. Restart I was planned for about 20:00 CST on November 14, 1985. There was local (Green

! Bay) media interest in the event due to the November 7 reactor trip breaker

! . test failures.

I River Bend Station

On November 8, 1985, Gulf States discovered 16 junction boxes which had not

, been sealed in accordance with their equipment qualification program.

1 Therefore, GSU declared the affected ESF systems inoperable and proceeded in

, accordance with the action statements of the Technical Specifications.

Simultaneously, GSU sealed the junction boxes within the time frame required by the action statements. No shutdown was necessary. Region IV is following up. -

3 Subsequent to finding the problem with the junction boxes, GSU conducted a thorough review of its records to determine if there exists similar problems

in other safety grade equipment. On November 13, 1985, this review effort i identified supplementary steel bracing to pipe supports for the service water piping system had not been installed as called for in the design. As a

! result, the service water system was declared inoperable, which initiated an i LCO. GSU was not able to complete the repairs within action statement's i time limit and the plant was taken to hot shutdown. GSU has completed i installation of the bracing on'one train of the service water system, and

expects to complete the other train later and to continue with surveillance testing. Prior to this shutdown, the River Bend Station was at 41% of rated

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power, approaching the rated conditions for reactor coolant pressure and i j temperature.

GSU received their low power license on August 29, 1985, went critical on i October 31, 1985. Ti.e Commission meeting on full power license for River Bend was scheduled for November 15, 1985.

ENCLOSURE B l

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! Fermi-2 At about 11:00 a.m. on November 13, 1985, emergency diesel generator (EDG)

No. 13 at the Fermi-2 facility suffered significant damage at about two hours into a 24-hour test run. The damage observed to date to cylinder no. 3 of the upper crankline is: (1) a cracked cylinder liner; (2) a broken piston skirt; and (3) damage to the connecting rod bearing. It is presumed that a nearby main crankline bearing has been damaged and initiated the observed damage in cylinder no. 3. Both division 2 EDGs (Nos. 13 and 14) had " cold, dry" starts on November 10, 1985, when they inadvertently were automatically started during a routine surveillance test. EDG Nos. 11 and 12 (division 1) suffered similar damage in January 1985. The cause for those failures was j attributed to " dry" starts (Fairbanks Morse Diesel Generators).

The Fermi-2 facility has been in cold shutdown since early October 1985 to install the independent alternate shutdown system for fire protection and to install environmentally qualified equipment. Prior to this damage to EDG No. 13, the Fermi-2 restart was scheduled for November 30, 1985. Restart after repairs is now tentatively scheduled for December 6, 1985.

i Peach Bottom Atomic Power Station, Unit 2 and 3 -

! On November 10, 1985, smoke was reported in the Radwaste Building. Unit 2 was at 100% power and Unit 3 was in a fuel reloading outage. The licensee's fire 4 and damage team responded and discovered a fire in a cable tray. The fire was extinguished within a few minutes with portable CO, and Ansul extir.guishers.

Due to a hourly fire watch in this area as a result of the licensee's

interpretation of the Peach Bottom TSs, the fire was detected and responded to

in an expeditious fashion. Follow-up investigations by the licensee and

, Regional personnel indicate that damage was confined to a section of the cable tray and associated cable.

1 l The affected equipment included the liquid radwaste processing system and associated controls. No safety related equipment cables or equipment were affected. No release of liquid radwaste occurred during this event and it

appears that no accidental liquid release would have occurred during this event due to equipment failure since the liquid radwaste is not continuously i released but rather batch released.

During the fire, voltage on a static invester dipped, resulted in a change in the e'ectro-hydraulic control system and consequently caused recirculation

runback, thereby reducing power to 75%. Fuel loading was suspended at Unit 3.

l The licensee replaced the damaged cable =and Unit 2 returned to 100% power

(from 75%) on November 11 and fuel movement was resumed on Unit 3. The Region

, has sent their fire protection personnel to the site to continue the investigation of this fire.

ENa0SURE B NOV 2 21985

South Texas Project Units 1 and 2 The owners of the South Texas Project have announced a delay in the projected fuel load for Unit 1 from December 1986 to " summer, 1987." They have characterized the delay as being of "approximately six months." No significant impact on the construction schedule for Unit 2 was announced, with completion scheduled "in 1989." It was noted that a comprehensive cost and schedule review is now underway to be completed by November 20, 1985.

Yankee Power Station During performance of secondary side inspections on the four steam generators (SG), the licensee identified weld cracks on feedwater spargers for SG Nos. 2 and 3. -The sparger on SG No. 2 had a 2" crack on the weld between the nozzle and the sparger ring. The sparger on SG No. 3 had a 360 degree circumferential crack in the wead between the nozzle and the sparger ring.

Additionally the licensee is investigating the possibility that three sparger monitoring brackets are missing from SG No. 3.

The licensee is formulating plans to perform repairs to the spargers and locate the missing brackets. The resident inspector is following the licensee's correction actions.

UCLA Recctor After four years of litigation and one year of negotiations among the parties, the UCLA proceedings for license renewal and their operating license have been terminated by ASLB Board Orders. One Order: (a) approves the parties' '

stipulation, (b) places all conditions and technical specifications of NRC License R-71 into the Order, (c) terminates License R-71, (d) permanently 1 prohibits operation of the UCLA reactor and any use of its parts in another  ;

l UCLA reactor, (e) grants UCLA's request to withdraw its license renewal application, and (f) terminates the license renewal proceeding. The second Order terminates the license termination (dismantlement) proceeding.

Comanche Peak Unit 1 and 2 Revised cost and schedule estimates were announced on November 18 by  !

Texas Utilities Electric Company. A detailed reanalysis and i reinspection effort is presently underway. This effort, and all related plant modifications that may be necessary, is now estimated {

to be complete in time to su) port commercial operation of Unit 1 in mid-1987 and Unit 2 six montis later.

If this schedule is achieved, it is estimated that the plant will cost

$5.46 billion. ,

Previous schedule and cost estimates made in January 1985 were: ear?y 1986 (Unit 1) and mid-1987 (Unit 2) and $4.56 billion.

NOV 2 21985 N LOSURE B

V Calvert Cliffs Units 1 and 2 We have received an application for exemption from Appendix E, dated November 18, 1985, which would reduce the Calvert Cliffs EPZ. At the present time, Appendix E requires a 10 mile EPZ; the licensee has requested a 2 mile EPZ.

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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING NOVEMBER 22, 1985 L

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! 1. DEFUELING j On November 18, 1985, the licensee modified their immediate defueling i strategy from that of pick and place to that of cutting the distorted i fuel rods. Defueling progress has been slow due to interferences and inability to separate fused endfittings. The licensee is cutting fuel

', rods to reduce the interference and improve packing density in the fuel canisters. A problem developed during the week with the defueling tools hydraulic system. Boron in the system plated out on system filters which caused the system to be shutdown on high filter differential pressure.

The fluid is being replaced by an alternate approved hydraulic fluid that

,' has boron in solution. Defueling should recommence on November 26, 1985.

Photographic mapping of the debris bed has been accomplished during the delay. NRC staff observations indicate licensee is continuing to aggressively pursue problem areas and is making imorovements that should enhance overall defueling efficiency.

l l 2. PLANT STATUS j

The facility remains in long term cold shutdown ,fith the Reactor

} Coolant System (RCS) vented to the reactor building atmosphere and i the reactor vessel head and plenum assembly removed from the reactor vessel.

l 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 l 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 l

oftheplenum).

The modified internals indexing fixture is installed on the reactor i

vessel flange and is flooded to elevation 327 feet 6 inches (151 l

feet above the top of the core region). The defueling platform is j installed over the Internal Indexing Fixture for defueling.

ENCLOSURE B NOV 2 21985

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- 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 71'F to 95 F with an average of 83*F.

The average reactor building temperature is 56 F. The reactor building airborne activity at the Westinghouse platform is 1.2 E-7 uCi/cc Tritium and 2.5 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 fuel carister storage racks.

, 3. WASTE MANAGEMENT

- Both trains of the reactor vessel filtration portions of the defueling water cleanup system (DWCS) have been shutdown when the -

filter differential pressure reached the procedural limit.

Evaluation is in progress of the particulate suspension in the RCS.

A procedure has been approved to backwash the filters.

Submerged Demineralizer System (SDS) processing of batch 126 continues, Fuel Transfer Canal recycle th'ough both Trains and "B" cation sand filter. A total of 319,705 gallons has been processed in batch 126 to date.

EPICOR II is temporarily shutdown while changing out liners.

Total volume processed through SDS to date is 3,511,667 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 cf 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.

5. 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.

ENCLOSURE B NOV 2 21985

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- TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 3 through November 9,1985. A gamma 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 3 through November 9, 1985. A gamma scan detected no reactor related radioactivity.

- The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between November 13 and November 20, 1985. No reactor related radioactivity was detected. Analysis showed lodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

C. REACTOR BUILDING ACTIVITIES

- 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 bal,nce 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 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.

ENCLOSURE B l NOV 2 21985 i

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9. PUBLIC MEETING The Advisory Panel for the Decontamination of TMI-2 met with the Commissioners in Washington, DC on November 19, 1985. At that meeting the Panel informed the Commission of their recent briefings by GPUN on defueling plans. Additional topics of discussion included: (1) licensee measures to prevent criticality during defueling, (2) licensee schedule for conducting defueling activities, (3) panel activities related to TMI-2 accident health effects issues, and (4) status of licensee plans for disposition of processed accident water.

The Panel also informed the Commission of its plans for discussing issues at future panel 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.

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 Marictta Avenue, Lancaster, Pennsylvania 17603.

ENCLOSURE B l NOV 2 21985 i

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending November 22, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

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.

The 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 is currently being prepared by ELD and DWM for i submittal to DOE.

NFS-Erwin Strike by OCAW members continues. There has been some negotiating between the Union and NFS within the last six weeks but no resolution has been reached.

NFS is conductir.g limited operations of the HEU production, scrap recovery and R&D facilities. No problems with site operations have arisen to date.

i ENCLOSURE C NOV 2 21985 l

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l Items of Interest Week Ending November P2, 1985

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

None.

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

a. PNS-I-85-15, Northeast Nuclear Energy (Millstone Units 1 & 2),

Handgun Found in Contractor Vehicle Exiting the Plant Protected Area.

b. PNO-I-85-87, General Public Utilities Nuclear Corporation (0yster Creek), Unplanned Scram and Steam Line Isolation.

c. PNO-II-85-109. Tennessee Valley Authority (Browns Ferry Units 1, 2, &

3), Contamination of Individuals During Emergency Drill.

d. PNO-II-85-109A, Tennessee Valley Authority (Srowns Ferry Units 1, 2,

& 3), Update on Contamination of Individuals During Emergency Drill.

e. PNO-II-85-110, Florida Power and Light Company (Turkey Point Units 1

& 2 and St. Lucie Units 1 & 2), and Florida Power Cor7 oration (Crystal River Unit 3), Actions in Response to Hurricane Kate.

f. PN0-III-85-95, Detroit Edison Company (Fermi Unit 2), Damage to Diesel Generator During Testing.

g. PNO-III-85-96, Commonwealth Edison Company (Byron Unit 2 and Braidwood Units 1 & 2), Commonwealth Edison Announces New Inservice Dates for Byron, Braidwood,

h. PN0-III-85-97, Testing Engineers and Consultants, Inc. (Troy, MI).

Theft of Moisture-Density Gauge.

i. PNO-IV-85-58, Gulf States Utilities (River Bend), Reduced Thermal Limit Potentially Exceeded.

j. PNO-IV-85-58A, Gulf States Utilities (River Bend), Personnel Error in Exceeding Reduced Thermal Limit.

k. PNS-V-85-05, Sacramento Municipal Utility District (Rancho Seco),

Improper Access Controls.

1. IE Bulletin 85-03, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings was issued November 15, 1985 to all holders of nuclear power reactor operating licenses or construction permits for action.

ENCLOSURE D NOV 2 21985

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

a. IE Information Notice 85-58, Supplement 1, Failure of a General Electric Type AK-2-25 Reactor Trip Breaker was issued November 19, 1985 to all nuclear power reactor facilities designed by Babcock and Wilcox, Combustion Engineering, and holding an operating license or a construction permit,

b. IE Information Notice 85-87, Hazards of Interting Atmospheres was

issued November 18, 1985 to all nuclear power reactor facilities i holding an operating license or a construction permit and fuel facilities.

c. IE Information Notice 85-88, Licensee Control of Contracted Services l

Providing Training was issued November 18, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

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d. IE Information Notice 85-89, Potential Loss of Solid-State Instru-mentation Following Failure of Control Room Cooling was issued i November 19, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

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! e. IE Information Notice 85-90, Use of Sealing Compounds in an Operating l System was issued November 19, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

4. Other Items

a. Senior Management Meeting l Director, IE, and Director, Division of Inspection Programs, were at the Pilgrim site November 21-27, 1985 to attend a senior manage-ment meeting and the exit meeting for the Safety System Functional Inspection conducted at Pilgrim.

b. Senior Management Meeting j

i Deputy Director, IE, attended a r.onfor management neeting in Region V

November 19-20, 1985 and visited the South Texas site November 21-22, 1985.

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c. Construction Apprairal Team (CAT) Inspection Branch Chief, Reactor Construction Programs Branch, Division of l Inspection Programs was at the South Texas site November 19-22, 1985 to participate in the final week of the CAT inspection. The exit meeting with the utility was held on November 22, 1985.

NOV 2 21985 l

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d. Vendor Program The Vendor Program Branch, Division of Quality Assurance, Verdor, and Technical Training conducted the following inspections this week:

(1) Valley Steel, St. Louis, MO - allegation inspection relating to improper material substitution.

(2) Combustion Engineering, Windsor, CT - to review CE actions concerning problems which occurred at Palo Verde when the pressurizer auxiliary spray system was lost and to review previous inspection findings.

(3) 3M, St. Paul, MN - to review 3M actions concerning recent problems with fire retardant tape that had been applied to cable trays to meet Appendix R requirements.

(4) Northeast Utilities, Millstone 1 and 2. CT, HQ, and Berlin, CT - to review licensee's equipment qualification program implementation as required by 10 CFR 50.49 for Millstone 1 and 2.

(5) Wyle Laboratories, Huntsville, AL - to review test results

. relating to recent EQ testing to TVA and Niagara Mohawk, inspect cables from previous HELB test, verify continued imple-mentation of the QA program, and perform technical review of recent test reports for other customers.

(6) TVA, Knoxville, Chattanooga, and Daisy, TN - to assist NRR in their EQ audit of Sequoyah nuclear plant.

e. Technical Training IE, regional, and NRR representatives met in Chattanooga on November 21, 22, 1985 as an Advisory Group to the TTC on technical training. MDTS also sent an observer,

f. Quality Assurance Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training visited Sargent and Lundy offices in Chicago, IL on November 18-22, 1985 in conjunction with inspection activities associated with implementation of corrective actions resulting from Byron 1 IDR and IDVP, and Clinton IDVP.

g. Seismic Qualification of Relays A representative of the Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response attended a meeting in Clearwater, FL on November 19-21, 1985 concerning seismic qualification of relays. ENCLOSURE D NOV 2 21985 l

1 - . _ . - . _ . _ _ _.

i

h. Intergrannular Stress Corrosion Cracking (IGSCC) Detection A representative of the Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response was at the EPRI NDE Center, Charlotte, NC November 20-22, 1985 to review requalification testing of ITL, GE, and TVA NDE personnel in IGSCC detection with Automated U.T. Systems. Retest results of LMT, CE and NES were also reviewed.

i. Incident Response (1) Indian Point 2 personnel visited the NRC Operations Center to discuss event reporting and NRC response to emergencies.

(2) On November 19, 1985, the Chief, Incident Response Branch, Division of Emergency Preparedness and Engineering Response '

- and staff member attended a meeting with FEMA and NRC to discuss the ground rules for NRC participation in the Shoreham exercise.

(3) Representatives of the Incident Response Branch, Emergency Preparedness Branch, and Operating Reactor Programs Branch, conducted a joint assessment of Region IV during the Wolf Creek exercise on November 20, 1985. Headquarters participa-tion in this exercise included the Executive Team with Commissioner Asselstine as ET Director, the Reactor Safety Team, Protective Measures Team, Liaison Teams, and the Administrative Support Team.

j. Emergency Preparedness (1) Representatives of the Emergency Preparedness Branch (EPB).

Division of Emergency Preparedness and Engineering Response participated as observers in exercises at Perry, Three Mile Island, and Wolf Creek, and as a member of the onsite emer-

! gency preparedness appraisal at Clinton.

(2) A representative of EBP was in Cario, Egypt this week assisting the Egyptian government in developing an onsite and offsite radiation monitoring program for nuclear power plants.

l l k. Public Meeting l A representative of the Reactor Construction Progrms Branch, Division of Inspection Programs attended the public meeting in Bethesda November 19-20, 1985 concerning the Comanche Peak Response Team j Program.

! ENCLOSURE D NOV 2 21985

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1. Events Analysis Representatives of the Events Analysis Branch, Division of Emergency Preparedness and Engineering Response, attended a meeting at Oak Ridge National Laboratory November 20, 1985 to discuss changes to the Nuclear Operations Analysis Center's Part 21/50.55(e) Data Base which was developed for the NRC. Tne purpose of these changes is to facilitate the use of this data base in tracking of Part 21/50.55(e) reports by NRC Headquarters and Regional Offices.

m. Assessment of Inspection Program A representative of the Safeguards M'aterials Program Branch, Division of Inspection Programs was on an assessment of inspection programs with Region I this week in Hartford, CT..

n. Trial Outage Inspection Representatives of the Reactor Construction Programs Branch, Division of Inspection Programs, and consultants, began the pre-operations readiness inspection part of the trial outage inspection at Fort Calhoun nuclear plant. The trial inspection program is scheduled for completion on December 6, 1985.

I ENCLOSURE D l NOV 2 21985

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0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest  ;

Week Ending Novenber 22, 1985 1

Melt-Progression Experiment DF-3 in ACRR The DF-3 (Debris Formation-3) experiment on core-melt progression under core-uncovery accident conditions has been successfully performed in the

ACRR test reactor at Sandia National Laboratories. DF-3 is one in a series of small integral (multi-effect) experiments to provide detailed data on the governing processes in the development of fuel damage, core-melt progression, and hydrogen generation. Results of these experiments are used for the development and validation of models of the governing i processes in the mechanistic SCDAP fuel damage and MELPROG core-melt-progression codes. Time-continuous data on the damage processes and on

i surface temperatures are taken by cinematography of the fuel bundle during , l j the temperature transient to about 2500K produced by steam oxidation of l the Zircaloy fuel cladding. The DF-3 experiment contained a PWR Ag-In-Cd l control rod in the center of the 9-rod fuel bundle, so that the control- l 3

l rod failure temperature and aerosol generation could be measured, along j with the effects of the control-rod materials on core-melt progression.

1 This program is part of the joint international integrated Severe Fuel Damage and Source-Term research program of the NRC and its ten foreign partners. Half of the funding of this program is furnished by the foreign program partners.

i' Preliminary results indicate that the DF-3 experiment successfully met its goals. A dense cadmium aerosol rapidly formed upon failure of the control rod at about 1700K. Peak temperatures from thermocouple readings were about 2400K. Information on surface temperatures and control-rod material t

effects on core melt progression must await detailed examination of the cinematographic film and post-irradiation examination (PIE).

NRU REACTOR TEST Full Length High Temperature test FLHT-2 will be run at Chalk River Canada 4

the week ending December 14, 1985. This is a coolant boilaway test of a i twelve rod full length, commercial enrichment fuel assembly. Peak cladding i temperatures will approach or excead 2400K. Hydrogen concentrations will

. be monitored as the test progresses. The cladding temperature and hydrogen release rate data are needed to evaluate the effectiveness of current accident progression computer models in predicting axial-temperature and 4 hydrogen release relationships for full length fuel assemblies.

i ENCLOSURE E NOV 2 21985

. o Oconee Steam Generator Overfill Transient Calculation As part of the confirmatory research on the pressurized thermal shock rulemaking, the Idaho National Engineering Laboratory has calculated the thermal hydraulic behavior of a combination main steamline break and steam generator tube rupture. The scenario was defined with assistance from staff working on Unresolved Safety Issues A-47 (Control Systems).

It is assumed that the steam generator overfills causing a steamline break and a subsequent rupture of two steam generator tubes. The calculations show that such a scenario would result in downcomer fluid temperatures of 230'F and a pressure of 1600 psia at approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> into the transient.

These results have been transmitted to NRR's Generic Issues Branch and RES' Reactor Risk Branch to establish the scenarios probability of occurrence and overall likelihood of providing "through-wall" cracks.

Nuclear Plant Data Bank (NPDB) Meeting with the Los Alamos National Laboratory (LANL)

The NPDB is a computer based storage system for reactor geometric and operating data. The purpose of the NPDB is to generate TRAC-PF1 and RELAP5 input decks in response to user mesh cell definitions. LANL, Scientech, Inccrporated, RES, and NRR staff met in Silver Spring on November 15, 1985 to ensure a coordinated effort with integrated results.

Cost reductions will be effected by LANL and Scientech by realigning the priorities of tasks in the project schedule.

NUREG-0956 MANAGEMENT The authors of the NUREG-0956 report on source terms met on November 14, 1985 with six former members of the American Physical Society study group to receive their individual comments. Among their most important comments were the following: (1) the science, apart form the numerical techniques, of the numerous source term computer codes should be widely published to permit a broader peer review; (2) the computer codes are not well vali-dated against experimental data, and more should be done to perform and document such comparisons; (3) notwithstanding their shortcomings, the new source term codes should be used for decision making because the present basis for decision making (viz., TID-14844) is wrong; (4) the conclusions in draft NUREG-0956 as stated by the staff are too opti-l mistic; (5) the NRC's two-tier code strategy (detailed mechanistic codes and integrated codes) is appropriate; (6) Uncertainties need more study so that an uncertainty range can be given for all results; (7) an impediment to further pro failure analyses; and (8)gress is the inability to do good containmentthe risk p deleted. The meeting was open to the public.

ENCLOSURE E NOV 2 21985

l Meetings on Natural Analogues to HLW Repositories On November 12 and 13 Dr. Peter Airey of the Australian Atomic Energy  :

Commission (AAEC), Mr. Harold Wollenberg and Dr. John Apps of Lcwrence Berkeley Laboratories (LBL), and Dr. E. J. Bonano of Sandia National Laboratories met with RES and NFSS staff to review research to date conducted by the AAEC on natural analogues to high level waste repositories. " Natural analogues" are >

naturally occurring geologic systems and features that in various ways can be viewed as qualitatively similar to anticipated stages in the lifetime of a geologic repository. The natural analogues being studied by AAEC are three large uranium ore deposits in northern Australia. By comparing calculated  !

results from repository performance models against n;easurements of species and concentrations of migrating radionuclides from natural analogues, some measure of the predictive capability and accuracy of such models can be realized.

A primary focus of the meeting was on establishing direct communication between the NRC mathematical modeling group at Sandia and the field and laboratory researchers at the AAEC and LBL. The group discussed specific problems and needs that should be addressed in attempting to test models. The data being developed by Dr. Airey's group is being used by them to test Sandia's SWIFT mcdel. Although preliminary, results to date indicate good agreement between model predictions and field observations. Further data developed by the AAEC group will be used by Sandia in their NRC research.

On November 5-7, 1985, Dr. Claudia Hackbarth, RES, participated in a meeting of the " Natural Analogues Working Group" convened under the auspices of the Commission of the European Communities in Brussels, Belgium. The primary ,

objective of this meeting was to stimulate international interaction between nodelers and earth scientists, in order to challenge the latter to provide  ;

usable data by the former from natural systems for testing of models used to assess expected performance of geologic repositories. The NRC-sponsored retearch presented by Peter Airey of Australia was the best example of such a successful interaction to date. Several other international projects were discussed, at least one of which the DOE may fund. Specifically, DOE is interested in studying a high-grade uranium ore body exposed by erosion in Brazil, as an analogue to radicnuclide trarsport f rom a high-level repository in crystalline rock, the probable media for DOE's second HLW geologic repository.

ENCLOSURE E

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L,me - - - s - -- *--4' 4 + a -d- A +- ---ei -+Aa-- - - - .+---iha- h ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS 1 WEEK ENDING NOVEMBER 22, 1985 t

Origin-Swaps Involving U.S.-Supplied Material In late October, staff members from IP, NMSS, and ELD met with representatives from DOE and State, at the request of State, to discuss the implications of " origin-swaps" which have the effect of changing the l

) nation:1 origin of the feed components for uranium inventories. The implications of origin-swapping were discussed in a report to the Commission in August 1979 (SECY-79-50A), in which the staff concluded that origin-swaps involve no proliferation concerns. Domestic origin-swaps occur with some regularity but transactions including swaps across national boundaries occur, on the average, only about once each year. Department of State requested a discussion of the origin-swap process because of its concerns that the U.S. might lose control rights. .

such as retransfer and reprocessing approval rights, over U.S.-supplied

. materials when swaps occur. State is continuing to review the matter to ensure that U.S. understandings regarding U.S. control rights continue to be shared by our trading partners. Future requasts for swaps will continue to be coordinated with the Executive Branch prior to approval.

Foreign Visitors On Tuesday Director General Howard K. Shapar of the OECD's Nuclear Energy Agency met with all five Commissioners and IP Director James R. Shea to discuss programs of mutual interest.

On Tuesday Mr. John Sidwell, Director of Security of the UK Atomic Energy Authority (UKAEA), and Mr. Wynn Llewelyn, Head of the UKAEA Programs Branch, met representatives of the NMSS Division of Safeguards i and the NMSS Division of Fuel Cycle and Material Safety to discuss '

i protection standards and transportation critoria for special nuclear materials, i

Foreign Trip Reports _

C. T. Alexander, M. A. Dinkins, N. D. McCollough, and H. R. Payne, ORNL August 5-September 6, 1985; Visited Japan:

The purpose of the trip was to supervise and perform the installation, termination of sensor esbles, and final checkout of Slab Co.e Test Facility-III ORNL/USNRC-supplied sensors at JAERI-Tokai.

l ENCLOSURE G NOV 2 21985

2 Foreign Trip Reports continued Nunzio J. Palladino, USNRC Chaiman Septemt'er 19-27, 1985; Visited Yugoslavia and Austria:

While in Yugoslavia, the Chairman signed a new Arrangement between NRC and the Yugoslav FCEI, helo discussions with senior nuclear safety officials, and visited the Boris Kidric Institute of Nuclear Sciences near Belgrade. In Vienna he attended the IAEA General Conference, participated in a special, two-day scientific program on nuclear safety involving senior regulatory officials from around the world, and signed a renewal of the hRC-Finnish STUK information exchange arrangement.

W. R. Corvin, Development Engineer, ORNL October 7-18, 1985; Visited Finland, the FRG, Italy, and France:

The purpose of the trip was to participate in the lith MPA Seminar on Safety and Reliability of Pressure Components and to obtain information from principal European lab uacories involved in reactor pressure vessel cladding and crack arrest research.

R. E. Battle, ORNL Staff Member October 16-18, 1985; Visited the UK:

The purpose of the trip was to participate in an on-site AC power system specialist meeting in London.

C. N. Kelber, Associate Director for Scientific Programs, RES

_0ctnber 26-November 9,1985; Visited France and the UK:

Dr. Kelber attended the CABRI project Comite Mixte meeting in Aix-en-Provence, the last meeting in which the NRC will participate. In Grenoble he attended the CEA international seminar on Cathare and Bethsy.

l In Culcheth, UK, he reviewed the SRD staff's technical views on selected i topics including LMFBR safety, plant aging, PRA technology, and advanced l computing methods.

Richard E. Cunningham, Director, FCMS, NMSS l October 28-November 2,1985; Visited the UK and France:

Mr. Cunningham participated in the ICRP meeting in Eastbourne, UK. The full commission and its four committees met during the session. In Paris he participated in the IEA/NEA Steering Committee Meeting and the jointly sponsored IEA/NEA " Year 2000" Workshop.

Kyo S. Kim, WMBR, RES November 14-19, 1985; Visited Japan:

Mr. Kim visited JAERI in Tokai-Mura to discuss the experiments that JAERI is undertaking under an NRC-JAERI Agreement. The discussions with JAERI staff related to (a) flow-through glass leaching experiments, (b) transportation of ATM-5 radioactive glass, (c) slow strain rate NOV 2 2198 gests, and (d) radionuclide migration experiments. ENCLOSURE G

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST .

WEEK ENDING NOVEMBER 22, 1985  ;

NARUC Conference ,

Jerome Saltzman attended the meeting of the Committee on Electricity of the National Association of Regulatory Utility Commissions (NARUC) in New York City on November 18. High level waste management, decommissioning and Price-Anderson were included among the subjects discussed by the MARUC Committee.  !

Meeting With Nuclear Insurers .

Jerome Saltzman met with principal officials of the American Nuclear Insurers (ANI) in their offices in Farmington, Connecticut on November 19.

Developments in Price-Anderson legislation, the general state of the casualty insurance industry, insurance views on NRC property insurance and cleanup funding rulemaking and other matters of continuing interest between the NRC and the nuclear insurance pools were discussed.

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I ENCLOSURE H NOV 2 21985

OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING NOVEMBER 22, 1985 At about 5:00am on November 21, 1985, San Onofre Unit 1 experienced a loss of an auxiliary transformer. This resulted in a loss of a vital bus, and the control room lighting was lost. Per procedures, the reactor was manually scrammed which resulted in a short-term (approximately four minutes) loss of all AC power. A sizeable, unisolable leak was then identified in the feedwater system which is used to maintain steam generator levels, and other failures were experienced in the plant equipment. The plant is now in cold shutdown.

There were no releases and adequate core cooling was maintained at all times.

Because of the nature and complexity of this event, the ED0 approved the sending of a five member Incident Investigation Team (IIT) of technical experts to the site to: (a) fact find as to what happened; (b) identify the probable cause as

~,

to why it happened; and (c) make appropriate findings and conclusions which would form the basis for any necessary follow-on actions.

The team is comprised of: The team leader, Thomas Martin, Director of the Division of Engineering and Technical Programs, Region I; Wayne Lanning, Chief, Incident Investigation Staff, AE0D; Steven Showe, Chief, PWR Training Branch, IE - Chattanooga; William Kennedy, Safety Operational Engineer, Division of Human Factors, NRR; and Matthew Chiramal, Chief, Engineering Section, AEOD.

The team was selected on the basis of their knowledge and experience in the fields of reactor systems, reactor operations, human factors, and power distribution systems. Team members have no direct involvement with San Onofre Unit 1. The team started the onsite investigation on November 22.

The licensee agreed to a request by Jack Martin, Regional Administrator, to preserve the equipment in an "as-found" state until the licensee and the NRC team have had an opportunity to evaluate the event. The licensee has also agreed to maintain Unit 1 in a shutdown condition until concurrence is received from the NRC to return to power.

The IIT report will constitute the single NRC fact finding investigation report.

It is expected that the team's report will be issued within 45 days from now.

NOV 2 21985

REGION 1 ENCLOSURE TMI-1 STATUS REPORT FOR THE PERIOD NOVEMBER 15-22, 1985 i

1. Plant Status As of 8:00 a.m. on November 22, 1085, TMI-I was at 48% power.

2. Test Program Status The licensee's planned test program and current status for restart of TMI-1 are shown on the attached Figure 1. As of 1:30 a.m. on November 23, 1985, the licensee will complete the required 30 days of operation at the 48% power testing plateau. Upon receipt of authorization from the Region I Administrator, the licensee plans to slowly increase power to the 75% testing plateau. Initial testing at the 75% power plateau will include a turbine runback to 60% of rated power and return to the 75%

plateau. As discussed in last week's status report, the licensee plans to remain at 75% power beyond the required 30 days to delay operation at 100% power until late December 1985. This would defer the planned trip from 100% power and subsequent maintenance / management review until after the holiday season.

3. Faci?ity Operations Summary Steady-state operation at 48% power continued throughout the period, except during'an inadvertent power excursion to 53% as described below.

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

Inadvertent Power Excursion On November 19, 1985, power was inadvertently raised from 48% to 53% of rated power as a result of an instrument and control technician accidentally raising the setting on the main turbine generator unit load demand module of the integrated control system (ICS). The technician was l in the process of replacing a meter located directly above the ICS l module; and, in reaching over the control room console, his belt buckle caught on the module toggle switch causing power to increase. The shift supervisor immediately recognized that the plant was in a transient and directed that manual control be taken off the turbine generator. Power l was returned to 48% of rated power within five minutes of the initiation

! of the transient.

t ENCLOSURE L NOV 2 21985 I

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2 Enclosure

Emergency Drill and Exercise The licensee conducted an annual emergency exercise on November 20, 1985.

The TMI-1 Restart Staff, in conjunction with NRC TMI-2 Program Office personnel, provided the initial NRC response during the exercise with subsequent participation and assessment by NRC personnel from Region I.

A post-exercise critique was conducted by the licensee at the licensee's media center on November 21, 1985. The NRC concluded that the licensee's emergency ' response was considered adequate to protect the public health and safety but several open items were identified. The detailed findings of the exercise are expected to be issued in four to six weeks.

New Fuel Shipments On November 19, 1985, the licensee received the last of nine shipments of new fuel for use during future refuelings through 1988. This shipment included ten fuel assemblies which brought the total new fuel assemblies

received to 103.

i' Meeting with Susquehanna Valley Alliance On the evening of November 21, 1985, the Director, TMI-1 Restart Staff, met with about fifteen members of the Susquehanna Valley Alliance near Lancaster, Pennsylvania. Following a discussion of the organization and functions of the staff, the Director responded to various questions from the group. SVA members expressed their general and specific concerns regarding the safety of ruclear power plants and their particular concerns regarding both TMI-1 and TMI-2. SVA plans to formalize a i request for additional offsite monitoring by NRC. SVA members stated i that information in past status reports was generally useful to them and they wanted to continue receiving these reports. They expressed disappointment regarding the time it takes to receive the reports.

5. TMI-1 Restart Staff Status During the Period l The TMI-1 Restart Staff continued 16-hour shift coverage during the period. The shifts were manned by NRC personnel from Regions II and IV and by a reactor operator examiner from EG8G Idaho, Inc., an NRC contractor. A Region I project engineer, a reactor engineer, and a startup inspector 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 areas 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 next hold point, which will be reached after 30 days of operation at 48% power as discussed previously in Section 2.

ENCLOSURE L NOV 2 21985 I .

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3 Enclosure Contact from the press and public was minimal throughout the period with the exception of the media coverage of the emergency exercise. We continued to maintain daily contact with representatives of the Commonwealth of Pennsylvania during this period.

The TMI-1 Restart Staff issued one daily highlight report for :;he Executive Director for Operations on November 20, 1985, regarding the inadvertent increase to 53% of rated power that occurred on November 19.

The sixth weekly status report for the period November 8-15, 1985, we.s issued on November 18, 1985.

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

W. F. Kane, TMI-1 Restart Director R. J. Conte, TMI-1 Restart Manager D. R. Haverkamp, Technical Assistant F. I. Young, Resident Inspector, TMI-1 W. H. Baunack, Project Engineer R. J. Urban, Reactor Engineer N. J. Blumberg, Startup Inspector W. D. Johnson, Shift Inspector, Region IV M. A. King, Shift Inspector, EG&G Idaho, Inc.

T. L. Morgan, Shift Inspector, EG8G Idaho, Inc.

W. T. Orders, Shift Inspector, Region II C. P. Ilix, Secretary L. M. Prough, Secretary ENCLOSURE L NOV 2 21985

REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT NOVEMBER 21, 1985 Plant Status 4

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.

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1 OM L NOV 2 21985 i

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Region III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO 0F AUGUST 5, 1985 SE 1. Item: Adequacy of the. licensee's management and maintenance activities w

w gj ACTION STATUS / COMMENTS m

(b) Evaluate and take action on the Region III is observing maintenance activities and evaluating licensee's response to findings LER's, DVR's and other items as they relate to the control of concerning management practices maintenance. A maintenance survey team inspection conducted (e.g., control of maintenance on September 16-20, 1985 confirmed previous concerns identified programs and post-trip reviews). 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 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,101 have been completed. 17 valves will require retest.

(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 differential valves such as torque switch bypass pressure conditions. Procedure reviews and evaluations of switches are clear and proper, and of the 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.

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7. Item: Adequacy of emergency notifications -

me SE ACTION STATUS / COMMENTS j o.

b) (a) Verify the adequacy of the licensee's investigationoftheadequacyofthelicensee'sprocedures

, gj procedures and training for the report- and training for the reporting of events to the NRC

' on ing of events to the NRC Operations Operations Center has been completed. One violation of NRC Center. requirements was found. Inspection results are documented ,

in Inspection Reports 85023 and 85034. IE Information  !

Notice 85-80 was issued dealing with timely declaration of i i Emergency Class, implementation of an Emergency plan, and Emergency Notifications based in part on the findings and conclusions derived from the Davis Besse June 9, 1985 event.

8. Item: Reliability of AFW pump turbines 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 i 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.

I (e) Review the implementation of the The licensee is developing a training program on resetting 4

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.

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9. Item: Reliability of the PORY 3E SE ' ACTION STATU3/ COMMENTS o (a) Monitor the licensee's troubic- Troubleshooting activities have been completed. Confirmatory ++

as shooting activities testing will be conducted at operating temperature and 2R pressure. Testing of an equivalent valve indicated a lower flow condition than expected. Flow results from Crosby (valve manufacturer) testing were higher than the flow results from the Marshall Steam Station test facility. All test data indi-cated flow was less than expected. Additional testing of a modified PORV completed at the Marshall Steam Station facility on November 15, 1985, demonstrated an acceptable flow rate.

12. Item: Resolution of equipment deficiencies ACTION STATUS / COMMENTS A

(a) Monitor the licensee's trouble- All the Region III activities relative to ,.

shooting activities troubleshooting / root cause activities have been completed and are documented in Inspection Reports

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85-021,85-022 and 85-025.*

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• Inspection Report 85025 is in draft and will be issued in approximately I week.

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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 associated instrumentation is in progress.

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

Nonconformance Reports (NCRs) have been written against 2119 of 2314 pipe supports inspected so far. Rework is required on 154 of the 797 supports that have had NCRs dispositioned (earlier status reports had reported the number of

NCRs in an interim stage of the disposition process) by the licensee's staff.

4 Rework has been completed on 44 supports.

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

onsite. Of the 101 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 NRC test review team continues to provide weekly coverage of licensee ++

testing activities. Presently, there are very few tests ready for performance.-

4 The rev.iew team believes that the testing schedule will accelerate by the first week in December and in the meantime is focusing its attentions on the review of the individual test procedures. The licensee's schedules presently indicate that the test program will be complete by February 2, 1986. The test i 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.

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ENCLOSURE L NOV 2 21985 5

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ITEMS ADDRESSED BY THE COPNISSION - WEEK'ENDING NOVEMBER 22, 1985 A. STAFF REQUIREMENTS'- YEAR END' PROGRAM REVIEW, 10:00'A.M.,* THURSDAY, NOVEMBER 7, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE)

Memo SECY to W. J. Dircks dated 11/20/85 The Commission met with the staff to receive the end-of-year status report on NRC expenditures, program goals and accom-plishments.

The Commission requested that staff provide a list of high priority items, including those discussed at the meeting, which they believe should receive attention in the next budget cycle.

(EDO) (SECY Suspense: 1/3/86)

The Commission requested a staff paper on the materials licensing backlog including how long renewals have been pending.

(NMSS) (SECY Suspense: 1/3/86)

' Chairman Palladino's interest in IZ's Outage Program resulted in staff plans to brief the Commission within the next few months.

(IE) (SECY Suspense: 2/86)

Commissioners Asselstine and Bernthal requested a report on l research projects which for budgetary reasons could not be l accomplished. The report should include the impact of cancelled l

or deferred research projects.

(RES) (SECY Suspense: 12/10/85)

Commissioner Zech requested the staff to consider the need for utilities with plants that are either closed or at which construction has been halted to maintain operational, con-struction and maintenance records in the event the utility contemplates reactivation or sale of the plant or plant equip-ment to another utility. The staff is to also examine the method by which the NRC could institute guidance or requirements in this area.

(NRR) (SECY Suspense: 1/10/86)

Although Commissioner Roberts agrees that the maintenance of records would be sound management on the part of the utilities, he believes that the NRC lacks jurisdiction to require licensees to maintain the pertinent records and that it would be inappro-priate for the NRC to involve itself in such utility management decisions. ,-  ;

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NOV S 21985

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B.

STAFF REQUIREMENTS - DISCUSSION OF ENVIRONMENTAL QUALIFICATION E PE00 DST - FORT ST. VRAIN, 2:00 P.M., TUESDAY, NOVEMBER 19, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Men SECY to W. J. Dircks dated 11/21/85 The Comanission met with staff and representatives of Public Service of Colorado to discuss the environmental qualification '

(EQ) extension of the November 30, 1985 deadline for Fort St.

Vrain.

The following persons participated in the meet!ng:

R.F. Walker '

Chairman of the Board, President, and CEO Public Service of Colorado O.R. Lee Vice President Electric Production .

Public Service of Colorado Chairman by 12 noon,Palladino directed the staff to provide to the commission Friday, November 22, 1985 staff's recommendation on Public Service of Colorado's extension request.

(NRR) (SECY Suspense i 11/22/85)

C.

STAFF REQUIREMENTS - AFFIRMATION /DICUSSION AND VOTE, 3:30 P.M., THURSDAY, NOVEMBER 14, l d COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE? Memo SECY to W. Diecks and H. H. E. Plaine11/21/85 dated I.

SECY-85-319A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Nine Mile Point Nuclear Power Station, Unit 1 The Commission, by a 5-0 vote, approved an order-granting an extension in the November 30, 1985 equipment qualification deadline to the next outage of sufficient duration to install the equipment but no later than March 30, 1986.

(Subsequently, on November 15, 1985 the Secretary signed the '

order.)

II.

SECY 85-321A - Order Regarding Environmental Qualification Extension of the November 30, 1985 Deadline for Brunswick Steam Electric Plant, Unit 2 The Com;nission, by a 4-1 vote (Commissioner Roberts disapproving) appi;oved an order denying a request by Carolina Power and Light Company for an extension of the November 30, 1985 equipment qualification deadline for Brunswick Unit 2.

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C. CONTINUED Commissioner Each notsd that in his view the circumstances in i this case may be a factor in mitigating any civil penalties.

(Subsequently, on November 15, 1985 the Secretary signed the order.)

III. SECY-85-322 - Final Amendments to 10 CFR 50.12, "_ Specific ,

Exe:nptions" The Cog. mission (with Chairman Palladino and Commissioners Roberts, Bernthal, and Each agreeing) approved for publication i'

final revisions to the criteria set forth in 10 CFR 50.12(a) for granting exemptions from the requirements of 10 CFR Part 50 with modifications as indicated on the attached pages 33, 51, 60, and 65. Commissioner Asselstine approved in part and disapproved in part. His disapproval is to the addition to page 33 and the failure to include his proposed changes to pages 56, 60, and 66, -

You should revise the rule as indicated and return it for signature and publication in the Federal Register.

(EDO) (SECY Suspense: 12/9/85) i Attachments:(tWecd60< cud As stated D. STAFF REQUIREMENTS - CONTINUATION OF 9/11 DISCUSSION OF PROPOSED STATION BLACK 0UT RULE, 2:00 P.M., THURSDAY, NOVEMBER 14, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to j W. J. Dircks dated 11/22/85 The Commission met with staff to- discuss the " Proposed Station Blackout Rule" (SECY-85-163).

Chairman Palladino and Commissioner Each requested staff to inform the Commission as to whether or not the Committee to Review Generic Requirements (CRGR) has significant technical reservations regarding the proposed rule.

(NNEF (DEDROGR) (EDOSuspense: 12/6/85)

Chairman Palladino requested that Commissioners provide the Secretariat with votes on SECY-35-163.

(OCM)

ENCLOSURE O NOV 2 21985

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• w as NRR MEETING NOTICES

• S? NOVEMER 22, 1985 DOCKET APPLICANT /

DATE/ TIME NUMER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/25/85 50-244 Ginna Site To discuss proposed RG&E Rochester Gas & J. Clifford 9:00 am Ontario, NY management organization Electric 11/26/85 50-344 Trojan Site To discuss requested exemp- Portland General Elec. E. Tourigny 9:00 am Columbia Cty., Ore. tions of Section III.G of

App. R (Fire Protection) and to tour affective 5 areas i 11/26/85 50-346 B&W Company Off. Discuss modifications to SFAS Toledo Edison A. De Agazio

) 9:00 am Landow 220 to assure compliance with Bethesda IEEE 279 t

11/26/85 50-206 P-114 To discuss the proposed stress- Southern Calif. R. Dudley 10:30 am Bethesda strain correlation for large Edison bore piping seismic analysis Impe11 Corp.

(San Onofre 1) 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 i 9:30 am 296 Bethesda revised Appendix R plan for j Browns Ferry i 12/3/85 P-422 Quarterly Meeting of EPRI EPRI D. Moran

! 1:30 pm Bethesda Light Water Reactor Steering AIF

g Committee and NRC Policy p Committee to aisess progress and g provide guidance for the EPRI l

g Advanced LWR Program

• Copi%s of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and socal public dodunent rooms  !

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DATE/ TINE NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/3/85 B&W Offices To discuss issues of current B&W Dwners 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 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-?!6 Bethesda tube leaks, tube plugging & Elec. Cn.

corrosion rate for surveillance i requirements in Unit 2 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.

4 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 1 Crpies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) j in the NRC and local public document rooms.

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z NHSS MEETING NOTICES SE FOR WEEK ENDING: 4/22/05 os -

o' Division of Fuel Cycle and Matcrial Sarcty ,

5'n DOCKET ATTENDEES /

APPLICANT NRC CONTACT NUMBER LOCATION PURPOSE DATE/ TIME 12/4/85 Bal timore, Presentation at Johns Hopkins R. Cunningham (FC) Cunningham 8:30-5:00 MD University - Seminar on Low-level Waste - Under the auspices of CARER.

12/6-7/85 40-6940 Reading, Accompany ORAU on confirmatory D. Cool (FC) Cool PA survey of KBI Reading facility. .

12/10-12/85 40-6563 St. Louis, Mallinckrodt - accompany Oak Ridge M. Horn (FC) Shum M0 Environmental Assessment Team on E. Shum (FC) site visit and to answer questions.

' Division of Waste Management Generic Seismo-Tectonics MBlackford SCoplan December 3-4 NRC, Willste Bldg.

Silver Spring, MD Meeting DOE staff BWIP ES Design JLinehan JLinehan December 3-4 BWIP, Richland, WA JBuckley DOE Staff Generic QA Meeting JKennedy JKennedy December 4-5 DOE,llQ Washington, DC DOE staff Division of Safeguards None E

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g3 RII MEETING NOTICE DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 11/25/85 RII Office Meeting with Georgia Licensee, NRR IE Walker 12:30 pm Power Company representa- and selected RII tives to discuss Vogtle personnel Readiness Review Module Submittals 1:30 pm RII Office Meeting with FEMA to FEMA representatives Stohr discuss results of the and selected RII Browns Ferry exercise personnel

. 11/16/85 RII Office First SALP Board Meeting Representatives from Stohr i

9:00 am B&W NNFD Facility NMSS. IE, ED0 and selected RII staff members 4

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,g REGION.11I MEETING NOTICES m

WEEK ENDING: November 22, 1985 DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 12/14/85 '. 50-373 Glen Ellyn, IL Enf. Conf. Commonwealth Edison A.B. Davis 50-374 LaSalle A.B. Davis & staff 2

t 12/15/85 50-155 Glen Ellyn, IL Fnf. Conf. Consumers Power A.B. Davis 9:15 a.m. Big Rock A.B. Davis & staff 1

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