ML20138H211

Weekly Info Rept for Wk Ending 851018

ML20138H211
Person / Time
Issue date:	10/24/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-851018, NUDOCS 8510280463
Download: ML20138H211 (41)

Text

t

{

9%  !

l i i

!i i i f i  !

j t I

} October 24, 1985 1

i -

For: The Commissioners I

) From: T. A. Rehm. Assistant for Operations, Office of the EDO l i

i

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 10, 1985 (

t s

l A summary of key events is included as a convenience to those Commissioners !

j who may prefer a condensed version of this report. l 1 [

j Contents Enclosure l l Administration A f

l Nuclear Reactor Regulation B  !

~

l Nuclear Material Safety and Safeguards C f Inspection and Enforcement D l f j Nuclear Regulatory Research E t j Executive Legal Director F* f i International Programs G* [

State Programs H* l Resource Management I* f Analysis and Evaluation of Operational Data J*

{

Small & Disadvantaged Business Utilization & Civil Rights K* [

Regional Offices L l CRGR Monthly Report M* l Executive Director for Operations N*

Items Addressed by the Comission 0 j Meeting Notices P 1 I Proprietary or Other Sensitive Information (Not for Q i externaldistribution) 1 i i

• No input this week,  ;

- [

p r.  !

05 tog Enty a

f4 lT.A.Re , stant for Operations

. g pon Office of the Executive Director  !

I for Operations  !

I

Contact:

l T. A. Rehm. EDO l 492-7781 l

l

i i

i HIGHLIGHTS OF WEEKLY INFORMATION REPORT l WEEK ENDING OCTOBER 18, 1985 i l

Fermi-2 i i

The plant was brought to cold shutdown on October 11, 1985 following a  !

reactor scram initiated by a spurious signal. The plant will remain'  !

, shutdown for about 30 to 40 days to install environmentally qualified  !

j equipment and to install and make operational the alternate independent [

j shutdown system for fire protection, j i

However, the pacing item in this shutdown may be replacement of the two  !

turbine bypass lines which have multiple through-wall cracks. These l cracked lines were instrumental in the decision by Region !!! not to l 1et Fermi-2 exceed 55 power prior to the present shutdown. l 1

! TMI-1 Start Up l j .

4 - The plant is at 405 reactor power. The original plan was to hold the l 4

plant at 405 untti late Thursday and conduct a reactor scram. However i

another steam leak has developed in the main turbine throttle drain [

1 lines. There are four drain lines associated with the main turbine '

throttles. Two of these drain lines had strainers and two did not.

Last week, one of the drain lines with a strainer developed a steam leak. When overspeed testing if the main turbine was coupleted, the  ;

i steam leak was repaired by cutting out the strainer and welding in a i new pipe to replace the strainer (a system design change). Now during  !

the first day of operation at 405 power, the remaining drain line with . [

a strainer has developed a steam leak at the strainer. i t

The licensee now plans to conduct the planned reactor trip on loss of  !

main feedwater late in the day on October 16, 1985 vice October 17,:.  ;

1945. The licensee then reaches another NRC hold point and must obtain t Reaion I approval before startup from this planned trip. In the l l original schedule the licensee was to proceed directly to 445 power j l upon starting up from this hold point. However now the licensee will l

have to hold at 405 power long enough to complete nuclear l

{ instrumentation calibration (i.e., allow for Xe buildup). Then the j i licensee will proceed to 485 and hold that power for 30 days. j i

Expansion of Biomedical Rule l

In July the staff met with Drs. Rosalyn Yalow, Henry Wagner, Edward Webster, and other members of the medical community, and pharmaceutical companies to

) explore the expansion of the biomedical waste rule. In that meeting, the  !

I staff made clear that the data necessary for our evaluation would have to be j , provided by the medical and pharmaceutical organization.

, On October 16, 1985, Dr. Rosalyn Yalow called Dr. Lidia A. Roche, of NMS$ '

o staff, to inform her that the American College of Nuclear Physicians has received a 00E grant to obtain the data requ' red to initiate this rule.

OCT 181985 [

t I

s 44 0FFICE OF ADMINISTRATION i Week Ending October 18, 1985 ADMINISTRATIONOFTHEFREEDOM0FINFORMATIONACT{ i STATUS OF REQUESTS i Initial Appeal of .

! Request Initial Decision I i

j Carryovers, 1984 179 23 i Received, 1985 705 40

} Granted 551 28 i Denied 162 16 7 Pending 171 19 i l ACTIONS THIS WEEK Received  ;

I ~

Kelly Epps Requests copies of NRC contracts. I (85-683)

Louise Ponce Requests eight categories of records regarding (85-684) radioactive materials and waste at the Stephan site in Maywood, New Jersey. l l Patty Day, Requests a copy of the record identified as reference l l NUS Corporation 5 in the September 18, 1975, ACRS letter from W. Kerr to I j (85-685) the then Chairman Anders regarding Westinghouse Report

, RESAR-41.

)

l Joseph L. Rhodes Requests records relating to the security of nuclear

(85-686) power plants. t Ken Bossong, Requests 17 categories of records written since  !

. Critical Mass January 1, 1984  !

! Energy Project l (85-687)

! Brandon Blatt, Requests copies of the contract and proposal for the

! Sterling Medical medical services program for Region I personnel.

i Associates, Inc.

(85-688) l Patty Day, Requests copies of SECY-85-150 and any applicable NUS Corporation supplements.

i (85-689) i

! CONTACT: J. M. Felton <

! 492-7211 I

l ENCLOSURE A ocT 181985

2 Received, Cont'd Gregory A. Holmes, Requests specified portions of transcripts of MHB Technical Consnission discussions on the Diablo Canyon nuclear Associates power plant on January 21, 27, and February 5, 1982.

(85-690)

Gregory A. Holmes, Requests four categories of records relating to meetings NHS Technical held on March 8 and April 19, 1982, between NRC and Associates utility officials regarding the Diablo Canyon nuclear (85-691) power plant.

David R. Ennis, Requests operator exam results for the Oconee nuclear I NUS Corporation power plant for 1979 through 1982.

(85-692)

Diane Curran, Requests a copy of the June 27, 1985, memorandum from Harmon & Weiss Harold Denton to William Dircks regarding the final (85-693) rule on backfitting.

Michael J. Alber, Requests copies of proposals submitted by Nuclear Waste GeoTrans Consultants, Inc., (NWC) under RFP RS-NMS-85-009 and (85-694) records related to the evaluvion of GeoTrans and NWC's conflict of interest.

Sheryl Wurl, Requests copies of any complaints lodged against the Dakota Midland Dakota Midland Hospital or Nuclear Services during Hospital calendar years 1984 and 1985 to date.

(85-695)

Billie P. Garde, Requests all records to date related to the loss-of-Government load test incident at the Palo Verde nuclear power Accountability plant discussed in NRC's October 2, 1985, letter to the Project utility.

(85-696)

Billie P. Garde, Requests all records related to NRC's Inspection Report  !

Government 50-456/80-04/50-457/80-04 dated June 10, 1980, regarding Accountability the Braidwood nuclear power plant.

Project (85-697)

Billie P. Garde, Requests all records to date related to incidents Government involving a shooting on September 23, 1985, and the Accountability shooting death on September 26, 1985, of Judith Penley Project at the Watts Bar nuclear power plart.

(85-698)

Billie P. Garde, Requests all records related to Board Notification 85-084 Government dated September 30, 1985, regarding the Comanche Peak Accountability nuclear power plant.

Project (85-699)

ENCLOSURE A OCT 181985

l 3

Received, Cont'd i Barbara A. Zuras, Requests copies of all records related to the OI

! Hobert, Finger, investigation of charges of discrimination and

! Brown, Cox & harassment made by Richard Parks and the NRC's Molligan August 12, 1985, notice of violation and imposition of  ;

i (85-700) civil penalty regarding the TMI nuclear power plant.

Scott Faust, Requests a copy of the transcript of a June 3, 1985, i The Wichita briefing by OI for the Chairman regarding the Wolf Eagle-Beacon Creek nuclear power plant.

4 (85-701) i

Lila Pope Requests records of each misadministration dose from (85-702) New Center Radiology of Detroit, Michigan.

Teresa S. Barnhart, Requests records, by division, providing the numbers of NTEU Steward NRC employees who received the ratings of outstanding, (85-703) excellent, fully successful, and unacceptable.

(NRCemployee) Requests cupies of two specified memoranda regarding

_ (85-704) herself.

I Mark T. Spears, Requests a list of all 1985 SBIR Phase I and Phase II Arthur Andersen winners.

(85-705) 1 Granted l Mark D. Douple In response to a request for records on the effects on (85-2M) any dairy products or any dairy animals within a twenty-five mile radius of the TMI nuclear power plant as a

, result of the March 28, 1979, accident, made available two records. Infortned the requester that four additional l records subject to this request are already available at the PDR. Also, informed the requester that we have referred one record to another Federal agency for i

direct response to him.

! Jim Pedro, In response to a request for copies of Westinghouse

NUS Corporation Owners Group Letter OG-110. " Evaluation of Alternate (85-657) RCP Trip Criteria," dated December 1, 1983 and Westinghouse Owners Group Letter OG-137, " Response to i NRC Question on RCP Trip," dated October 25, 1984, i

informed the requester that these records are already i available at the PDR.

Kathryn H. Urban In response tn a request for information submitted by (85-666) specified manufacturers and users of sealed sources for the " Registry of Radioactive Sealed Sources and Safety

! Evaluation of Sources," made available 11 records.

(NRCemployee) In response to a request for copies of records pertaining (85-667) to the granting of her security clearance, personnel files on herself, and inquiries regarding her employment i with the NRC, made available 21 records.

OCT 181985 ENCLOSURE A

4 Granted, Cont'd Fred R. Kling, In response to a request for five specific Inspection Willamette Reports, letters transmitting notices of violation, Industries, Inc. and the current license and license application for (85-682) Mallinckrodt, Inc., Maryland Heights, Missouri, made available 10 records.

Kelly Epps In response to a request for copies of NRC contracts, (85-683) informed the requester that the NRC routinely places copies of NRC contracts in the PDR.

Denied Billie P. Garde, In response to a request for the EG8G report on John S. Gregory, harassment and intimidation at Comanche Peak and records Government concerning the EG&G/NRC contract under which this report Accountability was produced, made available 24 records. Denied portions Project of three records containing confidential business (84-751) (proprietary) information. Denied portions of one record, release of which would cause a clearly unwarranted invasion of perscnal privacy.

Billie P. Garde. In response to a request for all records generated in Government connection with the NRC Interim Policy on Management of Accountability Allegations -- proposed NRC Manual Chapter 0517, Project " Management of Allegations," dated September 19, 1984, (85-365) and all drafts, comments, and proposals that led to this manual chapter, informed the requester that six records subject to this request are already available at the PDR.

Denied in their entirety approximately 100 records containing predecisional advice, opinions, and recommendations concerning the current development of proposed NRC Manual Chapter 0517. Denied nine records in their entirety, release of which would tend to inhibit the free and candid exchange of ideas and opinions essential to the current development of the Manual Chapter.

Michelle Adato, In response to a request for copies of records related to Union of Concerned the Brookhaven National Laboratory report on the need for

Scientists a nuclear safety board, made available 62 records.

(85-427) Informed the requester that additional records subject to this request are already available at the PDR. Denied three records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

1 ENCLOSURE A OCT .181985

I i i

I WEEKLY INFORMATION REPORT 1 DIVISION OF CONTRACTS l WEEK ENDING OCTOBER 18, 1985 .

L h

~

PROPOSAL UNDER EVALUATION RFP No.: RS-SDB-85-387

Title:

" Development of Business Opportunities for High Technology Small Business Firms with the U.S. NRC" i

Description:

The contractor shall analyze the nature of the prime l contract and subcontract market within the nuclear arena to establish a comprehensive listing of qualified small business firms, including 8(a) firms, capable of performing NRC's technical requirements.

Period of Performance: One year Sponsor: Office of Small & Disadvantaged Business Utilization / Civil Rights Status: RFP closed on October 15, 1985. Proposals forwarded to Source Evaluation Panel for review on October 15, 1985.

t j

4 t

i t

I

(

t 4

{

ENCLOSURE A i OCT 181985 i

\

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST ' ,

Week Ending October 18, 1985 Crystal River Unit 3 EFIC Initiation During Troubleshooting On October 9, 1985, at 9:36 a.m. during troubleshooting activities for a " test / reset" indicator both main steam isolation valves (MSIVs) associated with the "B" once through steam generator (OTSG) closed.

The MSIVs closed because troubleshooting activities inadvertently caused the "2 out of 4" logic of the Emergency Feedwater Initiation Control (EFIC) system to be satisfied and EFIC was initiated as expected. Crystal River personnel had anticipated this possibility

_ prior to the troubleshooting and per plant procedures manually tripped the unit. The unit would have automatically tripped eventually.

However, the reactor trip resulted in lifting the code safety relief valves of the "B" 0TSG, and one valve stuck open momentarily. In addition, when the MISVs shut, EFIC caused emergency feedwater (EFW) initiation in anticipation of low water level, resulting in overfeeding both OTSG's with main feedwater and cooler emergency feedwater. The plant cooled from 579'F to 550*F. As a consequence the pressurizer level dropped but was restored in approximately one minute with two makeup pumps.

All occurrences were not unexpected and adequate subcooling margin was maintained. Additional troubleshooting was continued until the defective module controlling the (test / reset) indicator was located and replaced and the system was checked before restarting at 6:40 p.m. The unit was back at 96% power by October 10 at 10:00 a.m.

Fermi-2 The plant was brought to cold shutdown on October 11, 1985 following a reactor scram initiated by a spurious signal. The plant will remain shutdown for about 30 to 40 days to install environmentally qualified equipment and to install and make operational the alternate independent shutdown system for fire protection.

However, the pacing item in this shutdown may be replacement of the two turbine bypass lines which have multiple through-wall cracks. These cracked lines were instrumental in the decision by Region III not to let Fermi-2 exceed 5% power prior to the present shutdown.

ENCLOSURE B OCT 181985

Maine Yankee Rosemont Transmitter Improper Installation With the plant in cold shutdown for refueling, Maine Yankee personne'l discovered on October 10, 1985 that the pressurizer pressure, pressurizer level and steam generator level transmitters had not been installed during a 1982 outage in complete agreement with the conditions of the qualification tests which were completed later.

The problem arose after an operator noticed that electrical leads were not tightly constrained by connectors (Conax seals) on certain Rosemont transmitters. Upon checking the Equipment Qualification test report, Maine Yankee found that the following discrepancies existed between the test configurations and the plant installations:

1. Some Conax seal assemblies (where leads enter) were not torqued up as tightly as in the test configuration.

__ 2. Some Rosemont/Conax seal ccnnections not torqued as tightly M so the test configuration. ~

3. Some venting enclosures on limit switches not screwed down as tightly as in the test configuration.

4 '. No drain holes in the bottom of junction boxes.

! 5. Rosemont covers not torqued down as tightly as in the test i

configuration.

6. The covers on all Conax RTDs and TCs (which were on the Equipment Qualification list) were not tightened as tightly as in the test configuration.

l Maine Yankee personnel have " verified" that all the discrepancies have been corrected. Maine Yankee personnel are looking for other installations that do not match the Equipment Qualification test configuration. Mr. John Garrity of Maine Yankee has said verbally that Main Yankee will not restart until there are no further discrepancies.

The vendor Inspection Branch of I&E is looking into this problem for generic aspects as well as for Quality Assurance aspects, i

l ENCLOSURE B OCT 181985

l l'

! Rancho Seco Nuclear Generating Station The Rancho Seco Nuclear Generating Station remains in hot standby. '

following an unplanned reactor trip on October 2, 1985, during an.

l attempted post refueling startup. The reactor trip occurred on primary j system overpressure following the trip of a main feed pump when the reactor was at 15% power. Several abnormalities occurred in nonsafety

related equipment in the secondary plant during the trip related transients. The transients have been analyzed by a B&W group and by an i

NRR technical group which was dispatched to the plant during the week of October 6, 1985.

Apparently, a higher than normal steam consumption by the secondary plant following the reactor trip, coupled with low decay heat in the

, core, caused a higher than normal cooldgwn rate in the primary system.

! Lefore stabilizing at approximately 470 F, the Tcold temperature trace shows a cooldown of 110 F in 20 minutes following the reactor trip.

l 1 _ Although the cooldown' rate exceeded the Technical Specifications limit, preliminary evaluation by B&W and the NRC staff concluded that the '

rapid cooldown did not exceed structural design limits, i

In an event not related to the reactor trip, on October 7, 1985, an electric driven auxiliary feed pump failed due to thrust bearing failure. Pump disassembly revealed that a slinger ring, which " slings" oil onto the thrust bearing, had been installed improperly and was not functioning. Previous pump maintenance had been performed in 1978 and

. 1974. The cause of the bearing failure is being evaluated.

j On Wednesday, October 16, 1985, utility /NRC management meeting was scheduled to discuss the significance of the events and corrective l actions needed prior to restart.

i TMI-1 Start Up i

, The plant is at 40% reactor power. The original plan was to hold the plant at 40% until late Thursday and conduct a reactor scram. However i

another steam leak has developed in the main turbine throttle drain lines. There are four drain lines associated with the main turbine throttles. Two of these drain lines had strainers and two did not.

Last week, one of the drain lines with a strainer developed a steam leak. When overspeed testing of the main turbine was completed, the

' steam leak was repaired by cutting out the strainer and welding in a new pipe to replace the strainer (a system design change). Now during the first day of operation at 40% power, the remaining drain line with a strainer has developed a steam leak at the strainer.

ENCLOSURE B OCT 181985 l

The licensee now plans to conduct the planned reactor trip on loss qf main feedwater lete in the day on October 16, 1985 vice October 17,:

1985. The licensee then reaches another NRC hold point and must obtain Region I approval before startup from this planned trip. In the original schedule the licensee was to proceed directly to 48% power upon starting up from this hold point. However now the licensee will have to hold at 40% power long enough to complete nuclear instrumentation calibration (i.e., allow for Xe buildup). Then the licensee will proceed to 48% and hold that power for 30 days.

ACRS Discussion Related to the GESSAR II Letter On October 11 and 12, 1985, the ACRS continued their discussion of the FDA denial letter that was proposed by the GESSAR II Subcomittee Chairman during the September ACRS meetings.

The discussions that ensued on the lith centered on the major policy

_ issues identified and the ramifications related to the negative conclusion of the letter. It was determined that a letter approving the FDA, with appropriate caveats, should be drafted for Comittee

. discussions, and that the policy issues, e.g., safeguards, safety goals and bunkered dedicated RHR systems, should be addressed in a separate letter to the Comission, with appropriate reference to this letter in the GESSAR II letter. Attempts at drafting these letters were made by two other committee members and they were read at the meeting held on the 12th. These letters will be revised over the next month to include member comments and be discussed at the November ACRS meetings.

It was noted by one Comittee member, that due to the difficulty of the GESSAR II letter, it was helpful to have the staff and applicant present during the discussions to answer Comittee questions as they arise.

OCT 181985 ENCLOSURE B

. - _ . ._ = - .-

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING OCTOBER 18, 1985 i

1. PLANT STATUS

- The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and

the reactor vessel head and plenum assembly removed from the reactor l

vessel.

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

- The modified internals indexing fixture is installed on the reactor 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 in preparation for defueling.

- Calculated reactor decay heat is less than 12 kilowatts.

i

- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 71*F to 93'F witn an average of 81*F.

- The average reactor building temperature is 58*F. The reactor building airborne activity is 1.5 E-7 uC1/cc Tritium and 2.0 E-10 uCi/cc particulate, predominantly Cesium 137,

2. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) completed processing batch 124 from neutralizer tanks (WDL-T-8 A/B) to SDS monitor tanks

.! (SDS-T-1 A/B). A total of 25,218 gallons was processed in this batch.

1 i

ENCLOSURE B CCT 181985 l-

2 EPICOR II completed processing batch 269, 10,578 gallons from SDS-T-1A to CC-T-2. Commenced processing batch 270 from SDS-T-1B to CC-T-2. This process was placed in temporary shutdown que to high radioactivity chemistry results on all liners after processing 5,835 gallons.

Total volume processed through SDS to date is 2,988,593 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.

3. DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building.

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.

Pressurizer mirror insulation is being removed prior to characterization. i

4. ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.

TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from September 28 through October 5, 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 September 29 through October 5,1985. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between October 9 and October 16, 1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.

Installation of the vacuum defueling system is in progress.

Work is in progress on the canister positioning system.

Canister handling bridge indexing is in progress.

Lower vessel debris samples have been shipped to Idaho National Engineering Laboratories for analyses.

{

ENCLOSURE B GCT 181985

3

6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES

- Installation of the DWCS continued. Partial DWCS turnoyer for processing RCS during early defueling is expected to be completed in October.

Spent fuel pool was cleaned and filling with borated water is in progress.

Fuel canister handling bridge indexing has been completed.

7. NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48 and 50.

- Recovery Operations Plan Change numbers 29, 31, and 32.

- Fuel Canister Technical Evaluation, Revision 1.

- Defueling Safety Evaluation.

- Application for seismic exemption.

SDS Technical Evaluation and System Description Update.

Core Stratification Sample Safety Evaluation.

Heavy Load Handling Safety Evaluation Report.

Boron Dilution Hazard Report

- Defueling Water Cleanup System Technical Evaluation Report, Revision 7.

Early Defueling Safety Evaluation Report, Revision 4.

8. PUBLIC MEETING On the evening of October 16, 1985, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a public meeting at the Public Safety Building in Lancaster, PA. At this n'eeting, the Panel was briefed by Dr. B. J. Snyder, Director, Three Mile Island Program Office (TMIPO), on the impending reorganization of TMIPO.

Dr. H. A. Muller, State Health Secretary, Pennsylvania Department of Health, department provided a detailed entitled, " Cancersummary of aMorbidity Mortality and recent study (released Incidence) by his Around TMI." The results of the Department of Health study, including both mortality and morbidity data, do not present evidence of an increased risk of developing cancer by local residents living near the TMI l facility. Dr. Muller answered questions from the public.

Mr. F. Standerfer, Vice President / Director, GPU Nuclear Corporation, provided a status report on the licensee's efforts to begin fuel removal.

The licensee expects to begin the early phases of fuel removal called

" pick and place" by the end of October.

j The next meeting of the Advisory Panel is scheduled for 11:00 AM, November 19, 1985, in Washington, DC, before the NRC Commissioners. The next meeting in the TMI area is scheduled for December 12, 1985, at the Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to approximately 10:00 PM.

ENCLOSURE B OCT 181985

4 s

. i 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 21E2 Marietta Avenue, Lancaster, Pennsylvania 17603.

i i

1 l

i i

l j

i 4

l  !

ENCLOSURE B  ;

i OCT 181985

{

l

.-. - - . , , _ . - _ ~ , , _ . . . , - , , . - . - _ . , . , , . .- , . . , - - . - _ , . , , , , . . , - , . , . , , _ , , , , . _ _ _ - _ . . _ , _ , , , , , - , . , - . , - _ - , , - , _ . , - _ . - , _ , _ . , , , , . - , . . , , -

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending October 18, 1985 Near-Tere NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 114(e) of NWPA: Project Decision Schedule Comments Action: DOE had requested comments on the draft PDS by September 13, 1985.

The Commission voted to approve the PDS comments with modifications on September 19, 1985.

Status: The final edited version was due to SECY from the Commission by October 15, 1985, for submittal to D0E.

Section: 134 of NWPA: Final Rule on Hybrid Hearings Action: The final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel was approved by the Commission on September 5, 1985. The final edited version was submitted to SECY on October 4,1985.

Status: The final rule was published in the Federal Register on Tuesday, October 15, 1985 (50 FR 41662)

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

Congress. If authorized, NRC will review DOE's license application and make the necessary licensing determinations.

Status: Proposed revisions to 10 CFR Part 72 were submitted to E00 for concurrence on October 10, 1985. CRGR will be briefed concerning the proposed revisions on November 13, 1985.

Section: 301 of NWPA: DOE Mission Plan Action: NRC testified concerning the final Mission Plan before both Houses of Congress in early September.

ENCLOSURE C OCT 181985

f

. Status: NRC is currently scheduled to testify, concerning the Mission Plan and other high-level radioactive waste topics, before the Senate Subcommittee on Nuclear Regulation (Simpson) on October:29,1985.

Section: 306 NWPA: Regulations for Training of Pcwer Plant Personnel.

1 Action: Proposed amendments to Part 55 dealing with simulator training requirements were published on Novermber 26, 1984. Resolution to

_ comments received on the proposal amendments were submitted to CRGR September 4, 1985.

Status: The final rulemaking package on Part 55 and three associated regulatory guides (1.134, 1.149, 1.8) is currently undergoing Division review until the end of October, and is expected to be

submitted to ACRS by late November for review.

i IAEA Advisory Group

- During the week of October 7-11, 1985, Dr. Donald Cool, NMSS, participated as U.S. expert in an IAEA Advisory Group meeting on the " Application of the Principles of Radiation Protection to Sources of Potential Exposure."

Expansion of Biomedical Rule 1

In July the staff met with Drs. Rosalyn Yalow, Henry Wagner, Edward Webster, and other members of the medical community, and pharmaceutical companies to i explore the expansion of the biomedical waste rule. In that meeting, the staff made clear that the data necessary for our evaluation would have to be provided by the medical and pharmaceutical organization.

On October 16, 1985, Dr. Rosalyn Yalow called Dr. Lidia A. Roche, of NMSS

staff, to inform her that the American College of Nuclear Physicians has received a DOE grant to obtain the data required to initiate this rule.

i NFS-Erwin I

Strike by OCAW members continues. NFS is conducting limited operations of the

. HEU production, scrap recovery and R&D facilities. No problems with site

operations have arisen to date.

i

! ENCLOSURE C OCT 181985 4

0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending October 18, 1985 ,

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

a. EN 85-39A, Further Action on Show Cause Order and Order Modifying License, was issued October 16, 1985 to Met Lab, Incorporated (Hampton,VA). After careful consideration, it has been determined that adequate cause has been shown why Met Lab's license should not be revoked subject to an Order Modifying License. This decision is based upon the detennination that Met Lab has made improvements in its program to comply with license requirements, and that the specific plans and commitments, including the performance of audits by an independent consultant, are adequate to enable Met Lab to conduct future activities in compliance with Commission requirements.

b. EN 85-50A, Imposition of Civil Penalty in the amount of $2,000 was issued October 10, 1985 toPrincetonUniversity(Princeton,NJ). The licensee responded to the Notice of Violation and Proposed Imposition of Civil Penalty (EN 85-50, June 28, 1985, $4,000) in a letter dated July 29, 1985. After careful consideration of the licensee's response, the staff has concluded that the violations did occur as set forth in the Notice. However, the licensee has provided sufficient basis for mitigation of the civil penalty because of its prompt identification, reporting, and evaluation of the incident.

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

a. PNO-I-85-78, Pennsylvania Power and Light Company (Susquehanna),

Reactor Water Cleanup (RWCU) Isolation on High Flow.

b. PNO-I-85-78A, Pennsylvania Power & Light Company (Susquehanna, Unit

1) Reactor Water Cleanup (RWCU) Isolation and Radioactive Spill (Update).

c. PNO-I-85-79, GPU Nuclear Corporation (TMI, Unit 1) Interruption of Power Escalation Program Due to Main Turbine Drain Line Leak.

d. PNO-II-85-95, Virginia Electric Power Company (North Anna, Unit 2),

Outage in Excess of 48 Hours.

e. PN0-III-85-89, U.S. Ecology (Zionsville, IN), News Media and Public

! Interest in Proposed Waste Storage Facility.

ENCLOSURE D OCT 181985 1

i e

i l

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

a. IE Information Notice 85-80, Timely Declaration of an Emergency Class, Implementation of an Emergency Plan, and Emergency'Notifica-i tion was issued October 15, 1985 to all nuclear power facilities j holding an operating license or a construction permit.

i

b. IE Information Notice 85-81, Problems Resulting in Erroneously High i Reading with Panasonic 800 Series Thermoluminescent Dosimeters, was '

i issued October 17, 1985 to all nuclear power reactor facilities ,

holding an operating license (0L) or a construction permit (CP) and i

certain materials and fuel cycle licensees who may use the subject ,

thermoluminescent dosimeters (TLDs).

1 j 4. Other Items

! a. Senior Management Meeting i

{ _ Deputy Director, IE was at the Rancho Seco site for a senior i

management meeting October 16-17, 1985.

b. Civil Penalties Paid i

On October 10, 1985, payment in the amount of $100,000 was received 4

from TVA (Watts Bar) for enforcement action (EA #85-64) relating to i violations involving failure to adequately implement positive

! controls on control room design status reports.

c. Emergency Preparedness 4

1) Representatives of the Emergency Prepardness Branch, Division of Emergency Preparedness and Engineering Response (DEPER) and the I Operating Reactors Program Branch, Division of Inspection Programs performed an assessment of Region V performance in

evaluating the Trojan full participation exercise on October 16, i 1985.

, 2) Representatives of IE, ELD, and NRR met with Georgia Power '

l personnel to discuss the status of emergency preparedness

programs for Vogtle this week.

1 3) Representatives of the Emergency Preparedness Branch, DEPER, l participated in the Region I evaluation of the Peach Bottom l exercise on October 16, 1985 and in the Region IV evaluation of j the Cooper exercise, also conducted on October 16, 1985.

d. Operations Center

! 1) On October 16, 1985, a safeguards drill was held in the NRC l Operations Center. Participants included the Executive Team I (including the Chairman), Status Officers and ET Secretaries, ENCLOSURE D OCT 181935 L

Safeguards Team, Protective Measures Team (Materials /Transporatation) and the Administrative Support Team.

2) A tour of the NRC Operations Center was conducted by:the Chief Incident Response Branch, DEPER, on October 16, 1985 for various managing editors from national labs. This tour disc 0ssed the agency's incident response program. .

e. Preventative Maintenance On October 16, 1985, Deputy Director, Division of Inspection Programs, Representative of Operating Reactor Program Branch (DI) and Chief Engineering and Generic Communications Branch, DEPER, attended a meeting in Crystal River, Florida between NRC and NUMARC to discuss industry activities related to preventive maintenance.

f. Constuction Appraisal Team A Construction Appraisal Team (CAT) inspection will commence at the South Texas plant on October 21, 1985. The inspection period will be from 10/21-11/01/85 and 11/11-11/22/85 with the exit meeting a with the licensee scheduled for November 22, 1985.

g. Readiness Review i

Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs (QAVT),

visited Washington Public Power Supply system offices in Richland, Washington on October 9 and 10, 1985 to inspect Engineering Assurance Program activities associated with the WNP-3 Readiness Review,

h. Engineering Assurance Program Representatives of the Quality Assurance Branch, QAVT, visited Stone and Webster Corporation offices in Boston, MA on October 15-17, 1985

~

to inspect South Texas Engineering Assurance Program activities.

1. Well Logging Representatives of Safeguards Material Program Branch, Division of Inspection Programs was in Bluefield, West Virginia this week to observe well logging operations in relationship to the Committee on Part 39.

ENCLOSURE D OCT 181985 i

_ .- ...m _,-- - . _ , . . ..._m -_-..,_.__-..-,,___.,-.,.,_.m., _ . . ~ , , . _ . .,m __...,.._,,m ,-,.- ._y- . . , . . - , , . . . . .

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest l Week Ending October 18, 1985 Continuing Integral Thermal Hydraulic Experimental Capability Scaling approaches are being evaluated by NRC to compare capabilities of existing integral thermal hydraulic experimental test facility capabilities with facilities that could be designed using alternate scaling approaches.

These results will be used to provide a design basis for possible future integral experimental facilities. Four scaling approaches have been selected for study, including those used in Semiscale, MIST and University of Maryland facilities, and EG&G Idaho has particily evaluated their capabilities and limitations. On October 10-11, 1985 experts from industry, universities, Department of Energy (DOE) laboratories and government met with NRC repre-

- sentatives to review and discuss the scaling study approach and results. The group generally agreed with the four scaling options chosen and the evaluation approach used. They also made specific recommendations for study improvement; for example, giving high priority to future code assessment data needs and to phenomena not well modeled in existing integral facilities (e.g., multi-dimensional behavior in reactor plena).

UKAEA/USNRC Containment Response Meeting i The second annual UKAEA/USNRC Information Exchange Meeting on Containment Response to Severe Accident Conditions was held on October 15, 1985 in Bethesda. The UKAEA representatives presented sumaries of methodical applications and comparisons of numerous experiments; codes and severe accident assessment methodologies developed by NRC/RES contractors as well as UKAEA methodologies. The UK representatives will sunnarize their conclusions at a meeting to be held October 21, 1985 The NRC/RES contractors will also present recent experimental results and analyses. These meetings are providing a valuable and totally independent peer review of U.S. research in this vital a rea.

Core Meltdown Research The Fifth Annual Information Exchange Meeting on Core Meltdown Research between i USNRC and the Federal Republic of Germany is being held on October 16-18, 1985 l at Shelter Island, NY. IDCOP and EPRI representing U.S. Industry are participating by presentations and discussions.

ENCLOSURE E OCT IS 1995

1

_2_

Aging Assessment of Components from Shippingoort Atomic Power Station A motor-operated valve assembly and a check valve were successfull'y removed and shipped to INEL and OR!4L, respectively, for post-service examination and tests as part of the continuing Shippingport Reactor Aging Evaluation i program. INEL will make a preliminary examination of the motor-operated gate valve to identify aging and service wear effects and then refurbish and ship the valve to the HDR test facility in W. Germany. This Geman test facility provides capabilities not available in the U.S. for testing of the valve in a piping system that can replicate temperatures, flow rates and pressures that such a valve would see in a commercial nuclear power plant along with simultaneously imposed seismic loadings. These tests will evaluate different seismic support designs that are used in the U.S. and Germany, and flow-induced forces resulting from valve operation and the influence of system effects on the behavior of the valve.

J Society of Exploration Geophysicists Meeting

~

It has not been possible to assign seismicity in the Eastern and Central U.S.

to active surface faults, so the tectonic province approach specified in Appendix A to 10 CFR 100 has had to be used to define hazards at nuclear plant sites in this region. Assigning seismicity levels to tectonic provinces based on the low recurrence rate earthquakes in this region is difficult, so that defining seismic hazards in the Eastern and Central U.S., where most of the nuclear reactors in this country are located, has been a difficult process.

Geophysical methods have increasingly been used to resolve some of the questions inherent in this problem.

Dr. E. Zurflueh, Geophysicist, Earth Sciences Branch, attended the annual meeting of the Society of Exploration Geophysicists recently held in Washington, D.C. Advancements in geophysical exploration methods; e.g. bore hole geophysics, seismic reflection, magnetic and gravity anomalies etc., were

discussed at the meeting. One of the special themes of the meeting was the use

! of exploration geophysics in defining the origins of seismic activity in the Eastern and Central U.S., where no direct correlation has been found between l

seismology and actise surface faulting. Geophysical methods can be used together with data on seismicity and geology to define such structural fea-tures. These methods permit defining such features at significant depths in the earth's crust where earthquakes occur. Infomation obtained at the meeting

will be used to help focus the use of geophysical techniques in NRC's research activities directed at developing a better understanding of seismic hazards in ,

the Eastern and Central U.S.

Regulatory Guide (s) to be Issued in the Near Future

Title:

Water Sources for Long Term Recirculation Cooling Following a

{ Loss of Coolant Accident (Task MS 203-4)

Description:

Revision 1 of Regulatory Guide 1.82 is a part of the resolution

! of U.S.I.-A43, " Containment Emergency Sump Performance." The guide is a no ENCLOSURE E l OCT IS 198packfit guide.

Contact:

W. E. Campbell, Jr.

443-7856

RES Rulemaking Activities Consideration of Earthouakes in the Context of Emergency Preparedness (Part 50) (Earthquakes and Emergency Preparedness)

The final rulemaking package was signed by the EDO on August 20. A Comission meeting was held on September 9. The Comission is expected to give the staff further instruction. An ACRS meeting was held on October 9. This meeting was held at the Comission's request in order to discuss SECY 85-283. An ACRS recomendation is expected by October 31, 1985.

Licenses and Radiation Safety Requirements for Well-Logging Operations (Part 39) (Well-Logging Rule)

A meeting of six cognizant staff members was held on October 10, to discuss how to resolve the public coments on the proposed rule approved by the Comission (SECY-85-11). The main unresolved public coments are that training requirements are excessive and that paperwork / record-keeping requirements are excessive. A visit to Virginia by four NRC staff members to observe miaeral logging and discuss the proposed rule with mineral loggers was held on October 15 and 16.

Contact:

S. Turel DRA0 44-37925 ENCLOSURE E

1 REGION III 4

- STATUS REPORT j DAVIS-BESSE LOSS OF FEEDWATER EVENT

! October 18, 1985 i Plant Status The plant remains in cold shutdown. The circulating water canal is drained.

J Decay heat removal loop No. 1 is drained for maintenance. Emergency Diesel l Generator No.1 is inoperable due to an inoperable ventilation damper. The j diesel firewater pump is inoperable due to a coolant problem and the jockey firewater pump (non-Tech Spec) is inoperable due to a damaged motor.

1 l

f I

h l

i i

i l

i i

i I

i l

i i

I OCT 181985

E

• i A%EQUIPMENTSTATUS(FOLLOWSTABLE5.1INNUREG1154) 5 TROUBLESHOOTING / ROOT CAUSE ITEM DETERMINATION ACTIVITIES COMMENTS RIII ACTIONS

1. Main Feedwater Cause determined to be component MFPs were tested on 09/05- Region III is monitoring Turbine failure in speed control circuit. 06/85 with no problems noted. licensee evaluation of Revised report issued 08/30/85. reliability of the MFPs.

2. Closure of MSIVs** Cause determined to be that circuit More testing will be scheduled RIII monitoring licensee's was overly sensitive to momentary later. activities and obse-ving system perturbation. Revised selected activities.

report issued 10/03/85.

3. Steam Safeties,** Defective electronic module in Ten MSSVs and three spares have RIII following licensee Atmos. Vents. ICS likely cause of problem with been removed and shipped to activities. Vendor i

atmospheric vent valves. Revised Wylie for full flow steam Programs Branch has been

. report issued 10/03/85. MSSVs testing. The valves will be notified of testing.

being evaluated, modified as recommended by Dresser.

4. Aux. Feedwater Cause considered to be condensation Modification of the steam supply RIII inspectors to observe Turbine ** in long steam inlet lines. Revised system has begun. The turbine activities.

report issued 09/16/85 governors that had been sent to Woodward have been returned l to the site. Governor for #1 AFWPT is being replaced with a new governor.

j 5. AFW Containment Causes were incorrect torque switch Additional dp and flow testing RIII following licensee Isolation Valves bypass settings and inadequate test is being evaluated. activities.

and maintenance procedures. Revised report issued 08/29/85. ,,,

P O

C i A r-2

E$ --

J o* TROUBLESHOOTING / ROOT CAUSE DETERMINATION ACTIVITIES COMMENTS RIII ACTIONS

• lsETEM '

4

) RIII to observe any

( 6. Steam Supply Valve Completed and revised report Activities completed.

additional testing.

i to AFPT No. 1 issued 09/09/85. Valve will be Additional testing i 1 inspected internally with a is planned in hot

! borescope.- standby.

J j 7. Source Range NI Revised report issued 09/19/85 Licensee will replace the RIII observing activities.

j on NI-2. NI-2 failed due to a containment cable penetration i j defective containment penetration module for NI-2. NI-1 is t j module. The root cause of the being monitored and is penetration failure is not yet functioning correctly.

l 1

known. Revised report issued

• l 09/16/85 on NI-1. Root cause I was bad connection between detector

] and cable.

1 i 8. PORV** Completed and report sent to NRR A spare valve was tested at RIIIandtheVendorProgrars!

j 08/23/85. Root cause not deter- Marshall Steam Station in Branch observed the testing

! mined. Terrell, N.C. on 10/18/85. activities.

The valve was cycled 100  ;

i times and no problems were

• I noted. The licensee is  !

I evaluating the test data and j will r build the original i

valve as needed. ,

9. S/U Feedwater Control Completed and reviseo report issued Work complete. None. [*

l Valve 08/29/85. The valve functioned

! correctly during the June 9 event.

' i i

i 10. Recovery of AFP Completed and revised report issued Procedure has been revised and RIII to review operator  !

Turbine 08/30/85. Training and procedural operator aids (instructions) training program to ,

l

deficiencies identified. will be posted at the turbines. assure proper operator l g;

1. 2 AFWPT trip throttle valve actions.

r> has been removed for inspection.

hi 4

' E n,

t r- t

3 t

t .

ca S i I U TROUBLESHOOTING / ROOT CAUSE ITEM DETERMINATION ACTIVITIES COMMENTS RIII ACTIONS

11. AFP No. 1 Suction Revised report issued 09/I7/85. Individual pump suction RIII observing activities.

Transfer Root cause determined to be strainers will be removed and the connon suction strainer will l excessive pressure drop across common strainer caused by be replaced with a coarser mesh -

. transient flow variations. strainer.

12. Turbine Turning Gear * ,

i i

13. Control Room HVAC*

14. Turbine Bypass Completed and revised report issued New drain header has been RIII to monitor.

i Valve 08/29/85. Valve failure caused by installed. New valve operator water hammer. has been received.

• Status not maintained on this item since these type failures occurred previously and do not appear to be unique to this event.:

• • Shows change in status from previous update.

4 4

b i

1 i

k t

9 99 g2 j 6!  !

55 m

r-  !

! 4

i l o

E3 B. REGION III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO OF AUGUST 5,1985

1. Item: Adequacy of the licensee's management and maintenance activities e,

ACTION STATUS / COMMENTS

, (b) Evaluate and take action on the Region III Davis Besse study group licensee's response to findings established to review LER's, DVR's i

concerning management practices (Deficiency Reports) and enforcement (e.g., control of maintenance history and determine if licensee's and i programs and post-trip reviews). Region III's actions were adequate and l

appropriate. Inspections are ongoing.

I i 6. Item: Reliability of the AFW containment isolation valves and other safety-related valves ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Region III inspection specialists from the shooting activities Division of Engineering and the Resident ,

Inspectors are monitoring the licensee's '

troubleshooting activities. (See Table A on Equipment Status.)

(e) Determine that the procedures for A Region III specialist is following the adjustments of the AFW isolation licensee's actions and has reviewed the valves such as torque switch bypass licensee's procedures for adjustment of '

switches are clear and proper, and torque switch bypass switches and torque  !

that associated training programs switches. The licensee has purchased a dre adequate. Confirm that adjustment M0 VATS machine to aid them in the setting settings are consistent with plant of all limitorque operated valves.

procedures.

Be i g2 8

!5 m

f" 5

l

__ . - _ . _ _ - - - - . - - . ~ - _ _ _ _ . - _- . -- -

E

--e I

7. gItem: Adequacy of emergency notifications

=

m ACTION STATUS / COMMENTS  ;

u, (a) Verify the adequacy of the licensee's Region III Emergency Preparedness has procedures and training for the report- reviewed the licensee's training ar.d ing of events to the NRC Operations procedures for reporting of events to the NRC. One violation of NRC requirements was l found. Region III is reviewing the licensee's reporting per 10 CFR 50.72 and ,

10 CFR 50.73. ,

1 Item: Reliability of AFW pump turbines i 8.

ACTION STATUS / COMMENTS  ;

I

! (a) Monitor the licensee's trouble- (See Table A.)

shooting activities including possible hot plant operation to confirm failure mode.

(d) Verify that the AFW system has been NRC testing review group consisting of IE, -

adequately tested to confirm system NRR, and Region III members established and l

configuration involved with design will review AFW system testing. First team

basis events. meeting was held on October 8,1985 in j Region III. The team was onsite 10/15-17/85 4 to develop a charter for their review process. I (e) Review the implementation of the A training assessment team inspection was i operator training program to assure completed on 9/26/85. Region III will proper operator actions, such as follow the licensee corrective actions resetting of trip throttle valve. relative to team findings.

- i

9. Item: Reliability of the PORY m

. M ACTION STATUS / COMMENTS I

E E(a) Monitor the licensee's trouble- Troubleshooting complete. One spare PORV E shooting activities has been rebuilt by Crosby rather than two, '

r- as reported last week and was tested at Marshall Steam Station in Terrell, N.C.

(See Table A).

, 6 l

3 . .

I e i o i

-4 3

12. 4 tem: Resolution of equipment deficiencies m

STATUS / COMMENTS is ACTION  ;

i w i (a) Monitor the licensee's trouble- (See Table A.) ,

shooting activities

.! i I

i i

1 4

L h

I l l L

I i i i i

, i 4

$ 5 1

l 1

,e. '-

4 a 2 a' n p i O

4 (n C

!. lE3 2

, m I

,l

! 7 j J

(

, -- . , , . - - . . _ - = = _ _ . , - --

Other Activities The new electric motor driven startup feedwater pump (SUFP) is in place.

Installation of pipe and valves is about 80% complete. Conduit installation, cable pulling and wire termination is in progress. The old SUFP has been electricallydisconnectedanditsdischargeisnolongerconnected30the feedwater system.

Evaluations and inspections relating to the auxiliary feedwater system restraints are continuing. Baseline inspections of the No. 2 liPI and the i No. 2 LPI systems are continuing. The licensee's engineering department has received 730 NCRs for evaluation. Nonconformance Reports (NCRs) have been written against 1106 of the 1199 pipe supports inspected so far. Rework is required on 66 of the 540 supports that have been evaluated. There are now 16 licensee inspection teams at work on this project. On October 17, 1985, P.egion III issued a Confirmatory Action Letter documenting licensee's actions relating to piping system inspections, evaluations, and corrective actions.

M0 VATS testing has resumed on the 166 safety-related motor-operated valves onsite. Seventy-four valves have been tested; a few of these will require retesting.

Toledo Edison has established a program to review the history of systems important to the safe operation of the plant. The review is intended to identify and correct problems which may potentially impact system operability.

A total of 31 systems have been selected for this review. The NRC Restart Test Review Group is on site evaluating the licensee's System Review and Test Program and also developing a plan for NRC review of the Test Program.

Corrective Action Plans Corrective action plans to repair equipment that malfunctioned during the event have been issued for the following equipment items. Work is in progress on most of the action plans. Item numbers correspond to Table 5.1 in NUREG 1154.

! ITEM PLAN DATE ISSUED

1. Main Feedwater Turbine 4 08/26/85 6 09/03/85

2. Closure of MSIVs 1 09/04/85

4. Auxiliary Feedwater Turbine 1 09/20/85 (Rev. 1)

5. AFW Containment Isolation Valves 1 09/07/85 (Rev. 1)

6. Steam Supply Valve to AFPT No. I 1 08/29/85

7. Source Range NI-1 1/2 09/26/85 (Rev. 1)

Source Range NI-2 1 09/23/85 l

ENCLOSURE L OCT 181985 8 l

i .

8. PORV 1 09/09/85 (Rev. 2) i 9. S/U Feedwater Control Valve 1 09/08/85(Rev.3)

10. Recovery of AFP Turbine 1 09/09/85

11. AFT No.1 Suction Transfer 1 09/04/85

14. Turbine Bypass Valve 1 09/05/85 (Rev. 1) 2 08/26/85 3

Davis-Besse Course of Action Report submitted on September 9,1985 and revised October 2, 1985 is under review. A separate inspection plan is being developed based on this review.

Miscellaneous Engineering personnel who have been working in downtown Toledo offices are now at the Davis-Besse Administrative Building.

1 i

i i

ENCLOSURE L OCT 181985 l 9 i

4 ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING OCTOBER 18, 1985 A. SECY-85-208 - INCIDENT INVESTIGATION PROGRAM Memo SECY to W. J. Dircks dated 10/16/85  ;

This is to advise you that the Commission, with Cha'irman Palladino and Commissioners Roberts and Zech approving, ap-prove the staff's plans, as described in SECY-85-208, to improve the existing program for the investigation of signifi-cant operational events.

Commissioner Asselstine would have preferred the establishment of a Commission-level Office of Nuclear Safety with executive and supervisory authority over accident investigation. Com-missioner Bernthal proposed that OPE carry out a comprehensive study of the concept of a small ONS investigative team that would report directly to the Commission and that the Commis-sion use that study as the basis for establishing such a team.

In connection with his approval, Chairman Palladino stated that the Commission reserves the right, in a given case, to form a special board when circumstances so warrant. Commis-sioner Roberts noted that he approved with the understanding that this in no way reopens the Incident Investigation Coor-dinating-Group issue discuosed in the Chairman's 1987 Budget memo of July 22, 1985. F' envisions the group (s) as being structured and working a m lar to the NRC Team on the Davis Besse Event.

.I B. STAFF REQUIREMENTS'- MEETING WITH CAROLINA POWER AND LIGHT COMPANY ON ENVIRONMENTAL QUALIFICATION EXEMPTION REQUEST FOR BRUNSWICK NUCLEAR STATION, 2:00 P.M., WEDNESDAY OCTOBER 9, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C.

OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 10/18/85 The Commission

• met with representatives of Carolina Power and Light Company (CP&L) to discuss environmental qualification of electrical equipment important to safety at the Brunswick nuclear plant.

The following persons participated in this meeting:

Sherwood H. Smith, Jr., Chairman / President, CP&L Ed Utley, Senior Executive Vice President, CP&L Al Cutter, Vice President, Nuclear Engineering

& Licensing, CP&L Pat Howe, Vice President, Brunswick Nuclear Project, CP&L Len Gucwa, Georgia Power Company 1

Chairman Palladino requested Commissioners to provide the Secretary with their votes on SECY-85-321.

(OCM)

(Subsequently, the four available Commissioners provided the ENCLOSURE O 007 18 1985 Secretary with their votes on SECY-85-321.)

Commissioner Asselstine was not present.

1 .

I l

i i

C.- STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND V0TE 11:30 A.M., THURSDAY, OCTOBER 10, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to H. H. E. Plaine dated 10/18/85 I. SECY-85-305 - Limerick Motions -

• 1 i The Commission, by a 5-0 vote,* approved an order'which denied 1 a request filed by the Graterford inmates and Robert' Anthony /- '

Friends of the Earth that the Commission stay operation of orders issued by the NRC which authorizes the issuance of a full power license for Limerick, Unit 1.

(Subsequently, on October 10, 1985 the Secretary signed the Order.)

II. SECY-85-324 - Hearing Request on Denial of Senior Operator's License The Commission, by a 4-0 vote, approved an order referring a request for a hearing from Mr. Kenneth Burton on the NRC staff's

! denial of his application for a senior reactor operator's license to the Chairman of the Atomic Safety and Licensing Board Panel for the appointment of an administrative law judge to i conduct a proceeding in accordance with the formal adjudicatory procedures set out in 10 CFR Part 2, Subpart G. Appeal from the initial decision would be handled by the Appeal Board with the

. Commission retaining its discretionary review authority.

j Commissioner Asselstine was not available to participate in this i action.

! (Subsequently, on October 10, 1985 the Secretary signed the Order.)

• Section 201 of the Energy Reorganization Act, 42 U.S.C. S 5841, provides that action of the Commission shall be determined by a'" majority vote of the members present." Commissioner Asselstine was not present when this item was affirmed. Accord-ingly, the formal vote of the Commission was 4-0 in favor of the

decision. Commissioner Asselst.ine, however, had previously

indicated that he would approve this paper and had he been

present he would have affirmed his prior vote.

l 4

i ENCLOSURE O OCT '181985

4 4

E!

l

-a

! we eo gg NRR MEETING NOTICES

• j 28 OCTOBER 18, 1985

! DOCKET APPLICANT /

l DATE/ TINE NUNBER LOCATION PURPOSE ATTENDEES NRR CONTACT i 10/21/85 50-424 P-114 To provide applicant with Southern Co. Serv. M. Miller ,

j 1:00 pm 50-425 Bethesda guidance re Tech Specs for

Vogtle

10/21/85 50-461 MNBB-6110 To discuss PVORT overall Illinois Power Co. B. Siegel j 1

00 pm Bethesda program plan prior to PVORT Sargent & Lundy BNL 1 10/21-22 50-369/370/ McGuire Site To discuss operating experience Duke Power Co. D. Hood 8:30 am 269/270/287 involving actions on wrong  ;

10/23-24 Oconee Site train of redundant systems or 8:30 am wrong unit of multi-unit facilities i

10/22/85 MNBB-6507 To discuss Topical Report NEDE- General Electric H. Bernard 9:00 am Bethesda 30996-P 10/23-24/85 P-118 To discuss Supplemental Safety Citizens Assn. A. Vietti-Cook 9:00 am Bethesda Evaluation Report Nos. 7-11 for Sound Energy (Comanche Peak)

10/24/85 50-416 P-422 To discuss design of Exxon fuel Mississippi Power L. Kintner 1

00 pm Bethesda assemblies for first refueling & Light 4

of Grand Gulf 1 i

'

• Copies of summaries of these meetings will be made publicly available and placed in the respective'dockeb-file (s) in the NRC and local public document rooms E2 i F2 I

6!

i 55

ni l

?

E$

a

>A m

g3 NRR MEETING NOTICES

• tn DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 10/24/85 50-219 Dept. of Env. To discuss Oyster Creek GPU Nuclear J. Donohew 9:30 am Protection Appendix B Environmental Tech State of New Jersey 380 Scotch Rd. Specs and to review status of Trenton, NJ licensing actions for Dyster Creek 10/24/85 50-321 416A (Old To discuss status of Hatch 1 & Georgia Power Co. G. Rivenbark 10:00 am 50-366 Phillips) 2 licensing activities Bethesda 10/24/85 50-302 AR-5033 To discuss NRC concerns with Florida Power Corp. H. Silver 9:00 am Bethesda DCRDR Summary Report - Crystal River 3 10/25/85 50-416 P-110 Discuss schedule for completion Mississippi Power & L. Kintner 10:00 am Bethesda of licensing actions Light 10/28/85 50-213/245 Northeast Util. To discuss and review plant Northeast Utilities F. Akstulewicz 1:00 pm Berlin, CT modifications made at Millstone 1 10/29/85 Millstone 1 Site and Haddam Neck in response to 9:00 am Waterford, CT IE Bulletin on Masonry Wall Design 10/29/85 Haddam Neck 1:00 pm East Hampton, CT 10/30/85 Northeast Util.

9:00 am Copics of summaries of these meetings will be made publicly available and placed in the respective d'ocket file (s) in the NRC and local public document rooms.

m N

8

!5 m

, 73

. E$ 1

--s co NRR MEETING NOTICES

• Sk DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTEN0EES NRR CONTACT 10/30-31/85 50-382 87th Floor Discuss confirmatory ar.alyses Louisiana Power & J. Wilson 8:30 am 2 Word Trade Ctr for common foundation basemat Light Co.

New York, NY at Waterford 3 BNL EBASCO 10/31/85 50-302 P-422 To discuss NRC concerns re- Florida Power Corp. H. Silver 1:00 pm Bethesda garding review of GDC-4 exemption request for RCP restraints I

E!

s2 ,

O E

m 7

I i

cs HMSS MEETING NOTICES

~ '

E3 . FOR WEEK ENDING: 10/18/85 wa Division of Fuel Cycle and Material Safety oo .

E$ DOCKET ATTENDEES /

"'DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 10/19-11/1/85 Vienna, Serve as U.S. expert or observer on J. Cook (FC) Cook Austria a Technical Connittee on the Assess-ment of the Radiological Impact from the Transport of Radioactive Material (IAEA).

10/22/85 40-2061 Glen To discuss the Kerr-McGee Kress Creek M. Horn (FC) Nixon Ellyn, IL hearing with RIII and also to discuss W. Nixon (FC) .

the progress of the ANL report on the RIII Reps Supplemental Environmental Impact Statement.

10/25-11/2/85 Eastbourne, Attend meeting of International R. E. Cunningham (FC) Cunningham -

England Commission on Radiological Protection Members of ICRP Comnittee 4 re Practical Application of Committee 4 Broad ICRP Recommendations to Operations.

10/28/85 Project West To meet with DOE, NY State and NRC con- N. Davison (FC) Davison M-32 Valley, NY tractors to discuss West Valley hydrology T. Nicholson (RES) and accomplished field studies. Reps of West Valley DOE Project Office 10/28-29/85 Seattle, WA To attend Commercial Spent Fuel J. Roberts (FC) Roberts Management Program Annual Review Meeting.

10/29/85 Knoxville, Attend DOE Radioactive and Hazardous C. MacDonald (FC) MacDon'al d .

TN Material Package Workshop. Reps fm DOE & DOT 11/3-9/85 Paris, Participate in high-level workshop R. Cunningham (FC) ' Cunningham

~

France on Nuclear Energy Prospects to the Year 2000 and Beyond jointly 52 sponsored by NEA and IEA.

f2 8

5 m

"U

I Page 2 of 2 NMSS MEETING NOTICES For Wrek Ending: 10/18/85

{

w

$ DIVISION O_F WAST._E_M_ANAGEMENT v' LOCATION SUBJECT ATTENDEES DATE CONTACT 11/6 Region I '

King of Prussia, PA Attend Region I State Liaison REBrowning SRomano, x74747 Officer's Meeting SRomano PA state reps Region I staff DIVISION OF SAFEGUARTS None.

l e ve i P 8 ,

E m

t

- - - - - - - _ _ _ _ _ __ _ . _ _ . _ . . - _ _ . _ _ _ . _ _ _ . _ _ . _ _ _ __~.__ . _ _ _ . _ __ _ _ _ _ _ . _ . - - . . _ _ . _ _ _ _ _ _ _ _ - _ -

o I

.O

$ OSP MEETING NOTICES _ October 18, 1985 I DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 11/6-7/85 King of Prussia, Region I State Liaison Region I State S. Weissberg Pennsylvania Officers' Meeting Liaison Officers F. Young i

t l

1 i r 4

4 1

i ... ,

E P

i St

!E m

"U

j? I October 18, 1985

-4 co RII MEETING NOTICE 8',

a DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 10/21/85 50-424 Region II Georgia Power Co. to Licensee, R. Walker 1:00 p.m. 50-425 present additional data selected RII Staff with respect to Readiness members Review Module No. 5,

! " Operations Organization

' and Administration" 10/22/85 50-280 Region II VEPC0 Enforcement Conf. Licensee, R. Walker i

10:00 a.m. 50-281 on Surry security issue selected RII Staff,

! 50-338 and North Anna issue in members 50-339 connection with an 0I Investigation report.

l 10/22/85 Chattanooga, TN Management Meeting with Licensee, NRR, IE R. Walker j 9:00 a.m. TVA concerning TVA's selected RII Staff planned response to members l

9/17/85 50.54(f) letter.

10/23/85 50-259 Athens, AL Management Meeting with Licensee, R. Walker l 11:00 a.m. 50-260 (Browns Ferry TVA to review status of selected RII Staff l (CST) 50-296 site) the Browns Ferry cable members

! tray and support design.

I 1

n E

. C, v

m 7

I i

. _ _ _ _ - - _ - . . . - _ _ - _ - - - - -