ML20133J583

Weekly Info Rept for Wk Ending 851011

ML20133J583
Person / Time
Issue date:	10/17/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-851011, NUDOCS 8510180528
Download: ML20133J583 (41)

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October 17, 1985 cFor: i The Comissioners .

From: T. A. Rehm, Assistant for Operations, Office of the E00

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 11, 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 a D Nuclear Regulatory Research E L]xecutive 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 (Not for Q er.ternal distribution)

• No input.this week. ' -

./

T. A. Rehm, s ant for Operations

i Office of the Executive Director for Operations

Contact:

T. A. Rehm, ED0

- 492-7781 85101s052s e51017 PDR COMMS NRCC WEEMLYINFOREPT PDR

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING OCTOBER 11, 1985 Cooper Nuclear Station The Cooper Nuclear Station reactor was manually tripped from 455 power at approximately 5:30 p.m. on October 5, 1985 due to excessive main.

turbine vibration. Bearing vibration of 0.008 to 0.010 inch was indicated in ene of the low pressure turbine elements; this was accompanied by a sudden increase in condensate conductivity. These indications led to an initial supposition by the licensee that a rotating turbine element was thrown and damaged one or more condenser tubes. This supposition was later strengthened by the discovery of a piece of metal (as yet unidentified) in the condenser just below the affected low pressure turbine stage.

Millstone Unit 2 On Reactor Coolant Pump Motors In the process of disassembling Reactor Coolant Pump "C" motor to determine the cause of the ground fault which had disabled the motor, Northeast Utilities found that a piece of the rotor (a spider finger) had come cut part way and cut 11 of the stator turns. The worse case was cut approximately 505 through. On disassembly, the licensee found that the 20 bolts contained within each rotor had lost approximately 905 of their initial required torque value of 400 ft. Ibs. GE, the motor manufacturer, suspects that the loss of this tension was responsible for the piece of rotor coming lose. The licensee is taking apart the other three motors to re-torque the bolts and expects to have them ready for service by the end of October. They have re-insulated the damaged motor and will either use that motor or possibly install a new motor due to arrive on site by first of November.

The motor is a GE Model 295X290, Type K Frame 6396. It is rated at 6.6 Kv, 6500 hp, 887 rpm and 525 amps.

This is a potential generic problem since the other three non-failed motors at Millstone Unit 2 also exhibited this loss of torque.

INPO is publishing a notice to their subscribers alerting them to the I

situation. The resident inspector is following the progress.

Department of The Army. Weldon Spring. Missouri DOE has informed us that as of October 1,1985, the fomer Weldon Spring .

Chemical Plant was transferred to the Department of Energy (DOE) from the Department of the Army. The Army is currently licensed for possession only of source material at this facility. DOE has stated that they will assume responsibility for maintenance, security, safety, environmental monitoring, and any remedial action at the site. The Weldon Spring plant is a former uranium feed materials facility operated by Mallinckrodt Chemical Company for the Atomic Energy Commission (AEC). The chemical plant was transferred to the Army for herbicide production in 1967, but the Army was never able to

. decontaminate the facility so that the plant could be used, i

OCT 111985

OFFICE OF ADMINISTRATION Week Ending October 11, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request . Initial Decision Carryovers, 1984 179 23 Received, 1985 682 40 Granted 543 28 Denied 158 16 Pending 160 19 ACTIONS THIS WEEK Received C. Coleman Bird, Requests six categories of records related to Ann Riley, Wald, Harkrader Ann Riley & Associates, Ltd., Tayloe Associates, Joseph

& Ross Gallo, and RS-SECY-82-473.

(85-675)

Martin Levy, Requests five categories of records regarding bargaining NTEU Chief Steward unit employees in NRR.

(85-676)

H. Anne Plettinger Requests all records between Gulf States Utilities (85-677) Company and the NRC commencing in 1978 regarding River Bend Unit 1.

Steven C. Sholly, Requests a list of NRC Project Managers and Resident MHB Technical Inspectors.

Associates.

(85-678)

Carol P. Barton, Requests a list of data bases, including mailing lists, Information that NRC subcribes to or buys from private or public Handling Services sources.

(85-679)

Marvin S. Lieberman, Requests copies of a Qualification Report for In Zuckert, Scoutt, Containment Radiation, or a similar record, and any other Rasenberger & records or information submitted by Kaman Instrumentation Johnson Corporation or Westinghouse Corporation concerning (85-680) instrumentation that can survive LOC /. and qualification of equipment, instruments, or other devices.under requirements of Regulatory Guide 1.97.

CONTACT: J. M. Felton 492-7211 ENCLOSURE A OCT 111985 i

2 Received, Cont'd Patricia Hainer Requests copies of all records regarding Serono (85-681) Diagnostics of Braintree, Massachusetts.

Fred R. Kling, Requests copies of five specified inspection reports, Willamette letters transmitting notices of violations, the current Industries Inc. license, and the license application regarding (85-682) Mallinckrodt, Inc., of Maryland Heights, Missouri.

Granted Bruce Millar, In response to a request for records pertaining to the Fort Worth-Star NRC staff review of the EG8G report on Comanche Peak, Telegram made available two records. Informed the requester that (84-869) additional records subject to this request are already available at the PDR in F01A-84-751.

Jane Fleckenstein, In response to a request for a copy of NRC license No.

ConDiesel Mobile 12-00722-06 issued to Rock Island Arsenal and records Equipment submitted in application for the license referencing (85-593) the M17, M18, M138, M171, M137, M139 and M172 tritium fire control components, made available five records.

Informed the requester that two additional records subject to this request are already available at the PDR.

Jim Pedro, In response to a request for a copy of WCAP-9964, " Iodine NUS Corporation and Cesium Spiking Source Terms for Accident Analysis,"

(85-652) informed the requester that the NRC is not in possession of this record.

Michael K. O'Mealia, In response to a request for a copy of the report on the

.. Doc-Seane. status of the Nuclear Plant Reliability Data System Associates (NPRDS), which is an attachment to SECY-85-56A, made (85-671) available a copy of the requested report.

Denied

. Billie P. Garde, In response to a request for all records related to a June 29,1984, meeting between TUECO officials and the Government Accountability NRC staff regarding the investigation concerning illegal Project use of drugs at Comanche Peak, denied one record in its (84-677) entirety pursuant to Exemption 5.

Nina Bell, In response to a request for copies of five categories of Nuclear records regarding pollution control bonds for plants, Information and made available 27 records. Informed the requester that Resource Service additional records subject to this request are already (85-426) available at the PDR. Denied one record in its entirety, release of which could interfere in the future with the candid expression of opinions by the staff.

ENCLOSURE A OCT 111985 l

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3 Denied, Cont'd Mozart G.. Ratner, In response to a request for copies of all memoranda Attorney-At-Law and notes of all conferences and conversations on which (85-542) the letter dated July 19, 1985, to Mr. Ratner from Mr. Jensen of NRC's Office of the General Counsel was based, denied one record in its entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

Mary Louise Wagner, In response to a request for copies of SECY-85-197 and McGraw-Hill a June 24, 1985, memo from Mr. Zerbe to the Commission Publications concerning NRC's role in the high-level radioactive Company waste repository program, denied the records in their (85-605) entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

e ENCLOSURE A OCT 111985

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING OCTOBER 11, 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: 2 years with an option to extend 1 additional year Sponsor: Office of the Secretary Status: RFP closed on October 7, 1985. Proposals forwarded to Source Evaluation Panel for review on October 8, 1985.

CONTRACT AWARDED RFP No.: RS-ADM-85-263 Title ~: " Technical Support Services for Data Telecomunications Equipment"

Description:

On-call repair services for data telecomunications equipment.

Period of Performance: 2 years Sponsor: Office of Administration Status: Time and Materials Requirement type contract awarded to SBA/Pailen-Johnson Associates, Inc. under the 8(a) program in the amount of $206,059.00 effective September 30, 1985.

ADMINISTRATIVE MATTER NRC has awarded ten Phase I and four Phase II contracts to small, high technology firms under the program established by Public Law 97-219, the Small Business Innovative Research Program (SBIR) in the total' amount of $1.3 million. The program is aimed at stimulating technological innovation in the private sector, strengthening the role of small business in meeting NRC's research and development needs, and contributing to the growth and strength

'of the nation's economy.

Projects funded by this program are conducted in two phases. Phase I awards are on a fixed price basis funded at approximately $50,000 to explore the feasibility of innovations proposed by small businesses. If the results of i

the Phase I award warrants, a Phase II contract is awarded to proceed with the technological innovation. Phase II awards are funded at approximately

, $250,000. Any work beyond Phase II would be. funded by either commercial firms or by non-SBIR funded production contracts with federal agencies.

ENCLOSURE A

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending October 11, 1985 Dresden Nuclear Power Station, Unit Nos. 2 and 3 Quad Cities Nuclear Power Station Unit Nos. 1 and 2 On October 3,1985 Coninonwealth Edison (CECO), in discussions with the staff, informed the staff that some of the wiring on Limitorque valves (approximately 35 valves / unit) was possibly not environmentally qualified per the requirements of 10 CFR Part 50.49. CECO stated, however, that documentation exists which justifies continued operation for those units which are presently operating. Dresden 2 is at present in an outage in which the wiring will be replaced with qualified wires. Dresden Unit 3 and Quad Cities Units 1 and 2 are currently operating. Quad Cities 1 and 2 will have qualified wiring in place by the November 30, 1985 deadline and Dresden 3 is shutting down on October 26, 1985 for an 8-month refueling and pipe replacement outage and it will be in compliance when it restarts. We informed CECO that if the wiring is not replaced by November 30, 1985, they must take actions in accordance with Generic Letter 85-15.

Diablo Canyon Unit 2 - Completion of RCP Repairs The rewinding of the failed motor of the reactor coolant pump has been completed and the motor has been reinstalled. Unit 2 is currently heating up. Criticality is expected early this week to be followed by completion of the low power testing. Full power operation (i.e., above 5 percent) is scheduled for mid October and commercial operation for early January 1986. Unit 1 continues operation at 100% power level.

Cooper Nuclear Station The Cooper Nuclear Station reactor was manually tripped from 45% power at approximately 5:30 p.m. on October 5, 1985 due to excessive main turbine vibration. Bearing vibration of 0.008 to 0.010 inch was indicated in one of the low pressure turbine elements; this was accompanied by a sudden increase in condensate conductivity. These indications led tu an initial supposition by the licensee that a rotating turbine element was thrown and damaged one or more condenser tubes. This supposition was later strengthened by the discovery of a piece of metal (a's yet unidentified) in the condenser just below the affected low pressure turbine stage.

ENCLOSURE B OCT 111985

On October 8, 1985 the licensee removed the cover from the low pressure turbine and began the preliminary visual observation. A more detailed examination is expected to begin on October 9, 1985. Although the duration of the shutdown will depend on the specific nature of the damage, the licensee's initial estimate is for a shutdown of 7 to 10 days.

Millstone Unit 2 On Reactor Coolant Pump Motors In the process of disassembling Reactor Coolant Pump "C" motor to determine the cause of the ground fault which had disabled the motor, '

Northeast Utilities found that a pie'ce of the rotor (a spider finger) had come out part way and cut 11 of the stator turns. The worse case was cut approximately 50% through. On disassembly, the licensee found that the 20 bolts contained within each rotor had lost approximately 90% of their initial required torque value of 400 ft. lbs. GE, the '

motor manufacturer, suspects that the loss of this tension was ,

responsible for the piece of rotor coming lose. The licensee is taking apart the'other three motors to re-torque the bolts and expects to have  :

them ready for service by the end of October. They have re-insulated r the damaged motor and will either use that motor or possibly install a '

new motor due to arrive on site by first of November.

The motor is a GE Model 295X290, Type K, Frame 6396. It is rated at

> 6.6 Kv, 6500 hp, 887 rpm and 525 amps. ,

i This is a potential generic problem since the other three non-failed i motors at Millstone Unit 2 also exhibited this loss of torque.

• INP0 is publishing a notice to their subscribers alerting them to the situation. The resident inspector is following the progress.

4 Fort St. Vrain Recentralization of Licensing Functions to NRR I Effective October 4, 1985, NRR reassumed responsibility for performing  !

l all licensing functions for the Fort St. Vrain Nuclear Generating i Station. The Region IV Regional Administrator had been assigned and [

l authorized the responsibility for certain Fort St. Vrain licensing functions since December 3, 1982.

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i OCT 111985 ENa05URE B

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING OCTOBER 11, 1985

1. PLANT STATUS The facility remains in long tenn cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactor vessel.

The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and 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 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 platfonn is installed over the Internal Indexing Fixture in preparation for defueling.

Calculated reactor decay heat is less than 12 kilowatts.

RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 71*F to 92*F with an average of 80 F. Average cold leg temperature will no longer be reported.

The average reactor building temperature is'60*F. The reactor building airborne activity is 9.1 E-7 uC1/cc Tritium and 4.9 E-11 uCi/cc particulate, predominantly Cesium 137.

2. WASTE MANAGEMENT The Submerged Demineralizer System (505) continues processing batch 124 from neutralizer tanks (WDL-T-8 A/B) to SDS monitor tanks (SDS-T-1 A/B). To date 21,501 gallons from this batch have been processed.

ENCLOSURE B l l

OCT 111985 l

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2 EPICOR II connenced processing batch 268, 3,046 gallons, from Chemical Cleaning Building sump to CC-T-2. Commenced processing batch 269 from SDS-T-1A to CC-T-2. To date 10,578 gallons from this batch have been processed.

Total volume processed through SDS to date is 2,984,874 gallons, and

, the total volume processed through EPICOR II is 2,694,902 gallons.

3. DOSE REDUCTION / DECONTAMINATION ACTIVITIES 1

Decontamination activities are continuing on the 291' 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.

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 21 through September 28, 1985. A ganma 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 22 through September 28, 1985. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site

, collected a sample between October 2 and October 9,1985. No reactor related radioactivity was detected. Analysis showed

, Iedine-131 and Cesium-137 concentrations to be less than the lower 71mits of detectability.

' 5. REACTOR BUILDING ACTIVITIES

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Defueling Water Cleanup System (DWCS) preoperational testing and i

modification continued.

Work is in progress on the canister positioning system and canister handling bridge.

Installation of the vacuum defueling system is in progress.

Canister transfer system has been installed and will be load tested.

Lower vessel debris samples have been removed and are undergoing preliminary analyses onsite. Samples will be shipped to Idaho

, National Engineering Laboratory for further analyses.

l ENCLOSURE B OCT 111985

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6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is expected to be completed in October.

- . All four of the fuel canister storage racks are being positioned in the spent fuel pool. Fuel canister handling bridge has been load tested and indexing is in progress.

7. RADI0 ACTIVE MATERIAL / WASTE SHIPMENTS These shipments were made from Three Mile Island during August and September 1985.

August 7 - 108 drums, 2 boxes - Combined unit contaminated laundry to Royersford, Pennsylvania.

August 9 - Unit 2 - Reactor Building cable samples were sent to a laboratory at Richland, Washington.

August 13 - 79 drums - Combined unit contaminated laundry to Royersford, Pennsylvania.

August 21 - 71 drums,1 box - Combined unit contaminated laundry to Royersford, Pennsylvania.

August 22 - Unit 1 - Liquid samples were sent to a contractor vendor laboratory at Rockville, Maryland.

- August 27 - 65 drums,1 box - Combined unit contaninated. laundry to Royersford, Pennsylvania.

August 27 - Unit 2 - Lead bricks were sent to a contractor at Columbia, South Carolina.

August 28 - Unit 1 - Dewatered resins and solidified liquids in steel liners were sent to Hanford, Washington.

August 30 - Unit 2 - Temporary waste solidification unit sent to vendor at Columbia, Maryland.

September 4 - Unit 2 - Reactor Building cable samples were sent to a laboratory at Hanford Washington.

September 6 - Unit 1 - Liquid samples to Rockvalle, Maryland.

September 10 - Unit - A solenoid-operated valve ard pipe from the Reactor Building were sent to Scoville, Idaho.

- September 16 - Unit 2 - Steel liner containing solidified demineralizer resins was sent to Hanford, Washington.

September 17 - 87 drums, 3 boxes - Combined unit contidninated laundry to Royersford, Pennsylvania.

September 18 - Unit 1 - Dewatered c:nineralizer resins to Barnwell, South Carolina.

September 19 - Unit 1 - Three liners containing dewatered demineralizer resins and solidified liquids to Hanford, Washington.

- September 27 - 57 drums, 3 boxes - Combined unit contaminated laundry to Royersford, Pennsylvania.

ENCLOSURE B OCT 111985 t

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8. 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.

j - Boron Dilution Hazard Report

- Defueling Water Cleanup System Technical Evaluation Report, Revision

7.

9. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for October 16, 1985 in Lancaster, Pennsylvania at 7:00 PM. The meeting will be held in the Lancaster Council Chambers at 201 North Duke Street. Dr. H. Arnold i Muller, Secretary, Department of Health will review the results of the

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Health Department's recently completed epidemiology studies.

Persons desiring the opportunity to speak before the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.

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ENCLOSURE B OCT 111985

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending October 11, 1985 Near-Term NRC Actions Under the NWPA Section: 134 of NWPA: Final Rule on Hybrid Hearings Action: The Comission voted to approve the final rule establishing procedures for expansion of onsite spent fuel storage capacity or transshipment of fuel on September 5, 1985.

) Status: The final edited version was submitted to SECY on October 4,1985 I

for publication in the Federal Register within the next (week) 10 days.

Section

114(e) of NWPA: Project Decision Schedule coments Action: The Comission voted to approve PDS comments with modifications on September 19, 1985.

Status: The final edited version is due to SECY by October 15, 1985 for submittal to DOE.

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, j

Status

Proposed revisions to 10 CFR Part 72 will be submitted to E00 for concurrence on October 10, 1985.

r Meeting with Local Tennessee Task Force on MRS I

On October 2, 1985, NRC staff met with a group from Oak Ridge and Roane County, Tennessee. The group represented the Clinch River MRS Task Force.

The Task Force was formed in April to evaluate the Department of Energy's (DOE) forthcoming proposal to the Congress for an integrated MRS. Task Force members were appointed by the Roane County Comission and the Oak Ridge City Council. The Task Force expressed an interest in the formation of a citizen's Review Board, appointed by Roane County, Oak Ridge and the State, who would have the authority for certain local controls over MRS operation. The Task Force group also visited 00E, congressional, and industry offices in the

. Washington, DC area.

ENCLOSURE C ,

OCT 111985 ,

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I Commonwealth Edison Company, Braidwood Station On October 8,1985, Commonwealth Edision Company was issued Materials License No. SNM-1938 for Braidwood Station, Unit 1, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies. It also authorized the receipt, possession, inspection, storage, and use of Post Accident Neutron Monitoring Detectors

. containing uranium enriched in the U-235 isotope, and use of a sealed 1

plutonium calibration source. All materials are for eventual use at the Braidwood Station, Unit 1.

Rockwell International Licensing Activities Dr. M. E. Remley, Director, Nuclear Safety and Licensing, Energy Systems Group (ESG) of Rockwell International, met with a NHSS staff member on October 9, 1985, to discuss their reorganization into the Rocketdyne Division of Rockwell International. ESG plans to submit page changes to the license conditions and demonstration sections of its license in the near future reflecting the change in organization.

Department of The Army, Weldon Spring, Missouri DOE has informed us that as of October 1, 1985, the former Weldon Spring j Chemical Plant was transferred to the Department of Energy (D0E) from the Department of the Army. Tha Army is currently licensed for possession only of source material at this facility. DOE has stated that they will assume

, responsibility for maintenance, security, safety, environmental monitoring, and any remedial action at the site. The Weldon Spring plant is a former uranium feed materials facility operated by Mallinckrodt Chemical Company fnr the Atomic Energy Commission (AEC). The themical plant was transferred to the Army for herbicide production in 1967, but the Army was never able to decontaminate the facility so that the plant could be used.

NFS-Erwin i

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.

DOE-NRC Meeting l A meeting has been arranged for the week of October 13, between NRC (NMSS) and i DOT to discuss the possibility of joint participation in spent fuel route

surveys with NRC having approval authority and DOT having an advisory role.

i ENCLOSURE C OCT 111985

r l OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest  !

i Week Ending Cctober 11, 1985

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

l week:  ;

t a. EN 84-69, a Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $5,000 was issued on October 8,1985 to j Met-Chem Engineering Laboratories (Salt Lake City, UT). This action  ;

1 is based on multiple violations that include the use of an unauthorized i and unqualified individual to perfonn licensed activities and an l

overexposure to a radiographer. l

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! b. EN 85-71 Notice of Violation and Froposed Imposition of Civil  !

Penalty in the amount of $50,000 was issued on October 8, 1985 to ,

, Arizona Public Service Company (Palo Verde Unit 1). This action is j based on a violation involving the Post Accident Sampling System.

! 2. The following IE Preliminary Notifications were issued during the past -

j week:

, a. PNS-I-85-13A, Boston Edison Company (Pilgrim), Discovery of Damaged j i

SpentFuelHandlingEquipment(Update).

j b. PNO-I-85-73, Northeast Utilities (Millstone, Unit 2), Unplanned Plant 1 Shutdown in Excess of 48 Hours. ,

i c. PNO-I-85-74, 8eth Israel Hospital (Boston, MA),-Unauthorized Transfer l and disposal of Radioactive Waste.

l d. PNO-I-85-75, Public Service Electric & Gas (Salem Unit 1),

j Unscheduled Outage. l d i

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e. PNO-I-85-76, Baltimore Gas and Electric (Calvert Cliffs Unit 1) i Unscheduled Shutdown Required by Technical Specifications. l l f '. PNO-II-85-94,DukePowerCompany(OconeeUnit1), Unscheduled i Shutdown Greater Than 48 Hours.

I g. PNO-III-85-87,CommonwealthEdison(ZionUnits182), Construction ,

Fatality.

! h. PN0-III-85-88,RegionIII(GlenEllyn,IL')SuspiciousPackage j Received by Region III, j 1. PN0-IV-85-52, Louisiana Power and Light Company (Waterford 3), Outage i Greater Than Two Days. .

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] j. PNO-IV-85-53, Omaha Public Power District (Fort Calhoun), Outage '

j Greater Than Two Days.

ENCLOSURE D I

l OCT 111985 I

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k. PNO-IV-85-54, Nebraska Public Power District (Cooper), Unplanned Reactor Shutdown Expected to Last More Than 72 Hours.

1. PNO-Y-85-68, Arizona Nuclear Power Project (Palo Verde Unit 1), Loss I of Offsite Power at Palo Verde Unit 1.

m. PN0-V-85-69, Arizona Nuclear Power Project (Palo Verde Unit 1),

Switchyard Electrical Distribution Malfunction (PNO-V-85-68 Update). ,

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n. PNO-V-85-70, Portland General Electric Company (Trojan), Short Circuit of Non-Safety Related Motor Control Center. i

o. PNO-V-85-71, Sacramento Municipal Utility District (Rancho Seco),

Auxiliary Feedwater Pump Thrust Bearing Failure.

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

l None. l

4. Other Items l i

a. Enforcement Conference Representative of Enforcement Staff was in Region II October 9,1985 for an Enforcement Conference on Turkey Point. r

b. Transportation of Radioactive Material Course i

Representative of Safeguards and Materials Programs Branch, Division  ;

of Inspection Programs was in Region III this week to present a  :

Transportation of Radioactive Materials Course to selected members of RIII staff.

c. Davis-Besse Two representatives of the Engineering and Generic Communications  !

Branch, Division of Emergency Preparedness and Engineering Response, visited the Davis Besse site on October 8 and 9,1985 an-1 met with the licensee and RIII personnel. Their role was to assfst in the j review of the adequacy of the pipe supports, considering differences  :

between the as-designed and as-built conf.igurations. l l

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ENCLOSURE D OCT 111985

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d. Outage Inspection Trial Program -

An interim exit meeting was held at the Omaha Public Power District headquarters in Omaha on October 8 for the purpose of briefing the 1 utility on the results of the design review portion of the Fort Calhoun outage inspection. Supervisory and management personnel from  !

the Division of Inspection Programs and the Division of Quality 4

Assurance, Vendor, and Technical Training Center Programs attended 4

the meeting. The vendor inspection part of the trial program is ongoing with an inspection at Westinghouse this week. The remaining installation and testing inspections are planned for November and early December 1985. ,

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e. Vendor Program

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Vendor Program Branch, Division of Quality Assurance, Vendor and Technical Training conducted the following inspection this week ,

! Westinghouse Electric Company, Nuclear Services Division, Pittsburgh, PA - To review the testing of 4160/480V transformers, implementation  !

of the QA program and other requirements as required by the Ft.

Calhoun outage work package. t l f. Operations Center Tours of the NRC Operations Center were conducted by representatives of the Incident Response Branch, Division of Emergency Preparedness and Enjineering Response on October 7,1985 for a Chinese delegate

, from Taiwan Power; on October 8,1985 for representatives from Stone l

& Webster Engineering; and for representatives from the agreement  ;

states on October 10, 1985. These tours discussed the agency's '

incident response program.

g. Relocation Tabletop Exercise On October 8,1985, a Relocation Tabletop Exercise (RTE) working  !

group session was held to finalize planning for the December exercise. Participants include members from the Incident Response -

Branch, Division of Emergency Preparedness and Engineering Response,  ;

FEMA and their contractor, EPA and DOE.

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ENCLOSURE D

OCT 111985

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0FFICE OF NUCLEAR REGULATORY RESEARCH 1

Items of Interest Week Ending October 11, 1985 TMI-2 Post Accident Examinations Initial agreement was reached October 2,1985, that two large

" core-bore" samples of the TMI-2 core would be examined under the NRC/RES

, TMI-2 examination program in coordination with the overall TMI-2 exanination effort. The agreement was reached in a meeting among DOE, 1 EG&G, ANL, and NRC/RES personnel. These two " core-bore samples will i consist of stratified samples of core material from two radial locations, obtained from a geologic-style core-drilling operation providing an up to eight feet long continuous sanple several inches in diameter. The core-drilling operation will take place this winter and, allowing for complicated shipping and sample preparation plans, the examinations will be performed next spring and summer. -

The TMI-2 Accident Evaluation Program Plan Advisory Group met on Thursday,

October 3 to provide comments to EG8G on their proposed examination plans .

as presented in a preliminary draft made available for review about one week prior to the meeting. The Advisory Group meeting was attended by representatives of EPRI, GE, B&W, GPUN, Energex, MIT, Fauske & Assoc., and NRC/RES. It was the intent of DOE and EG&G that the Advisory Group

, critique and advice would provide for a peer-reviewed planning document ensuring a proper focus in the program en appropriate source term and severe accident issues. The NRC views oa the planning draft, taken from .

l comnents provided by NRR and RES personnel prior to the meeting, were well 2

received in the Advisory Group and are embodied in the collective comments "

1 J being provided for DOE /EG&G use. An adjusted final planning document will be issued in about one month.

'l ENCLOSURE E OCT 111985' I

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2 Nuclear Plant Analyzer (NPA)

The NPA is a system consisting of existing thermal hydraulic codes (RELAP5' and TRAC-PWR) with interactive capabilities and the color-graphic software (NPA-Executive) to analyze reactor system transients in order to provide the Office of Nuclear Rea'ctor Regulation (NRR) with a broad technical basis for licensing decisions. The Idaho National Engineering Laboratory (INEL) completed the coding for the replay capability at a local terminal and a draft users manual for the NPA. The draft manual will be sent to NRC for review.

International Code Assessment Program (ICAP)

Thirteen countries have signed agreements with NRC to provide unique test data and code assessment studies for the thermal hydraulic codes (TRAC, RELAP,andCOBRA-TRAC). In return, as part of the U.S. contribution, INEL has issued: (1) the second newsleter on the RELAP5/ MOD 2 code, and (2) documents describing procedures for error corrections in the code and review of assessment reports.

2D/3D Program The Japan Atomic Energy Research Institute (JAERI) completed the Core-II test series in its Slab Core Test Facility (SCTF) in June 1985 and will present the test results at the 20/3D Program Coordination Meeting to be held at the Holiday Inn, Bethesda, Maryland on October 28-31, 1985.

Present at this meeting will be representatives of NRC, JAERI, and the Federal Republic of Germany, as well as NRC contractors (INEL, Los Alamos National Laboratory, Oak Ridge National Laboratory, MPR Associates, and Creare Incorporated) and the industry representatives. The SCTF is a large-scale test facility. Its reactor core contains eight full-size bundles (about 2000 rods) of electrically heated fuel rods. These bundles are arranged in slab geometry to simulate a radial segment of a full-size reactor and is used to study the effect of radial power variations.

ENCLOSURE E OCT 111985 l

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3 Meeting on EPRI Solid Waste Environmental Studies Program A meeting of contractors working for the Electric Power Research Institute (EPRI) on the Solid Waste Environmental Studies (SWES) program was held in Denver, Co. on Oct. 1 & 2, 1985,to review ongoing research which is focused on assessment of contaminant leaching and subsequent ground-water transport associated with conventional electric power plant was 2 streams. The long-term objective of the SWES program is to develop and validate improved methods for predicting the environmental fate of chemicals released from power plant solid waste disposal facilities.

(The present focus is on ash ponds from coal fired plants.) As part of RES' continuing effort to be aware of, and where possible adopt, work by others which may be useful to NRC's licensing program, RES (T.J.

Nicholson of the Earth Sciences Branch) attended this EPRI meeting to assess the applicability of the work to the resolution of issues in the LLW and HLW licensing programs. EPA was also represented at the meeting because of its regulatory responsibilities with respect to conventional power plants.

The specific projects discussed were (1) development and evaluation of geohydrochemical models, (2) contaminant immobilization studies, (3) leaching studies, (4) ground-water transport studies, (5) ground-water sampling methods and related field measurements, and (6) unsaturated zone transport studies. The work on geochemical modeling and sampling of contaminants in both the saturated and unsaturated zones could be of considerable benefit to NRC's uranium recovery and low-level waste regulatory activities. The methodology for modeling contaminant plumes seems to be applicable to radioactive plume analyses, since the chemical mechanisms.and hydraulic processes are similar. RES will continue to follow developments in the EPRI SWES program.

l Workshop on Radiological Health Effects Models for Nuclear Accident Consequence Analysis The NRC recently received a report from Sandia National Laborato'les entitled " Health Effects for Nuclear Power Plant Accidents Analysis,"

NUREG/CR-4214. This report was prepared by a group of U.S. scientists headed by the Harvard School of Public Health, and its objective was to update and improve the health effects models used 10 the Reactor Safety Study (WASH-1400).

Public comments on the report have been raquested. Ultimately, the staff intends to use the methods and data in the report for health effects risk assessments of potential radiation exposures from accidents and normal operations of NRC-licensed facilities.

ENCLOSURE E OCT 111985

4 A workshop was held from 9/30 to 10/2/85 at the Nuclear Research Center Karlsruhe (KfK), Germany, to evaluate the models and coefficients proposed in NUREG/CR-4214 and to compare them to those used in Germany and Great Britain. The workshop was attended by KfK staff members, several prominent German scientists and British scientists from the National Radiological Protection Board (NRPB). U.S. participants were Dr. J. S. Evans, Harvard, the principal investigator on NUREG/CR-4214, and Dr. S. S. Yaniv RES, NRC.

The Germans are revising their Reactor Safety Study and wished to evaluate the validity and applicability of the models used in NUREG/CR-4214. At present the health effects models used by the Germans and the British are different from each other and different from those described in NUREG/CR-4214 Although there were some minor criticisms, the models and numerical values proposed in the U.S. report were, in general, accepted by the participants. Significantly, the British and German scientists expressed the opinion that it would be very desirable if the health effects models and risk coefficients used in Europe and the U.S. were exactly the same, because this would enhance public confidence in risk estimates. The participants agreed that NUREG/CR-4214 might serve as a basis for arriving at internationally accepted health effects models and coefficients.

Contact:

S. S. Yaniv 42-74581 Experinental Research Work on Containment Failure Modes Under Severe Accident Conditions The major source of risk to the public from the operation of nuclear power plants stems from accident scenarios that lead to a containment failure.

The regulatory concern is that the failure modes and associated load levels for containment structures cannot be predicted with confidence by state-of-the-art methods. This is especially so if the contemplated failure mode is localized leakage; through containnent penetrations, or purge and vent valves, er the localized failure of structure. These potential weak links in containment performance fonn the basis for experimental resen ch being sponsored by the NRC and the Electric Power Research InstitKe (EPRI).

EPRI and NRC are engaged in complementary research on concrete containment behavior under severe accident conditions. NRC's efforts utilize a 1/6 size model of a concrete containment to focus on overall behavior. EPRI's efforts utilize full-size specimens to examine localized behavior. The efforts have been coordinated so that the programs, when taken together, would yield a complete picture about the failure nodes of concrete containments.

ENCLOSURE E OCT 111985

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e The NRC sponsored research consists of testing of steel and concrete i containment models with simulated penetrations, and experiments to understand the behavior of penetration seals and gaskets under severe i accident pressures and temperatures. EPRI efforts concentrate on understanding potential leak paths in concrete (reinforced and prestressed)

. containments. The EPRI experimental work is carried out at the j Construction Technology Laboratories (CTL) of Portland Cement Association (PCA). ,

The CTL just completed a separate effects test on the junction of base mat

! and containment wall representing the details of a prototype prestre; sed  :

concrete containment including the containment lower liner. The purpose of 1

this test was to determine the ultimate strength of this test configuration by loading it until it failed. Instrumentation readings indicate that the inside face of concrete and liner in the wall were highly strained. The

! exact strains in terms of yielding in the material are not yet known. The ,

i concrete was extensively cracked and the liner plate was distorted in some

! places and experienced through wall cracking at a few locations. Since the j test data have not been reduced, it is not yet known whether the liner j

cracks developed before the yielding of the reinforcing bars or what j equivalent pressure was required to initiate high strains in the liner plate. The cracking in the liner supports a tentative conclusion that gross containment failure will not occur before a potential leakage path is l opened. Further information will be available after the data are reduced and evaluated.

{ Regulatory Guide Activities The ACRS Regulatory Activities Subcommittee concurred in the staff positions of Revision 2 to Regulatory Guide 1.105, " Instrument Setpoints for Safety-Related Systems," and of Regulatory Guide 1.153, " Criteria for Power, Instrumentation, and Control Portions of Safety Systems." The guides are now cleared for issuance as effective guides, i  :

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ENCLOSURE E

OCT 111985 t 3

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6 RES Rulemaking Activities Pressurized Thermal Shock (PTS): In SECY-85-262, the EDO stated he would keep the Comission informed of the development of a draf t regulatory guide (Rev. 2 of Reg Guide 1.99) that includes a method for calculating RT differentthanthatincludedinthepressurizedthermalshockrulepublisb on July 23, 1985.

coment: On September 25, CRGR reviewed and approved publishing for (1) the proposed revision to Reg Guide 1.99, and (2) the proposed PTS Reg Guide, For the PTS Reg Guide, the next steps are: NRR will make the changes i

recomended by CRGR. '

at The plan is then to send the guide to ACRS for comment the same time we send it to Congress and the Federal Register. ACRS review in parallel with public comment is appropriate for this guide because: ,

(1) issuing this guide for public coment constitutes resolution of USI A-49, a milestone which NRC committed to comp ate by the end of FY 85; and (2) the ACRS periodically has reviewed the PTS research results and regulatory plans l

upon .whichcriterion acceptance this guide is based. 6 The only new thing in the guide is the of 5x10~ per reactor-year mean frequency  !

through-wall crack. of ;

on the PTS guide in parallel with public coment.Therefore staff believes we public cowent period. Staff is planning a 90-day GDC-4:

Rulemaking to modify GDC-4 was initiated at the request of NRR in order to These exclude dynamic effects associated with postulated pipe ruptures.

postulated pipe ruptures require protective devices which are now ,

believed to not be needed and which could negatively affect plant safety.

Work began in December 1984 and the proposed rule was published in July 1985.

Most recently, analysis of public comments has been completed. Resolution of ,

seven The issues issues has been prepared in draft fom for review by RES, NRR and ELD.

are: (1) expand scope of affected piping; (2) allow redesign of heavy component supports; (3) extend rule to ECCS, containment and/or EQ; (4) provide guidance on analysis requirements; (5) modifications may not involve an unreviewed safety question; needed;and(7)modificationmaynotrequirelicensingemendment.(6) aug Emergency Preparedness for Fuel Cycle and Other Radioactive Material Licensees:

In 1981 the NRC issued orders to certain fuel cycle and other radioactive material radiological emergency licensees plans. requiring them to submit comprehensive ensite those orders. The rulemaking The proposed rulemaking is a codification of package is in concurrence chain. FEMA concurred "in the language of the proposed. rule as written with the understanding that FEMA and NRC will develop a joint Guidance Memorandum for State and local governments on this effort."

had in mind at the next interagency coordinating committee meeting.lE plan C0f4 TACT: S. Turel, DRA0 ENCLOSURE E 44-37925 OCT 111985

i ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS j WEEK ENDING OCTOBER 11, 1985 International Visitors On Monday and Tuesday Mr. Irving I. L. Wang, Head of the Health Physics i Division, Nuclear Operations Department, Taiwan Power Company, met I

representatives of the IE Division of Emergency Preparedness and

Engineering Response, the RES Division of Radiation Programs and Earth

Sciences, and the NRR Division of Systems Integration.

On Tuesday Mr. Toichi Sakata, First Secretary for Scientific Affairs',

i and Mr. Masao Senzaki, Special Assistant for Scientific Affairs, Embassy of Japan, met the Director and Deputy Director of the NMSS Division of

Safeguards and IP representatives for an overview of NRC's responsibilities in the physical protection, safeguards, export i

licensing, and non-proliferation fields.

On Wednesday Messrs. H. Liemersdorf and G. Philips of the German I

organization GRS and Mr. R. Wittman of KWU, the Geman reactor vendor, I

held discussions with RES and NRR on several areas related to fire hazards and fire protection principles.

On Thursday Mr. Piotr Pons of Flygt AB, the Swedish manufacturer of pumps and valves, visited with RES and NRR to review the latest information available to NRC on the perfomance and problems of various valves and seals in use at nuclear installations in the U.S.

On Thursday, October 17, two members of Sweden's Nuclear Installations Inspectorate, Jan Mattson and Uno Heakensson, will be visiting Region II to discuss NRC inspections of nuclear facilities.

Foreign Trip Reports 3

W. F. Bethmann, Jr., and J. E. Smith, ORNL Staff Members July 15-August 2. 1985; Visited FRG: s i

The purpose of this trip was to provide engineering troubleshooting services at the Upper Plenum Test Facility in Mannheim for sensors that had failed and to provide field assistance in installation of the improved electronic bridge balancing circuit, field-tested at Karlstein j for acceptance.

ENCLOSURE G OCT 111985 i

2 Foreign Trip Reports continued G. A. Murphy, Manager, Operations and Analysis, ORNL August 19-23, 1985; Visited Belgium:

Mr. Murphy participated in the 8th International Conference on Structural Mechanics in Reactor Technology in Brussels. He presented a paper " Survey of Operating Experience to Identify Structural Degradation of Nuclear Power Plant Components." The subject of the paper was drawn from initial ORNL work conducted by the traveler in the Nuclear Plant Aging Research Program.

James T. Han, Fuel Systems Research Branch, RES August 19-30, 1985; Visited China:

Mr. Han was invited to lecture in Beijing August 19-30 on (1) severe accident progression and consequences, and (2) severe accident prevention and management.

C. Z. Serpan, Chief, MEB, RES August 21-22, 1985; Visited Belgium and the UK:

Mr. Serpan chaired the annual meeting of the OECD-NEA Principal Working Group No. 3 on primary system integrity in Brussels. In London, he met with English researchers on cooperation in the Gundrensningen project.

J. Muscara, MEB, RES August 30, 1985; Visited Italy:

Mr. Muscara participated in the first meeting of the PISC III management board meeting held at the Palace Hotel in Varese, Italy on August 30, 1985.

Michael Tokar, Section Leader, EB, WM, NMSS

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September 7-14, 1985; Visited 5weden:

Mr. Tokar participated in the Ninth International Symposium on the 1 Scientific Basis for Nuclear Waste Management, held on September 9-11, in Stockholm. He also visited the STRIPA underground test station.

ENCLOSURE G OCT 111985

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I 0FFICE OF RESOURCE MANAGEMENT i '

ITEMS OF INTEREST Week Ending October 11, 1985

! Relocation Services for Federal Employees The General Services Administration is considering contracting for relocation services which, when in place, could be used by federal agencies, thereby 4

eliminating the need for each agency to separately contract for such services, j RM attended an information exchange meeting with GSA on 10/8/85 to provide NRC i input and to stay abreast of the latest developments in providing relocation services for federal employees.

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OFFICE OF SMALL AND DISADVANTAGED BUSINESS UTILIZATION / CIVIL RIGHTS Item of Iterest Week Ending October 11, 1985 Small and Disadvantaged Business Utilization Program The staff of NRC's Small and Disadvantaged Business Utilization Program recently participated in the Third Annual Minority Enterprise Development (MED) Week (October 6-10,1985).

President Reagan's proclamation designated this week as one of celebration and commemoration of the many accomplishments made by minority Americans throughout the Nation. Top honors and awards to the Minority Entrepreneurs of the year were presented at the White House by Vice-President Bush. The Maxima Corporation of Bethesda, MD, which is a firm that NRC is quite familiar with, was selected as Minority Government Contractor of the Year.

Because of the large number of minority contractors (High Tech as well as other disciplines) present during MED Week, the staff was able to meet many s new firms and obtain copies of their capability statements during two complete days set aside for market place activities.

ENCLOSURE K OCT 111985

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REGION III J

J STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATEF. EVENT j October 15, 1985

Plant Status i

- The plant remains in cold shutdown. The circulating water canal is drained.

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

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O A. EQUIPMENT STATUS (FOLLOWS TABLE 5.1 IN NUREG 1154)

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TROUBLESHOOTING / ROOT CAUSE DETERMINATION ACTIVITIES COMMENTS RIII ACTIONS -

ITEM Main Feedwater Cause determined to be component MFPs were tested on 09/05- Region III is tronitoring 1.

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.

Cause determined to be that circuit More testing will be scheduled RIII monitoring licensee's

2. Closure of MSIVs**

was overly sensitive to momentary later. Specialist from NRR activities and observing system perturbation. Revised will observe testing as selected acti~~:ies.

report issued 10/03/85. Trouble- required.

shooting now in progress should not effect root cause determination.

Defective electronic module in Remaining ten MSSVs have been

3. Steam Safeties,**

removed, six have been shipped RIII following licensee Atmos. Vents. ICS likely cause of problem with atmospheric vent valves. Revised to Wylie for full flow steam activities. Vendor report issued 10/03/85. MSSVs testing. Six remain to be Programs Branch has been being evaluated. shipped including two spares, notified of testing.

The valves will be modified as reconnended by Dresser.

Aux. Feedwater Turbine Cause considered to be condensation Preparations are being made to RIII inspectors to observe 4.

in long steam inlet lines. Revised modify the steam supply system. activities, report issued 09/16/85. Governor from #2 AFWPT has been removed and sent to Woodward along with two spare governors for inspection and modifications.

Governor for #1 AFWPT is being replaced with a new governor.

Causes were incorrect torque switch Additional dp and flow testing RIII following licensee

5. AFW Containment.

Isolation Valves bypass settings and inadequate test is being evaluated. activities.

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

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6. Steam Supply Valve Completed and revis.ed report Activities completed. RIII to observe any to AFPT No. 1 issued 09/09/85. Valve will be Additional testing additional testing, inspected internally with a is planned in hot borescope. standby.

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

on NI-2. NI-2 failed due to a . containment cable penetration '

defective containment penetration module for NI-2. NI-1 is module. The root cause of the being monitored and is penetration failure is not yet functioning correctly.

known. Revised report issued 09/16/85 on NI-1. Root cause was bad connection between detector and cable, Completed and report sent to NRR RIII observing activities.

8. PORV** The origasneeded). (inal valve One will be Vendor Programs Branch has 08/23/85. toot *cause not deter- rebuilt

' mined. rebuilt PORV (rather than been notified.

two, as reported last week)

. has been shipped to Marshall Steam Station in Terrell, N.C.

1 for testing week of 10/21/85.

A third PORV will be rebuilt, if necessary, based on test j resul ts.

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9. S/U Feedwater Control Completed and revised report issued Work complete. None.

Valve 08/29/85. The valve functioned .

4 correctly during the June 9 event. l 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 deficiencies identified. will be posted at the turbines. assure proper operator ,

1. 2 AFWPT trip throttle valve actions.

E2 has been removed for E2 inspection.

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TROUBLESHOOTING / ROOT CAUSE DETERMINATION ACTIVITIES COMMENTS RIII ACTIONS ijflTEM

11. AFP No. 1 Suction Revised report issued 09/17/85. Individual pump suction RIII observing activities.

Transfer Root cause determined to be strainers will be removed and excessive pressure drop across the common suction strainer will common strainer caused by be replaced with a coarser mesh transient flow variations. strainer.

12. Turbine Turning Gear *

13. Control Room HVAC*

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

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.

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!kl. REGION III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO OF AUGUST 9,198'5

1. Item: Adequacy of the licensee's management and maintenance activities 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 concerning management practices (Deficiency Reports) and enforcement (e.g., control of maintenance history and determine if licensee's and programs and post-trip reviews). Region III's actions were adequate and appropriate. Inspections are ongoing.

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

are adequate. Confirm that adjustment M0 VATS machine to aid them in the setting settings are consistent with plant of all limitorque operated valves.

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7. Item: Adequacy of emergency notifications ACTION STATUS /C0fmENTS e

c2 Region III Emergency Preparedness has 2 (a) Verify the adequacy of the licensee's procedures and training for the report- reviewed the licensee's training and w

ing of events to the NRC Operations procedures for reporting of events to the g

o, NRC. One violation of NRC requirements was found. Region III is reviewing the licensee's reporting per 10 CFR 50.72 and 10 CFR 50.73.

8. Item: Reliability of AFW pump turbines ACTION STATUS / COMMENTS (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, NRR, and Region III members established and adequately tested to confirm system ,

configuration involved with design will review AFW system testing. First team basis events. meeting was held for October 8,1985 in Region III.

(e) Review the implementation of the A training assessment team inspection was 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 throttie valve. relative to team findings.

9. Item: Reliability of the PORY ACTION STATUS /COPMENTS Troubleshooting complete. Two spare PORVs (a) Monitor the licensee's trouble- have been rebuilt by Crosby and will be E shooting activities P shipped to Marshall Steam Station in Terrell, y N.C. for testing next week. '

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, 12. Item: Resolution of equipment deficiencies .

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

g shooting activities ,

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Other Activities The licensee stopped work 9/25/85 on all nuclear safety related work due to problems with control of vendor manuals. Corrective actions taken by the licensee included instruction of all maintenance personnel on procedure control of maintenance activities and use of vendor information; identifica-tion of work requiring reference to vendor information and prioritizing Station Review Board review of procedures and applicable vendor information. Most work has now resumed.

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

Installation of pipe and valves is about 75% complete. Conduit installation, cable pulling and wire termination is in progress. The old SUFP has been electrically disconnected.

Evaluations and inspections relating to the auxiliary feedwater system restraints are continuing. Baseline inspections of the No. 2 HPI and the No. 2 LPI systems are continuing. An inoperable hanger in the No. 2 HPI system did not make the HPI system inoperable. Nonconformance Reports (NCRs) have been written against 964 of the 1038 pipe supports inspected so far. Rework is required on 32 of the 375 supports that have been evaluated. There are now 16 licensee inspection teams at work on this project. A meeting between RIII and TEco was held cn site October 9, 1985 to discuss the status of the licensee's activities.

M0 VATS testing has resumed on the 166 safety-related motor-operated valves onsite. Seventy-four valves have been tested.

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)

ENCLOSURE L

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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 1 09/23/85

8. PORV 1 09/09/85 (Rev. 2)

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 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.

Planned Meetings Meeting to review AFW reliability - October 16, 1985.

Planned Special Insrections and Evaluations Annual INPO Evaluation September'30 - October 11, 1985.

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

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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING OCTOBER 11, 1985 A. STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 3:30 P.M., THURSDAY, OCTOBER 3,1985, C0ffilSSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks and H. E. Plaine dated 10/11/85 I. SECY-85-298 - Delegation of Additional Rulemaking Authority to the Executive Director for Operations The Commission, by a 3-2 vote (with Chairman Palladino and Commissioners Robert and Zech agreeing), approved a final rule which delegates additional rulemaking authority to the Executive Director for Operations. The delegation provides the EDO authority to issue (1) minor rules under Parts 0, 2, and 110; and (2) minor amendments of a non-policy or corrective nature to Commission regulations including those in Parts 0, 2, 7, 8, 9 Subpart C, and 110.

The approval is subject to a condition that the EDO obtain the concurrence of OELD, OGC, and both adjudicatory Panels before promulgating an addition to, or an amendment of the rules of practice. In the absence of this concurrence the EDO must submit the proposed addition or anendment to the Commission for "its consideration. (See attached manual chapter revisions to implement this concurrence requirement.)

Commissioners Asselstine and Bernthal disapproved the rule change. (Commissioner Bernthal would have delegated the responsibility to the Chairman.)

You should forward the Federal Register Notice for signature and publication.

(OGC) (SECY Suspense: 10/21/85)

The revised manual chapter should be incorporated into the NRC

. Manual.

(EDO) (SECY Suspense: 10/21/85) l ENCLOSURE O OCT 111985

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C 5$ NRR MEETING NOTICES *

'" OCTOBER 11, 1985 DOCKET APPLICANT /

NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT DATE/ TIME 10/16/85* 50-244 P-422 To present status report on Combustion Engrg. M. Fairtile 9:00 aa 50-305 Bethesda Upper Plenum Injection Rochester Gas & Elec.

Evaluation Model development. Wisconsin Public. Serv.

P-110 To discuss ; proposed resolu- BWR Owners Group F. Cherny 10/17/85 GE, T/R Representatives 9:00 am Bethesda tion of sticking pilot disk problem with T/R 2-state safety / relief valves 50-219 Dept. of Env. To discuss Dyster Creek GPU Nuclear J. Donohew 10/24/85 State of New Jersey 9:30 am Protection Appendix B Environmental Tech 380 Scotch Rd. Specs and to review status of Trenton, NJ licensing actions for Oyster Cr.eek 50-321 416A (Old To discuss status of Hatch 1 & Georgia Power Co. G. Rivenbark 10/24/85 10:00 am 50-366 Phillips) 2 licensing activities

'Bethesda 10/24/85 50-302 AR-5033 To discuss NRC concerris with Florida Power Corp. H. Silver 9:00 am Bethesda DCRDR Summary Report - Crystal River 3

• NOTE: This meeting will be closed due to the proprietary nature of the information that will be discussed

• Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms k

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t NMSS MEETING NOTICES I

g -

Divisitn of Fuel Cycle and Material Safety

[0R WEEK ENDlHG: 10/11/85

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[ DOCKET ATTENDEES /

NUMBER LOCATION. PURPOSE APPLICANT NRC CONIACT_

"'DATE/ TIME g

Dr. J. Hofmann, et Ayer 10/15/85 Frankfurt, Battelle Frankfurt Fire and FRG Explosion Modeling Status, al. (Batelle)

J. Ayer (FC) 10/17-18/85 Karlsruhe, Radioactive Contamination Dr. H. Schmidt, et Ayer FRG Behavior in Fires - E.K. al. (Euratom Experimental Results. J. Ayer (FC) 10/18/85 Karlsruhe, Reactor Containment Aerosol Dr. W. Schock Ayer -

FRG Experiments in West Germany. (Kernforschungszentrum)

J. Ayer (FC) 10/18/85 Bethesda, MD Present talk on "NRC Licensing" P. Vacca (FC) Vacca 9:00-11:00 an at the Naval Hospital. (Medical Officers Course in Nuclear Medicine & Radioisotope Techniques) 10/19/85- Vienna, Serve as U.S. expert or observer J. Cook (FC) Cook 11/1/85 Austria on a Technical Committee on the Assessment of the Radiological Impact from the Transport of Radioactive Materials (IAEA).

10/21/85 Bologna, LA Experiments with Radioactive Dr. V. Prodi Ayer Italy Contamination in Fires. (Univ. (U. of Bologna) of Bologna and Lavora Ambiente). J. Ayer (FC)

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10/21/85 Project West Valley, Program Review Meeting with DOE W. Hannum, et al.(DOE) Clark M-32 NY and Contractors on West Valley L. C. Rouse (FC)

Demonstration Project. A. T. Clark (FC) 10/24/85 Aberdeen Present talk on "f'RC Licensing P. Vacca (FC) Vacca m Proving Update." (U.S. Amy Environmental g Ground, MD Hygiene Agency, Nuclear Medicine g Science Officer Conference) m -

N>tSS MEETING NOTICES

. PAGE 2 - FOR WEEK ENDING: 10/11/85 w

8 Divisirn of Fuel Cycle and Matcrial. Safety .

![ DOCKET ATTENDEES /

,m DATE/ TIME NUPEER LOCATION . PURPOSE APPLICANT NRC CONTACT 0?

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

England Connission on Radiological Pro- Members of ICRP tection Committee 4 re Practical Connittee 4 Application of Broad ICRP Recom-mendations to Operations.

10/28/85 Project West. Valley, To meet with DOE, NY State and N. Davison (FC) Davison M-32 NY. NRC contractors to discuss West T. Nichcison, RES

• Valley hydrology and accomplished Represt.ntatives of l

field studies. West Valley DOE l

Project Office 10/29/85 Knoxville, Attend DOE Radioactive arid C. E. MacDonald (FC) MacDonald ,

TN Haiardous Material Package Representatives from Workshop. DOE and DOT 11/3-9/85 Paris , Participate in high-level work- R. E. Cunningham, (FC) Cunningham France shop on Nuclear Energy Pros pcts J. G. Davis (WtSS) to the Year 2000 and 8eyond jointly sponsored by NEA and IEA.

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a DIVISION OF WASTE MANAGEMENT U , PLANNED MEETINGS V

g DATE LOCATION PURPOSE ,

ATTENDEES CONTACT 10/22/85 Columbus, Ohio To attend and' speak at 3rd. MJBell MJBell Annual Midwest Workshop on LLW Radioactive Waste Mget and also to meet with NRC site rep in Columbus 10/28-31/85 Orlando, Florida To attend and present speech PJustus PJustus at Engineering Geology Session at the GSA Annual Meeting 10/31-11/1 Albuquerque, NM Nat'l Conference of State 0Mattson DMattson.

Legislatures (NCSL)

DIVISION OF SAFEGUARDS None 9

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