ML20132C169

Weekly Info Rept for Wk Ending 850920

ML20132C169
Person / Time
Issue date:	09/24/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850920, NUDOCS 8509260469
Download: ML20132C169 (43)

Text

. PDR September 24, 1985 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 20, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report. .

Enclosure Contents A

Administration B

Nuclear Reactor Regulation Nuclear Material Safety and Safeguards C D

Inspection and Enforcement E

Nuclear Regulatory Research Executive Legal Director F*

International Programs G H-State Programs Resource Management I Analysis and Evaluation of Operational Data J Small & Disadvantaged Business Utilization & Cf.vil Rights K*

L Regional Offices CRGR Monthly Report M*

Executive Director for Operations N*

I Items Addressed by the Commission 0 P

Meeting Notices Proprietary or Other Sensitive Information (Not for Q external distribution)

• No input this week.

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[.T. A. Rehm, Assistant for Operations 8509260469 850924 PDR COMMS NRCC Office of the Executive Director WEEKLYINFOREPT PDR for Operations l

Contact:

T. A. Rehm, ED0

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HIGHLIGHTS OF WEEKLY INFORMATION REPORT

- WEEK ENDING SEPTEMBER 20,.1985 St. Lucie Plant, Unit 2 At 7:20 pm on September 10, 1985 St. Lucie Plant, Unit 2 was manually tripped as a precautionary measure due to high vibration on RCP 2A2.

This is the same RCP that experienced vibration and an oil fire on August 24, 1985. The Unit had experienced a seal failure in the motor prior to the fire. This was repaired and the Unit had returned to power and operated for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before this manual trip.

Examination of the motor has revealed that the same seal was again damaged. The licensee and its consultants and vendor have established a special task team to determine the root cause of this problem. The current outage is expected to last 6 to 10 days.

Section 107 Report to Congress The Office of Resource Management, OPE and numerous offices are developing a programmatic, objectives-oriented structure for meeting a reporting requirement outlined in Section 107 of the Senate's version of NRC's authorization Legislation for FY 1986/1987 (S.895). This structure will also be used in the Five Year Plan. The report is scheduled to go to Congress shortly after the first of next year. .

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Annual All Agreement State Meeting During the period October 8-10, 1985, the Office of State Programs will host the 1985 All Agreement State Meeting. The Directors of the 27 Agreement State radiation control programs will meet at the Holiday Inn of Bethesda. Panel discussions which will include NRC staff will cover the following topics: Low-Level Waste, Materials Licensing and Compliance, Regulations, Radioactivity in Unauthorized Places and Radiation Litigation. ,

Delinquent Occupational Dose Reports The Code of Federal Regulations, specifically 10 CFR 20.407, requires certain types of NRC licensees to submit an annual statistical sumary of the personnel monitoring information recorded by the licensee for monitored l

individuals. The report provides _ the total number of individuals that the licensee monitored for exposure to radiation and indicates the distribution of the doses received by the individuals. About 500 hRC licensees ~were required to submit such a report for calendar year 1984 by March 31, 1965. As of this date, there are 63 licensees that are delinquent in the submission ~of this report. A reminder letter is being sent to these licensees advising them that the report is overdue and that unless submitted within 30 days, the matter will be referred to their Regional NRC Administrator for appropriate

! enforcement action.

l SEP 2 01985

OFFICE OF ADMINISTRATION Week Ending September 20, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION'ACT-STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers ,1984 179 23 Received, 1985 641 39 Granted 516 26 Denied 140 14 Pending 164 22 ACTIONS THIS WEEK Received Eli J. Lake, Requests records relating to nuclear disasters or (85-627) nuclear accidents and information concerning the actual or potential use or manufacturing of nuclear materials, nuclear weapons, or nuclear related research in the U.S.

Michael Deane, Requests copies of SECY-85-208; procedures used by 01 NUS Corporation regarding the rights of utility employees; and minutes (85-628) from past Regulatory Requirements Review Committee meetings, t

Nina Bell, Requests three categories of records related to notices Nuclear Information and hearings for source materials licenses.

and Resource Service (85-629)

Nina Bell, Requests copies of records related to the Sequoyah Nuclear Information facility in Gore, Oklahoma, to convert depla+ ' anium and Resource hexafluoride to depleted uranium tetrafluoride.

Service

. (85-630) ,

Nina Bell, Requests all records regarding the environmental Nuclear Information assessment relating to the license amendment for the and Resource Sequoyah facility in Gore, Oklahoma, to convert depleted Service uranium hexafluoride to depleted uranium tetrafluoride.

(85-631) .

Nina Bell, Requests all records related to correspondence between Nuclear Information NRC and Kerr-McGee regarding the Sequoyah facility prior.

and Resource to the September 23, 1969, license application and the Service license renewal application submitted in September 1982 (85-632) and revised in October 1983.

ENCLOSURE A CONTACT: J. M. Felton 492-7211

, SEP 2 01985

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2 Received, Cont'd Diana R. Jackson, Requests a copy of the proposal submitted under RFP SAI RS-NRR-85-052.

-(85-633)

Jean Whitney, Requests a set of gummed mailing labels for IE The Keenan Information Notices issued by the Division of Corporation Emergency Preparedness and Engineering Response.

(85-634)

Pamela Jarvis, Requests gummed mailing labels for five categories Colorado State of records.

Universit (85-635 Steven Aftergood, Requests copies of SECY-85-152, the application for Committee to award of attorney fees, and the order approved by the Bridge the Gap Commission disposing of the application.

(85-636)

John D. Crandall, Requests five copies of the 10 and E0 mile radius maps State of Iowa for~the Duane Arnold nuclear power p! ant.

(85-637)

Henry Barru Requests records identifying locations of reactors, (85-638) radioactive materials storage facilities, processing facilities, and radioactive waste disposal facilities.

Rod Buckles, Requests'that the NRC provide to NUS remote NUS Corporation accessibility to its computerized document control (85-639) system.

Patty Day, Requests all records pertaining to the historical NUS Corporation background of 10 CFR 50.59.

(85-640)

Michael O'Mealia, Requests records containing pass / fail statistics for Doc-Search licensing and requalification examinations given to Associates R0 and SR0 candidates since the issuance ~ of SECY-84-81C, (85-641) dated December 13, 1984.

Granted Alanson Bowen, In response to a request for copies of all-background E.I. Du Pont de materials on the proposed sale of a reactor by Union Nemours & Company Carbide to Hoffman-LaRoche and the hearing date, made (85-266) available three records. Informed the requester that two additional records are already available at the PDR.

ENCLOSURE A i SEP 2 01985 l

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3 Granted, Cont'd John I. Riesland In response to a request for a nonproprietary listing (85-521) of shipping dates of fresh fuel shipments to nuclear power facilities, made available a computer printout.

Eric R. Smith, In response to a request for the meeting minutes, NUS Corporation notes, transcript, and handouts from a July 23-24, (85-553) 1985, CRGR meeting regarding IST/ISI Pump and Valve Programs, informed the requester that there was no meeting of the CRGR on July 23, 1985, that no transcript was made at the July 24 meeting, and that no handouts were distributed at tha July 24 meeting, with the exception of six records available at the POR.

Stephen H. Hanauer, In response to a request for copies of Power Plant Technical. Analysis Examination Results Summary Sheets for examinations Corporation given before the issuance of the operating license for (85-582) 10 listed power plants, made available summary sheets for five of the plants. Informed the requester that the l

sumary sheets for the remaining five plants were destroyed prior to receipt of his request.

Mary Louise Wagner, In response to a request for a copy of SECY-85-237, made '

McGraw-Hill available a copy of the requested paper.

Publications Co.

(85-604)

Andrea L. Kronzek, In response to a request for a copy of the application for FOI Services, Inc. license amendment filed by New England Nuclear (85-606) Corporation regarding extension of the pre-calibration time on technitium' 99m generators, made available two records.

l Andrew Fischman, In response to a request for all records related to an Charles E. Simon application submitted by Mars, Inc., or Kalkan for use of and Company an irradiation process for the sterilization of pet food (85-609) at a new Kalkan pet food processing facility, informed the requester that the NRC has no records subject to this request.

Teresa S. Barnhart, In response to a request for a list of awards that were NTEU Steward presented to employees in the Office of Administration (85-622) from January 1, 1984, through September 1, 1985, made available the requested list.

Lyle Graber, In response to a request for the August 1985 memorandum NUS Corporation with enclosures from Victor Stello to William Dircks (85-622) regarding the Meeting Minutes from CRGR Meeting Number 79, informed the requester that records subject to this request are already available at the PDR.

ENCLOSURE A SEP 2 01985

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4 Denied Brian B. Smith, In response to a request for three categories of Stark and Gordon records related to an NRC inspection of clinics run (85-140) by Dr. Ramasami Gunabalan in the Detroit, Michigan, area, made available two records. Denied three records in their entirety, release of which could allow those being investigated to learn the scope, direction, and focus of investigatory efforts, and thus could possibly allow them to take action to shield potential wrongdoing or a violation of NRC requirements from investigators. Denied one record in its entirety and portions of one record because they were compiled as part of an ongoing enforcement proceeding and disclosure would constitute a clearly ~ unwarranted invasion of personal privacy.

Billie P. Garde. In response to a request for records related to the Government March 22,1985, letter from Mr. C. E. Norelius, Region Accountability III, and Mr. James W. Cook, Consumers Power Company, Project regarding the January 10, 1985, Brookhaven National (85-342) Laboratory Report concerning the allegation, of Mr. E.

Earl Kent, informed the requester that records subject to this request are already available at the PDR. Cenied two records in their entirety, disclosure of which would interfere with an enforcement proceeding.

Susan Grossberg, In response to a request for 11 categories of records Harmon, Weiss relating to Inspection Report No. 50-443/84-12 and

& Jordan 50-444/84-06 for the Seabrook nuclear power plant, made (85-560) available 12 records. Informed the requester that one additional record subject _to this request is already available at the PDR. Denied one record in its entirety, disclosure of which would constitute.a clearly unwarranted invasion of personal privacy.

Charles Barnes In response to a request for records maintained in Docket (85-569) 40, SUA-809, and Docket 40, SUA-797, made available 67 '

records. Denied portions of four records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy. Suggested that he also contact the States of Colorado and Oregon.

SEP 2 01985 ENCLOSUREp

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WEEKLY INFORMATION REPORT

-DIVISION OF CONTRACTS WEEK ENDING SEPTEMBER 20, 1985 l

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CONTRACT AWARDED RFP No.: RS-NRR-85-054

Title:

" Development of an NRC Simulation Facility Evaluation Program"

Description:

The contract objectives are to develop, refine and validate criteria and methodology for the review of nuclear power '

1 plant simulation facilities; recommend size and make-up of a review team; and develop a schedule for conduct of review. Work will include a review of applicable literature; ,

development of a methodology; testing this methodology through 4 conduct of actual simulation facility reviews and preparation of detailed recommendations.

Period of Performance: Basic -_14 months with an option for an additional 6 months.

Sponsor: ' Office of Nuclear Reactor Regulation Status: Cost-Plus-Fixed-Fee contract awarded to Micro Analysis & Design

.in the amount of $345,214 effective September 16, 198 5.~

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r-0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending September 20, 1985 Byron 1 On September- 10, 1985 Byron 1 completed $ts initial. test program. We' anticipate that the licensee will send in a letter stating that Byron l' achieved commercial operation on September 10. The plant is being lir.tited to 92% power to prevent moisture carryover to the turbine. The licensee is planning a shutdown in' November.1995 to modify the moisture separators in

.the steam generators so that the plant can be run at 100% power. During this outage, the licensee also intends to make the equipment replacements necessary to satisfy the license condition dealing with equipment qualification. The licensee condition requires that all electrical .

equipment within the scope of 10 CFR 50.49 be environmentally qualified by November 30, 1985. -

Cherokee Units 1, 2, and 3 On September 12, 1985, the NRC, at the request of the permit holder, Duke Power Company, revoked the Construction Permits for Cherokee 1, 2, and 3.

l The plants had been cancelled by Duke in 1982 and 1983. .

Clinton Power Station, Unit 2

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On September 11, 1985 an Order revoking the Construction Permit for Clinton Power Station, Unit 2 was sent to the Illinois Power Company.

The authorization for this Order was issled by the Atomic Safety and Licensing Board on July 11, 1985 per the May 17, 1985 reque'st of the Illinois Power Company. js St. Lucie Plant, Unit 2

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At 7:20 pm on September 10, 1985 St. lxcie Plant, Unit 2 was manually tripped as a precautionary measure due to high vibration on RCP 2A2.

This is the same RCP that experienced vibration and an oil fire on August 24, 1985. The Unit had experienced a seal failure in the motor prior to the fire. This was repaired and the Unit had returned to power i and operated for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before this manual trip.

Examination'of the motor has revealed that the same seal was again '

l damaged. The licensee and its consultants and vendor have established l a special task team to determine the. root cause of this problem. The l

current outage is expected to last 6 to 10 days.

ENCLOSURE B SEP 2 01985

San Onofre Nuclear Generating Station, Unit 1 On September 13, 1985 the NRC staff met with the licensee and discussed the possible need for inspection of additional diesel engine crankshaft journals. The licensee presented new information which showed a much slower growth rate of postulated cracks in crankshaft journal #12.

Based upon the licensee's presentation, the staff concluded that immediate inspection.of journal #12 was not required. The licensee will fully inspect each engine during the refueling outage scheduled for November 30, 1985.

San Onofre Nuclear Generating Station, Unit 2 At 1:25 pm EST, on September 12, 1985, San Onofre Unit 2 tripped from 100% power due to a turbine trip. The turbine trip was caused by a disintegrated generator exciter slip ring which caused an electrical fire in the generator exciter enclosure. An unusual event was declared,

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and the site fire brigade and the San 2

Clemente Fire Department responded.

The fire was extinguished by a CO system inside the exciter enclosure, and reactor shutdown proceeded as expected. The unusual event was terminated within an hour of its declaration. There does not appear to be a safety concern, but the plant will probably be down for some time for repairs. Unit 3 is scheduled to shutdown for its first refueling outage on September 20, 1985.

Grand Gulf, Unit 1 The Mississippi Public Service Commission has granted Mississippi Power

& Light Company rate increases totaling 49% over an 8 year interval.

The initial increase in the first year is expected to total $68,000,000.

River Bend On September 13, 1985, the ACRS met to discuss issues relevant to its report (full power) on the application by Gulf States Utilities for the River Bend Station. At the close of the meeting, the ACRS states that it would be issuing a favorable full power letter but it would include a request for an update in one year on.the issue of emergency procedures for containment venting and a request to review the results of the research by the hydrogen control owners group on degraded core accidents for BWR reactors.

The Commission is currently scheduled to meet on October 9, 1985, to consider the full power license for River Bend.

ENCLOSURE B SEF 2 01985

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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING SEPTEMBER 20, 1985

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1. PLANT STATUS'

- The facility remains in long term cold shu' down t with th'e Reactor CoolantSystem(RCS)ventedtothereactorbuildingatmosphereand the reactor vessel head and plenum assembly removed from the reactor vessel.

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

- The modified internals indexing fixture is installed on the reactor vessel flange and is ' flooded to elevation 327 feet 6 inches (151 1 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.'

- RC5' cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range' from 71*F to 89*F with an average of 79'F. Average cold leg temperature is; 53*F.

- The average reactor building temperature is 56*F. The reactor building airborne activity is 3.5 E-7 uti/cc Tritium and 8.9 E-10 uti/cc particulate, predominantly Cesium 137.

2. WASTE MANAGEMENT

- TheSubmergedDemineralizerSystem(SDS)wasshutdownduringthis period.

- EPICOR II ccamenced processing batch 266 from Condensate Tank.1A (C0T-1A). To date 49,955 gallons from this batch have been processed.

- Total volume processed through SDS to cate is 2,953,375 gallons, and tne total volune r.rocessed through EFICG*.11 is 2,65E,937 pillent.

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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 i 347' level of the reactor building and is 67 mrem per hour on the l 305' level of the reactor building.

4. NEW RIVER WATER SAMPLING POINT

- Since July 19, 1985, the EPA has sampled the Susquehanna River

~ water prior to the water entering TMI. A one gallon sample is taken over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by a' metering pump at the inlet to the Unit I water pre-treatment system. This one gallon sample is collected daily and analyzed. A portion _ is composited with like quantities from the other six days of the week. The sample will be used to verify the source of activity in the TMI site outfall water samples. In the .;

i past some radionuclides in the river water taken into the plant have 4 caused concern until the source was determined not to be TMI but due to an upstream medical administration.

5. ENVIRONMENTAL MONITORING

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

- TMI water samples taken by EPA at the. plant intake from the river consisted of seven daily composite samples taken from August 31 to

September 7, 1985. -The gamma scan for the seven day composite was negative. Daily composites for two samples taken between September r 2 and 3 and September 5 and 6,1985 detected a trace of Iodine-131.

I - TMI water samples taken by EPA-at the plant discharge .to the river consisted of seven daily composite samples taken from August 31 to September. 7,1985. Two 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> composite samples, one taken between September 2 and 3, 1985 and the other taken between September 5 and 6,1985 each detected a trace of Iodine-131. Essentially the same

. . concentration of Iodine-131 was detected by the upstream sampler.

This indicates that the Iodine-131 was taken into the plant from the- .

river and the plant was not the source. No reactor ~related activity was detected. The detected concentration of Iodine-131.was less than 1% of the NRC allowable limit for release to unrestricted areas.

! - The Lancaster water sample taken at the water works intake and

• analyzed by EPA consisted of a se,ven day composite sample taken from

September 1 to September 7,1985. _ A gama scan detected no reactor. t related radicactivity. -

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ENCLOSURE B l

SEP 2 01985

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- The NRC outdoor airborne particulate sampler at the TMI Site l collected a sample between September 4 and September 11, 1985. No i reactor related radioactivity.was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower i limits of detectability.

6. REACTOR BUILDING ACTIVITIES  !

DefuelingWaterCleanupSystem(DWCS)preoperationaltestingand l

. modification continued. '

- Installation of cable tray shielding continued.

Preoperational testing of the reactor building sump recirculation

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system components is in progress. The system is expected to be operable' this. w'eek.

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

7. 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 have been delivered to the TMI site and inspected. Critical welds and those welds which would hav'e engaged the dunnage during shipping were examined on the fourth canister storage rack to be. delivered onsite. Penetrant testing (PT) was used for examination of the welds and revealed eight welds with identifiable defects. However, some of these defects would have been discernible'through visual examination. GPU performed a visual. examination of all welds on the fourth rack 4

delivered. This examination revealed about 50 linear. indications. '

Subsequent PT of about 10% of these linear indications did not i

reveal any PT indications of cracking or any other deleterious effects in the welds.- The eight positive indications were grou'nd in such a manner as'to fully expose the defect.  ;

. The first rack delivered onsite was layed on its side and internal i welding was visually examined by an inspector crawling inside the affected modular cells. Two visual indications were noted but subsequent PT examination revealed that the indications were not i

significant.

The third rack which has not shown any indications of questionable l welds is being prepared for installation in the "A" spent fuel pool.

The installation is tentatively scheduled for the week of September 23, 1985. -

! . Further examinations and evaluations are - being performed. A completion date to affect repairs has net been determined. -

l ENCLOSURE B l SEP 2 01985

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8. RSC EVALUATIONS IN PROGRESS

- Technical Specification Change Requests numbers 48, 49, 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 Evhluation.

- Heavy Load Handling Safety Evaluation Report.

9. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for October 1985 in Harrisburg, Pennsylvania. Exact date and location for this meeting will

, be announced at a later date.

Persons desiring the opportunity to speak before the Panel are asked to l

contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.

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l 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending September 20, 1985 Near-Term NRC Actions Under the NWPA Section: 121(a): EPA Final High-Level Waste Standards Action: EPA signed its final high-level waste standards on August 15, 1985.

Status: EPA final high-level waste standards will be published in the Federal Register on Thursday, September 19, 1985 (FR 2870-3), and will become effective 60 days later. Staff will review the NRC's high-level waste criteria for conformance with EPA standards and will provide a proposed rule to the Commission by December 1985.

Section: 134 of NWPA: Hybrid Hearings '

Action: The Commission 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: Staff is currently awaiting the staff requirements memo to prepare the final rule for publication in the Federal Register.

Section: 301 of NWPA: DOE Mission Plan Action: NRC testified before Senate and House committees concerning the Mission Plan on Thursday and Friday, September 12 and 13, 1985.

Status: NRC has been requested 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.

NFS-Erwin Strike by OCAW members continues. NFS is conducting limited operations of'the HEU production, scrap recovery and R&D facilities.~ Ne problems with j operations have arisen to date.

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.2-NRDC Hearing On September 18, 1985 staff provided ELD with a draft memorandum to the Commission requesting that the NRDC Hearing concerning NFS-Erwin be terminated,.since the licensee had met all of the requirements as stipulated in the 1983 Joint Agreement. A set of all the applicable backup documents was also provided to ELD. Mr. Fonner now has the lead for this final action in the NRDC Hearing.

Criticality Safety in Storage of Fissile Material, Jackson, W'yoming The ANS Nuclear Criticality Safety Division sponsored a topical meeting on Nuclear Criticality Safety during the period of September 9-12, 1985. Papers were presented by authors from the US, Japan, England, and France on the subject of experiments, data applications, and calculations. NMSS attendees were George Bidinger, Chairman of the opening session, and Norman Ketzlach.

Foreign Visitors On September 17, 1985, representatives of FC and RES met with Messrs.

Chalabreysee and Camarasa of the Service D' hygiene Industrielle, Commissariat a l'Energie Atomique, France, to discuss current research and regulatory experience with uranium. This visit was part of a series of meetings to be held by the French representatives with NRC, NRC licensees, DOE, and several national laboratories.

Kerr-McGee A prehearing conference was held September 11, 1985, in Bethesda, Maryland, on the Kerr-McGee West Chicago Rare Earths Facility Proceeding and on the Kress Creek Decontamination Proceeding. In the Kress Creek Proceeding, the staff filed a motion to hold the proceeding in abeyance pending a determination by the United States Environmental Protection Agency to take such actions as it l deems appropriate under the Comprehensive Environmental Response, Compensation l

and Liability Act of 1980 (" CERCLA" or "Superfund").

ENCLOSURE C SEP 2 01985

0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending September 20, 1985

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

a. EN 85-62, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $500 was issued September 16, 1985 to Kay-Ray, Inc. (Arlington Heights, IL). This action is based on an extremity exposure of 19.61 rems to one licensee employee in excess of the 18.75 rems'reraiatory limit.

b. EN 85-63, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $3,750 was issued September 16, 1985 to Metro Helth Center (Erie, PA). This action is based on multiple violations that represent a breakdown in management oversight and

. control of the radiation safety program.

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

a. PNO-III-85-82, Northern States Power Company (Prairie Island), Bomb Threat.

b. PNO-III-85-83, Detroit Edison Company (Femi Unit 2), Cracks in Non Safety-Related Steam Bypass Line.

c. PN0-IV-85-47, Arkansas Power and Light Company (Arkansas Nuclear One Unit 2), Outage Greater Than Two Days.

d. PNO-IV-85-48, Arkansas Power and Light Company (Arkansas Nuclear One Unit 2),OutageGreaterThanTwoDays.

e. PNO-V-85-57A, Southern California Edison, Inc. (San Onofre Unit 2),

Unit 2 Shutdown on September 12, 1985, Due to a Fire in the Turbine Generator Enclosure, Update as of September 13, 1985.

f. PNO-V-85-58, Arizona Nuclear Power Project (Palo Verde Unit 1),

Unusual Event Associated with a Planned Load Rejection Test at Unit 1.

g. PN0-V-85-59, Arkansas Nuclear Power Project (Palo Verde Unit 1),

Reactor Trip With Subsequent Safety Injection (PNO-V-85-58 Update).

h. PNO-V-85-60, Pacific Gas and Electric; Southern Californfa Edison (San Onofre; Diablo Canyon), Pacific Coast Tsunami Watch.

i. PNO-V-85-61, Providence Hospital (Anchorage, AL), Teletherapy Source Retraction Problem.

j. PNS-V-85-04, Sacramento Municipal Utility District (Rancho Seco),

Unusual Event. ENCLOSURE D SEP 2 01985

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

a. IE Information Notice 85-76. Recent Water Haniner Events, was issued September 19, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

4. Other Items

a. Incident Response (1) The Chief, Incident Response Branch, Division of Emergency Preparedness and Engineering Response attended the Federal Radiological Preparedness Coordinating Coninittee (FRPCC) meeting on September 17, 1985 in Bethesda, MD.

(2) The Chief, Incident Response Bra'nch and staff member attended the FRPCC Subconunittee Response meeting on September 19, 1985 in Bethesda, MD. .

(3) On September 20, 1985, the Chief, Incident Response Branch and staff member attended a Relocation Tabletop Exercise management meeting in Philadelphia, PA.

(4) Members of the Incident Response Branch attended a contractor review meeting with INEL in Idaho Falls, Idaho on September 19-20, 1985.

(5) .The Incident Response Branch sponsored two 1-day seminars.in Bethesda, MD conducted by Combustion Engineering for the Reactor Safety and Protective Measures Teams. These. seminars discussed Degraded Core Scenarios, Emergency Operating Procedures and Assessing Core Damage Using the Post Accident Sampling Systems and Other Indicators.

l b. Operations Center The Chief, Incident Response Branch, Division of Emergency Prepared-ness and Engineering Response conducted a tour of the NRC Operations Center on September 19 1985 for visitors from Finland. This tour discussed the agency's incident response program.

c. Construction Appraisal Team (CAT) Inspection The exit meeting for the CAT inspection for the Bryon Unit 2 plant l with the licensee, Commonwealth Edison, was conducted September 20, l 1985.

l l ENCLOSURE D SEP 2 01985 l

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d. Emergency Preparedness Representatives from the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response, and ELD are observing the emergency preparedness exercise at Waterford this week.

e. Vendor Inspection Program The following inspections were conducted by the Vendor Branch, Division of Quality Assurance, Vendor, and Technical Training Pro-grams this week:

(1) Nuclear Energy Services, Danbury, CT - to review steam generator nozzle dams to be used during the Ft. Calhoun outage.

(2) Westinghouse Nuclear Technology Division, Pittsburgh, PA - to

,' observe the HELB test on a 600 HP Emergency injection Charging 4 Pump Motor.

(3) Wyle' Laboratory, Huntsville, AL - to observe test of Davis-Besse safety relief valves manufactured by Dresser Industries.

(4) J. T. Ryerson & Son, Inc., Chicago, IL - 10 CFR Part 21 report by Calvert Cliffs. The plant purchased 17-4 PH stainless steel bar and was supplied 316 stainless steel instead.

(5) Gessellschaft fur Nuclear-Service MbH, Essen, West Germany - to review the implementation of GNS's QA program pertaining to the fabrication of VEPC0's CAST 0 Dry Spent Fuel Storage / Transport Casks.

f. PRA For Inspection Applications The first course in PRA for Inspection Applications was given last week-in Chattanooga. The course was developed by IE in cooperation with RES and MDTS. Representatives from all regions and from IE Headquarters with direct inspection functions attended the course.

The course emphasizes practical ways to use available PRA information to focus on the most significant safety issues in planning inspec-tions. The next course is planned for January 1986.

g. Requalification Test Program of IS-UT Personnel Representative of the Engineering and Generic Comunications Branch, Division of Emergency Preparedness and Engineering Repsonse, was at the EPRI-NDE Center, Charlotte, NC this week to review the ongoing requalification testing and earlier results of the requalification test program of ISI-UT personnel.

ENCLOSURE D SEP 2 01985

h. Davis-Besse The Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response, at the request of Region III, arranged for and participated in a joint meeting on the pipe supports at the Davis-Besse power plant in Bethesda on September 18, 1985. The participants were representatives of IE, Region III, and NRR.

1. Outage Design And Outage vendor Inspection ~

IE personnel and consultants began the Fort Calhoun Outage Design Inspection and Outage Vendor Inspection September 16, 1985. Both inspections are part of the Trial Outage Inspection Program which will be' conducted at the Fort Calhoun and Dresden Units.

j. Quality Assurance (1) Representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, visited the Millstone 3 site on September 18 and 19, 1985 to inspect Engineering Assurance Program activities.

(2) Representatives of the Quality Assurance Branch met with Houston Power and Lighting Company on September 17, 1985 in Bethesda, MD to discuss South Texas Engineering Assurance Program activities.

(3) A representative of the Quality Assurance Branch attended the ASME Code Section III meetings, Working Group on Quality Assurance and Stamping and Subgroup General Requirements, September 17-18, 1985.

k. Problems With Maintenance Program for Anker-Holth Snubbers Energy Products notified NRC Headquarters by letter on August 29, 1985 of a problem with the maintenance program for Anker-Holth snubbers. The problem concerns the Technical Maintenance Instruc-tions provided by Anker-Holth at the time of snubber delivery. These have been determined to be inconsistent with current industry stand-ards for maintenance procedures for snubber seals and fluids. The possibility exists that seal and fluid degradation may occur in these snubbers over extended periods of time. Owners of these snubbers have been notified that these potential problems exist and that the Technical Instruction Manuals for these will be revised in the near future.

ENCLOSURE D l

SEP 2 01985 l

1. High-level Waste Solidification Representative of Safeguards Materials Program Branch, Division of Inspection Programs was in West Valley, NY this week to observe DOE-High Level Waste Solidification Process as a background for developing IE' monitoring procedures.

m. ANSI Meetir.g Representatives of Safeguards Materials Program Branch, Division of Inspection Programs attended the ANSI N-14 Committee Meeting on

~ Packaging and Transportation Issues at the Hyatt Regency at Capitol Hill this week.

ENCLOSURE D l SEP 2 01985

e-OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending September 20, 1985 International Code Assessment and Applications Program (ICAP)

The NRC hosted an information meeting April 23-26, 1985 for a proposed coordinated international effort on the assessment of the thermal-hydraulic transient codes TRAC PF1/M001, RELAP5/M002 and TRAC-BD1/ MOD 1.

RES extended alinvitation on July 22, 1985 to participate in this' collaborative endeavor to Austria, Belgium, Finland, France, Federal Republic of Germany, Italy, Korea, Netherlands, Spain, Sweden, Switzerland, Taiwan, the United Kingdom and the Commission of the European Communities. The basis of the program is a series of bilateral exchange agreements between NRC and the different countries covering the approximate period 1985-1990. The first meeting of the ICAP Program Group is scheduled to be held on October 21, 1985 at the Holiday Inn in Gaithersburg to review administrative management for the program.

TRAC-PWR Program Review On September 9-10, RES staff met with TRAC-PWR code developers and code assessors at Los Alamos National Laboratory (LANL) and Sandia National Laboratory (SNL) to review the status of the program.

RES staff discussed with the code developers the mechanisms which could be used to address code problems identified through the various international and domestic programs that utilize the TRAC-PWR code. LANL will propose a mechanism which will streamline the process of " trouble shooting" user identified needs and will ensure that all such needs are documented and appropriately responded to.

ENCLOSURE E SEP 2 01985

s 1

Conference on Potential Beneficial Effects of Low-Level Irradiation Certain experiments have indicated that animals irradiated withSuch low-level a

fonizing radiation survive longer than unirradiated controls.

stimulatory effect, also noted with toxic chemicals, has been termed

" hormesis," and refers to a beneficial biological effect of an agent administered at low doses or dosages which is normally toxic at higher doses or dosages.

Dr. Jerome Puskin, biophysicist with the RES Health Effects Branch, attended a conference on radiation hormesis sponsored by the Electric Power Research Institute and the Northern California Sections of the American Nuclear Society and the Health Physics Society which was held August 14-16 in Oakland, California. Data were presented at the meeting pertaining to enhancement effects on microorganisms, human cells, plants, animals and humans.

However, while fairly strong evidence was presented in support of stimulating effects on the growth of microorganisms and plants, it was Dr. Puskin's opinion that there was no convincing evidence presented for any beneficial effects of low-level radiation in higher animals and humans.

Contact:

R. E. Alexander 74370 Delincuent Occupational Dose Reports The Code of Federal Regulations, specifically 10 CFR 20.407, requires certa'in types of NRC licensees to submit an annual statistical summary of the personnel monitoring information recorded by the licensee for monitored individuals. The report provides the total number of individuals that the.

licensee monitored for exposure to radiation and indicates the distribution of the doses received by the individuals. About 500 hRC licensees were required to submit such a report for calendar year 1984 by March 31, 1985. As of this date, there are 63 licensees that are delinquent in the submission of this report. A reminder letter is being sent to these licensees advising them that the report is overdue and that unless submitted within 30 days, the matter will be referred to their Regional NRC Administrator for appropriate enforcement action.

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! ENCLOSURE E l SEP 2 01985 t

l l

Final Rule Signed by ED0 On September 4,1985, the Executive Dintetor for Operations approved a final rule which revises 10 CFR 50.55a, Codes and Standards. This final rule updates the reference that incorporates the American Society of Mechanical Engineers Boiler and Pressure Yessel Code (ASME Code) into the NRC regulations. The updated reference incorporates into the rule the Winter 1982 Addenda, Summer 1983 Addenda, Winter 1983 Addenda, Sumer 1984 Addenda and 1983 Edition of Section III, Division 1, and the Winter 1982 Addenda, Summer 1983 Addenda, and 1983 Edition of Section XI, Division 1, of the ASME Code.

I Public Coment Period Closes on Rulemaking to Modify General Design Criterion 4 Twenty-one public comments were received from utilities, industry groups, architect-engineering firms and reactor vendors addressing the proposed rule allowing exclusion from compliance with GDC-4 requirements of certain pipe ruptures in the primary loops of PWRs when supported by acceptable analyses. Each commentor endorsed the proposed rule or the intent of the rul e. Several ninor issues were raised which are being treated in the preparation of the final rule scheduled to reach the Commissioners in December,1935.

i Managers' and Technicians' Perceptions of NPP Health Physics Tech Job Compared Brookhaven National Laboratory, under contract to the NRC/RES is publishing NUREG/CR-4.364, " Management Perceptions of the Health Physics Technician Job."

This study is a follow-up to the 1984 industry-wide job analysis of nuclear power reactor health physics technicians. The 1984 job analysis identified 389 specific tasks which were important, difficult and performed frequently and thus should constitute the elements of effective training programs. The job analysis provides comprehensive guidance for the development and evaluation of health physics technician training programs and job incumbent qualifications.

The follow-up consisted of having the managers of the health physics technicians at NPP's complete the same job analysis questionnaire used in the 1984 study. Managers' perceptions frequency of performance were compaof theperceptions red to the task difficulty, importance of th'e and job incumbents.

Results indicated that there is strong agreement between the managers and technicians as to what constitutes the health physics technician job. A secondary conclusion is that the supervisor / manager responses validated the health physics technician job analysis.

l ENCLOSURE E l

U.S. and Foreign NPP Dose Experience Compared Brookhaven National Laboratory (BNL), under contract with RES/NRC, is publishing NUREG/CR-4381, " Comparative Assessment of U.S. and Foreign Nuclear Power Plant Dose Experience." This report is a BNL analysis of extensive data accumulated at the 1984 BNL International Workshop on Dose Experience and Dose Reduction (ALARA) at Nuclear Power Plants.

The BNL analysis concludes that large differences in collective dose exist between countries and also between comparable plants within countries, with the U.S. experiencing the higher doses in all categories. The report identifies and analyzes fourteen factors in addition to plant age which contribute to the dose differences: plant chemistry, water purification, special tooling, low cobalt and nickel materials, primary system decontamination, required multiplant actions, use of pennanent work force,

' passivation of primary systems, management commitment to dose control, multiplant sites, design for ALARA, quality assurance, standardization, and shielding.

In addition to providing explanations for the higher U.S. doses, the report identifies the major areas of plant design, operation and maintenance where significant dose reductions could be realized.

RES Rulemaking Activities Decommissioning Rule Arendments: Categorization and analysis of the 136 public commants thus far received is continuing. Potential consultants having expertise in tax, accounting, legal and related areas have been contacted to supply aid in preparing resolutions of some complex public comments.

10 CFR 50, Appendix J: Subject to satisfactory resolution of certain comments and concems the CRGR recommended that the EDO forward Appendix J and Regulatory Guide MS 021-5 to the Comission for its review and approval to issue a Federal Register Notice for public comnent. A Comissien package is now being prepared.

GDC-4: The proposed, limited scope, interim rule was published in the Federal Register--July 1,1905 (50 FR 27006). The comnent period ended September 2, 19d5. Twenty-one generally favorable coments have been received and the staff is working on resolution of the comments. The broad scope rule was approved by ELD and is now at NRR for concurrence.

Emergency Preparedness for Fuel Cycle and Other Radioactive fiaterial Licensees:

Rulemaking package in concurrence chain. Discussions with staff of NilSS, IE, and ELD indciate concurrence is likely from these offices. We expect to submit the rulemaking package to the EDO by September 30.

l CONTACT: Mort Fleishnan, DRA0 t

ENCLOSURE E l SEP 2 01985 i

i Publications to be Issued in the Near Future

Title:

Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Tyoe)

(Draft Regulatory Guide - Proposed Rev. 2 to R.G. 3.44)

Contact:

W. R. Pearson 443-7663

Title:

Standard Format for the Safety Analysis Report for an Independent .

Spent Fuel Storage Installation (Dry Storage) (Draft Regulatory Guide - Proposed Rev.1 to R.G.~ 3.48)

Contact:

W. R. Pearson 443-7663 -

Title:

Guidance on Preparing a License Application to Store Spent Fuel and High-Level Radioactive Waste (Draft Regulatory Guide - Proposed Rev. I to R.G. 3.50)

Descrip tion: This guide suggests a format acceptable to the NRC staff for submitting information specified in Part 72 for a license application to store spent fuel or high-level radioactive waste.

Contact:

W. R. Pearson 443-7663

Title:

Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication Plants and Uraniun Hexafluoride Production Plants (R. G. 4.16. Rev.1)

Description:

Provides guidance on effluent monitoring programs and associated data reporting for uranium fuel fabrication plants and uranium hexafluoride p roduction.

Contact:

W. R. Pearson 443-7663 ENCLOSURE E SEP 2 01985

c

Title:

Format and Content of Decommissionig Plans for 10 CFR 30, 40 and

'70 Licensees (Draft Regulatory Guide)

Description:

Guidance identifying and presenting a format for submitting <

information needed by the NRC staff for reviewing decommissioning plans submitted by 10 CFR Parts 30, 40, and 70 licensees.

Contact:

C. R. Mattsen

' 443-7910 4

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. ENCLOSURE E

SEP 2 01985 l

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING SEPTEMBER 20, 1985 International, Meetings The following international meeting notices supplement those previously announced:

October 14-18, 1985, Vienna, Austria - IAEA Working Group to Finalize a Manual on the Maintenance of Systems and Components Important to Safety as a Supplement Document to the Safety Guide 50-SG-07 October 28-31, 1985, Vienna, Austria - IAEA Meeting of Scientific Program Comittee to Prepare for June 1986 International Symposium on Packaging and Transport of Radioactive Materials November 11-15, 1985, Vienna, Austria - IAEA Technical Comittee to Prepare a Safety Document on the Assessment of Occupational Intake of Radioactive Materials November 11-22, 1985, Vienna, Austria - IAEA Working Group Meeting to Prepare the First Draft of a State of Art Report on Safety Aspects of Nuclear Power Plant Aging December 10-12, 1985, Bombay, India - IAEA Specialists Meeting on Load Following Control of Nuclear Power Plant Including Availability Aspects June 23-27, 1986, FRG - IAEA Seminar on Operations Procedure for 1 Abnormal Conditions in Nuclear Power Plants Foreign Trip Reports Joseph Muscara, MEB/NRR September 24-October 19, 1984; Visited Italy, Sweden, and the FRG:

Mr. Muscara participated in and chaired the Steam Generator Group Project's Technical Advisory Group (TAG) meeting held in Rome. He also attended the NEA CSNI specialist meeting on Steam Generator Problems in Stockholm, and participated in meetings of the NEA CSNI, PISC, and NDE Reliability Group held in Florence, Italy.

Donald R. Hopkins, Senior Health Physicist, DRA/RES July 8-12, 1985; Visited Austria:

Mr. Hopkins attended the IAEA Advisory Group Meeting to Revise Advisory Material for the Application of the IAEA Transport Regulations.

ENCLOSURE G SEP 2 01985 l

4

- 0FFICE OF STATE PROGRAMS ITEtiS OF IllTEREST WEEK ENDING SEPTEf1BER 20, 1985 Annual All Agreement State Meeting During the period October 8-10, 1985, the Office of State Programs will host the 1985 All Agreement State Meeting. The Directors of the 27 Agreement State radiation control programs will meet at the Holiday Inn of Bethesda. Panel discussions which'will include NRC staff will cover the following topics: Low-Level Waste, Materials Licensing and Compliance, Regulations, Radioactivity in Unauthorized Places and Radiation Litigation.

Uranium Mill Tailings Reclamation James Petersen, OSP, met with URF0 and NMSS Waste Management staff in Denver, September 16-18, 1985. The group reviewed financial arrangements provided by each uranium mill licensee to reclaim mill tailings in accordance with 10 CFR 40, Appendix A. Findings will be presented to URF0 in written reports from Headquarters staff.

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ENCLOSURE H l

SEP 2 01985 l

OFFICE OF RESOURCE MANAGEMENT Items of Interest Week Ending September 20, 1985 Section 107 Report to Congress The Office of Resource Management, OPE and numerous offices are developing a programmatic, objectives-oriented structure for meeting a reporting requirement outlined in Section 107 of the Senate's version of NRC's authorization Legislation for FY 1986/1987 (S.895). .This structure will also be used in the Five Year Plan. The report is scheduled to go to Congress shortly after.the first of next year.

Generic Issue Management System At the direction of the EDO, the Office of Resource Management has been coordinating the development of agencywide information requirements to be ,

included in a new automated system. The system will assist in the management of power reactor generic safety issues / items from the time they are identified until the time requirements have been implemented and verified. Inputs for an initial manual report to test the system information needs have been received from the four program offices. This report is being finalized and will be submitted to the ED0's office in early October. Once a final determination is made regarding system information needs, the ADP aspects of the system will be evaluated and development will begin.

Budget Justification Book The presentation aspects of the NRC budget submissions--Blue Book to the OMB and Green Book to the Congress--have and are being improved. Following the initial changes to the FY 1987 Blue Book format, representatives of ADM and RM are examining several composing techniques' and production methods that would further improve upon our budget presentations in the Green Book to the Congress. Final format will be developed by the end of October,1985.

ENCLOSURE I SEP 2 01985

I OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST WEEK ENDING SEPTEMBER 20, 1985

1. AE0D Engineering Evaluation Report, E513, entitled, "High Pressure Core Spray System Relief Valve Failures," was issued on September 16, 1985.

The report evaluated the recurrent HPCS relief valve failures at LaSalle County Station and the potential for similar failures at other BWRs with HPCS systems. The AE0D study found that the relief valve failures at LaSalle were caused by excessive back pressure on the discharge port of the relief valve. Excess.back pressure was found to occur whenever the HPCS system operated because the relief valve discharge was hard piped to the HPCS minimum flow line. Special tests showed that the back pressure on the relief valve reached approximately 100 psi whenever the HPCS pump was running. However, the Crosby relief valve involved in the failures has a back pressure rating of only 90 psi. The consequences of valve failure were significant valve leakage into the HPCS compartment and a loss of containment integrity. The. elevated back pressure problem was corrected at LaSalle by routing the relief valve discharge to the reactor building equipment drainage system.

AE0D's review of the HPCS system flow diagrams and the relief valve designs for each of the other potentially affected BWRs concluded that River Bend Unit I was the only other plant with a potential for relief valve failures of the type which occurred at LaSalle. At River Bend, the HPCS pump discharge line relief valve is also manufactured by the Crosby Valve Company and has a discharge which is hard piped to the HPCS minimum flow line. In view of the similarities between the two plant designs, AE0D suggested that Region IV request Gulf States Utilities to evaluate the suitability of the River Bend HPCS relief valve discharge piping design

' in light of the failures which occurred at LaSalle.

2. An evaluation of recent valve operator motor burnout events was issued as

AE0D/S503. The Special Report provides a limited review and evaluation of valve operator motor burn i.t events subsequent to those reviewed in Case

~

Study AEOD/C203 which addressed events during 1978 to 1980.

This report illustrates that operating plants have not corrected this problem and thus corroborates the original recommendation. Although only a few events were reviewed and analyzed, the report identifies more than 200 valve operator motor burnout events including more than 180 events during the approximate four year time frame from 1981 to early 1985.

This number of events raises potential significant safety issues for the following reasons: (1) motor operated valves are used extensively in

safety systems where performance of the safety function requires that valves must open and/or close; (2) the motor failure mechanism.can be >

common mode based on an overall plant philosophy covering thermal overload i

' devices and surveillance procedures; (3) the failed motors can remain undetected for long periods of time; and (4) motor burnout has resulted

( in damage to the valve operator in a manner that prevented valve operation by either motor or manual drive mechanisms.

ENCLOSURE J r SEP 2 01985

e i

t REGION III [

STATUS REPORT i DAVIS-BESSE LOSS OF FEEDWATER EVENT 1-

' SEPTEMBER 20, 1985 <

l Plant Status l

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

Decay heat removal loop No.1 is drained for maintenance. ,

4

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q ENCLOSURE L SEP 2 01985

EQUIPMENT STATUS (F0LLOWS TABLE 5.1 IN NUREG 1154) o o

G5 TROUBLESHOOTING / ROOT CAUSE RIII ACTIONS DETERMINATION ACTIVITIES COMMENTS ITEM E MFPs were tested on 09/05- Region III is monitoring Main Fcedwater Cause determined to be component licensee evaluation of

1. 06/85 with no problems noted.

Turbine failure in speed control circuit. reliability of the MFPs.

Revised report issued 08/30/85.

Testing will continue through RIII monitoring licensee's

2. Closure of MSIVs Cause determined to be that circuit next week. Specialist from activities and observing was overly sensitive to momentary NRR will observe testing as selected activities.

system perturbation. Revised report issued 09/07/85. Additional required.

root cause determinations are continuing.

Eight MSSVs have been shipped RIII following licensee

3. Steam Safeties, Defective electronic module in to Wylie for full flow steam activities.

Atmos. Vents. ICS likely cause of problem with atmosphere vent valves. Revised testing and internal inspec-report issued 09/06/85. MSSVs tion. Vendor Programs Branch being evaluated. will be observing the testing activities.

Preparations are being made to RIII inspectors to

4. Aux. Feedwater Turbine Cause considered to be condensation modify the steam supply system. . observe activities.

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

Governor for #1AFWPT has been replaced with a new type governor.

Additional dp and flow testing RIII following licensee's

5. AFW Containment Completed and revised report issued 08/29/85. Misadjustment of bypass is being evaluated. activities.

Isolation Valves torque switch settings and inadequate testing procedure.

Activities completed. km I to observe any

6. Steam Supply Valve Completed and revised report issued additional testing.

Additional testing to AFPT No. 1 09/09/85. is planned in hot g standby.

n E

2 g

m r"*

4 TROUBLESHOOTING /R0OT CAUSE 5

COMMENTS RIII ACTIONS DETERMINATION ACTIVITIES

[ ITEM RIII observing activities.

Revised report issued 09/16/85 Licensee is considering

@7. Source Range NI replacing the containment cable

• on NI-1. Root cause was bad penetration modules. NI-1 is connection between detector and being monitored and appears unle.

stable.

Valve will be rebuilt (as RIII observing activities.

8. Completed and report sent to NRR Vendor Programs Branch has PORV needed). Two spare PORVs are 08/23/85. Root cause not deter- being rebuilt at Crosby, and been notified.

mined, will be tested at Marshall Steam Station in Terrell, N.C.

in October.

Work complete. None.

9. S/U Feedwater Control Completed and revised report issued Valve 08/29/85. The valve functioned correctly during the June 9 event.

RIII to review operator Completed and revised report issued Procedure has been revised and

10. Recovery of AFP operator aids (instructions) training program to Turbine 08/30/85. Training and procedural assure proper operator deficiencies identified. will be posted at turbines.

actions.

Individual pump suction RIII observing activities.

11. AFP No. 1 Suction Revised report issued 09/17/85.

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

12. Turbine Turning Gear *

13. Control Room HVAC*

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

14. Turbine Bypass Valve installed. New valve operator 08/29/85. Valve failure caused by water hammer, has been shipped from vendor.

i t CStatus not maintained on this item since these type failures occurred previously ar.d do not appear to be unique to th s even .

cfNo change in status from previous update.

E n

3 5

E M

/

i Other Activities The new electric motor driven auxiliary feedwater pump is grouted in place.

Installation of pipe and valves is about 60% complete. Conduit installation, cable pulling.and wire termination is in progress. The existing SUFP has been electrically disconnected. Region III specialist will be onsite to.

4 review work progress.

I 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. Nonconformance Reports (NCRs) have been written against 438 of the 467 pipe supports inspected so far. Licensee's engineering department has received 355 NCRs for evaluation. Sixty-nine- '

NCRs have been dispositioned, fourteen require rework, none require welding.

Eight additional licensee inspection teams will be onsite next week to begin inspection of 800 pipe supports in containment.

5 Initial testing of motor operated valves by MOVATS, Inc. on the 51 valves that'must be tested before the plant is taken to hot standby is completed.

Thirteen valves. require retest. M0 VATS testing will resume next week. A Region III specialist will be onsite to review this program and witness testing.

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 corrective action plans. Item numbers correspond to Table 5.1 in NUREG-1154.

ITEM PLAN NO. DATE ISSUED

1. Main Feedwater Turbine 4 08/26/85

2. Closure of MSIVs 6 09/04/85

4. Auxiliary Feedwater Turbine 1 09/07/85 l

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

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

8. PORY I 09/09/85(Rev.2)

T

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

(

ENCLOSURE L SEP 2 01985' 4

,, . ,- - ------a .- -n., r -,

e.

ITEM PLAN N0. DATE ISSUED

14. Turbine Bypass Valve 1 09/05/85 (Rev. 2) 2 08/26/85 Davis-Besse Course of Action Report 09/09/85 Planned Meetings Congressman Markey hearings - October 2, 1985.

ACRS Subcommittee Site Visit - October 4,1985.

. Planned Special Inspections and Evaluations Training Accreditation Inspection (NRR/RIII) - September 24, 1985.

Inspection of M0 VATS Testing (IE/RIII) - September 23-27, 1985 Inspection of Auxiliary Feedwater Pump Installation - September 23-24, 1985.

j _

Annual INP0 Evaluation - September 30 through October 11, 1985.

4 i

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ENCLOSURE L SEP 2 01985 5

ITEMS ADDRESSED BY THE CO MISSION - WEEK ENDING SEPTEMBER 20, 1985 A. STAFF REQUIREMENTS - PERIODIC BRIEFING ON NTOLS, 2:00 P.M., TUESDAY, SEPTEMBER 3, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (PORTION OPEN TO PUBLIC ATTENDANCE) Memo fm SECY to W. J. Dircks, H. H. E. Plaine and R. F. Fraley dated September 17, 1985 The Commission

• met to be briefed by sOf f on the status of near term operating license (NTOL) plants.

Chairman Palladino requested the Office of the General Counsel to review the meeting transcript to determine whether any portion of the transcript should be served on the parties to any pending proceeding.

(OGC) (SECY Susper,se: 9/20/85)

Commissioner Asselstine requested the Advisory Committee on ~

Reactor Safeguards to provide an updated Committee position on Palo Verde Unit 2 prior to any anticipated low power or full power operating license decision for this plant by the staff or the Commission if the Committee has a different view from that contained in their December 15, 1981 report on Palo Verde.

(ACRS)

Commissioner Zech requested the staff to provide information on plants for which the staff has approved or had knowledge of the dual SRO/STA role.

(Subsequently, in a memorandum dated 9/11/85, the staff provided the information to the Commission.)

4

• Commissioner Roberts was not present.

I B. STAFF REQUIREMENTS - ORAL PRESENTATIONS ON TIMING OF DOE'S PRELIMINARY DETERMINATION ON SUITABILITY OF SITES FOR DEVELOPMENT AS REPOSITORIES,'

! 9:30 A.M., FRIDAY, SEPTEMBER 6,1985, COMISSIONERS' CONFERENCE ROOM, D.C.-OFFICE (OPEN TO PUBLIC ATTENDANCEJ Memo SECY to H. H. E. Plaine dated September 17, 1985 The Commission met to receive oral presentations from the Department of Energy (DOE) affected Indian Tribes and states, and interested environmental and industry groups onJthe timing of DOE's preliminary determination,, required by the' Nuclear Waste Policy Act, on the suitability of three sites for .

development as high level waste repositories. i l

ENCLOSURE O SEP 2 01985

2 I

B. ' CONTINUED The following persons participated in this meeting:

i Ben Rusche, Director Of fice of Civilian Radioactive Waste Management DOE Del White Ron Halfmoon .

Nez Perce Indians (Idaho)

Dean Tousley .

Yakima Indians (Washington) i l Tom Lehman State of, Minnesota

! Malachai Murphy State of Nevada Steve Frishman i State of Texas i

Patrick Spurgin State of Utah Don Provost State of Washington Carl Sinderbrand State of #isconsin-

, David Berrick l Environmental Policy Institute I

Loring E. Mills, Vice President Jay Silberg

Edison Electric Institute 1

The Commission requested that the Office of the General Counsel

' provide a legal analysis and recommendation concerning the need to reopen the concurrence process on the siting guidelines or

, take other action as a result of DOE's proposed departure from the Commission's concurrence statement regarding timing of the preliminary determination.

(OGC) (SECY Suspense: 9/20/85)

Chairman Palladino requested that all written submissions of interested parties be received no later.than Wednesday, 3

September 11, 1985.

ENCLOSURE 0 l SEP 2 01985 i

e .,

e I m

-u to C3

-- NRA MEETING NOTICES * '

$k '

SEPTEMBER 20, 1985 DOCKET

• APPLICANT /

DATE/ TIME NUMBER LOCATION I PURPOSE ,

ATTENDEES NRR CONTACT 9/24/85 50-244 P-110 Review Masonary Wall Design '

' Rochester Gas & Elec. C. Miller Bethesda FRC Dredel University (Ginna) 9/24/85 50-289 416 (Old To discuss licensing actions GPU Nuclear J. Thoma 10:00 am Phillips) in general and overall (TMI-1)

Bethesda schedules for completion of active issues -

9/24/85 50-335 AR-2242 To discuss an alternative Florida Power & Light D. Sells 10:00 am Bethesda method to hydrostatic testing Taledo Edison

as proposed by H.A.F.A.

International

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9/24-26/85 50-443 Seabrook Site Tc inspect completion of Power Public Serv. Co. of V. Nerses 50-444 Seabrook, NH System Branch confirmatory New Hampshire items 9/25/85 Ramada Inn To discuss assessment of IDCOR Z. Rosztoczy 9:00 am Bethesda severe accident uncertainties 9/25/85 50-413 Catawba Site To audit Catawba Inadequate Duke Power Co. K. Jabbour 10:00 am 50-414 Clover, SC Core Cooling Instrumentation ORNL for Implementation Review

. 9/26/85 50-267 'P-114 To discuss Equipment Qualifi- Public Service Co. K. Hietner 9:00 am Bethesda cation for Ft. St. Vrain of Colorado -

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• 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

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DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE '

ATTENDEES NRR CONTACT I

9/26/85 50-335 P-114 To discuss Intrusion Alarm 1:30 pm Bethesda Systems .

orida g r & Light D. Sells t.

10/3/85 P-118 To discuss examiner requali- Bolling Water Reactor R. Hermann i

9:00 am Bethesda fication program, scope and Owners Group program of BWROG II on inter-granular stress corrosion cracking research, and other technical issues related to IGSCC.  ;

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.

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HMSS MCETING NOTICES-FOR WEEK ENDING: 9/20/35 Division cf fuel Cycla and Mat;rlal Safcty .

DOCKET ATTENDEES /

I.0 CATION PURPOSE APPLICANT _ NRC CONTACT _

$ DATE/ TIME m _ NUMBER 9/22-24/85 ,

Tulsa, To attend as resource person meeting A. L. Soong Soong OK of Radiation Measurements Committee-of the Conference of Radiation Control Program Directors.

9/23/85 70-364 llarrisburg, To discuss proposed Volume Reduc- J. Ilambright (PDER) Loysen PA tion Services Facility at Babcock P. Loysen (FC) ,

and Wilcox Parks Township site with PA Dept. of Environmental I Resources (PDER).

10/7-9/85 L ivennore, To discuss Modal Study contract R. Cunningham (FC) Cunningham CA with Lawrence Livermore officials. J. Malaro (RES)

F. Gillespie (RES)

Division of Waste Management None Divi _sion of Safeguards None E

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$ IE MEETING NOTICES x

co DOCKET. ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 9/24/85 - FEMA Region III. 0ffice Discussion re Susquehanna E. L. Jordan E. L. Jordan D. B. Matthews <

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OSP MEETING NOTICES September 20, 1985 o

ts 3 DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 10/3-5/85 Albuquerque, N.M. Advanced Management of J. Lubenau, OSP JLubenau, OSP Radiation Accidents Workshop (University of New flexico)

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S:pt. 20, 1985

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g RII MEETING NOTICE DOCKET ATTENDEES /

NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME 09/25/85 RII'0ffice Enforcement Conference Licensee, Regional Walker 10:00 am Georgia Power Company - Administrator and e Vogtle Nuclear Plant selected RII and HQs (

staff members RII Office Enforcement Conference Same as above Walker 09/26/85 10:00 am Virginia Electric and

- Power Company - North Anna and Surry Facilities 1:30 pm RII Office Enforcement Conference Same as above Stohr Tampa VA Hospital i

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