ML20153H202

Weekly Info Rept for Wk Ending 860214

ML20153H202
Person / Time
Issue date:	02/20/1986
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-860214, NUDOCS 8602280699
Download: ML20153H202 (35)

Text

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90b February 20, 1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the E00

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 14, 1986 A summary of key events is included as a convenience to those Connissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F*

International Programs G State Programs H*

Resource Management I*

Analysis and Evaluation of Operational Data J*

Small & Disadvantaged Business Utilization & Civil Rights K*

Reginnal Offices L CRGR Monthly Reports M*

Executive Director for Operations N*

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

• No input this week. '

/

T. A. , ssistant for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, ED0 492-7781 8602280699 860220 PDR COMMS NRCC WEEKLYINFOREPT PDR

, HZGl! LIGHTS OF WEEKLY INFORfMTION REPORT WEEK ENDING FEBRUARY 14, 1986  !

i V.C. Sumer Trip Report The reactor trip from turbine trip of February 2,1986, is being followed up by Region II. The NRR Project Director and PM discussed the event onsite with the Senior Resident Inspector on February 5, 1986. The root causs is personnel error in developing an incorrect electrical load list (a coridensate valve was de-ener -

maintenancewhentheloadlistsaiditwouldnotbe)gizedduring . Also, it appears that the post-trip review was incorrect in one area. Region II is evaluating for violations.

South Texas Project, Units 1 and 2

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The applicant informed the Project Manager late in the afternoon of February 7,1986, that a significant non-conservatism had been discovered in the analyses supporting the Auxiliary Feedwater (AFW)

System design. The vendor, Westinghouse, had discovered an analytical

, error, and at this time, appears to affect only the South Texas Project.

The applicant infomed us that correction of the analyses would result in a change in the success criterion for auxiliary feedwater supply, from requiring AFW to one steam generator to two steam generators to remove decay heat under accidents in Modes 2, 3, and 4. Physical modifications involving valves will be required to meet the applicable

. regulatory criteria. In addition, the FSAR and the proposed Technical i

Specifications will need to be changed. A fomal communication i describing the scope of the problem is expected shortly.

Comanche Peak Unit 1

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By order dated February 10, 1986, the staff granted an extension to the latest construction completion date for Comanche Peak Unit No. I to August 1, 1988. The Applicants have resumed normal construction j activity.

l Additional Observations about the January 31, 1986 Earthquake in Ohio On February 12, two staff seismologists from the U.S. Geological Survey presented a briefing about two toxic-waste (not radioactive) deep injection l wells and their possible causal relationship to the January, 31 earthquake in Ohio. The wells are located between the Perry Nuclear Power Plant and the ,

epicenter of the earthquake. Following the earthquake, the Ohio Environmental Protection Agency inquired of the USGS if the earthquake could have damaged the wells because there were anomalous readings on the wellhead pressure gauges, i The NRC staff was alerted to the preliminary information about the potential l for a causal relationship between the wells and the earthquake because

! additional data obtained about the well and its injection history showed some similarities to known cases of injection well induced seismic activity. This hypothesis is being investigated by the U.S.G.S. RES will follow this study closely.

{ FEB 1 < 1986

OFFICE OF ADMINISTRATION Week Ending February 14, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 83 9 Granted 73 2 Denied 21 0 Pending 170 22 ACTIONS THIS WEEK Received Cindee Virostek, Requests copies of seven specified records concerning Kiski Valley B&W's facilities in Apollo and Parks Township, Coalition Pennsylvania.

(86-73) ,

Al Stern, Requests a list of firms requesting the solicitation Al Stern for the SBIR FY86 Program.

Associates, Inc.

(86-74)

Ann R. Thompson, Requests the names of contractors and copies of International contracts with trucking companies which have Brotherhood of permission to transport nuclear materials.

Teamsters (86-75)

Jim Pedro, Requests copies of 10 specified papers.

NUS Corporation (86-76)

Jim Pedro, Requests records reflecting the total fees charged for NUS Corporation 1985 under 10 CFR Part 170 for the McGuire, Salem, (86-77) Sequoyah, and North Anna nuclear power plants.

Catherine Quigg, Requests copies of all records regarding the performance Illinois Safe of high burnup fuel and high burnup spent fuel in Energy Alliance reactors and spent fuel pools in the U.S. and other (86-78) countries.

CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A FEB 1._ 1:;3

2 Received, Cont'd Sanuel S. McHard, Requests reports submitted to NRC by Comonwealth-Katz, McAndrews, Edison, Iowa-Illinois Gas and Electric Company, or Durkee, Blach & the Quad-Cities plant regarding an electrical Lefstein, P.C. explosion at that plant on May 7, 1985.

(86-79)

Billie P. Garde, Requests all records generated or prepared by Victor Government Stello begininning with his appointment as Acting Accountability Executive Director.

Project (86-80)

Billie P. Garde, Requests all records regarding Region IV audits of Government Comanche Peak.

Accountability Project (86-81)

Billie P. Garde, Requests all records generated or prepared by Victor Government Stello beginning with his appointment as Acting Accountability Executive Director.

Project (86-82)

David N. Perkey, Requests information concerning all NRC contracts with NUS Corporation National Labs since 1979.

(86-83)

Bobby G. Hardwick, APPEAL TO THE ED0 for the release of threc denied McClure, Brannan records regarding a request, on behalf of his client,

& Hardwick for all records concerning his client's exposure to (86-A-7-85-763) radiation at the Clinton nuclear power plant.

Albert V. Carr, APPEAL TO THE EDO for the release of six denied records Duke Power in NRC's partial response dated January 8,1986, Company regarding records related to and underlying Enforcement (86-A-8-85-584) Action No. EA-84-93 on the Catawba nuclear power plant.

Albert V. Carr, APPEAL TO THE COMMISSION for the release of nine denied Duke Power records in NRC's partial response dated January 7, 1986, Company regarding records related to and underlying Enforcement (86-A-9-85-584) Action No. EA-84-93 on the Catawba nuclear power plant.

Granted Steven C. Sholly, In response to a request for a copy of Science MHB Technical Applications, Inc., Final Report SAI-354-84-9A, Associates " Containment Event Trees for PWRs and BWRs," dated (85-803) Febraary 1983, informed the requester that the NRC does not have the requested record.

ENCLOSURE A FEB 1 C3

3 Granted, Cont'd Marvin Turkanis, In response to a request for copies of all registrations Neutron Products from the NRC Source and Device Catalog for the following Inc. fims: Siemens Corporation; Toshiba Corporation; GE (86-49) Company; U.S. Nuclear Corporation; and Alpha-Omega Corporation, made available 82 records.

Larry M. Hununel , In response to a request for a list of names and Pathfinder addresses of organizations licensed to use and store Laboratories, Inc. carbon-14 and tritium, made available the requested (86-60) list.

Nan Taylor, In response to a request for copies of NRC's 43a and International 43b Budget Submissions in response to 0MB Circular A-11 Data Corporation TM-56 of June 25, 1985, made available two records.

(86-63)

Ronald G. Harper, In response to a request for copies of all licenses held Brandhurst Inc. by Emergi-Lite Inc. of Westbrook, Connecticut, informed (86-67) the requester that the NRC has no records subject to this request.

Denied

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Nina Bell, In response to a request for all records related to Nuclear Information certain allegations made by Frank Peguese about the and Resource Shearon Harris nuclear power plant and instances or (85-358) allegations of water leakage at the Shearon Harris plant, made available 20 records. Denied portions of 10 records in order to withold the names, home addresses, home telephone numbers, and identifying information of confidential sources and other individuals.

Stephen H. Hanauer, In response to a request for copies of the Daily Staff Technical Notes for the period January 11, 1982, through February 17, Analysis Corp. 1982, made available 21 records. Denied portions of (85-778) five records, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

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FEB 1s 1985 ENCLOSURE A L

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WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS l

WEEK ENDING FEBRUARY I4, 1986 4

s RFP ISSUED 4

RFP No.: RS-NRR-86-054 [

Title:

" Program to Support Regional Operator Licensing Activities l

Description:

The work conducted under this contract will provide technical

expertise to assist the NRC regional offices in administering initial, replacement and requalification examinations required in the process of licensing commercial nuclear power plant reactor ,

operators (RO) and . senior reactor operators (SRO).

Period of Performance: Three years Sponsor: Office of Nuclear Reactor Regulation

{ Status: Date for receipt of proposals extended to March 7, 1986.

PROPOSALS UNDER EVALUATION RFP No.: RS-NMS-86-004

Title:

" Fuel Cycle Licensing Technical Assistance"

Description:

The contractor shall provide technical assistance to the NRC as requested by issuance of task orders, in conducting safety i and/or environmental reviews of license applications for the construction, operation, or decommissioning of fuel cycle facilities.

Period of Performance: Three years Sponsor: Office of Nuclear Material Safety and Safeguards l Status: RFP closed and proposals forwarded to Source Evaluation Panel for review on February 12, 1986.

! RFP No.: RS-ADM-86-217 f

Title:

" Acquisition Training" ,

Description:

The contractor shall present the " Acquisition Training" course from materials provided by the NRC to NRC employees responsible for monitoring contractual arrangements.

Period of Performance: Two years i Sponsor: Office of Administration j I Status: The competitive range has been established and negotiations are 1 scheduled for the week of February 24, 1986.  ;

I RFP No.: RS-ADM-86-216

Title:

" Regulatory Process Training" I

Description:

Presentation of two-day course entitled, "The Regulatory Process".

Period of Performance: 24 months l Sponsor: Office of Administration l Status: The competitive range has been established and negotiations are scheduled for the week of February 10, 1986.

4 ENCLOSURE A l FEB 14 E;5 f.

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Wdekly Information Report Division of Contracts PROPOSALS UNDER EVALUATION (cont'd)

RFP No.: RS-NMS-86-001

Title:

" Technical Assistance in Environmental and Socioeconomic Assessrents"

Description:

Contractor shall provide technical assistance to NRC in the review of DOE programs relating to the development of Environmental Impact Statements.

Period of Performance: Three years Sponsor: Office of Nuclear Material Safety and Safeguards Status: The competitive range has been established and negotiations are scheduled for the week of February 18, 1986.

RFP No.: RS-NRR-86-055

Title:

" Assessment and Application of Thermal-Hydraulic Phenomena for Severe Accident Decisions"

Description:

Generic assessment of thermal-hydraulic issues associated with severe accidents, review all LWR designs to determine the specific applicability of results of the generic assessment of thermal-hydraulic issues and provide support for implementation of NRC's severe accident policy, review of probabilistic risk assessments and prioritization of generic issues.

Period of Performance: 30 months Sponsor: Office of Nuclear Reactor Regulation Status: Best and Final offers received and for varded to Source Evaluators for review on February 7, 1986.

CANCELLATION RFP No.: RS-SDB-85-387 Title : " Development of Business Opportunities for High Technology Small Business Firms with the U.S. NRC"

Description:

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

Period of Performance: One year Sponsor: Office of Small and Disadvantaged Business Utilization / Civil Rights Status: RFP cancelled on February 13, 1986.

CONTRACT CLOSED-0UT NoC-10-80-383 JWK International Corporation ENCLOSURE A FEB 1 E;3

Wcekly Information Report Division of Contracts ADMINISTRATIVE MATTER Bids under ADM-86-256, for archival storage in an environmentally controlled and protected area, were opened en January 24, 1966. Based on a preliminary pre-award survey of the low bidder's facility on January 28, 1965, the Division of Contracts

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found the firm to be nonresponsible since the facility was not in compliance with the cited environmental standards and specifications. The matter was referred to the Small Business Administration (SBA) which concurred in the NRC's judgment on February 12, 1986. Evaluation of the next low bidder is in process.

O i

FEB 141995 ENCLOSURE A

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending February 14, 1986 Millstone 3 Millstone 3 is currently at about 15 percent power and continuing SG level testing. The unit experienced a main feed isolation due to high C SG 1evel. This event was caused by work being done to set up for the steam dump control test when a ster.n pressure transmitter was inadvertently shorted out. The motor driven aux feed pump was started and SG level was restored. Then the motor driven main feed pump was

. started and aux feed was secured. The unit was stable at 8 percent power.

Also, a primary to atomospheric leak (i gal / min) occurred through a loop flow transmitter fitting. Power was reduced to 5 percent while the leak was repaired. Power level was then restored and SG level testing continued.

V.C. Summer Trip Report The reactor trip from turbine trip of February 2,1986, is being followed up by Region II. The NRR Project Director and PM discussed the event onsite with the Senior Resident Inspector on February 5,

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1986. The root cause is personnel error in developing an incorrect electrical load list (a condensate valve was de-ener maintenancewhentheloadlistsaiditwouldnotbe)gizedduring . Also, it appears that the post-trip review was incorrect in one area. Region 11 is evaluating for violations.

South Texas Project, Units 1 and 2 The applicant informed the Project Manager late in the afternoon of February 7,1986, that a significant non-conservatism had been discovered in the analyses supporting the Auxiliary Feedwater (AFW)

System design. The vendor. Westinghcuse, had discovered an analytical error, and at this time, appears to affect only the South Texas Project.

The applicant informed us that correction of the analyses would result in a change in the success criterion for auxiliary feedwater supply, j from requiring AFW to one steam generator to two steam generators to t

remove decay beat under accidents in Modes 2, 3, and 4. Physical

, modifications involving valves will be required to meet the applicable regulatory criteria. In addition, the FSAR and the proposed Technical l Specifications will need to be changed. A fora.al comunication

describing the scope of the problem is expected shortly.

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< FEB 14 E5 EflCLOSURE B

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i Fort St. Vrain By letter dated February 7,1986, the Director of NRR authorized operation at up to 35 percent of full power for the Fort St. Vrain Station through May 31, 1986. This authorization is based on a Connission Memorandum and Order, dated November 26, 1985, granting Public Service Company of Colorado an extension to the Novereber 30, 1985 deadline for equipment qualification at Fort St. Vrain.

This limited operation was approved following the licensee's satisfaction of a number of confirmatory actions ider.tified in the Metnorandum and Order.

Issuance of Renewal of Facility Operating License TR-1 for the

General Electric Test Reactor i

By letter dated October 21, 1975, the licensee requested renewal of 4 Facility Operating License No. TR-1. Opportunity for hearing was afforded by the Notice of Proposed Renewal of Facility License 4

puolished in the FEDERAL REGISTER on September 15, 1977 at 42 FR j 46427. A request for hearing and petition for leave to intervene was filed following notice of the proposed action. In 1977 the resulting hearing was set aside pending other hearings on an NRC Order to Show Cause concerning potential effects on the reactor dua to postulated i extreme seismic events. Hearings were terminated in August 1982 and

, the Order to Show Cause was rescinded in April 1983. Proceedings on the original petition to intervene were resumed.

An agreement between GE and the one remaining intervenor on the renewal application resulted in withdrawal of the contentions, acceptance of the agreement conditions by the ASLB, and termination of the hearing in 3

April 1985 by the ASLB. In accordance with the agreement, by letter dated June 26, 1985, as supplemented July 15, 1985, GE submitted an amendment to its license renewal application requesting renewal for

• l possession only. This request was noticed in the FEDEPAL REGISTER on September 11, 1985 at 50 FP 37083. ho petitions to intervene wera

! received. This license renewal amendment for " Possession Only" dated ,

4 February 4,1986, is for seven years, to October 1992, and completes -

the license renewal action. ,

Comanche Peak Unit 1 By order dated February 10, 1986, the staff granted an extension to the  !

latest construction completion date for Comanche Peak Unit No. I to August 1, 1988. The Applicants have resumed normal construction 1 activity.

i ENCLOSURE B FEB 141935

Millstone 3 Millstone 3 completed SG level control testing and the steam dump control test on February 11, 1986. The unit was synchronized to the grid at 0816 hours0.00944 days <br />0.227 hours <br />0.00135 weeks <br />3.10488e-4 months <br /> on February 12, 1986, at about 20 percent power.

Fort Calhoun Station The Fort Calhoun Station has completed its refueling / modification outage and has been returned to service. The staff was notified that because of a modification perfonned during the outage, the alternate shutdown capability for the control room / cable spreading room has been compromised.

The alternate shutdown capability for the control room / cable spreading room at Fort Calhoun was approved by the staff in August 1982. One of the aspects of the alternate shutdown capability was to electrically isolate the control room / cable spreading room from the alternate shutdown panels at two inverter locations. This was to be accomplished by a procedure by opening a breaker inside the inverter cabinets. New inverters were installed during the recent outage, and the subject circuit breakers were not an integral part of the new inverters.

The licensee has taken corrective actions. The operators were alerted to the situation and a procedure change was made that would require electrical isolation of the control room / cable spreading room by manual means at the inverter locations.

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The licensee is evaluating various hardware changes to address the problem.

Millstone 3 Millstone 3 is currently in Mode 3 (hot standby) while the turbine is being turned by the jacking gear in order to correct vibration caused by a bow in the shaft.

Yesterday, the unit tripped from 30 percent power on low-low SG level in all four generators at 1042 hours0.0121 days <br />0.289 hours <br />0.00172 weeks <br />3.96481e-4 months <br /> on February 12, 1986. This is the 4th unplanned trip since initial criticality. The trip resulted from low condensate pump suction pressure when the licensee was switching over from the turbine driven main feed pump to motor driven feed pump.

The licensee determined that this procedure should be modified to include startup of the second condensate pump.

9 ENCLOSURE B FEB Ic 1936

4-River Bend At 6:17 a.m. CST on February 12, 1986, RiverBendStation(RBS) experienced a reactor trip due to turbine trip. The turbine trip resulted from a high water level in a moisture separator reheater (MSR). This high water level was caused by an apparent malfunction of the MSR drain and dump valve.

At the time of the scram, the reactor was operating between 30 and 35 percent of rated power. The NRC's senior resident inspector was in the control room at the time of the reactor trip and reports that all affected sytems appear to have functioned as designed.

This is the 5th reactor trip so far in 1986.

CRYSTAL RIVER UNIT 3 SECOND REACTOR COOLANT PUMP FAILURE As part of the recovery effort from the shaft failure of RCP "A" discussed in the Daily Highlight of January 23, 1986, the shafts of_the other three pumps were examined by UT techniques. Pump "B", in the same loop as "A", showed an indication of an extensive but shallow crack in the same location as the "A" pump. The licensee has decided to replace this shaft as well. The "B" pump has not yet been disassembled to confirm the indication. The shafts' of the "C"and "D" pumps did not show any indications.

Examination of the "A" shaft is not yet completed, but preliminary information indicates that the failure resulted from a fatigue crack initiating at a circumferential sharp-cornered rectangular groove.

Repair of both pumps is scheduled to be completed by early April. The licensee will provide a presentation to the NRC prior to restart. It is noted that at least several other plants have similar or identical Byron Jackson pumps.

ENCLOSURE B FEB 1.,E;3

NRC TMI-2 CLEANUP PP0dECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING FEBRUARY 14, 1986

1. DEFUELING

- Two filled defueling canisters were transferred from the Canister Positioning System in the reactor vessel to the canister storage racks in the "A" Spent Fuel Pool (SFP). There are 12 filled defueling canisters in the SFP containing a total net debris weight of about 8,800 lbs. The estimated total weight of damaged fuel and structural materials in the reactor vessel prior to start of defueling was 308,000 lbs.

- A Temporary Reactor Vessel Filtration System (TRVFS), a small circulating pump and diatomaceous earth filter is filtering reactor coolant water. Its purpose is to improve reactor vessel water clarity to provide sufficient visibility for defueling operations.

- The licensee announced a proposed change to the organization plan intended to improve the efficiency of defueling activities as they progress to the production phase of defueling. The change consolidates responsibility for all defueling related operations, engineering, and support functions into one defueling organization reporting directly to the Office of the Director, TMI-2. The NRC staff has reviewed and approved the change which will be implemented in the near future.

2. PLANT STATUS

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

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

- The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the internals indexing fixture.

Calculated reactor decay heat is less than 11 kilowatts.

- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 71*F to 96"F with an average of 81*F.

The average reactor building temperature is 54 F. The reactor building airborne activity at the Westinghouse platform is 6.7 E-8 uCi/cc Tritium and 5.4 E-11 uCi/cc particulate, predominantly Cesium 137.

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

' ENCLOSURE B FEB 141986

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

3. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this week.

- Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,822,963 gallons.

4. DOSE REDUCTION / DECONTAMINATION

- The 281' annulus area is being painted after decontamination.

- - 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.' The average dose rate to workers on the defueling work platform is 8 mrem per hour.

- Decontamination scabbling is being done in the 281' fuel handling building makeup valve alley.

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 discharge to the river consisted of seven daily composite samples taken from January 25 through February 1, 1986. A gamma scan detected no reactor related activity.

- The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from January 26 through February 1, 1986. A gamma scan detected no reactor related radioactivity.

- The NRC outdoor afrborne particulate sampler at the TMI site collected a sample'between February 7, and February 12, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

6. REACTOR BUILDING ACTIVITIES

- Initial defueling of the reactor core is in progress.

- The licensee began a prcgram to obtain core bore samples from the unpainted cement block wall beneath the enclosed stairwell in the reactor building basement. The samples will be obtained by a robot (ROVER), and will be used to assess the contamination absorbed by the material.

FEB 14 in3 ENCLOSURE B

• • 7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of Defueling Water Cleanup System (DWCS) and canister dewatering system continued.

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

- Preparations are being made for decontamination in the Seal Injection Room, 281' auxiliary building.

- Disassembly of the makeup and purification demineralizer elution hardware is in progress.

8. NRC EVALUATIONS IN PROGRESS

- Technical Specification Change Request number 49.

- Recovery Operations Plan Change number 31.

- SDS Technical Evaluation and System Description Update.

- Core Stratification Sample Safety Evaluation.

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

- Containment Air Control Envelope Technical Evaluation Report, Revision 5.

- Solid Waste Facility Technical Evaluation Report.

- Reactor Building Sump Criticality Safety Evaluation Report.

9. PUBLIC MEETINGS The Advisory Panel for the Decontamination of Three Mile Island Unit 2 met on February 12, 1986, in Harrisburg, Pennsylvania. The Panel was briefed by GPUN on progress of the cleanup and on licensee actions to correct deficiencies in the radiochemistry program that caused erroneous Strontium-90 analysis. Dr. Travers of the NRC TMI-2 Cleanup Project Directorate briefed the Panel on current NRC activities. The Panel heard a presentation by the U.S. Department of Energy (DOE) on plans for the shipment by rail of fuel removed from the damaged reactor to a DOE

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interim storage facility in Idaho. They also received a presentation by Jane Lee on health effects in the area surrounding the TMI facility. She was critical of the Pennsylvania State Department of Health and its recent health effects study.

The next meeting of the Panel is tentatively scheduled for April 10, 1986 in the Harrisburg area. The exact date, location, and agenda for the meeting will be announced in the future.

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I' d ENCLOSURE B

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending February 14, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 121(a) of NWPA: EPA Final HLW Star.dards Status: Staff briefed the ACRS on January 15, 1906 on proposed revisions to 10 CFR Part 60 for conformance to EPA standards.

Action: The proposed revisions to Part 60 are scheduled to be submitted to the Commission in late February 1986.

Section: 141(b) of NWPA: Comments on MRS Proposal Status: Staff comments on the MRS proposal (SECY-86-9) were approved by Commission on February 5,1986 and transmitted to 00E.

Action: NRC comments were to be submitted by DOE with the proposal tc Congress in early February 1986. However,' successful legal challenge by the State of Tennessee has postponed the submission of the MRS proposal to Congress indefinitely.

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

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Status: The final rulemaking on Part 55 and three associated regulatory guides has received ACRS approval, and final Office review has been completed.

Action: The final rule was submitted to the CRGR for review on February 12, 1986, and then to the Commission for approval.

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

Action: The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1985 for approval, which is expected after DOE officially submits the proposal to Congress.

ENCLOSURE C FEB ls E!3

Near-Term DOE Actions of Interest February 7, 1986 - DOE submittal of MRS proposal to Congress delayed indefinitely by legal injunction.

February 10, 1986 - DOE to issue Final Transportation Business Plan.

Early February 1986 - DOE to issue draft Request for Proposals (RFP) for the reactor fuel cask.

February 1986 - Submit Fee Adequacy Report to Congress.

February 1986 - Submit FY 1985 OCRWM Annual Report to Congress.

April 1986 - Issue Environmental Assessments for first repository.

April 1986 - Issue Nominations and Recommendations for first repository candidate sites for characterization.

April 1986 - Issue Transportation Institutional Plan.

Review of FEMA Report on States' Emergency Preparedness Training and Needs for Federal Training Assistance The staff reviewed the survey report on states' participation in emergency preparedness training and their needs for Federal assistance in this area.

Comments on the draft report were provided through the NRC representative on the interagency Coordinating Committee on Emergency Preparedness.

NFS-Erwin Strike by OCAW members continues. There has been no progress made during the past week in resolving differences between the Union and NFS. NFS continues to conduct limited operations of the HEU production, scrap recovery, and R&D facilitics.

ENCLOSURE C FEB 141525

Office of Inspection and Enforcement Items of Interest Week Ending February 14, 1986

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

a. EN 86-06, Nebraska Public Power District (Cooper Nuclear Station), a Notice of Violation and Proposed Imposition of Civil Penalty in the -

amount of $50,000 was issued on February 13, 1986. This action involves the failure to properly implement surveillance procedures and the failure of surveillance inspections to detect inoperable equipment.

b. EN 86-07, Pacific Gas and Electric Company (Diablo Canyon), a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued on February 13, 1986. This action involves a wiring error rendering one channel of the actuating logic of one main steam isolation valve (MSIV) inoperable.

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

a. PNS-I-86-02, Long Island Lighting Company (Shoreham), Bomb Threats.

b. PN0-I-86-13, Washington Hospital Center (Washington, D.C.), Cobalt-60 Teletherapy Treatment Administered to Wrong Patient,

c. PNO-II-86-13, Virginia Electric & Power Company (Surry Units 1 and 2), Packaged Weapon Undetected By X-Ray Search.

d. PNO-III-86-09B, Cleveland Electric Illuminating (Perry), Earthquake (Second Update).

e. PNO-III-86-12, Consumers Power Company (Big Rock Point), Shutdown to Repair Valve Leakage.

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

a. IE Information Notice No. 86-10, Safety Parameter Display System Malfunctions was issued February 13, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

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4. Other Items

a. Senior Management Meetings Deputy Director, IE attended a meeting with representatives of Detroit Edison and NRR on February 12, 1986 to discuss pipe failures at their Monroe fossil fuel plant.

b. Generic Issues (1) A member of the Engineering & Generic Communications Branch, Division of Emergency Preparedness and Engineering Response (DEPER) and two NRR staff members visited Stone & Webster Engineering, Cherry Hill, New Jersey on February 11-12, 1986 to discuss matters related to the Comanche Peak piping analysis.

(2) A member of the Engineering & Generic Communications Branch, DEPER, visited the TVA engineering offices, Knoxville, Tennessee and Chattanooga, Tennessee on February 11-14, 1986 for TVA tasks efforts.

(3) A member of the Engineering & Generic Communications Branch, DEPER was in Salt Lake City, Utah on February 10-14, 1986 to attend Section XI, ASME Code Meetings related to ISI and owners certification.

c. Incident Response A member of the Incident Response Branch, Di.ision of Emergency Preparedness and Engineering Lesponse, presented two papers at the Federal Radiological Emergency Response Plan Course held in Emmitsburg, Maryland at the FEMA Emergency Management Institute on February 12, 1986. The papers discussed Severe Accident Protective Actions and the NRC Role.

d. Vendor Program (1) The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Program (QAVT) is continuing its equip-ment qualification inspection at the TVA Sequoyah plant this week.

ENCLOSURE D FEB 14 'i03

(2) In a followup to the San Onofre water hammer event, the Vendor Program Branch (QAVT) is conducting inspections at two check valve vendors this week, Atwood and Morrill, and MCC Pacific Valve Company, and is visiting Millstone Unit 2 and North Anna 1 and 2 to review IST and maintenance activities related to safety-related check valves.

(3) The. Vendor Program Branch (QAVT) is conducting an inspection at Parson Peebles Electrical Products as a followup on electrical generator problems for the HPCS diesel generator at Grand Gulf.

e. Safeguards Materials Inspections (1) A member of the Safeguards and Materials Programs Branch, Division of Inspection (DI) is participating with a Region II inspector on assessments of materials licensees at various loca-tions in Puerto Rico.

(2) A member of the Safeguards and Materials Programs Branch (DI),

is participating in a regulatory appraisal of the Sequoyah Fuels Corporation's facility in Gore, Oklahoma.

f. Allegation Followup The Branch Chief, Safeguards and Materials Programs Branch, Division of Inspection, is participating in a meeting with NFS and Region 11 staffs on the Nuclear Fuel Services facility (Erwin, Tennessee) in Atlanta, Georgia.

g. Technical Training Center The former Black Fox control room simulator, located at the Technical Training Center in Chattanooga, is in final preparation for turnover for NRC use on February 14, 1986.

h. Quality Assurance (1) On February 11-14, 1986 members of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs (QAVT), and contractors were in Reading, Pennsylvania to inspect Gilbert Commonwealth's design review program for TVA's Sequoyah Unit 1.

(2) A member of the Quality Assurance Branch, 0AVT was in Chattanooga,

< Tennessee February 10-14, 1986 assisting Region II in its inspection of Sequoyah's implementation of their QA program plan.

! i. Construction Appraisal The exit meeting for the Construction Appraisal Team inspection con-ducted at the Palo Verde plant was conducted with the licensee on February 14, 1986. ENCLOSURE D

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j. Commissioner Briefing A member of the Program Support and Analysis Staff attended a meeting at Commissioner Asselstine's office February 14, 1986 to discuss the proposed employee survey as part of the Affirmative Action Advisory Committee,

k. ACRS Briefing Members of the Events Analysis Branch, Division of Emergency Pre-paredness and Engineering Response, NRR and Region III conducted a briefing of the ACRS on recent significant operating events at nuclear power plants.

1. Emergency Preparedness

1. The Division Director and staff members from the Division of Emergency Preparedness and Engineering response attended the Shoreham exercise on February 13, 1986. On February 11-12, 1986, staff members attended pre-exercise training on their role during the exercise.

2. FEMA has provided their interim findings on offsite radiological emergency plans and preparedness for Artificial Island (Salem /

Hope Creek). No deficiencies were identified and the results of the plan reviews and the exercises for New Jersey and Delaware were acceptable.

3. An emergency preparedness exercise report provided by FEMA for Vermont Yankee was forwarded by IE to Region I for appropriate action. While three deficiencies were identified by FEMA at the exercise, a later remedial exercise demonstrated that the deficiences were corrected.

m. Transportation Inspection A member of the Safeguards and Materials Program Branch, Division of Inspection is participating with Region I inspectors at a transporta-tion inspection of the Union Carbide facility in Texedo, New York.

FE914 333 ENCLOSURE D

I I

& OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest

, Week Ending February 14, 1986 k

Replacement of Greenwich Mean Time (GMT) by Coordinated Universal Time (UTC)

During the February 6,1986 meeting of the Comittee for Basic Services of the

. Federal Committee for Meteorological Services and Supporting Research, member Federal agencies were advised that as of January 16, 1986 Coordinated Universal Time (UTC) replaced Greenwich Mean Time (GMT) as the official clock time in the U.S. This change is the result of a U.S. National Bureau of Standards agreement with the International Conference on Weights and Measures in Paris, France. UTC is the basis for time in most other countries.

The practical effect of this change is merely to replace the title of a specific time from " Greenwich Mean Time (GMT)" to " Coordinated Universal Time (UTC)." Numerical times are not affected by this change. The standard abbreviation "Z" following a time will be retained, but will now indicate UTC rather than GMT.

An awareness of this change by Federal agencies such as the NRC is necessary since time references such as Federal Aviation Administration (FAA), National Oceanic and Atmospheric Administration (NOAA), U.S. Geological Survey (USGS) and National Earthquake Information Center (NEIC) advisories, forecasts, warnings, bulletins and other products that may be used by the NRC staff will

. now indicate UTC instead of GMT.

ENCLOSURE E FEB .t s 03

IPIRG - International Piping Integrity Research Group A new research program is currently being organized by RES to conduct research on nuclear piping so as to improve and validate the analytical methods used to predict piping behavior under a range of loadings, including full-scale tests under extremes of loading such as water-hammer and seismic.

The NRC is soliciting membership in the program from all states having significant reactor power programs and from the Electric Power Research Institute (EPRI), representing the U.S. nuclear industry research comunity, so that the research program developed will be broad based reflecting the needs and issues of the international comunity. It is expected that the results of this program will also form the basis for selection of a new pipe rupture criterion that will replace the double ended guillotine break, now being eliminated for certain cases in the GDC-4 revision. Because the elimination of the double ended guillotine break and formulation of its 4 replacement are such watershed issues, international cooperation in the implementing research is considered very necessary.

An organizational meeting of potential IPIRG members was held on October 31-November 1,1985, that was attended by people from twelve countries. The basic thrust of the program was embraced by the participants at that time. Since then, letters of intention to join the program have begun to arrive at NRC.

We have just received word this week from Spain, through Comissioner Goded, that Spain will very likel This brings the list of confirmed or very likely (y join the IPIRG program.such as Spain) participants to the Britain, France, Japan, Switzerland / Sweden, EPRI, and now Spain. Still to be heard from are West Germany, Italy, Belgium and Canada. We believe the Gemans will make a decision during March as the cognizant review comittee meets then and will pass their recomendation up to the BMFT; the outcome of the German decision is still up in the air, i

FEB 14 E'3 ENCLOSURE E.

South Carolina Earthquake on 13 February 1986 A small efrthquake, magnitude 3.5 on the Richter Scale, occurred in South Carolina near the juncture of South Carolina, North Carolina, and Georgia at 6:35 a.m. EST on February 13, 1986. This activity is being monitored by the NRC southeastern regional seismographic network and was reported to the NRC Project Manager by the Tennessee Earthquake Information Center shortly af ter its occurrence. Preliminary reports on the earthquake by this NRC contractor include the location, 34.76* N and 82.96* W, and the occurrence of seven aftershocks. This seismic activity is probably associated with the continuing low level of seismicity associated with the man-made Lake Jocassee and Lake Keowee reservoirs. The Oconee Nuclear Power Plants are about 25 km from the epicenter of this earthquake and it was reported to have been felt by personnel at the plant, but it did not trigger the seismic instrumentation at the site.

Additional Observations about the January 31, 1986 Earthquake in Ohio On February 12, two staff seismologists from the U.S. Geological Survey presented a briefing about two toxic-waste (not radioactive) deep injection wells and their possible causal relationship to the January, 31 earthquake in Ohio. The wells are located between the Perry Nuclear Power Plant and the epicenter of the earthquake. Following the earthquake, the Ohio Environmental Protection Agency inquired of the USGS if the earthquake could have damaged the wells because there were anomalous readings on the wellhead pressure gauges.

The NRC staff was alerted to the preliminary information about the potential for a causal relationship between the wells and the earthquake because additional data obtained about the well and its injection history showed some similarities to known cases of injection well induced seismic activity. This hypothesis is being investigated by the U.S.G.S. RES will follow this study closely.

EllCLOSURE E FEB 1415:6

4-RES RULEMAKING ACTIVITIES

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Decomissioning Criteria for Nuclear Facilities (Parts 30,40,50,51,70,71)

The rulemaking would provide more specific guidance on decomissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licenses. This action is intended to protect public health and safety and to provide the applicant or licensee with appropriate regulatory guidance for implementing and accomplishing nuclear facility

• decomissioning. The notice of proposed rulemaking was published on February 11, 1985.

Public coment letters (143) on the proposed decomissioning rule have been received and the contents categorized into about 100 separate public concerns requiring resolution. DET is preparing draf t comment resolutions and will circulate them for NRC staff review and input on how the resolutions should respond to public comments and be considered in the preparation of the final '

rule amendments. The goal is to complete the draft coment resolutions, which will include contractor and consultant input, and issue the draft final decommissioning rule in April 1986 for NRC division review.

Limiting the Use of Highly Enriched Uranium in Domestic pesearch and Test Reactors (Part 50)

The final rule would require that nonpower reactors use only low-enriched uranium fuel (LEU), with certain exceptions. Major features of the final rule include provisions for (1) assuring Federal Government funding for conversion-related activities, and (2) minimizing the nossibility of licensees becoming involved in hearings on conversion on issues unrelated to safety questions.

The Commission unanimously approved the final HEU/ LEU rule. The Comission decided that the requirements of the backfit rule are not applicable to this rule.

i Comission of European Conmunities' (CEC) Review of NRC Health Effects Models At the January 21-22, 1986, meeting in Paris, France, of the Group of Experts on Accident Consequence Analysis (GRECA), Dr. Jaak Sinnaeve, CEC, offered to l

pursue with CEC management the organizing of a formal CEC review of NUREG/CR-4214, " Health Effects Model for Nuclear Power Plant Accident i Consequence Analysis." We have verbal confirmation of CEC management consent.

The results (which preliminary comments indicate will be positive) are planned j for transmittal to the Director, Office of Nuclear Regulatory Research, in August 1986, following collection and collating of coments from 25 experts from CEC member nations.

FEB 14 E3 ENCLOSURE E

Y Publication to be Issued in the Near Future

Title:

Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit (Draft Regulatory Guide -

Proposed Rev. 2 to R.G. 1.114)

Description:

Describes a method for complying with the pertinent regulations on operators and senior operators in the control room of a nuclear power unit.

Contact:

F. H. Rowsome NRR Recently Issued Publications Draft Regulatory Guide and Value/ Impact Statement: Proposed Revision 2 to Regulatory Guide 1.99, " Radiation Damage to Reactor Vessel Materials".

Task ME 305-4. The second paragraph of the Introduction of this Draft Regulatory Guide explains the relationship of this proposed guide to the pressurized thermal shock rule. While comments and suggestions are encouraged in all areas, coments are specifically requested from licensees and the technical community on the technical merits of this proposal as a basis for calculating pressure-temperature limits. Licensees may also discuss the effects on calculated pressurized thermal shock risk at their plants if the reference temperature correlation in the pressurized thermal shock rule were replaced by the one proposed in this guide. Coments are requested by April 15, 1986.

Contact:

P. N. Randall (301-443-7711)

Regulatory Guide 1.105, Rev. 2 - Instrument Setpoints for Safety-Related Systems NUREG-ll59 - Training Manual for Uranium Mill Workers on Health Protection from Uranium ENCLOSURE E FEB 141986

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

I ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS FEEK ENDING FEBRUARY 14, 1986 i

International Meetings f The following interrational meeting notices supplement those previously l announced: l i March 10-14, 1986, Vienna, Austria - Working Party on Nuclear Fuel i CycleRequirements(WNPNFCR) i March 10-14, 1986, Vienna, Austria - Consultants' Meeting on IRS Generic 4 Safety Issues Identification i

. April 7-11, 1986, Vienna, Austria - IAEA Meeting of Advisory Group to Prepare Technical Guidance Document Entitled Maintaining On-Site Habitability During Accidents at Nuclear Installations April 7-11, 1986 Vienna, Austria - IAEA Seminar on Regulatory Inspection During Nuclear Power Plant Construction, Comissioning and Operation 1

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April 21-25, 1986, Vienna, Austria - IAEA Advisory Group Meeting to Complete Preparation of a Document on the Methodology for Source and Individual-Related Environmental Monitoring and Effluent Monitoring April 21-25, 1986, Vienna, Austria - Advisory Group to Prepare Safety 1

Series Recommendations on the Provision of Radiation Protection Services

] in Research Reactor Facilities i

4 May 26-30, 1986, Plzen, Czechoslovakia - Specialists' Meeting on Reactor Pressure Vessel 8ehaviour Under Transient Conditions Caused by Therr.al -

Shock i

May 26-30, 1986, Vienna, Austria - Advisory Group Meeting on Ouality i Assurance for Computer Software l May 26-June 6,1986, Yalta. USSR - Technical Comittee and Workshop on Fusion Reactor Design and Technology i June 2-5, 1986, Grenoble, France - Seventh Consultants' Meeting -

i Nuclear Structure and Decay Data (NSDD), Centre d' Etudes Nucleaires de Grenoble i September 10-12, 1986, Vienna, Austria - Consultants' Meeting - Sixth i Meeting of the Atomic and Molecular (A plus M) Data Centre Network

October 13-17, 1986, Vienna, Austria - Seminar on Radionuclide Generator

Technology i

ENCLOSURE G FEB 3 4 ?3 i

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2 Foreign Visitors On Monday Mr. E. Morris, Principal Inspector of the UK Nuclear Installations Inspectorate (NII), met NRR and RES representatives to discuss NRC's approach to and use of PRAs in regulation.

Monday through Wednesday Mr. Sakurama and Dr. Komata of the Japanese Nuclear Power Safety Infonnation Center (NUSIRC) met AE00 representatives to discuss the Licensee Event Report System and the Sequence Coding and Search System.

On Monday Mr. Lars Hoegberg, Deputy Director of Sweden's Nuclear Power Inspectorate (SKI), accompanied by Mr. Dick Weibahr, head of Forsnark reactor inspections office, met with NRR management and staff for discussions on Sweden's new1,i proposed severe accident protection regulations and other technical issues of BWR safety. In the afternoon they met with RES managemer.t and staff to discuss NRC research priorities in light of budget reductions.

On Wednesday Messrs. Hoegberg and Weibahr met with Comissioners Asselstine and Bernthal and Acting EDO Stello at H Street to discuss issues of mutual interest.

On Thursday the visitors met with Philadelphia Electric Company officials for a site visit to Limerick NPP.

On Friday they had further discussions with Peco officials and from there drove to Region I for discussions with Dr. T. Murley and other Region I staff.

Mr. Hoegberg lef t behind several Swedish reports which are being sent out for translation and subsequent distribution to appropriate NRC staff. One set of reports consisted of a utility-sponsored historical overview and lessons learned on the safety of operation of the Barsebaeck NPP, and SKI's review of that report. A second set of reports provided further details on the Swedish requirements to improve protection in cases of severe reactor accidents.

FEB 14 iS3$ ENCLOSURE G

REGION III STATUS REPORT ,

DAVIS-BESSE LOSS OF FEEDWATER EVENT FEBRUARY 14, 1986 Plant Status The plant remains in cold shutdown.

Restart Activities A NRR maintenance survey inspection team will be on site March 24-28 to ++

followup on previous findings and to evaluate the licensee's actions concerning management practices as they relate to the maintenance area.

MOVATS testing, environmental qualification work and other maintenance ++

activities continue on the 167 safety-related motor-operated valves onsite.

The licensee has completed all planned work on sixty two valves and returned them to service. Representatives from NRR visited the site this week to observe valve testing and to meet with the licensee to discuss the scope of the valve testing program. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.

The NRC test review team continues to provide weekly coverage of licensee ++

testing activities. Testing activities have accelerated with sixteen tests performed last week and the testing schedule is anticipated to continue at this level of activity until restart. Mode 1 is presently scheduled for

. April 28, 1986. The NRC test review team discussed five violations in an exit interview on February 13, 1986, which were identified by the licensee through their System Review and Test Program. These violations will be documented in Inspection Report 50-346/85039. Repairs and testing of the Incore Monitoring system is continuing. Testing of Emergency Diesel Generator 1-1 began this week, the licensee plans to complete this testing during the weekend. Further system testing awaits completion of equipment modifications.

Other Activities Inspections of safety system piping supports in the auxiliary building are continuing. Evaluation of the nonconformances (NCR) found on supports in containment is in progress. Of the support NCRs requiring disposition prior to restart, eighteen remain to be dispositioned.

The licensee has suspended their investigation of the cause of the restricted flow of water from Lake Erie to the plant. The investigation will continue when lake ice conditions are safe for divers. The flow has returned to normal.

The licensee's repair, replacement and engineering evaluation of items ++

requiring environmental qualification (EQ) is continuing. Inspectors from Region !!! and headquarters will be assisted by contract personnel in ENCLOSURE L performing an EQ audit from February 24 through February 28.

FEB 11 G

4 l

Davis-Besse Review Group The Nuclear Regulatory Commission has established an Ad Hoc independent review

. group to review issues arising out of the June 9, 1985, incident at the Davis-Besse

Nuclear Power Plant. The purpose of this review group is to identify additional lessons that might be learned from the incident, and from these to make i recommendations to improve the NRCs internal procedures and the regulation of

! power reactors.

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ENCLOSURE L FEB 141986 l

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ITEMS ADDRESSED BY THE COPNISSION - WEEK ENDING 2/14/86 A. STAFF REQUIREMENTS - BRIEFING BY INPO, 10:00 A.M., THURSDAY, JANUARY 23, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello dated 2/10/86 The Commission met with representatives of the Institute for Nuclear Power Operations (INPO) for a briefing on INPO pregrams ,

and activities.- The following representatives of INPO were in attendance Zack T. Pate, President Institute of Nuclear Power Operations (INPO)

Kenneth A. Strahm, Vice President and Director Training and Education Division INPO and Executive Director National Academy for Nuclear Training Walter Coakley, Manager of Accreditation INPO Stephen L. Rosen, Vice President and Director Analysis and Engineering Division INPO INPO promised to provide to the Commission information on the o chloride erosion process and data on INPO's rating of plant performance programs. During the discussion on NRC's use of INPO's Nuclear Plant Reliability Data System (NPRDS) , Commis-sioner Asselstine requested that the staff review the data available on check valve failures.

(AEOD) (SECY Suspense 4/1/86)

B. STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTF, 2:00 P.M., THURSDAY, FEBRUARY 6, 1986, COMMISSIONERS' CONFERENCE R00ti, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello, H. H. E. Plaine, John E. Zerbe, C. Kammerer, and J. Fouchard dated 2/14/86 I. SECY-86-17 -- Final Rule, " Limitation on the Use of Highly Enriched Uranium (HEU) in Research and Test Reactors" The Commission, by a 5-0 vote, approved a final rule that amends the regulations to limit the use of highly enriched uranium fuel in domestically licensed research and test reactors.

The amendments generally require that newly licensed non-power reactors use low enriched uranium fuel and, contingent on Federal Government funding, that licensees of existing non-power reactors replace HEU fuel with LEU fuel acceptable to the Commission.

ENCLOSURE O FEB 141986

e B. CONTINUED Chairman Palladino and Commissioner Asselstine have additional views to be incorporated in the Federal Register Notice. The Commission has also agreed that the backfit rule should not be applied to this amendment of the regulations which relates only to non-power reactors.

You should make the editorial changes noted by the Chairman in i his vote sheet, make any necessary format changes that Rules and Records recommend for compliance with Federal Register procedures, incorporate the additional views of the Chairman and Commissioner Asselstine, and forward the package for signature and publication in the Federal Register.

(OPE /OGC) (SECY Suspense: 2/28/86)

The appropriate Congressional committees should be advised and' a public announcement made.

(OCA/OPA) (SECY Suspense: 2/28/86)

II. SECY-86 Review of ALAB-826 (In the Matter of Metro-politan Edison Company The Commission, by a 5-0 vote, approved an order indicating that the Commission decided that review of ALAB-826 is not -

warranted. The Commission order also provides comments on the Licensing Board's conclusions regarding the INPO accreditation program and notes that with this order the TMI-1 restart administrative proceeding comes to a close.

(Subsequently, the Secretary signed the order on February 6, 1986.)

The Commission also directs the staff to discuss with INPO the questions raised by the Board in regard to INPO failing to comply with its own criteria during the accreditation of the TMI-1 program and report back to the Commission on the results of the discussion.

1EDor (NRR) (SECY Suspense 3/28/86)

Attachments: . nxA awacked As stated FEB 141986 ENCLOSURE 0

NRR MEETING NOTICES

• FEBRUARY 14, 1986 u

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DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 2/20/86 50-219 Oyster Creek Discuss the status of licensing GPUNC/NRC J. Donohew 10:30 a.m. Plant Site actions for the plant with Forked River, plant personnel.

New Jersey 2/20/86 50-275 Room 6507 Discuss seismic structural issues PG&E H. Schierling 9:00 a.m. 50-323 MNBB regarding the proposed spent fuel pool reracking and structure for Diablo Canyon Units 1 and 2.

2/20/86 -

P-Il4 Discuss new design changes to ASEA-ATOM L. Phillips 9:30 a.m. Phillips Bldg. ASEA-ATOM control blades for US BWRs, supporting exposure results and the details of the proposed confirmatory surveillance program.

2/26/86 50-424 P-118 Meeting on Vogtle Safety Parameter Georgia Power Co. M. Miller 8:30 a.m. 50-425 Phillips Bldg. Display System (SPDS) and detailed & Southern Co.

control room design review (DCRDR). Services 2/26/86 50-219 Oyster Creek To tour the station site. GPUN J. Donohew 8:30 a.m. Plant Site Forked River, Eg New Jersey P

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o 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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NMSS M ETING NOTICES

[ FOR WEEK ENDING: 2/15/86 Division of Fuel Cycle and Material Safety T*,

DOCKET ATTENDEES /

DATE/ TIE NUISER LOCATION PURPOSE APPLICANT NRC CONTACT h rch 4-5, 1986 Arlington, TX Conduct the httonal Program D. Chape11 (FC) Chape11/Cobb Review of Region IV's decen- L. Cobb (IE) tralized material licensing J. Hickey (FC) activities & inspection activites.

N rch 6-7, 1986 Walnut Conduct the htional Program D. Chape11 (FC) Chape11/Cobb Creek, CA Review of Region V's decen- L. Cobb (IE) tralized material licensing J. Hickey (FC) activities and inspection activities.

Nrch 3,1986 Livermore, Participate in DOE Transportation C. N cDonald (FC) mcdonald 9:30-12:30 CA Packaging Workshop.

DIVISION OF WASTE MANAr.DtENT 2/27-3/1 Chicago, Illinois International Symposium on REBrowning SRomano Alternative LLW Technologies 3/2-6 Tucson. Arizona iM '86 Conference JKennedy University of Arizona REBrowning -

SCoplan 3/3-7 Department of Energy Mtg IAEA Symposium on Siting. Design JKennedy JKennedy in Hanover Germany Construction of Underground Repositories m

5 DIVISION OF SAFEGUARDS E

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33 RII MEETING NOTICE

'd DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 02/19/66 RII Office Enforcement Conference Licensee and Selected Walker 10:00 am Brunswick Facility RII Staff Members 02/20/86 RII Office MP&L Management Meeting Same as above Walker 10:00 am E

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