ML20137D546

Weekly Info Rept for Wk Ending 850816

ML20137D546
Person / Time
Issue date:	08/16/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850816, NUDOCS 8508220509
Download: ML20137D546 (37)

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For: The Commissioners .,

From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING AUGUST 16, 1985 A summary of key events is included as a convenience to those Commissioners 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 I Executive Legal Director F*

International Programs G State Programs H Resource Management I*

Analysis and Evaluation of Operational Data J .

Small & Disadvantaged Business Utilization & Civil Rights K*

Regional Offices L*

CRGR Monthly Report M* -

I' 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.

& , r T.A.Rehm,AssistantforOpera(i.ons Office of the Executive Director:

for Operations

Contact:

T. A. Rehm, ED0 492-7781 8508220509 850816 PDR COMMS NRCC WEEKLYINFOREPT PDR

i* HlGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING AUGUST 16, 1985 f' Waterford In an internal memorandum published earlier this year LP&L announced an austerity program within the company designed to reduce operating costs and overhead and increase efficiency. At the staff's request, LP&L has. formally i placedonthedocketaclarificationoftheausterityprogram'sefffeton ,

Waterford 3. In this submittal, LP&L states that the program has not and i will not adversely impact the safety of Waterford 3, compliance witif NRC regulations or meeting regulatory requirements. LP&L further assured the

' staff that established programs and comitments, such as the plant-specific simulator, have not been decreased in scope nor have their schedules been i extended.

EPA Plan to Develop Residual Radioactive Contamination Criteria

-The Acting Assistant Administrator of EPA for Air and Radiation has responded affirmatively to NRC's requests to develo Federal guidance on the establishment of residual radioactivity limits for lands, facilities, equipment, and materials to be released on an unrestricted basis. RES has been advised by EPA that it 61ans to develop such guidance on a " vigorous" basis and would welcome NRC's participation.- Criteria to be developed include: criteria for release of land.

i and buildings from deconsnissioned facilities; criteria for recycling ,

, contaminated materials and equipment without restrictions; and criteria for

- designating low-level waste streams as having radioactivity levels that are . '

"below regulatory concern." As a first step in this cooperative effort EPA =

staff has provided NRC staff with a draft development plan and a draft advance notice of proposed rulemaking (ANPR) for establishing Federal guidance on criteria and/or a methodology for establishing requirements for cleanup of land and facilities associated with decommissioning a facility. These drafts were

provided for NRC review and comment in conjunction with recent meetings between EPA and RES staff to explore and discuss ways of cooperating and working together to expedite the development of this Federal guidance. EPA statf plans '

- to publish the ANPR in the Federal Register later this year to obtain public coments. -

Nuclear Fuel Services (NFS) Erwin

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On May 15, 1985, the Oil, Chemical and Atomic Workers Union (OCAW) at the

- Nuclear Fuel Services (NFS) Erwin facility went on strike. Since the strike started, ocly limited operations have been conducted at the facility using trained salcried personnel. By letter dated July 16, 1985, and its supple-ment dated Jsly 22, 1985, NFS submitted their " Planning Guidelines for the Period of Reduced Operations." These Guidelines describe additional produc-tion operations which NFS wishes to perform using salaried personnel. After ,

the NRC staff's evaluation of the Guidelines, NFS was informed, by letter dated Augur,t 14, 1985, that NRC has no objection to this expanded operation.

Super Compactor License Issued by Tennessee On August 7, 1985, the State of Tennessee issued a license to a Tennessee company, Scientific Ecology, to operate a comercial compactor f.acility.

The licensee's operations will be located at Clinch River Industrial Park, Lot 5 in Oak Ridge Tennessee. The license authorizes receipt, processing, storage and. transfer of materials and items as radioactive waste. Processing includes opening, sorting, compaction and repackaging of waste in a form suitable for transportation and burial. The compactor, which was custom built,is capable of 1 million pound per square inch. The licensee is limited to 180 days of storage at their facility.

AUG 161985

OFFICE OF ADMINISTRATION Week Ending August 16, 1985 .

ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT- !' '

STATUS OF REQUESTS .

Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 575 32 Granted 447 24 Denied 120 13 Pending 187 18 _,

ACTIONS THIS WEEK Received Susan Grossberg, Requests, on behalf of New England Coalition on Nuclear.

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Harmon, Weiss & Pollution, records relating to the August 13-17 and 2-7-31, Jordan 1984 NRC inspection of the facility at Set. brook, New "

(85-560) Hampshire (Inspection Report No. 50-443/E4-12 and 50-444/

84-06).

Edgar Tiffany Requests records outlining American involvement with the (85-561) Vietnan Atomic Energy Office, 1961-1975.

Lyle Graber, Requests a copy of SECY-85-103. .

NUS Corporation (85-562)

Michael R. Deane, Requests copies of subsequent versions of " Severe  !

NUS Corporation Accident Research Program" dated November 1984.  !

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(85-563)

Dona DeZube, Requests all correspondence the NRC has~ received during The Sentinel the past two years from Representatives Michael Barnes, (85-564) Beverly Byron and Maryland Senators Paul Sarbanes and Charles Mathias.

Richard A. Sloan, Referral from the Is0J of one record regarding the Phillip C. industrial gas industry.

Goldstick &

Associates, Ltd. -

(85-565) -,

l Derwin Weldon,

_r i Requests correspondence concerning EAD Metallurgical Doc-Search Inc., from April 1, 1985.

Associates (85-566)

CONTACT: J.M. Felton ENCLOSURE A 492-7211 AUG 161985

2 Received, Cont'd Patrick Neel Requests four categories of records under DOE's (85-567) authority and information on the PG&E nuclejr power plant at Diablo Canyon. .

(NRC employee) Requests records relating to an allegation tf (85-568) misconduct. ,

Charles Barnes Requests all records in Docket 40, SUA-809, Colorado (85-569) Ventures, Inc., and 40, SUA-797, Oregon Pacific Industries.

Jim Pedro, Requests a copy of " LWR Standardized Plant Design NUS Corporation Evaluation -- Generic Safety and Licensing Issues,"

(85-570) interim and final report.

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_ Ophelia G. Williams, Requests records containing qualificications, background, J/R/A Associates experience, biographical sketch, etc. about an NRC (85-571) employee.

Ellyn R. Weiss, Requests a copy of an ACRS letter of July 1985 .

Union of Concerned to the Commission related to the ACRS position on the .

Scientists Commission's policy on safety goals. .

(85-572',

Susan B. Bevill, Requests four categories of records pertaining to Balch & Bingham allegations by Shannon Doyle regarding the Farley (85-573) nuclear power plant.

Vincent Clark, Requests copies of licenses issued to Brandhurst, Inc.,

Delta of Danbury, Connecticut, and Safety Light Corp. of .

(85-574) ,

Bloomsburg, Pennsylvania.

(NRC employee) Requests records relating to Vacancy Announcement No.

(85-575) 85-2087-5.

T Sylvia Tognetti, APPEAL TO THE COMMISSION for the release of one denied Christic Institute record regarding the Supreme Court decision in Silkwood (85-A-32-85-456) v. Kerr-McGee.

Granted Steven C. Sholly, In response to a request for all records concerning the Union of Concerned probabilities, consequences, impacts and magnitudes of Scientists in-vessel /ex-vessel steam explosions occurring during (85-448) core meltdown accidents at light water reactor power

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plants, made available 99 records. ..

Kenneth 0. Young, Inresponsetoarequestformachinereadablecopiesof Westlaw Services, NRC Decisions from 1975 to date, informed the requester Inc. that the NRC does not have the NRC Decision's in machine (85-458) readable tapes from 1975 to June 1981. However, informed the requester that those Decisions are publicly available on AUG 16198,a microfiche and in hardcopy at the PDR.

ENCLOSURE A

3 Granted, Cont'd Anthony L. Kimery In response to a request for three categories of (85-502) records related to Kerr-McGee's Cimmaron and Sequoyah facilities and copies of the NRC's regul4tions in the Code of Federal Regulations, infomed the r'e quester that these records are already available at the PDR.

Richard A. McCormack, In response to a request for a list of attendees at The Energy Daily the Nuclear Reactor Decommissioning Planning Conference (85-530) held on July 16-18, in Bethesda, Maryland, made available a copy of the requested list.

Jonathan L. Alpert, In response to a request for.any records pertaining to Fowler, White, NRC's quality assurance / quality control program regarding Gillen, Boggs, Rinker Materials Corporation, infonned the requester that Villareal and. the NRC has no records subject to this request.  ;

Banker, P.A.

(85-533)

Scott W. Morgan, In response to a request for computer printouts of ,

~Rawle & Henderson publicly available records on the Apollo facility,

. (85-537) Docket 70-364, and the Parks Township facility, Docke_t '70-135, made available copies of the requested printouts.

W.F. Lawless, In response to a referral from the DOE of one record Paine College regarding management of defense transuranic (TRU) wastes, (85-543) made available a copy of the requested record.

Rod Buckles, In response to a request for copies of (1) memorandum NUS Corporation from Engelken to Denton regarding startup testing at '

_ (85-544) San Onofre, Unit 3, dated March 15,1983, and (2) memorandum from Engelken to DeYoung regarding startup testing at San Onofre Unit 3, dated March 13, 1983, made available a copy of item 1. Informed the requester that the NRC could not locate a copy of item 2. -

Steven C. Sholly, In response to a request for copies of a report by Sandia Union of Concerned National Laboratories, "ASEP Plant Survey and Initial Scientists Plant Grouping Letter Report," and all other versions of (85-545) the report, made available copies of two reports.

Billie P. Garde, In response to a request for all records relevant to Government and/or generated in connection with all communications Accountability between Harold Denton, William Dircks, and Victor Stello Project regarding Comanche Peak, made available three records.

(85-547) ,,

Jim Pedro, In response to a request for a copy of the praft NUS Corporation Regulatory Guide regarding the implementatibr of the ECCS (85-550) proposed rule mentioned on page 2 of Enclosure E of the Weekly Report to the Commission dated April 26, 1985, made available a copy of the requested record.

AUG 161985 ENCLOSURE A

Granted, Cont'd John J. McCaffrey, In response to.a request for 11 listed records New York Public regarding spent fuel and transportation, informed Interest Research the requester that three records are already Group available at the PDR and the remaining recairds (85-551) are available for purchase through NTIS. ,' [

Denied .

. Steven B. Litzell, In response to a request for four categories of Software AG records related to Request for Proposal (RFP) RS-(85-469) ORM-85-312, made available one record. Denied one record in its entirety and portions of one record, containing information created and considered during the deliberative process of evaluating proposals, forming and exchanging opinions, and making recom-mendations concerning contract award. .

e Michele O'Mealia, In response to a request for the August 23, 1984, Doc-Search Regulatory Guide (CE-306-4), " Standard Format and

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Associates Content for a Topical Safety Analysis Report for a Dry (85-495) Spent Fuel Storage Cask, denied this report in its *

, entirety since it was intended only for purposes of .-

internal review prior to establishing the agency's  ;

position and has been subject to review and revision.

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AUG 161985 ENCLOSURE A

. . WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING AUGUST 16, 1985  :

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PROPOSALS UNDER EVALUATION ,

RFP No. : RS-NRR-85-054

Title:

" Development of an NRC Simulation Facility Evaluation Progr.am"

Description:

The contract objectives are to develop, refine and validate criteria and methodology for the review of nuclear power 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 conduct of actual simulation facility reviews and preparation of detailed recommendations.

Period of Performance: 14 months with an option for an additional 6 months. -

_ Sponsor: Office of Nuclear Reactor Regulation '

. Status: Best and Firdi offers due on August 19, 1985.

RFP No. : .RS-NMS-85-007

Title:

" Facility Systems Analysis Support" -

Description:

Provide technical support in the form of reports, analytical, ,

2 and engineering experience to fully implement the regulatory effectiveness review program for all power plants.

Period of Performance: 24 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: Negotiations were reopened on August 14, 1985. Best and Final offers due on August 23, 1985.

CONTRACT CLOSED-0VT

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NRC-33-83-461 . Intel Systems Corporation ADMINISTRATIVE MATTERS

((~ 1. A protest was filed by Alderson Reporting on August 12, 1985, against

. award under IFB No. RS-ASB-85-401, " Stenographic Reporting Services."

The protestor contended that NRC had no authority to require a bid guarantee which exceeds the amount required for the performance bond.

The protestor also asserted that the term " bid price" in the solicitation was ambiguous and that requirement for a bid guarantee unnecessarily limited competition. Additionally, the protestor requested an extension to the bid opening date. Based on a review of these issues, the Contracting Officer.(CO) determined that an extension to the date for receipt of bids was not warranted. The bid opening was held on August 13, 1985. On August 15,1985, the C0 issued a decision denying the protest stating that the bid guarantee and performance bond were necessar} to protect the governments interest and solicitation terms were clegly defined and not unduly restrictive. Award was made to Ace-Federal Reporters, Inc. on August 15, 1985.  ;

ENCLOSURE A AUG 161535 i

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J Divisien of Contracts Weekly Information Report ADMINISTRATIVEMATTERS(cont'd) .-

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2. On August 14, 1985, a second protest was filed against IFB No.:,RS-ASB-85-401.

Ann Riley & Associates alleged that the bid submitted by Ace-Federal Reporters, Inc. was materially unbalanced and should be rejected as nonresponsive. On August 15, 1985, the Contracti.ng Officer issued a decision denying the protest. Award was made to Ace-Federal Reporters, Inc.

on August 15, 1985.

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1F ENCLOSURE A AUG 161985

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST ., i

t-Week Ending August 16, 1985 -

GESSAR II On August 9,1985, in accordance with the Comission's newly-published severe accident policy statement (50 FR 32138), the Office of Nuclear Reactor Regulation issued Amendment No. 1. to Final Design Approval FDA-1 for General ~.

Electric Company's GESSAR II design to be referenced in new construction ,

permit and operating license applications.

Amendment No. I to FDA-1 makes GESSAR II the first nuclear power plant design to be suitable for referencing in new construction permit applications since .

the THI-2 accident. ,

It should be noted that the staff is nearing the completion of its review of the GESSAR II design for the Comission's severe accident concerns. At the completion of that review FDA-1 will be further amended to reflect the results of that review.

Limerick On August 9,1985, the Delaware River Basin Comission (DRBC) approved the ,

Philadelphia Electric Company application to the DRBC for authorization to re-allocate to Limerick that Schuylkill River water currently allocated to an oil and a coal fired plant. This is expected to enable the Limerick plant to continue its startup test program for several weeks, i.e., up to 20-25% of 7 rated power. -

~ Waterford In an internal memorandum published earlier this year, LP&L announced an austerity program within the company designed to reduce operating costs and overhead and increase efficiency. At the staff's request, LP&L has formally placed on the docket a clarification of the austerity program's effect on Waterford 3. In this submittal, LP&L states that the program has not and will not adve; sely impact the safety of Waterford 3, compliance with NRC regulations or meeting regulatory requirements. LP&L further assured the staff that established programs and comitments, such as the plant-yecific simulator, have not been decreased in scope nor have their schedules b~een extended. _j i-ENCLOSURE B AUG 161985

Diablo Canyon Unit 2  ; .

The applicant advised the staff today that he plans to initiate rbd* withdrawal and bcron dilution for Unit 2 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, Wednesday, August 14 1985.

Criticality is expected in 12 to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. Although his schedule for exceeding 5% power was not stated, based on his previous schedule he would be ready to exceed 5% power around August 24, 1985.

Midland Plant, Units 1 and 2 By letter dated August 9, 1985, to the ASLAB, Mr. M. Miller, Esq. of Isham, Lincoln and Beale transmitted the Tax Plan of Consumers Power Company regarding-the Midland Plant. The letter and plan notes that after August 24, 1985, the '

company expects to in niate steps to claim an abandonment loss in 1985, for tax purposes, of the process steam equipment, systems and facilities which could only be used to produce and deliver process steam to Dow.

With respect to minimizing its tax liability in 1986 and thereafter, the plan -

notes

" ...the Company has basically five options...; (1) offset its tax  ;

liability with non-Midland ITC., (ii) abandon portions of the Midland Project, such as Midland Unit 1, (iii) abandon the Midland Project as a whole,.(iv) sell the Midland Project, or (v) sell or abandon other assets. The Company believes that abandonment of the Midland Project as a whole can be accomplished by.

taking certain appropriate steps which will result in a tax loss to the Company of approximately $2.6 billion. However, the possibility of abandoning only Unit 1 or some other assets is still under study, and the Company may request an IRS ruling ~or rulings on this. -

In addition, the Company is considering proposing legislation that would allow a tax loss on the Midland Project without requiring action that would render the plant useless. The Company will decide before October 1 of each year what _

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actions it will take to minimize taxes." -

-Arkansas Nuclear One, Unit No. 1 (ANO-1)

At 4:16 pm, Sunday, August 11, 1985, ANO-1 tripped on an anticipatory trip of loss of feedwater. The The "B" Main Feedwater (MFW) pumpplant tripped was at offapproximately on a signal of98% power thrust bearing at the time.

wear.

The "A" MFW pump then tripped because of the Reactor-Protection System received a signal of low pressure from the MFW pump "A." The Emergency Feedwater (EFW) system actuated normally. The operators manually initiated High Pressure Injection for about 30 seconds (150 to 200 gallons) when pressurizer level went below 40 inches (this is normal procedure). The licensee is repairimg. the MFW pump bearing, checking the pressure switch of the "B" MFW pump, andscorrecting a secondary leak in a flange connection of a hand hole of a steam-generator.

The licensee should be able to start up later today. - F ENCLOSURE B AUG 161985

Limerick 1 7

At about 1:00 am on Saturday, August 10, 1985 Limerick Unit 1 exceeded the 5%

power level for the first time. At 2:55 pm, Monday, August 12,1985, with the reactor at about 6% power, the MODE switch was placed in the RUN position for the first time.

The plant achieved 10% power at 9:00 pm on Monday, August 12, 1985 where it has been stabilized while running tests for the feedwater controller, IRM/APRM overlap, and the turbine electro-hydraulic control pressure regulator. The licensee anticipates rolling the turbine about August 15, 1985.

Millstone 1 The Millstone 1 period of 374 days of continuous operation at rated power level',

ended at 12:07 pm Tuesday, August 13, 1985 while placing a regenerated -

demineralizer (RWCU) back in service. The reactor scramed due to a high steam line radiation signal (i.e., radiation signal 7 times greater then normal).

Typically the radiation level at the steam line monitors in the steam tunnel ,

increases (spikes) from 300 mR/hr to 450 mR/hr when placing a demineralizer

. back in service. On this occasion, the radiation signal reached 1800 mR/hr. _ ~

The spike typically results form N u formed from the oxygen in the entrapped air within the regenerated deminerdTizer (imperfect venting of the demineralizer after regeneration and prior to return to service).

Post trip chemistry confirmed no unusual activity in the primary coolant. The plant transient was normal, i.e., all rods scrammed, no ECCS challenges, etc.

Normal recovery is underway: the plant is in the process of start up (3 pm, ,

_ August 13, 1985).

University of Michigan

_On July 29, 1985, the Office of Nuclear Reactor Regulation issued a 20 year . -

~ renewal of the Class 104 Facility Operating License R-28 for the University of Michigan (UM) reactor.

, The UM reactor is a heterogeneous pool-type reactor using the recently -

l developed Low Enriched Uranium (LEU) plate-type fuel. The reactor, licensed for a thermal power level of 2MW, is utilized for teaching students and power reactor operators, and for experiments.

Wolf Creek Approximately 6:15 pm on August 12, 1985, Kansas Gas and Electric!s-Wolf Creek Generating Station completed its 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> continuous warranty run af 100% power.

This continuous run is part of the 250 hour0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> full power operation th p must be completed before the unit can be declared commercially operational.g. ,

The fuel load and low power license was issued on March 11, 1985 and the full power license was issued on June 4, 1985.

ENCLOSURE B AUG 161:s5

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I Three Mile Island Nuclear Station, Unit No. 2 On August 13, 1985 the Director of HRR, the Region I Administrator (nd members of their senior management staffs met with Lancaster, Pennsylvanii Mayor Arthur Morris who serves as Chairman of the NRC's Advisory Panel for the Decontamination of TMI Unit 2. The purpose of the meeting in Lancaster was to discuss recently announced changes in NRR's organization and NRC's continuing role in regulatory oversight of the TMI-2 cleanup.

Mr. Denton, Dr. Murley and their staffs later made an entry into the TMI Unit 2 Reactor Building to observe general cleanup progress and to view recently installed equipment which will be used in defueling the reactor.

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ENCLOSURE B 6 1965

NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT f

WEEK ENDING AUGUST 16, 1985 ..

1. PLANT STATUS The facility remains in long term cold shutdown with the 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 top ofthe~ 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).

Calculated reactor decay heat is less than 12 kilowatts.

RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 70*F to 91'F with an average of 80*F. Average cold leg temperature is 56*F. -

The average reactor building temperature is 57*F. The reactor building airborne activity is 1.6 E-7 uCi/cc Tritium and 5.5 E uC1/cc particulate, predominantly Cesium 137.

2. L'ASTE MANAGEMENT T The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this period.

Total volume processt.d through SDS to dcte is 2,963,375 gallons, and the total volume processed through EPICOR II is 2,547,671 gallons.

Preparations are being made to transfer the contents of condensate L tank 1A (C0T-1A) to EPICOR II. The tank will be desludged and used  :

as a storage tank for borated makeup water. l l

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1 AUG 161985 ENCLOSURE B l

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3. DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281':livel of the Auxiliary Building.  : i.

Average general area radiation dose rate is 40 mrem pEr; hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building. -

4. ENVIRONMENTAL MONITORING EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, HRC requirements, and the City of Lancaster Agreement.

TMI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite

- samples taken from July 27, to August 3,1985. Gamma scans detecte'd no reactor related radioactivity.

The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consists of a

__ seven day composite sample taken from July 28 to August 3,1985. A.

gamma scan detected no reactor related radioactivity. .

The NRC outdoor airborne particulate sampler at the TMI Site -

collected a sample between August 7 and August 15, 1985. No reactor

. related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES Installation of the rotating work platform and service platform .

(over the reactor vessel) has been completed.

Equipment was staged into the reactor building and installation is almost complete on the cable management system.

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Installation of tool racks for defueling tools continues.

Defueling Water Cleanup System (DWCS) preoperational testing T continued this week. On August 14, 1985, a hose connection

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separated, spilling 3,000. gallons of water from the test rig to the reactor building basement. The portion of the DWCS being tested used the fuel transfer canal (FTC) as its water source. The FTC level dropped 10 inches as a result of the spill. No environmental releases nor increases in reactor building radiation levels resulted from the event. The FTC water level was restored by transferring water from the borated water storage tank.

6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES _

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Installation of the DWCS continued. Partial DWCS turnoter for processing RCS during early defueling is scheduled to_b( completed in late August. - V The first of four fuel canister racks are on site with further deliveries scheduled through August.

AUG 161985 ENCLOSURE B

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7. REINSTATEMENT OF WASTE BURIAL IN WASHINGTON STATE On Friday, August 16, 1985, GPU Nuclear's burial privileges at Hanford, Washington were restored. The suspension, involving three.m drums, was reported in the August 12, 1985 Weekly Status Ripe rt.{sclassifie.d

-The waste burial permit was reinstated after Washington State officials reviewed GPU Nuclear's corrective actions. ..

8. NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.

Recovery Operations Plan Change numbers 29, 31, 32, and 34.

Fuel Canister Technical Evaluation.

Fuel Handling Senior Reactor Operator Training Program .

Defueling Safety Evaluation.

Application for seismic exemption.  ;

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9. PR0JECTED SCHEDULE OF FUTURE EVENTS Start of Defueling: October.1985

10. PUBLIC MEETING ,-

The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 11, 1985. The meeting will be at the Environmental Matters Committee Room (Room 160), House Office Building, College Avenue, Annapolis, Maryland from 6:00 to 9:00 PM. The purpose of the meeting is to inform the public of progress being made in the TMI-2 cleanup and to allow the public to voice concerns and make comments on any aspects of the cleanup. The status of the processed ,

_ water will also be discussed.

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ENCLOSURE B AUG 161985

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS -

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'6 Items of Interest  ;.[ l Week Ending August 16, 1985 -

Near Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 114(e) of NWPA Action: NRC received DOE Draft Project Decision Schedule on July 18, 1985.

Status: DOE requested NRC comments by September 13, 1985. Staff comments '

are currently being transmitted to the Commission for their approval' and transmittal to 00E.

Section:

114(e) of NWPA Action: The DOE's Mission Plan and draft Project Decision Schedule state

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2 that DOE will make the preliminary determination on site suitability at the time of site nomination and recommendation.

Status: NRC concurrence with DOE Siting Guidelines contained an agreement-between the two agencies concerning the timing of the preliminary determination. The Commission is currently considering its options.

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Hearings before the Senate Subcommittee on Nuclear Regulation are tentatively scheduled for October on this issue.

Monitored Retrievable Storage On August 6, 1985, Mr. Roger Hilley, Associate Director for Storage and Trans-

! ._. portation Systems, Office of Civilian Radioactive Waste Management, DOE, and -

l . members of his staff presented a briefing on the status of the MRS project. -

This project is being conducted by DOE under provisions of the Nuclear Waste Policy Act. Representatives from NMSS, RES, IE and ELD were present. The l status of the MRS proposal, which is to be submitted to Congress by DOE on l January 15, 1986, was reviewed, including need and feasibility, the relation-ship of the MRS to the repository under the integrated concept, transportation l aspects and site selection. The conceptual designs for the MRS receipt, j handling and storage facilities at the proposed Clinch River (Tennessee) site were described. The DOE schedule for delivery of the completed proposal j to NRC and EPA for comment is December 2, 1985.

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_E i-I ENCLOSURE C i

AUG 161985

Sequoyah Fuels Corporatica OnAugust6and7,1985,rembersofSequoyahFuelsCorporationandfKerr-McGee Corporation met with representatives of HMSS to discuss license co ditions proposed by the NRC staff related to environmental protection and ther licensing issues. The issues discussed included action levels for investi-gation of effluent treatment systems, the objectives of groundwater monitoring in the area of treated raffinate storage, unrestricted release of treated raffinate, and stabilization of a previously used burial area.

On August 8, 1985, a Memorandum and Order for Notice of Informal Hearing and Opportunity to Become a Party was issued (ASLBP No. 85-513-03-ML, 50 FR 32128) in response to petitions for a hearing filed by the Native Americans for a Clean Environment Client Council, the Cherokee Nation, and Citizens Action for a Safe Environment. The hearing will consider issues and contentions related -

to an amendment application to Source Material License SUB-1010 filed by '

Sequoyah Fuels Corporation (SFC) for construction and operation of a facility to convert depleted UFs to UF4 . The proposed facility would be operated by SFC at Gore, Oklahoma.

Nuclear Fuel Services (NFS) Erwin ,

On May 15, 1985, the Oil, Chemical and Atomic Workers Union (0 CAW) at the Nuclear Fuel Services (NFS) Erwin facility went on strike. Since the strike started, only limited operations have been conducted at the facility using.

trained salaried personnel. By letter dated July 16, 1985, and its supple-ment dated July 22, 1985, NFS submitted their " Planning Guidelines for the Period of Reduced Operations." These Guidelines describe additional produc-tion operations which NFS wishes to perform using salaried personnel. After

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the NRC staff's evaluation of the Guidelines, NFS was informed, by letter '

dated August 14,.1985, that NRC has no objection to this expanded operation.

Orders Implementing EPA's Mill Tailings Standards

._ Eleven of the thirteen licensees who were ordered to comply with certain of

. the ground-water monitoring requirements of EPA's standards in 40 CFR 192 have requested hearings. The Uranium Recovery Field Office (URF0) issued the orders July 19, 1985. The bases for the hearing requests included:

1) procedural aspects of cited sections of the Atomic Energy Act, 2) views that the EPA standards are invalid since they are not general environmental standards, 3) lack of independent cost benefit analyses by NRC on the standards,

4) NRC's failure to conform its rules in 10 CRF 40 to the EPA standards, and

5) insufficient basis for the orders being immediately effective.

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i Alternate Concentration Limit (ACL) Methodology Information Exchange On August 13, 1985, NRC and EPA technical staff met as part of the! continuing information exchange and coordination on ACL methodologies. The;pirpose of the meeting was to discuss the status of each agency's work and comments on draft methodologies each agency has prepared. The methodologies are a part of imple-mentation of EPA standards. If a mutually acceptable methodology (ies) can be developed, the methodology is expected to eliminate the need.for EPA concurrence in site specific ACL decisions by NRC currently called for in EPA's mill tail-ings standards in 40 CFR 192. NRC considers such~ site specific concurrence outside EPA's authority. Based on the work to date, no obstacles exist that would preclude eventual development of mutually acceptable methodologies. The next meeting is tentatively planned for early October!

EPA HLW Standard

• EPA staff informed NRC staff that Administrator Thomas signed'the final EPA HLW standard (40 CFR Part 191) August 15, 1985, and it-was sent to the Federal Register. A staff paper informing the Commission of the content of the final ,

standard and of the resolution of NRC's earlier comments on the proposed "

. standard has been provided to the Commission (SECY-85-272). -

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AUG 161985 ENCLOSURE C 1

OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending August 16, 1985 if-

1. -The following Significant Enforcement Actions were taken durin$ the past week: -

a. EN 85-54, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $64,000 was issued to GPU Nuclear Corpora-tion (TMI Unit 2). This action is based on a violation involving acts of discrimination against a contractor employee for raising safety concerns associated with the TMI-2 polar crame refurbishment in 1983.

b. EN 85-55, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $64,000 was issued August 13, 1985 to Duke -

Power Company (Catawba Units 1 & 2). This action is based on alleged' discrimination against an employee for engaging in a protected activity. The Atomic Safety and Licensing Board, during an operating licensing proceeding, found that a quality control welding inspector

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at the Catawba Nuclear Station, Clover, South Carolina was poorly

• rated in his 1982-83 performance appraisals because of his and his -

- crew's expression of nuclear safety concerns to management. This 15 a violation of 10 CFR 50.7.

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

a. PNO-TMI-85-07, GPU Nuclear Corporation (TMI Unit 2), Water Spill During DWCS Test.

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b. PNO-II-85-77, Virginia Electric & Power Company (Surry Unit 1),

Unscheduled Shutdown Greater Than 48 Hours.

! --- c. PN0-II-85-78, Tennessee Valley Authority (Sequoyah Unit 1), Leading _

. Primary Coolant Sample Line. -

I d. PN0-III-85-67A, Detroit Edison Company (Fermi Unit 2), Temporary Halt

! to Low Power Testing (Update).

e. PN0-IV-85-390, Western States Company (Evanston, WY), Apparent Over-exposure of Two Radiographers (Update).

f. PNO-IV-85-41, Kansas Gas & Electric Company (Wolf Creek), Potentially Generic Hardware Problems at the Wolf Creek Generating Station.

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, g. PN0-V-85-53, Pacific Gas and Electric Company (Diablo Canyon Units .

& 2), Auto Accident / Grass Fire.

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l l AUG 161985 ENCLOSURE D l

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

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a. IE Information Notice 85-42, Loose Phos Badge Thermoluminescent DosimeterElements (TLD)phor in Panasonic 800 Series was issued August 12, 1985 to certain materials and fuel cycle licensees who may use the subject TLDs.

b. IE Information Notice 85-68, Diesel Generator Failure at Calvert Cliffs Nuclear Station Unit I was issued August 14, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

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c. IE Information Notice 85-69, Recent Felony Conviction for Cheating on' Reactor Operator Requalification Tests was issued August 15, 1985 to '

all nuclear power reactor facilities holding an operating license or a construction permit, all NRC licensed reactor operators and senior .

reactor operators. ,

. . d. IE Information Notice 85-70, Teletherapy Unit Full Calibration and . '

Qualified Export Requirements (10 CFR 35.23 and 10 CFR 35.24) was =

issued August 15, 1985 to all NRC licensees authorized to possess and use sealed sources in medical theletherapy units.

4. Other Items

a. -Structural Mechanics in Reactor Technology (SMiRT) Conference 4 - The Deputy Director attended and presented papers at the SMiRT "8" Conference in Brussels, Belguim August 16-23, 1985. He will be participating in the Post-SMiRT "8" Conference in Milan, Italy August 24-29, 1985.

Vendor Inspections b.

7-The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs conducted the following inspections this week:

(1) Trojan Nuclear Plant, Prescott, OR. Inspection of licensee /

vendor interface on specific hardware issues. The Director, Division of Quality Assurance, Vendor, and Technical Training Programs will be attending the exit interview on August 15.

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1 AUG 161985 ENCLOSURE D

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1 (2) Brunswick Steam Electric Plant, Southport, NC. Seieltth in a series of pilot inspections to review licensee equipient quali-fication program implementation as required by 10 CFR 50.49.

(3) Joseph T. Ryerson & Son, Inc., Philadelphia, PA. Concerns 10 CFR Part 21 report by Calvert Cliffs. The plant purchased 17-4 pH stainless steel bar and was supplied 316 stainless instead.

(4) Pacific Scientific Company, Anaheim, CA and Paul-Monroe Hydraulics, Inc., Orange, CA. Concerns with snubber failures.

A recent BNL technical report reviewed snubber performance at nuclear power plants and identified these two vendors as major ',

vendors.

c. Operations Center

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A tour of the NRC Operations Center was conducted by a member of the '~

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Incident Response Branch, Division of Emergency Preparedness and -

Engineering Response on August 1-4, 1985 for management representa =

tives from Consumers Power and the Big Rock Point Resident Inspector.

A tour will be conducted on ' August 16, 1985 by the Incident Response Branch Chief for the members of the course, "NRC - What It Does."

These tours will discuss the agency's incident response program,

d. Incident Response (1) On August 13, 1985, an Emergency Response Data System drill was conducted with LaSalle Nuclear Power Plant. The Reactor Safety Team, Protective Measures Team, and Administrtive Support Team participated in the drill from the NRC Operations Center.

Region III monitored the transmission of the ERDS data. -

(2) A member of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response attended an interagency meeting on August 14, 1985, to discuss the lessons learned from Response 85, the FEMA earthquake exercise held in June 1985.

e. Emergency Preparedness A member of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response is participating in the onsite appraisal of the Hope Creek emergency preparedness prograp with the

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Reigon I inspection team. .

_i ENCLOSURE D AUG 161985

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f. NRC-State Radiography Steering Committee .i

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Chief, Safeguards Materials Program Branch, Division of; Inspection Steering Programs attended a meeting of the NRC-State Radiography'eeting Committee on August 8, 1985Ein Silver Spring, MD. The m involved the NRC members and was held to discuss progress and future action on NRC-generated items including a rule for radiography equip-ment improvements, a NUREG to provide guidance on source recoveries, use of alarming personnel dosimeters in radiography operations, a guide for incidents reports, standard test questions for potential radiographers, and improvements in the NRC inspection program.

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ENCLOSURE D gus 161985 i

l OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending August 16, 1985  ; .

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Semiscale .

Several unsuccessful attempts were made to run Semiscale test S-FS-11. On i Wednesday, August 7,1985 multiple attempts aborted because of power failures.

Later it was detemined that one of the heater rods failed. This was corrected l with a replacement heater rod but when another attempt was made to run the '

test on Friday, August 9,1985, one of the pump seals failed. The test was  :

aborted and seal replacement initiated. The next attegt to conduct the test 1 will be during the week of August 12, 1985. l TRAC-BWR A TRAC-BWR workshop will be held in Idaho Falls, Idaho on September 17-20, 1985.

The purpose of this workshop is to provide instruction in the use of

• TRAC-BDl/ MOD 1 and TRAC-BF1 to both domestic and international TRAC-BWR users. -

2 Lecture material and slides are being prepared by EG8G Idaho.  ;

, A one-wolume' document describing the TRAC-BF1 code is being prepared. This will include a description of all the new capabilities in TRAC-BF1, including i input changes, program alterations, and developmental assessment results. This document will also include the preparation of an extensive errata to the TRAC-BDl/M001 manual. The developmental assessment of TRAC-BF1 is now in

progress.

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NUREG-0956, " Reassessment of the Technical Bases for Estimating Source Tems"

! .__ A staff report, NUREG-0956, " Reassessment of the Technical Bases for Estimating

.. Source Tems," was published last week in draft for public comment. New -

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_ source terms for many accident sequences were found to be lower than those in - --

WASH-1400, but some were larger. Source tems were found to depend strongly  !

on plant design and construction details. The new analytical techniques reported in NUREG-0956 are greatly improved cogared with those used in WA!H-1400, and the new techniques can distinguish between those plant types or plant features that lead to lower source tems and those that do not. The new analytical i techniques in the fom of a Scurce Term Code Package have been tested thoroughly )

and peer reviewed, as described in NUREG-0956. The new Source Term Code Package is now being used in a systematic updating (or rebaselining) of the severe accident risk of five reference plants, to be described next yeat in a proposed report, NUREG-ll50. Subsequently, NUREG-0956 and NUREG-ll50 shou 4d fom the basis for evaluating major potential changes in regulatory practise pursuant )

i to the recent Severe Accident Policy Statement. .- ( .

t AUG 161985 EllCLOSURE E L

il ___ _.

l Computers and Video Display Units (VDUs)

I The use of computers and video display units (VDUs) to aid in thd operation I of nuclear power plants has increased significantly in recent ie(rs. A need '

exists for NRC guidelines for detemining whether VDUs effectively accomplish the objective of aiding operator performance. Because of this need, RES sponsored research with Idaho Nuclear Engineering Laboratory to develop such guidelines.

As a result of this project, INEL/EG&G has published in July 1985 a report, NUREG/CR-4227, titled " Human Engineering Guidelines for Evaluation and li Assessment of Video Display Units". This report provides the NRC with a single source that documents known guidelines for conducting fomal human factors evaluation of VDUs. The report is fomatted as a " handbook" or

" cookbook" of acceptance guidelines for the reviewer faced with the task of -

evaluating VDUs already designed or planned for service in NPP control rooms.'

The areas addressed are video displays, controls, control / display integration, and workplace layout. Guidelines relevant to each of those areas are

. presented. The exist'e nce of supporting research is also indicated for each l g0ideline. A coment section and method for assessment section are provided *

) , for each set of guidelines to aid.the reviewer. .~

Reactor Containment Leakage Testing A meeting was held on August 6,1985 at Region III office to discuss reactor containment leakage testing (as part of program to review regulatory requirements

that may have marginal igortance to safety). Participants of the meeting were

l F. Maura of Region III, H. Whitener of Region II, and A. Tse of RES. Topics '

. _ of the discussion included the inspection experience from the two Regions, the current leakage testing practices and problems, and the 'effect on accuracy and cost of the test if the licensees were allowed to deviate from the current practices.

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Handbook for Value-Impact Assessment, NUREG/CR 3563 i

i A series of half day cost-benefit workshops were held in the Regions to familiarize the staff with the applications and procedures for performing regulatory analysis described in the Handbook for Value-Imoact Assessment, NUREG/CR 3568. These procedures have been adopted by the NRC as the recommended guideline for performing value-impact analysis. (Ref: Regulatory Analysis Guidelines, NUREG/BR 0058, Rev. I, llay 1984).

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AUG 101985 ENCLOSURE E

The thrust of the workshops focused on supporting the objectives and procedures of NRC Manual Chapter 0514 dealing with management of plant-specific backfits, and in particular Section 042 which describes the requirement t'o perform regulatory analysis. -=

Regions visited were: Region V (7/25/85), Region IV (8/6/85), Re'gion II (8/7/85),

and Region I (8/8/85). Region III will be visited at a later date.

1 Severe Accident Risk Analysis A management meeting was held in Albuquerque on August 8 to discuss the status of the five reference plant studies underway to support the NRR-IDCOR interface and to provide the basic information for the preparation of NUREG-ll50. - The studies are proceeding in accordance with the master schedule established June 27, which calls for all of the technical work to be completed, documented in draft, and available to NRR by April 1986. Based on the availability of

, this information as scheduled, NUREG-ll50 will be published in draft for peer Yeview and public comment by mid-sunener of 1986.  ;

2 Three plant visits (Surry, Peach Bottom, and Sequoyah) have been conducted successfully as scheduled, and the remaining two (Grand Gulf and Zion) are scheduled for completion by mid-September. Coding problems are being encountered for the needed source term runs, but these problems have not yet impacted the schedule. The issue currently receiving the greatest staff

ttention is the method of analyzing and documenting uncertainties. It is expected that this issue will be resolved in the next few weeks, and a summary of the resolution will be documented in the safety goals implementation plan. ,

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Calibration of Instruments Used for the Dosimetry of Beta Radiation In connection with a project funded jointly by the National Bureau of _

Standards (NBS) and the Nuclear. Regulatory Comission, NBS has developed a

. facility to calibrate beta sources and transfer instruments sent to NBS by comercial calibration services or NRC licensees. After return to the sender, the transfer instrument or sources may then be used for the on-site calibration of radiation protection instruments. The standard beta sources that are currently available at the NBS facility for this calibration service are: Strontium-90, Thallium-204 and Promethium-147. The results of this i project have been published in NUREG/CR-4266 " Standard Beta-Particle and Monoenergetic Electron Sources for the Calibration of Beta-Radiation Protection Instrumentation." The purpose of this work was to improve the accuracy of radiation surveys that licensees are required to perform.

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NUREG/CP-0050, " Proceedings of the International Beta-Dosimetry , .

Symposium",1983, showed that present beta measurements may be in error by as much as a factor of 100 if the dependence on beta energy, sourceedetector geometry, mixed radiation fields and environmental conditions ard not properly

~ factored into the measurement. NRC will distribute copies of NUREG/CR-4266 and an NBS announcement on the availability of this service to all NRC licensees whose activities might benefit from this service.

ERCLOSURE E

Contact:

R. Neel, 427-4559 AUG 161985

EPA Plan to Develop Residual Radioactive Contamination Criteria The Acting Assistant Administrator of EPA for Air and Radiation:has responded affirmatively to NRC's requests to develop Federal guidance on ihe establishment l of residual radioactivity limits for lands, facilities, eouip[neQt, and materials - l to be released on an unrestricted basis. RES has been advised by EPA that it olans 1 to develop such guidance on a " vigorous" basis and would welcome NRC's .

participation. Criteria to be developed include: criteria for release of land  !

and buildings from decomissioned . facilities; criteria for recycling contaminated materials and equipment without restrictions; and criteria for  :

designating low-level waste streams as having radioactivity levels that are l "below regulatory concern." As a first step in this cooperative effort, EPA staff has provided NRC staff with a draft development plan and a draft advance notice of proposed rulemaking (ANPR) for establishing Federal guidance on criteria and/or a methodology for establishing requirements for cleanup of land and facilities associated with decomissioning a facility. These drafts were provided for NRC review and coment in conjunction with recent meetings between EPA and RES staff to explore and discuss ways of cooperating and working together to expedite the development of this Federal guidance. EPA staff plans to publish the ANPR in the Federal Register later this year to obtain public, coments. ,

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Publications to be Issued in the Near Future

Title:

Standard Fonnat and Content for the Safety Analysis Report (SAR) for Onsite Storage of Spent Fuel Storage Casks (Draft Regulatory Guide)

Description:

Provides guidance to reactor licensees for submittal of an SAR when applying for onsite storage of spent fuel in casks under Part 72.

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Contact:

W. Pearson 443-7663

Title:

Standard Fonnat and Content Guide for Access Authorization Plans T for Nuclear Power Plants

Description:

The guide describes the infonnation required in the access authorization plan submitted as part of an application for a license to operate an NPP. The guide also explains the intent of the various provisions of proposed 173.56 of 10 CFR Part 73.

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Contact:

Kris Jamgochian 443 '/985

Title:

Reporting of Physical Security Events (Draft Regulatory Gdide)

Description:

_ The guide is being revised to reflect proposed Tre isions to 10 CFR 73.71.

Contact:

Kris Jamgochian ENCLOSURE E 443-7935 -

AUG 161985

Publication Recently Issued

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Oraft Regulatory Guide and Value/ Impact Statement: Guide for t.heIPreparation of Applications fcr Nuclear Pharmacy Licenses, Task FC 410-4. - Cbmments requested by October 31, 1985.

Contact:

P. Vacca (301) 427-4QO2.

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ENCLOSURE E AUG 161985

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS -

WEEK ENDING AUGUST 16, 1985  ;}-

Foreign Trip Reports W. H. Bamford, Westinghouse Electric Corp. (under contract to ORNL)

May 14-22, 1985; Visited Japan:

The purpose of the trip was to participate in the IAEA Specialists Meeting on Subcritical Crack Growth and the semiannual meeting of the International Cyclic Crack Growth Rate (ICCGR) Cooperative Group.  ;

T. M. Cate, H. R. Payne, and J. E. Smith, ORNL May 15-28, 1985; Visited Japan:

- The purpose of the trip was to check the fit-up and assembly of fuel

• bundle end boxes (provided by the Federal Republic of Germany) with fuel, -

- bundle grid spacers provided by JAERI. .

T. S. Kress, Manager, NRC/DAE Programs at ORNL May 21-22, 1985; Visited Switzerland:

The purpose of this foreign travel was to participate in a meeting of an OECD/CSNI Special Task Force on Source Terms.

Leon L. Beratan, Chief, Earth Sciences Branch, NRR '

June 14-29,.1985; Visited Portugal, France, and Austria:

Mr. Beratan met in Lisbon with the Director of Geophysical Services of

___ INMG and staff to discuss their use of seismic networks, the geology, _

.. programs and the tectonics of Portugal. In France, he participated in -

meetings at CEA and discussed the proposed agreement of cooperation for the existing experiment the NRC is funding at Mammoth Lakes, California, to measure downhole attenuation -in a deep layer of glacial till. The French would like to have the experiment duplicated in an alluvial soil site on a cost-sharing basis. In Vienna, Mr. Beratan attended the TRC meeting at IAEA on Safety Guide SG-S8, " Safety Aspects of Foundations of Nuclear Power Plants."

Betty F. Maskewitz, Director of EPIC, ORNL June 14-July 8,1985; Visited France, Italy, and Israel: _.

The purpose of the trip was to discuss radiation protection, transport, and shielding and to engage in information exchange discussion % with specialists in France, Italy, and Israel. OFFICIAL USE ONLY. F ENCLOSURE G AUG 101985

2 Foreign Trip Reports continued h

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• T. S. Kress, Manager, NRC/DAE Programs at ORNL  ;,

June 18-26, 1985; Visited Italy and the UK:

The purpose of the trip was to participate in meetings of two separate CSNI Committees: (1) a Special Task Force established by CSNI for the purpose of preparing a report on current knowledge in the LWR source term area, and (2) a Special Committee of the CSNI Group of Experts on Source Terms (GREST) established to conduct a calculational benchmark exercise for containment aerosol behavioral codes.

J. E. Hardy, ORNL Staff Member, AIRS Program July 4-13, 1985; Visited Japan: ',

The purpose of this trip was to supervise the removal of ORNL-supplied sensors from the Slab Core Test Facility -- Core II (SCTF-II) and to

__ measure and record the status of the sensors. ,

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ENCLOSURE G AUG 1 G 1985

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING AUGUST 16, 1985 _

$f-Super Compactor License Issued by Tennessee .,

On August 7, 1985, the State of Tennessee issued a license to a Tennessee company, Scientific Ecology, to operate a commercial compactor facility.

The licensee's operations will be located at Clinch River Industrial Park, Lot 5 in Oak Ridge, Tennessee. The license authorizes receipt, processing, storage and transfer of materials and items as radioactive waste. Processing includes opening, sorting, compaction and repackaging of waste in a form suitable for transportation and burial. The compactor, which was custom built,is capable of 1 million pound per square inch. The licensee is limited

- to 180 days of storag'e at their facility.

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0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM 0F INTEREST WEEK ENDING AUGUST 16, 1985 .

AE0D Engineering Evaluation Report, E511, entitled, " Closure of Emergency Core Cooling System Minimum Flow-Valves," was issued. The report, evaluated

'the inadvertent closure of minimum flow valves at both the Brunswick and Peach Bottom units. The study found that the minimum flow bypass lines provide an essential pump protection feature and that the affected safety system trains at both the Brunswick and Peach Bottom units should have been declared inoperable when the minimum flow valves for these systems were closed and deactivated. An evaluation of a data search for similar events at other plants indicated that not all licensees may recognize the importance of minimum flow valves for ECCS pump operability. An evaluation of the control logic of the Brunswick core spray system minimum flow valves also ..

- found that the design was inadequate to assure that the valves could perform ,

their containment isolation function in all required situations.

The st'udy suggested that IE consider issuing an Information Notice to remind licensees of the importance of the. minimum flow bypass line pump protection .

feature, the dependency of pump operability on minimum flow valve operability, .

2 and the possible need for licensees to review the control logic of ECCS .~

minimum flow valves to ensure that it is adequate to satisfy containment isolation requirements.

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ENCLOSURE J AUG 161985

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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING AUGUST 16, 1985 ,

l A. STAFF REQUIREMENTS - DISCUSSION OF DOE HIGH LEVEL WASTE MANAGEMENT PROGRAM, 2:00 P.M., MONDAY, JULY 29, 1985, COMISSIONERS' CONFERENCE R001, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 8/12/85: .

Th'e Commission met to be briefed by Mr. Ben Rusche;-Director of the Office of Civilian Radioactive Waste Management, U.S.

, Department of Energy (DOE) , on DOE.high level waste management programs.

Chairman Palladino requested that C y issioners give attention to options described in SECY-85-237- for addressing DOE's present position on the timing of the preliminary determination of the suitability of three candidate sites for the first ~ '

_ repository. ,

[ " Timing of the U.S. Department of Energy's ' Preliminary .

Determination' required by the NWPA that three sites are .

. suitable for development as repositories." -

l B. STAFF REQUIREMENTS - CONTINUATION OF 5/15 BRIEFING ON PROPOSED REVISION OF PART 20, 10:00 A.M., TUESDAY, JULY 30, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks dated 8/12/85 The Commission

• met to resume the May 15, 1985 briefing by .

staff on the " Proposed Revision of 10 CFR Part 20, ' Standards for Protection Against Radiation'" (SECY-85-147).

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The Commission requested information on studies performed to estimate the level of risk that people are willing to accept in 7 their daily (lives without altering 4

RES) (SECYtheir lifestyles.

Suspense: 8/20/85)

Chairman Palladino requested Commissioners to provide their notation votes on SECY-85-147.

(OCM)

• Commissioner Asselstine was not present.

o ENCLOSURE O AUG 161985 I

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C. STAFF REQUIREMENTS - DISCUSSION /POSSIBLE V0TE ON FULL POWER OPERATING LICENSE FOR DIABLO CANYON-2, 10:30 A.M., THURSDAY, AUGUST 1, 1985, COWISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks dated 8/14/85 .i The Commission met to discuss a full power operating license for Diablo Canyon Unit 2.

The Commission heard statements from the Government Account-ability Project (GAP) read by Nina Bell of the Nuclear Informa-tion and Resource Service and from George A. Maneatis, Executive Vice President for Pacific Gas and Electric Company.

The Commission voted 4-1 (with Commissioner Asselstine dis -

agreeing) to authorize the staff to issue a full power license for Diablo Canyon Unit 2.

The Commission also considered requests by joint intervenors

- for a stay of the effectiveness of any authorization by the -

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Commission of the issuance of a full power license for Diablo-

_ Canyon Unit 2 and to take revigw of ALAB-811 (ref: SECY-85 263) .

The Commission voted 4-1 (with Commissioner Asselstine dis-agreeing) to deny both the stay and review requests (this completes action on SECY-85-263).

(Subsequently, the Secretary signed an order to that effect.)

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_i i-l ENCLOSURE O AUG 161985 l

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

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m NRR MEETING NOTICES

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DOCKET

.DATE/ TIME APPLICANT /

NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT j 8/20/85 50-286 P-110 To discuss results of the 10:00 am Power Authority of J. Neighbors Bethesda steam generator tube the State of NY inspections

'8/21/85 50-272 P-110 To discuss proposed changes .Public Serv. Elec.

8:30 am 50-311 E. Reeves Bethesda in tech specs as followup to & Gas Co. '

meeting on July 25, 1985 l 8 /27-7V85 P-422 Working Meeting on specific EPRI

! D. Moran .,,.,

8:30 a i Bethesda generic safety issues impacting '

the EPRI/ Industry advanced LWR -

Requirements Document 8 /2P /I. 50-286 P-114 To discuss exemptions to Power Authority of l J. Neighbors

1:00 I"i Bethesda Appendix R the State of NY l .

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PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166 .

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

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NHSS MEETING NOTICES t '

e i. ,_ FOR WEEK ENDING: 8/16/85 E

Division ef Fuel Cyclo rnd Matcrial Safcty .

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[ DOCKET ATTENDEES /.

APPLICANT NRC CONTACT

-AATE/ TIE NUPEER LOCATION PURPOSE 8/20/85 Willste To discuss nuclear stethoscope W. Walker (Health Cunningham 2

00 pm 5th floor training requirements. Physics Services, Inc.)

conf room R. Cunningham V. Miller N. McElroy .'

8/27/85 Project Willste To discuss NUTECH Topical Report J. Massey, et al . , Roberts .

10:00 am M-39 Sth floor Review. (NUTECH) conf room Reps of CP&L J. Roberts (FC) i F. Sturz (FC) .

I J. Schneider (FC) -

8/29/85 72-3 Hartsville, Site visit to Carolina Fower & J. Kozyra, et al., Sturz .

SC' Light Co.'s.H. B. Robinson site

• (CP&L) to discuss Environmental Assessment E. Pentecost (NRR) of proposed independent spent fuel F. Sturz (FC) storage installation.

9/5/85 Washington, To discuss issues on cask develop- Reps from DOE and DOT Cunningham '

All day DC (D0E ment under the Nuclear Waste R. Cunningham (FC) office) Policy Act. J. Cook (FC)

C. MacDonald (FC) i Division of Safeg'uards .

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j Division of Haste Management i ES

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$ RES FIEETING NOTICES August 16, 1985

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DOCKET ATTENDEES /

' 5 ui DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 8/28/85 NL-5650 Conduct program review on plant INEL Au procedures research FIN A6394 RES

. and A6826 8/29/85 GPC Review status and draft report for GPC Au Columbia,MD FIN B8973 on task analysis of control INEL

. room applications - Part I: Procedures NRR 4

Interface Issues RES I .

9/5-6/85 NL Program review " Statistical l'ethods HARC Frattali i for i1CAA of SY1" NP.C

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l 9/6/85 AR P.eview status & draft report for FIN GPC Au 88973 on Task Analysis of Control Room NRP.

, Apolications - Part II: Skills, RES Knowledge & Training 1

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$ RII MEETING NOTICE i

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w DOCKET -ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 08/19/85 RII Office Meeting with GA Power Licensee, Regional Walker 12:30 pm Company representatives Administrator and

'to present two Readiness Selected NRR, IE and Review Modules to the RII Staff Members RII Staff 08/20/85 RII Office Regional Meeting with Resident Inspectors, Walker 8:00 am Resident and Senior Selected HQs and Resident Inspectors Regional Staff Members

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