ML20214A886

Weekly Info Rept for Wk Ending 860207

ML20214A886
Person / Time
Issue date:	02/12/1986
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-860207, NUDOCS 8602200434
Download: ML20214A886 (43)

Text

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f February 12, 1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the EDO

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING FEBRUARY 7, 1986 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 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 Right", K*

Regional 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. Rehm, Assistant for Operations Office of the Executive Director for Operations

Contact:

h2h78 8602200434 860212 '

PDR CDPMB NRCC WEEMLYIDFOREPT PDR.-

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING FEBRUARY 7, 1986

, TVA 4

On January 30 and 31. Steve White of TVA called Mr. Denton and Mr. Taylor to

notify NRC thct he had directed his staff to reschedule the licensing i

meetings planned for the next few weeks. He stated that he is taking this action in order to permit him to understand the issuas being discussed with

. NRC prior to these meetings being scheduled. (Those meetings primarily dealt with Brown Ferry Restart Issues). Mr. Taylor stated that our -

agreement not to hold licensing meetings can no way impact our inspections or evaluations of ongoing programs at TVA facilities. ~

i Also, TVA signed the contract with QTC extending their participation at a reduced scope and level in the Employee Concern Program.

Perry Earthquake ,

, Asaresultofanearthquakewhichoccurredincloseproximity(about 10 mi) of the Perry plant site on January 31, 1986, a joint Region

, III/NRR investigating team visited the plant on a fact finding mission during February 1-2, 1986. The USGS has indicated that the earthquake had a magnitude of 5.0.

! Based on preliminary data obtained from the licensee during its 2-day l visit, the investigating team found that earthquake motion recorded '

inside the plant (the first such data obtained from a nuclear plant outside of California) appears to mainly fall within OBE/SSE design  !

spectrum except possibly in the relatively high frequency range of l greater than 15 Hz. An analysis by the licensee of the recorded data '

i is underway to determine whether or not (and if so at what frequencies) the design was exceeded. A meeting with the licensee is tentatively j scheduled for February 7,1986, at the plant site, during which time the licensee will advise NRC of his preliminary findings on this event and i

his plan of action. The licensee's preliminary findings are scheduled l l to be filed today, February 5, 1986.

l NFS-Erwin '

Strike by OCAW members continues. NFS made an offer on February 5 to the Union for their consideration. The offer was voted on by the Union Membership and i

rejected. NFS continues to conduct limited operations of the HEU production j and scrap recovery facilities.

I i Swedish Administrative Arranaement Staff has been attending interagency meetings to review a draft administrative arrangement for implementing the US/ Sweden Agreement for Cooperation. One provision of the proposed arrangement would necessitate the development of new  !

NRC regulations for reporting and. tracking foreign nuclear components within 1 the U.S. which are made subject to such agreements. Staff is concerned about i implementation costs and lack of statutory authority to impose such a requirement.

Sequoyah Fuels Corporation On February 4, 1986, Sequoyah Fuels Corporation was authorized to receive and store any uranium concentrates (yellowcake) which were enroute at the time of the January 3, 1986 accident. All other activities remain suspended as provided by the confirmatory acticn letter dated January 17, 1986, between Sequoyah Fuels and NRC's Region IV.

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4 OFFICE OF ADMINISTRATION

- Week Ending February 7, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1985 181 15 i Received, 1986 72 15

. Granted 64 1 Denied 18 0 Pending 171 20 ACTIONS THIS WEEK Received

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l Midori Higuchi, Requests copies of the records of the investigation of The Yasuda Fire & the accident at Kerr McGee's Sequoyah plant in Gore, 1- Marine Insurance Oklahoma.

Company of America (86-61)

George Conril Brown, Requests a copy of the Defense Contract Audit Agency Dickstein, Shapiro audit report of Ace-Federal Reporters, Inc., regarding

& Morin contract NRC-17-85-207.

(86-62.)

Nan Taylor, Requests copies of NRC's 43a and 43b budget submissions International Data in response to OMB Circular A-11 TM-56 of June-25,1985.

Corporation (86-63)  !

1 i (NRC employee) Requests the names and position titles of.the panel l (86-64) members for Vacancy Announcement No. 85-0777-5.

l R.P. Pulec, Requests.a copy of draft NUREG/CR-4178.

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C.R. Steinhardt, Wisconsin Public Service Corporation  !

i (86-65)

Jim Pedro, Requests records regarding NRC support for development NUS Corporation of a remote operated robot called SURBOT.-

l (86-66)

CONTACT

Donnie H. Grimsley 492-7211

_ ,986- ENCLOSURE A FEB i

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2 Received, Cont'd Ronald G. Harper, Requests copies of all licenses held by Emergi-Lite, Brandhurst, Inc. Inc., Westbrook, Connecticut.

(86-67)'

L.R. Petersen, Requests a copy of the proposal submitted by Science Sonalysts, Inc. Applications in response to RFP OIE-86-162.

(86-68) -

(NRCemployee) Requests all records regarding an 0IA investigation on' (86-69) herself.

Lars Pellas Requests copies of releasable versions of inspection (86-70) reports from 1983 on Cambridge Medical Diagnostics, Billerica, Massachusetts.

Thomas A. Isaacson, Requests copies of all records relating to delays in or Howrey & Simon the progress of construction at the Bellefonte nuclear (86-71) power plant.

John W. McKendree, Requests copies of all records pertaining to the proposed Oil, Chemical & acquisition of Nuclear Fuel Services, Inc., by Nuclear Atomic Workers Assurance Corporation.

International Union (86-72) l Stevi Stephens, APPEAL TO THE EDO for the lack of response for a request Nuclear Awareness for Office of Investigation records on investigations Network related to Wolf Creek which have occurred within the last (86-A-6-85-327) year.

Granted Steven C. Sholly, In response to a request for three categories of records MHB Technical regarding source terms, made available 11 records.

Associates

(85-781)

Philip M. Holzman, In response to a request for five categories of records Engineering regarding the cost benefit workshops given to the NRC l Planning and regional staffs in 1985, made available one record. 1 Management, Inc. Informed the requester that three additional records  !

(86-3) subject to this request are already available at the PDR.

Gene Stilp, In response to a request for records regarding radium Essential dial workers, the Ottawa, Illinois, dial painting plant, Information health of the workers, locations where radium instrument (86-27) painting was or is practiced, etc., informed the requester that the NRC has no jurisdiction over the use nf radium.

Made available four records regarding the tritium at.the Ottawa plant.

FEB 7 1986 ENCLOSURE A "w+ 4

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'Kathryn H. Urban, In response to a request for a list of licensees for Medi+ Physics Iodine 125 and Gadolinium 153 sealed sources, made (86-44)' available one record.

T.J. Vukovich, In response to a request for a copy of NUREG/CR-4380, C.R. Steinhardt, ' informed the requesters that this^ report has already Wisconsin Public been made publicly available through the Government .

Service Corp. Printing Office.

, (86-47)

Robert G. Todd In response to a request for the-contents of the' file (86-57) on FOIA-85-848, made available four records.-

Denied i . .

Ellyn R. Weiss, In response to a request for copies of the NRC inspection Hamon, Weiss & report and related records regarding the evaluation of Jordan the auxiliary feedwater system at Turkey Point Units 3 (85-729) and 4, made available 40 records. Infonned the requester that additional records subject to this request are 4

already available at the PDR. Denied. portions of one record, disclosure of which would. constitute a' clearly unwarranted invasion of personal privacy. Denied six records in their entirety, disclosure of which would -

inhibit the candid and frank exchange.of consnunications in future deliberations.

Steven C. Sholly, In response to a request for (1) records concerning the MHR Technical second annual UKAEA/USNRC Information Exchange Meeting Associates on Containment Response to Severe Accident Conditions held (85-784) on October 15, 1985; (2) records concerning the Fifth Annual Research Information held October Exchange 16-18, 1985;- Meeting (on Core

3) papers Meltdown presented at the most recent Light Water Reactor Research Information Meeting concerning source terms, probabilistic risk assessment, and seismic safety.research; (4)'

records generated as a result of a recent meeting of the Society.of Exploration Geophysicists; and (5) a copy of the SECY paper presented at or prepared for the Commission  :

i meeting on " Consideration .of Earthquakes in:the Context of Emergency Preparedness" on September 9, 1985,-made available 4

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

Denied eight records in their entirety containing information received in confidence from foreign sources.

Robert M. Rader, In response to a request for copies of SECY-85-367A and Conner & SECY-85-371, denied portions'of these papers, release of Wetterhahn, P.C. which would tend to inhibit the open and frank exchange (85-826) of ideas essential to'the deliberative process.

ENCLOSURE A eco ,..,eS6

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4 penied, Cont'd

'Dudley K. Pierson, In response to a request for copies of the 01 report The Detroit News on the July.2,1985, inadvertent criticality incident (85-834) at the Enrico Fermi 2 plant potential coverup, and all' OI communications to utility officials, specifically Chairman W. McCarthy, regarding the-incident, informed the requester that 0I had.no written communication with the utility regarding this incident. Denied the OI report in its entirety, release of which would interfere with an enforcement proceeding.and could allow those.

2 being investigated to_ learn the scope, direction, and focus of investigatory efforts.

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ENCLOSURE A FE3 . 1555

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WEEKLY INFORMATION REPORT DIVISION ~OF CONTRACTS WEEK ENDING FEBRUARY 7, 1986 IFB ISSUED IFB No.: RS-ADM-86-224

Title:

" Shuttle Bus Service"

Description:

The contractor shall provide regularly scheduled and extra shuttle l services required to transport passengers, intra-agency mail and/or Government-controlled materials / equipment, to buildings occupied by NRC employees within the Montgomery County, Maryland Metropolitan Area.

Period of Performance: Two years Sponsor: Office of Administration Status: Closing date has been extended to February 11, 1986.

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

Title:

" Program to Support Regional Operator Licensing Activities"

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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: RFP issued on January 28, 1986. Proposals due February 28, 1986.

PROPOSALS UNDER EVALUATION i

l RFP No.: RS-ADM-86-213

Title:

"Information Technology Services (ITS)"

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Description:

Operation and maintenance of the ITS Training Laboratory, including l the provision of ADP training to managers and other technical and nontechnical end users.

I Period of Performance: 24 months Sponsor: Office of Administration Status: RFP closed on February 5, 1986. Proposals forwarded to Source Evaluation Panel for review on February 5, 1986.

RFP No.: RS-NRR-86-055

Title:

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

Description:

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

Period of. Performance: 30 months Sponsor: Office of Nuclear Reactor Regulation -

ENCLOSURE A Status: Receipt of Best and Final offers extended to February 7, 1986.

FE3  ? 1986

f OFFICE OF NUCLEAR REACTOR REGULATION fI ITEMS OF INTEREST l Week Ending February 7, 1986 I

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TVA On January 30 and 31, Steve White of TVA called Mr. Denton and Mr. Taylor to .

. notify NRC that he had directed his staff to reschedule the licensing 1 meetings planned for the next'few weeks. _He stated that he is taking this -

action in order _to permit him to understand the issues being discussed with

NRC prior to these meetings being scheduled. (These meetings primarily ,

j dealt with Brown Ferry Restart Issues). Mr. Taylor stated that our .

agreement not to hold licensing meetings can-no way impact our inspections or evaluations of ongoing programs at TVA facilities.

l-Also, TVA signed the contract with QTC extending their participation at a .

reduced scope and level in the Employee Concern Program. l Perry Earthquake

l. As a result of an earthquake which occurred in close proximity (about l 10 mi) of the Perry plant site on January 31, 1986, a joint Region

! III/NRR investigating team visited the plant on a fact finding mission .

j during February 1-2, 1986. The USGS has indicated that the earthquake

had a magnitude of 5.0.

Based on preliminary data obtained from the licensee during its 2-day-visit, the investigating team found that earthquake motion recorded ,

inside the plant (the first such data obtained from a nuclear plant '

outside of California) appears to mainly fall within OBE/SSE design i Il spectrum except possibly in.the relatively high frequency range of l greater than 15 Hz. An analysis by the licensee of the recorded data _

is underway to determine whether or not (and if so at what frequencies)

! the design was exceeded. A meeting with the licensee is tentatively

, scheduled for February 7, 1986, at the plant site, during which time the i licensee will advise NRC of his preliminary findings on this event and

his plan of action. The licensee's preliminary findings are scheduled j to be filed today, February 5, 1986.

Limerick i The Philadelphia Electric. Company declared Unit 1 of the Limerick Generating Station to be in Commercial Operation at 12:01 a.m. last Saturday, February 1,1986.

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ENCLOSURE B i FEU  ? 1985 i

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2-Millstone'3 The full power license was issued for Millstone 3 on Friday, January 31, 1986. Millstone 3 entered Mode 1.(5% power) at approximately 2200 t hours on February 3, 1986. At about midnight main feed. valve isolation j occurred due to high SG level and, at 0636 on February 4,1986, the unit tripped from about 15% power on low SG level. The licensee is investigating the cause.

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i i ENCLOSURE B FEB  ? 1986

NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING FEBRUARY 7, 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 10 filled defueling canisters in the SFP containing a total net debris weight of about 5,800 lbs. The estimated total weight of damaged fuel and structural materials in the reactor vessel prior to start of defueling was 308,000 lbs.

- The licensee has increased the actual defueling time to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> with four reactor building entries per day. This represents a significant increase (over 200%) in defueling hours per day since the beginning of defueling. The deletion of respirator requirements based on airborne concentration histories and the number of trained operators available for defueling have contributed to this increase.

Two canisters were loaded with about 1,000 lbs of debris using a spade bucket tool. This tool allows loading some of the finer high-density debris. Previous canisters were loaded with end fittings and fuel pins which resulted in much lower packing densities. These canisters were volume limited and loaded with only about 250 lbs of debris.

On February 8, 1986, the licensee installed and started a Temporary Reactor Vessel Filtration System (TRVFS) which consists of a small circulating pump and a diatomaceous earth filter. Its purpose is to improve reactor vessel water clarity to provide sufficient  ;

visibility for defueling operations. During operation of the l Defueling Water Cleanup System (DWCS), the filters developed high pressure drops before significant quantities of water had been processed. The TRVFS will be used temporarily until the licensee develops a permanent program to improve the DWCS performance.

Results of the TRVFS operation will be evaluated when more operating experience becomes available.

2. PLANT STATUS The facility remains in long term cold shutdown with the Reactor j Coolant System (RCS) vented to the reactor building atmosphere and )

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

FEB 7 1986 ENCLOSURE B-

- 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 12 kilowatts.

-- RCS cooling is by natural heat loss to the reactor building ambient atmosphere. Incore thermocouple readings range from 72"F to 95'F with an average of 81*F.

The average reactor building temperature is 56*F. The reactor building airborne activity at the Westinghouse platform is 7.7 E-8 uCi/cc Tritium and 5.4 E-11 uCi/cc particulate, predominantly Cesium 137.

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

3. WASTE MANAGEMENT The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this week.

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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 Decontamination flushing of the 281' annulus area is in progress.

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.

5. ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis.results show TMI site liquid effluents to be in accordance with r:gulatory .

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 19 through January 25, 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 19 through January 25, 1986. A gamma scan detected no reactor related radioactivity.

FEB 7 1986 ENCLOSURE B

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- The NRC outdoor airborne particulate sampler at the TMI site _

collected a sample between January 29, and February 7,1986. No reactor related radioactivity was detected.- Analysis showed Iodine-131 and Ce:ium-137 concentrations to be less than the lower limits of detectability.

. 6. REACTOR BUILDING ACTIVITIES

- Initial defueling of.the reactor core is in progress.

- A tctgorary reactor vessel filtration system was installed and placed in service in the reactor building.

The licensee began a program 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.

t 7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of 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).

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 next meeting of the Advisory Panel is scheduled for February 12, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.

FEB 71926 ENCLOSURE B

At this meeting the Panel will receive a presentation by.the US ~

Department of Energy (DOE) on plans for the shipment of fuel removed from the damaged THI-2 reactor to a DOE facility for interim storage. The Panel will also receive a status report on the progress of defueling from GPU Nuclear Corporation. Members of the public will be given the i opportunity to address'the Panel.

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

!. The ACRS full committee will be briefed on February 13, 1986 (3:15 PM -

5:15 PM) at NRC offices at 1717 H Street, Washington, D.C.

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-FEB 7 1536 ENCLOSURE B l l

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Intere:t Week Ending February 7, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 121(a) of NWPA: EPA Final HLW Standards Status: Staff briefed the ACRS on January 15, 1986 on proposed revisions to 10 CFR Part 60 for conformance to EPA standards.

3 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) are awaiting Commission approval.

Action: NRC comments are to be submitted with the proposal to Congress in

, early February 1986.

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

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

Action: The final rule is scheduled to be 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 Cormission (SECY-85-374) on November 15, 1985 for approval, which is expected after DOE officially submits the proposal to Congress  ;

in early February. l l

ENCLOSURE C.

FEB  ! 2:5 i

Near-Term DOE Actions of Interest Early February 1986 - DOE to issue Final Transportation Business Plan.

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

Early February 1986 - DOE submits MRS proposal to Congress.

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.

Financial Arrangements for Cleanup of Accidental Releases

On January 28, 1986, Mary Jo Seeman, NMSS, briefed the Washington State Senate Energy and Utilities Committee on the status of the Commission's rulemaking on financial arrangements for cleanup of accidental releases. Ms. Seeman also met informally with committee staff to discuss the state's upcoming study on financial responsibility for the low-level radioactive waste disposal site, ilFS-Erwin Strike by OCAW members continues. NFS made an offer on February 5 to the Union for their consideration. The offer was voted on by the Union Membership and rejected. NFS continues to conduct limited operations of the HEU production and scrap recovery facilities. I Swedish Administrative Arrangement Staff has been attending interagency meetings to review a draft administrative arrangement for implementing the US/ Sweden Agreement for Cooperation. One provision of the proposed arrangement would necessitate the development of new NRC regulations for reporting and tracking foreign nuclear components within 4

the U.S. which are made subject to such agreements. Staff is concerned about implementation costs and lack of statutory authority to impose such a requirement.

ENCLOSURE C FEB i U23

Sequoyah Fuels, Gore Oklahoma On February 6 and 7, 1986, the Ad Hoc Interagency Task Force, evaluating the impact of the UF accident on public health, will meet at the Willste Building to discuss the scope of the impact assessment and to initiate the write-up of ..

the public health impact sections of the technical report. It is anticipated that a draft report will be out for interagency review by February 18, 1986.

Sequoyah Fuels Corporation On February 4,1986, Sequoyah Fuels Corporation was authorized to receive and store any uranium concentrates (yellowcake) which were enroute at the time of the January 3, 1986 accident. All other activities remain suspended as provided by the confirmatory action letter dated January 17, 1986,'between Sequoyah Fuels and NRC's Region IV.

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FEB 7 1935 ENCLOSURE C

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Office of. Inspection and Enforcement Items of Interest Week Ending February 7, 1986 j

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

' a. EN 85-70A, Imposition of Civil Penalty in the amount of.$50,000 was 'l j

issued (VermontFebruary)3,1986 Yankee . to Vermont Yankee Nuclear Power Corporation i r . .

b. EN 86-04, a Notice of Violation'and Proposed Imposition of Civil j Penalty in the amount of $500 was issued February 4, 1985 to Pacific .i

Power and Light Company (Point of' Rocks, WY). This action is based 1 J on two violations which involve

(1) use of an unsupervised indi- -i vidual to perform licensed activities which involved a leveling gauge

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containing a 500 millicurie Cs-137 source, and (2) failure to follow i

- established procedures.

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c. EN 86-05 Sacramento Municipal Utility District (Rancho Seco), a Notice of Violation and Proposed Imposition of Civil Penalty in the i amount of $25,000 was issued on February 5, 1986 based on.two viola-j tions: introduction of a weapon.to the site protected area,-and i improper badging of perscnnel.

l 2. The following IE Preliminary Notifications were issued during~the past

week

j i j a. PNO-I-86-11, Philadelphia Electric Company (Limerick Unit 1),

j Limerick Commercial Operation.

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] b. PNO-II-86-12. Law Engineering Company (McLean, VA), Potential Over- .i j exposure of Radiographer.

i c. PNO-III-86-06A Allied Chemical Company (Metropolis, IL), UF6 Cylinder Overfill Incident in 1984.

d. PNO-III-86-09, Cleveland Electric Illuminating (Perry Nuclear Power

[ Plant), Earthquake. '

e. PNO-III-86-10, Indiana & Michigan Electric Company (D.C. Cook Unit 2), e Unit Shutdown in Excess of 48 Hours for Repairs. J

f. PNO-III-86-11, Detroit Edison Company (Fermi-2), Stress Reports and J j Hanger Design Calculations Not Performed. ]

l' g. PNS-V-86-01, Sacramento Municipal Utility District (Rancho Seco i Nuclear Generating Station), Contraband Discovered in Possession of i

NRC Inspector at Access Control Point.

l- h. PNO-IV-86-06,SequoyahFuelsCorporation(Gore,OK),IntrusionInto b Sequoyah Facility Site.

i. JENCLOSURE D

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1. PN0-V-86-04, Naval Construction Training Center (Port Hueneme, CA),

Loss of Portable Moisture / Density Gauge.

j. PNO-86-05, Arizona Nuclear Power Project (Palo Verde Unit 1), Reactor Trip and Engireered Safety Feature Actuation. -

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

a. IE Information Notice No. 86-06, Failure of Lifting Rig Attachment While Lifting the Upper Guide Structure at St. Lucie Unit 1, was issued February 3, 1986 to all nuclear power facilities holding an operating license or a construction permit,

b. IE Information Notice No. 86-07, Lack of Detailed Instruction and Inadequate Observance of Precautions During Maintenance and Testing of Diesel Generator Woodward Governors, was issued February 3,1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

c. IE Information Notice No. 86-08, Licensee Event Report (LER) Format Modification, was issued February 3, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

d. IE Information Notice No. 86-09, Failure of Chock and Stop Check Valves Subjected to Low Flow Conditions, was issued February 3, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

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4. Other Items

a. Enforcement Conference 4 Director, Enforcement Staff was in Region I February 5, 1986 for an enforcement conference on Nine Mile Point (Unit 1).

b. Civil Penalties Paid (1) On February 4,1986, payment in the amount of $80,000 was received from Maine Yankee Atomic Power Company (Maine Yankee) for enforcement action (EA 85-108) relating to violations involving the inoperability of the steam generator low pressure trip function.

l (2) On February 3,1986, payment in the amount of $50,000 was received from South Carolina Electric and Gas Company (Summer) for enforcement action (EA 85-121) relating to violations involving RHR inoperability during startup.

ENCLOSURE D FD ,

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c. Operations Center On January 29, 30, 1986, technical training drills for the Reactor Safety Team and Protective Measures Team were conducted in the Operations Center using the INEL Nuclear Plant Analyzer. , - -

d. Incident Response (1) Incident Response Branch Chief, Division of Emergency Prepared-ness and Engineering Response (DEPER) conducted a briefing and tour of the NRC operations Center on February 3 for Ruth Crutchmeyer, an Illinois Commerce Connissioner, and Ben Hayes, Director of the Office of Investigations. The briefing dis-cussed the agency's incident response program.

(2) On February 5, 1986, the Chief, Incident Response Branch' con-ducted a briefing and tour of the NRC Operations Center fo~r-representatives from the FBI. The briefing discussed the

agency's incident response program.

4 (3) A member from the DOE Public Affairs Office met with the Chief, Incident Response Branch on February 6 to discuss NRC response capabilities and responsibilities.

(4) On February 7, 1986, the Chief, Incident Response Branch and staff members conducted a briefing and tour of the NRC Opera-tions Center for visitors from Japan. The briefing discussed i the agency's incident response program.

l l (5) On January 31, 1986, the Chief, Incident Response Branch and t

staff members attended a special response subcommittee meeting of the FPRCC to discuss the Kerr-McGee interagency notifications and responsibilities.

e. Vendor Program (1) The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs (QAVT), conducted the following inspection this week:

Corporate Consultants, Ltd., Research Triangle Park, NC - to 1

witness testing of Rockbestos cabling.

(2) Representative of the Vendor Program Branch, QAVT, met in Region I with Niagara Mohawk (Nine Mile Point Facility) in an enforcement conference on February 5, 1986 to discuss EQ.inspec-tion results and corrective actions.

ENCLOSURE D FEB 'l C

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f. Qua'lity Assurance A representative of'the Quality Assurance Branch staff,'QAVT, partici -

pated in a public meeting involving Texas Utilities, its contractors, f

and NRR this week regarding the status of TUGCO's Comanche Peak j Response Team's construction and design. inspection.

i

g. Construction Appraisal Representatives of the Reactor Construction Branch, Division of Inspection Programs (DI), and consultants were at Palo Verde Unit 3 4 this week to continue Construction Appraisal Team Inspection. :An j exit meeting is scheduled for February 14, 1986.

j h. Medical Uses of Radio Isotopes Representative of Safeguards Materials Fuels Branch (DI), was in San Antonio, TX February 5,1986 to lecture on medical uses of

radio isotopes.

! 1. Safeguards Inspection Representative of Operating Reactors Program Branch'(DI), partici-pated in a special Region V safeguards inspection at Rancho Seco l this week.

j. Allegation Followup

! Chief, Safeguards Materials Fuel Branch (DI), was at NFS plant

! (Erwin, TN) February 6, 1986 to assist in investigations of alle-

gations at the plant.

k. Comanche Peak Response Team (CPRT) l Chief, Reactor Construction Programs Branch (DI), attended a meeting 2 in Region IV with Texas Utilities on February 6, 1986 regarding CPRT

activities. On February 7, 1986, the Comanche Peak site was visited i with Region IV representatives to discuss CPRT Program Plan imple-mentation.

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,. ENCLOSURE D

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OFFICE OF NUCLEAR REGULATORY RESEARCH Itens of Interest

^

Week Ending- February 7, fl986

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Cooperative Agreement'Between USNRC and Tractionel (Belgium) on Development of Nuclear Plant Analyzer Preliminary discussions were held between E. Stubbe (Tractionel) and F. Odar (NRC) on a possible cocoerative acieement between .

the USNRC and Tractionel (Belgi'um). The USNRC would implement the RELAP5/M002 code in a minicomputer (Alliant FX18) and Tractionel would provide the necessary funds. This would provide NRC with the mini-computer (stand alone) version of RELAP5/M002 which can be used by NRC technical staff and contractors for rapid analysis of operational transients . It is estimated that the project would be: completed by' 1 mid-1988.

Direct Containment Heating A meeting was held at the Willste Building Silver Spring, Maryland on January 29, 1986 for a joint review, by RES and NRR, of preliminary plans of research programs at Sandia National Laboratories (SNL), and at Brookhaven National Laboratory-(BNL), regarding the issue.of direct heating of containment by molten core materials ejected under pressure from the reactor vessel during certain severe accidents. The question of whether direct containment heating could cause early containment-failure is a major source of uncertainty in estimating the risk fron severe accidents. The centerpiece of SNL's program will be the experiments in the newly acquired SURTSEY facility that is designed to quantify various effects of this phenomenon. BNL's effort will be directed at small-scale, separate effects tests and will address the effect of structure around the reactor cavity on core debris dispersion.

NUREG-0956 NUREG-0956, " Reassessment of the Technical Bases for Estimating Source Terms," was issued as a draft for public comment in August 1985 and the period for comments ended on January 7,1986. Work is.now underway to

< revise the draft for publication'as a final report. In addition to addressing public comments, the report is beinp revised to reflect updated computer codes and new numerical results produced for'the risk rebaselining study to be described in NUREG-ll50. Publication of NUREG-0956 is scheduled for early June 1986.

ENCLOSURE E FEB 7 1536 s

'RES/ DOE-NE MEETING ON B&W DESIGN REVIEW RES staff met with DOE staff in Germantown on February 5,1986 to discuss what help DOE might be able to provide to the NRC review of the B&W design. DOE' was asked to consider any of the following areas of NRC need: a)developinga full risk model of a B&W plant (other than for Oconee which RES has) which would be available on a DOE Lab computer for NRC to query; b) determine the ,,

state of applicability and goodness of the NRC thermal hydraulic safety analysis codes (TRAC and RELAP) as currently configured as far as their ability to analyze operational transients now being experienced in B&W reactors and as far as their ability to model-B&W hardware configurations; and c) what are the effects of human reliability / human factors as they especially affect the safety performance of B&W plant systems?

DOE staff indicated their current effort related to the B&W design was two fold. They are pulling together data to be used in an international standard problem to analyze the TMI-2 accident. DOE feels that sufficient information has been gathered over the past several years to tie down times and temperatures during the accident. The Standard Problem will- be presented to the CSNI Principal Working Groups 2 & 4 in September. Also DOE is examining current problems and current methodologies for all reactor systems including B&W as part of their Advanced Reactor Assessment Program. - This is in -

preparation to look at potential design improvements.

DOE will consider the NRC proposals and provide some initial response midweek-during the week ending February 14. ,

Rule Amendments Requiring Licensees to Notify NRC of Cases of Bankruptcy Filing Following approval by the Acting Executive Director for Operations of initiation of rulemaking, work began on preparation of amendments requiring licensees to notify NRC in the event they file for bankruptcy. Notification of NRC will direct NRC's specific attention toward a; bankrupt licensee so NRC can be assured that radioactive materials in the licensee's possession pose no undue risk to public health and safety during and after the bankruptcy proceedings. The amendments are being prepared for division review in February 1986.

FEB  ? ig2 ENCLOSURE E

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'- Seismic Category I Structures Program. l Primary program emphasis is to obtain credibility of previous experimental l

work by resolving the reported differences between analy A series of credibility experiments is planned using both small scale (1 inch' thick walls) and large scale (4 inch thick wall) structures. l Testing of the first small scale structure has been coupleted and the second. i small scale structure is underway. Evaluation of the test data obtained ,

to date indicates that the analytical-experimental stiffness at low load - )

levels agree within 15-30%. At higher load levelst the results agree with -l previous. test data; that is, anal i l stiffnesses agree.

l i

within 75% (off by a factor of 4)ytical-exper men a -

The testing of the first large scale structure at the U.S.~ Army Corps of _ .

~~ ;

i Engineers Construction Engineering Research Laboratory was conducted between '

j January 6-17, 1986. Preliminary evaluatial of the test data indicates that  ;

4 analytical-experimental stiffness' at low ioad levels agree within 10%. -In

. I addition, the first four modes and frequencies for this large scale model i

and the small scale model are nearly identical, demonstrating that.

structurally, the models are nearly identical. Test data on the' higher 4

load levels has not been evaluated yet.

l ANL staff will issue a quick-look report in February comparing the test yesults of the small- scale and large scale structures with one another, rrevious test results, and analysis. The report will also contain LANL

[ recommendations to resolve the stiffness difference issue.

l .

Biological Effectiveness of Neutrons 4

j; Recently (1985 ICRP meeting in Paris) the ICRP recommended that the quality ,

factor (Q) for neutron exposure be raised by a factor of 2 to a value of 20.

A worker's dose in rems is obtained by multiplying the. dose, as measured in  !

, rads, by Q. This multiplication permits the addition of neutron and gamma  !

doses. Several years ago the NRC staff recognized that there were I uncertainties concerning the adequacy of Q when applied to exposures to -  !

fission neutrons. This was of special concern because:some power plant i workers receive significant neutron doses. -In order to establish a technical ,

basis for decisionmaking, it was decided to fund a research project which i would provide scientific confirmation of neutron quality factor values in an 1 animal study. The study, conducted at ANL, involved weekly exposures of a large number of mice to either pure fission neutrons or Co-60 gama rays. A range of. total doses (2-40 rads neutrons, 100-600 rads' gamma) and a variety of biological end points were employed. The data have now been collected and are  !

being analyzed. The final report is scheduled for publication in 1986.

Preliminary results appear. to support the new ICRP. recommendation.

J. Foulke 42-74563 1 i

' ENCLOSURE E j FES i C:^

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l Interagency Meeting on Worker Exposure Limits On January 29, 1986, Dr. Aurel Goodwin of the Mine Safety and Health Administration (MSHA) met with Mr. Robert E. Alexander, Chief, Radiation Risk Assessment and Management Branch, to discuss issues of concern to _

both agencies regarding exposure limits for workers. Representatives from the Occupational Safety and Health Administration, the Department of Energy, the Department of Defense, and other NRC offices were also present.

The major issue discussed was rulemaking under consideration by MSHA which would lower its present exposure limit for radon daughter products by one-

' third. NRC's proposed new 10 CFR Part 20, as written, retains the present standard. Also discussed were potential reductions in the intake limits for airborne uranium. Such reductions have been proposed in the new Part 20, but MSHA has not yet taken action in that regard. Another meeting is planned after MSHA and the NRC have received public comments on these reductions. It was recognized that Federal standards of this nature should be in agreement.

Judith Foulke 42-74563 4

Respirator Studies Indicate Current Protection Factors May Be Non-Conservative When it is impracticable to apply process or engineering controls to limit-occupational intakes of airborne radioactive material to within regulatory values, workers are normally required to use respiratory protection equipment. NRC regulations (10 CFR Part 20) include allowable " protection factors" for each type of respirator, i.e., a factor used to estimate respirator efficiency. The larger the protection factor, the greater the protection to the worker. Recent studies by the National Institute for Occupational Safety and Health (NIOSH) show that protection factors measured under actual working conditions are characteristically smaller than the corresponding factors measured under laboratory conditions (the source of values for protection facturs presently incorporated into 10 CFR Part 20). An ongoing cooperative research study conducted by LANL for the NRC and OSHA is i to determine to what extent workplace conditions affect protection factor i values. Freliminary results tend to confirm those published by NIOSH, and

lead to the conclusion that better methods for testing respirator efficiency are necessary to be representative of field conditions. As a result of this study the staff is considering recommendations to the Commission to modify certain protection factors that now appear in 10 CFR Part 20.

R. B. Neel 42-74559 ENCLOSURE E )

FEB  ? E05 1 l

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P- -s-I Workshop on Validation of Mathematical Models for HLW Repositories

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On Januar.y 27, 28, and 29, 1986,:the Waste Management Branch of the Division '

?

of Radiation Programs and Earth Sciences held a workshop on " Validation' of t Mathematical Models for Waste Repository Performance Assessment." The emphasis of the workshop was on validation of models applied to assessing performance.of high-level radioactive waste disposal and its objective was to-I focus on the uncertainties inherent in performance assessment models and i

provide the insights and understandings by which the RES staff will identify specific tests.and experiments needed to build confidence in those models.

The tests and experiments so identified will be used in planning HLW research

activities beginning in FY 87.

Each day of the workshop emphasized modeling~in a different part of the

, repository system. The topics for the three days were, respectively, the thermally undisturbed zone, the thermally disturbed zone, and the engineered l

barrier system. Each day's schedule consisted of formal-presentations by j modelers, questions for presenters, a panel discussion. and a session.on 4

identification of needed experiments and validation procedures. Nearly all of the workshop was recorded and the proceedings of the workshop will be pub-lished in May 1986. The proceedings also will contain papers given by the .

presenters and panelists and an analysis of validation procedures reconsnended at the workshop. The proceedings will be prepared by the workshop's or-ganizers, Drs. John D. Randall of NRC, Evaristo-J. Bonano of Sandia, and Frank A. Kulacki of the Colorado State, University.

f Attendees at the workshop included staff members from the Offices of Nuclear Regulatory Research and Nuclear Material Safety and Safeguards; contractors for both offices; and observers from the Advisory Committee on Reactor Safeguards, the U. S. Department of Energy (the HLW licensee), and other i

countries. Dr. Kjell Andersson of Sweden's Nuclear Power Inspectorate (SKI) gave a presentation on INTRAVAL, an international effort planned by SKI to test the validity of mathematical models applied to the thermally undisturbed zone of a HLW rerository. Dr. Andersson is very interested in coordinating j the work of INTRAVAL with NRC's planned validation activities.

,t For further informatic7 on the workshop, contact John D. Randall at,(301 or FTS) 427-4633.

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NRC Regional Seismographic Networks and the January 31, 1986 Earthquake in Ohio ,

1 A_ moderate earthquake, magnitude of 4.9,' occurred in Northeast Ohio at 11:46 a.m., EST, on January 31, 1986. The Perry Nuclear Power Plant, which is due for initial startup later this year, is located about 15 miles narth of the -

epicenter. Three other nuclear power plant sites are within 150 miles of the i, epicenter.

y The National Earthquake Information Center determined the epicenter location using 17 seismographic stations telemetered to the Center in Colorado. Nine of the 13 stations within 1000 Km of the epicenter are part of the NRC's regional seismographic networks; two others are supported by DOE. The NRC established 8

these regional seismographic networks in the central and Eastern United States. o beginning in about 1975. The networks were initiated for two basic reasons:

(1) the NRC needed the data to carry out its mission, and (2) no other Federal- '

agency would accept responsibility for them. The networks are providing accurate seismological data; 1.e., location, magnitudes and recurrence rates, for NRC licensing decisionmaking. The network stations were carefully sited

taking into consideration both the location of seismically active areas and '

existing and planned nuclear power plant sites.

Based upon the information obtained from the NRC regional seismographic l networks during the January 31 earthquake (over a hundred records were' recorded '

by the NRC networks), five NRC rdsearch contractors dispatched teams to the j area to deploy portable seismographs to record any aftershocks which might occur; these accelerographs and microearthquake recorders were recording within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the primary shock on January 31.- Within the first 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,.

three small aftershocks were recorded,' reports by residents who felt the shock -

, were being noted and reconnaissance teams were checking for any signs of primary ground rupture; i.e., fault displacements (none noted). The Corps of f Engineers reported that the strong motion accelerographs at the M. J. Kirwan Dam and the Erie Pennsylvania Veterens Hospital triggered during the earthquake and that the records are being recovered. The dam is about 45 km and the hospital is about 100 km from the epicenter. Other strong motion instrumentation is being checked for triggers. This type of equipment will provide data only for major seismic events (greater than 0.01g at the location of the instrument) and by itself is inadequate to fully' characterize even'a 1

major earthquake, such as the location of its epicenter or its focal parameters.

l The affected site area is located within the Central Stable Region-Tectonic l

,' Province. Except for the 1929, magnitude 5.2, PWI VIII "Attica Earthquake," .

which is related to the Clarenden-Linden Fault Zone in Northwestern New York, -l 4 there is little evidence that elucidates any correlation between seismicity and tectonic structure. Therefore, the tectonic province approach as prescribed by Appendix A of 10 CFR 100 has been used to develop the earthquake design bases-j for nuclear power plants in this area. Three historic earthquakes and three i

ENCLOSURE E j FFP 7~3

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-7

' clusters of minor seismicity are associated with the northeastern portion of this tect'onic province, including the 1929 Attica Earthquake. The other two l earthquakes were the 1937, magnitude 5.0 -.5.3, maximum M I VII-VIII, Anna,  ;

Ohio,. Ear'thquake and the 1980, magnitude 5.0 - 5.3, maximum M I VII, -

.- Sharpsburg, Kentucky, earthquake. The clusters of minor activity were located about 20 miles west, about 175 northeast, and about 180 miles south of the _

epicenter of the current earthquake.

i!

The regional reology has been analyzed by the licensees for the several nuclear i power plants in the area and their consultants, by the USGS and by the NRC.

Collectively, it has been concluded that there are no capable faults within the l northeastern portion of this tectonic province.

This earthquake provides a unique opportunity to examine seismic effects at an Eastern NPP. Nine strong motion records are available from the plant itself; at least two sets of'accelerograms from off-site have been identified, and over a hundred " weak motion" records were recorded by the NRC networks. This 1

invaluable data set will be the focus of a major effort to develop an improved insight into the relation between recorded accelerations and specific effect t within an NPP. A detailed assessment of the seismic response of an NPP to a i number of high amplitude accelerations in narrow-frequency bands is a prime '

topic for such study.

i i Due to badget reduction pressures and the recognition that operation of the l

! regional seismic networks is more properly a U.S. Geological Survey

! responsibility, RES had been negotiating with the USGS for it to assume responsibility for monitoring seismic activity in the entire United States, including the central and eastern portions. A draft memorandum of

! understanding that would have accomplished this had been prepared, whereby the l 4

USGS was to assume responsibility for operation of the' regional networks. In i return, the NRC was to provide certain funds to the USGS for.the. purchase of new, better equipment, which the USGS would install and operate, and thereby replace the NRC networks. Due to budgetary limitations, RES has had to withdraw from these negotiations and it plans to terminate its support for the

! NRC networks in fiscal year 1987; i.e., no NRC funding in 1988. Thus the-l majority of the seismographic stations east of the Continental Divide may well cease to operate in 1988, so that the accurate location and measurements of ,

! intensity and magnitude of earthquakes throughout the central and Eastern U.S.  !

, will no longer be available. This will greatly increase the difficulty of- i i licensing decisions that will have to be made concerning the licensing and

! continuing safe operation of nuclear power plants affected by such an event.

, There is legislation pending (S.1765) to amend the Earthquake Hazard Reduction

Act of 1977 to provide for the establishment of national seismic data centers.

These centers would collect and analyze data from regional seismographic

^

networks, coupile this data and make it available for governmental and public use. If this bill is passed and the centers established,' they could provide ~a source of seismologic data alternative to the present NRC networks.

ENCLOSURE E FEB ,. . b, ,.

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f RES Rulemaking Activities i

Emergency Preparedness for Fuel Cycle and Other Radioactive Materials Licensees -

(Parts 30, 40, 70)

In 1981 the NRC issued orders to certain fuel cycle and other radioactive "

material licensees requiring them to . submit comprehensive ensite radiological emergency plans. Subsequently, rulemaking was initiated to place a. requirement for emergency plans in the regulations.

1 Staff work on the proposed rule is complete. However, in light of the recent i

UF release at the Sequoyah Facility, the SECY psper has been revised 'slightly to6better characterize the intent of the rule regarding onsite and offsite responses to chemical and radiological threats from accidents involving licensed materials and to include a comparison of predicted consequences of a UF, release with the consequences from the Kerr McGee accident. A briefing on thM rule was held on January 27, 1986, for the Director, NMSS, and he suggested f

adding a few paragraphs to the Federal Register notice to emphasize the need for prompt notification of offsite authorities and to point out that the need' for public information programs should be left to the discretion of these

.' offsite authorities. The Director, NMSS, supported promptly sending the rule j to the Comission. On February 5,1986, NMSS concurred in a revised Comission

! paper and Federal Register notice. We plan to forward the rulemaking package.

j to the E00 by February 7, 1986.

i Definition of High Level Radioactive Waste (HLW) in 10 CFR Part 60 4

This advance notice of proposed rulemaking (ANPRM) seeks to revise the defini-tion of HLW in Part 60 to' reflect certain changes in the legal definition of HLW contained in the Nuclear Waste Policy Act of 1982. A revision of the j

definition of HLW would affect DOE's plans for a geologic repository, State plans for regional compacts to manage low-level waste, Federal vs. State responsibility for some above Class C wastes, costs of waste disposal for ,

certain waste generators, and the development of new technologies and 1 I

facilities to dispose of certain types of wastes. A definition of HLW which reduces uncertainty about responsibility for different types of wastes would benefit the radioactive waste management system.

In response to a Commission directive, RES and NMSS staff are reviewing regula-  ;

tory options for definition of high-level radioactive waste rulemaking in light i j

of relevant provisions of recent legislation which an.nded the Low Level Waste j l Policy Act of 1980. A staff paper recommending a course of action is to be- i submitted to the Commission within the next few days.

4 FEB 7 E3 ENCLOSURE E

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• - ITEMS OF INTEREST- .

, 0FFICE OF INTERNATIONAL PROGRAMS WEEK ENDING FEBURARY 7,'1986 ,

Radium Source in Scrap Metal Shipment The Atomic Energy Control Board has notified IP that on December 11,.1985 a-

vacuum gauge containing a small radium source was discovered by a scrap metal .

J' dealer in Canada in a shipment of scrap received from the General Motors Technical Center in Detroit. GM officials were nctified of the' incident and i the gauge was retrieved by GM. Readings taken at the site confirm that the-1 radioactivity was confined to the vacuum gauge. IP advir.ed.the NRC staff of this incident soon after its occurrence and followed it up in mid-January-with the full AECB report on the incident.

Foreign Visitors l .

! On Monday K. Stadie, Deputy Director General of the OECD Nuclear Energy' Agency.

i (NEA) met with the EDO and with NRC staff involved in the NEA Committee on the Safety of Nuclear Installations to discuss on-going NRC cooperation with that. 1

Committee.

J

. On Friday Messrs. K. Abe and T. Oikawa of the Risk Analysis Laboratory of ,

the Japan Atomic Energy Research Institute met representatives of IE, AE00, i

f and the PDR to discuss automated infomation storage and retrieval . systems ,

} as they relate to incident response and event reporting. '

On Friday Dr. Dan Litai, Director of the Licensing Division of the Israeli j Atomic Energy Commission, met a representative of IE to discuss the role

, and function of the vendor inspection program.

Foreign Trip Reports

} Thomas J. Nicholson, Earth Sciences Branch, RES November 18-22, 1985; Visited France:

[ e.

Mr. Nicholson attended the Third Hydrocoin Workshop and Coordinating Meeting held at the OECD/ Nuclear Energy Agency headquarters in Paris. He also went on a field trip to Limoges to visit the International Training Center for Prospecting and Validation of Industrial Radioactive Ores. (CIPRA) and to nearby uranium mines where high-level radioactive waste research in fractured granite was being conductea.

[ W. F. Bethmann and 1 J. E. Smith, ORNL j October 25-November 16, 1985; Visited the FRG:

The purpose of this ' trip was to participate in the steam / water checkout of the drag body, break-through detector and DP measurement systems at the Upper

! Plenum Test Facility (UPTF) in Mannheim.

ENCLOSURE G i FEE  ; ~

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4

, OFFICE OF STATE PROGRAMS ,

ITEMS OF INTEREST WEEK ENDING FEBRUARY 7,1986 Five-Week Health Physics Course

, The five-week Health Physics Course for State radiation protection personnel will commence on February 10, 1986, at Oak Ridge, Tennessee.

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ENCLOSURE H 1

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W F

OFFICE OF RESOURCE MANAGEMENT Item Of Interest

. Week Ending February 7, 1986 i

i President's Budget for FY 1987 The NRC President's Budget Estimates of $405 million for FY 1987 was forwarded to the Congress on February 5, 1986. The President's Budget request also includes the assumption that the NRC will impose user fees to recover approxi-mately $200 million in FY-1987. This estimate is based on a fee of $500 per j million watts of rated thermal capacity on all-operating nuclear _ power plants.

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ENCLOSURE I-

[ FEB 7 L83

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E

! REGION III STATUS REPORI DAVIS-BESSE LOSS OF FEEDWATER EVENT

, FEBRUARY 7, 1986 Plant Status The plant remains in cold shutdown. The licensee discovered a smali fire in containment on February 5. The fire was immediately extinguished with a hand'

held extinguisher. There was no damage to plant equipment. The fire was detected by security personnel and the fire detection system did not alarm.

Restart Activities f

i A NRR maintenance survey inspection team will be on site in late March 1986 ++ '

1 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, j_ The licensee has determined that the thrust developed by the motor operators

for six valves was less than the thrust recommended by the valve vendor to ,

i close the valves. The licensee has completed all work on fifty seven valves

! and returned them to service. The licensee is repairing and testing valve j motor operators continuously with three overlapping ten-hour shifts.

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

_ testing activities. Repairs and testing of the Incore Monitoring system is_

continuing. No major testing was' accomplished this week. Further system testing awaits completion of equipment modifications.  ;

f Other Activities i

The licensee determined that all fire dampers in the plant were inoperable ++

t '

because there are no expansion gaps between the dampers and the structures in jr which they are imbedded.

1 In response to a violation identified during an NRC fire protection ++

inspection the licensee has inspected 163 boot seals used as fire barriers and as part of negative pressure boundaries. The licensee's inspection disclosed numerous inoperable boot seals. Most have been repaired.

Inspections of safety system piping supports in the auxiliary building are  !

continuing. Evaluationofthenonconformances(NCR).foundonsupportsin j containment is in progress. Of the support NCRs requiring disposition prior

to restart, eighteen remain to be dispositioned.

f

N LOSURE L FEB  ? E23 i

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i 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 is continuing.

A Region III_ inspection team is on site this week to review the licensee's response to previous inspection findings. ,

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i ii ENCLOSURE L 2

ITEMS ADDRESSED BY THE COMISSION - WEEK ENDING FEBRUARY 7, 1986 A. ' STAFF REQUIREMENTS - PRESENTATIONS BY PARTICIPANTS ON PROPOSED AENDMENTS TO PART 60, 9:30 A.M., FRIDAY, JANUARY 24, 1986. COMISSIONERS CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dtd 2/3/86

'~

The Commissioners met with interested states, Indian Tribes, public interest groups, the Department of Energy, and Edison Electric Institute to_ hear comments on proposed changes to NR

' regulation 10 CFR Part 60.

The following persons participated in this meeting:

Malachy Murphy

State of Nevada i

Steve Frishman State of Texas Patrick Spurgin State of Utah Tom Lehman i State of Minnesota Don Provost State of Washington Dean Tousley Yakima Indian Nation Suzan Shown Harjo National Congress of American Indians David Berrick Environmental Policy Institute, and

. Natural Resources Defense Council James McGranery, Jr.

Scientists and Engineers for Secure Energy Ralph Stein Jim Knight

. Department of Energy Loring Mills Edison Electric Institute 4

ENCLOSURE O FEB 7 1986 I I

i

A. CONTINUED Mr. Stein of DOE agreed to provide a response to Commissioner Asslestine's question regarding implementation of the DOE /NRC Procedural Agreement for public meetings on development of.the site characterization plan.

_n Chairman Palladino requested the participants to provide any --

additional information they wish on this subject no later than Friday, January ?l.

.B. STAFF REQUIREMENTS - DISCUSSION /POSSIBLE VOTE ON FULL POWER ODERATING t LICENSE FOR MILLSTONE 3, 10:00 A.M.. WEDNESDAY, JANUARY 29. 1986.

COM4ISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PLELIC ATTENDANCE)

Memo SECY to V. Stello dtd 2/7/86 The comminaios cet to direuen the innere of a full power j license for the Millstone Nuclear Power Station, Unit 3.

The Commission voted 5-0 to authorize the staff to issue a full l power license for Millstone, Unit 3. l The Commission was advised by the Acting EDO that the staff would examine the efficacy of interconnecting sources of emergency AC power (both safety-grade and nonsafety-grade) at sites with more than one unit. The Acting EDO further advised that the staff would perform a generic analysis on check valves.

The results will be forwarded to the Commission.

(NRR) .

(SECY Suspense: 3/31/86) l ENCLOSURE O FEB i in:

t l- .

C. STAFF REQUIREPENTS - AFFIRMATION / DISCUSSION AND VOTE. 3:30 P.M. WEDNESDAY, JANUARY 29,1986 COP 91ISSIONERS' CONFERENCE ROOM D.C. OFFICE (OPEN TO ,

PUBLIC ATTENDANCE) Memo SECY to H. H. E. Plaine dtd 2/7/86 A

~

i I. SECY-86 Intervenors' Motion for Cancellatien of Shoreham Emergency Planning Exercise -

The Commission by a-3-2 vote (with Chairman Palladino and Commissioner Asselstine disagreeing), approved an order denying a request by New York State, Suffolk County, and the Town of-

Southampton that the Commission cancel the emergency planning ,

exercise for Shoreham scheduled for February 13, 1986. Chairman

~

1 i -

Palladino provided dissenting views with which Commissioner Asselstine agreed. The majority also had additional views in i

response to the minority position.  ;

4  :

5 (Subsequently, on January 30, 1986 the Secretary signed the order.)

l II. SECY-86 Order on ALAB-812 (In the Matter of Louisiana ruwet s !.1;ht % =nv, watarford. nnit 3)

, The Commission by a 3-2 vote (with Chairman Palladino and i Commissioner Asselstine disagreeing) , approved an order responding i to ALAB-812 and denying the request by Joint Intervenors to i reopen the Waterford proceeding on issues that may relate to I

matters under investigation by OI. Chairman Palladino also had separate views with which Commissioner Asselstine agreed.

(Subsequently, on January 30, 1986 the Secretary signed the i orde r. )

III. SECY-85-386 "60 Minutes" Broadcast on Shoreham Construction The Commission by a 4-1 vote (with Commissioner Asselstine j disapproving), approved an order denying a March 27, 1985

Suffolk County /New York State motion for an immediate investi- ,

i gation of issues raised during a March 24, 1985 CBS broadcast of i "60 Minutes" and for the Commission to hold in abeyance all l' Commission proceedings on Shoreham licensing and operation pending completion of the investigation. Commissioner i

Asselstine indicated that he preferred to-treat the motion for j an investigation as a 2.206 petition and refer it to the staff.

(Subsequently, on January 29, 1986 the Secretary signed the i

Order.)

! l i

4

! l ENCLOSURE O

FEB 7e .

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! D. STAFF REQUIREMENTS - BRIFFING ON SAN ONOFRE AND STATUS OF RANCHO SECO, j -

10:00 A.M., WEDNESDAY, JANUARY 22, 1986 COMISSIONERS' CONFERENCE ROOM D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello dtd 2/7/86 I

The Commission was briefed by the staff on the status of the <

' San Onofre Unit 1 Nuclear Power Plant (SONGS-1). The staff

.also provided a brief status report on the Rancho Seco Nuclear 4 i Power. Plant. Additionally, the Commission received a short

presentation from Lawrence Papay, Senior.Vice President of the

! . Southern California Edison Company and Ken Baskin, Vice President

of Nuclear Engineering Safety and Licensing, also of Southern j -California Edison.

The Commission instructed.the staff to reexamine the' design

, criteria of the SONGS-1 diesel generators, which would not

! permit load sequencing upon a loss of offsite power event I without an actuated safety injection signal. This design j; review should be discussed with the licensee and its impact on the event assessed.

(eDe)(NRR) (SECY Suspense: 4/1/86) i Chairman Palladino requested that the staff reexamine the USI

! on water hammer and decide if the influence of check valves on

water harner need to be reexamined . He further requested that j the staff develop a follow-on plan for SONGS-1 and suggested i that the licensee also develop one. The staff is to compare i i its plan with that of the licensee to determine consistency on '

the significant issues.

I (EDG) (NRR) (SECY Suspense: 4/1/86)

Commissioner Asselstine requested that the staff examine the i

event at SONGS-1 to determine whether the check valve problems

that occurred were a function of the unique design of the plant i or generic in nature. >

) 4EDO)-(NRR) (SECY Suspense 4/1/86) 1 l

k Commissioner Bernthal requested that the staff examine the

! question of whether the plant's long period of outage might '

have had an affect on some of the plant's components.

tepe) (NRR) (SECY Suspense 4/1/86) j The Commission and the staff agreed to meet for a more extensive briefing on Rancho Seco.

I

• (Subsequptly,theCommissionattheagendaplanningaessionon Thursday, January 23, 1986 scheduled a meeting with the staff on Rancho Seco for February 20, 1986.)

The representatives of Southern California Edison suggested

that they meet with the Commission'to further discuss the status of SONGS-1.

ENCLOSURE O FE? s a-l

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D. CONTINUED (Subsecuently, at the agenda planning session on Thursday, January 23, 1986 the Commission scheduled a meeting with representatives of Southern California Edison for February 21, 1986.)

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I ENCLOSURE O FEB

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C i NRR MEETING NOTICES

• FEBRUARY 7, 1986 8

DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 2/11/86 50-424 P-110 Discuss streamlining (i.e., Georgia Power M. Miller 9:00 a.m. 50-425 Phillips Bldg. elimination of redundant or Company unnecessary portions) of the Vogtle - specific Tech Specs.

2/11/86 -

GPU Nuclear Discuss special circu.nstances Oyster Creek J. Donohew 8:30 a.m. Headquarters for the licensee's requested Nuclear Generating Parsippany, N.J. exemptions to Appendix R to 10 Station CFR 50.

2/12/86 50-305 Room 5033 Discuss licensee's detailed Kewaunee Nuclear M. Fairtile 8:30 a.m. AR Bldg. control room design review Power Plant summary report.

2/12/86 50-219 P-114 Discuss the draft integrated GPUNC J. Donohew 1:30 p.m. Phillips Bldg. schedule for Oyster Creek.

2/13/86 50-508 550 EWW Bldg. WPPSS representatives will WPPSS Nuclear T. Michaels 9:30 a.m. Bethesda, MD discuss recent developments Project No. 3 with regard to Engineering Assurance Program of the Readiness Review Program.

2/13/86 -

P-118 NRC/AIF meeting on source term -AIF/NRC Z. Rosztoczy' 9:00 a.m. Phillips Bldg. related regulatory changes.

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• Ccpies 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

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

S tn NRR MEETING NOTICES

• FEBRUARY 7, 1986

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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.

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

N NHSS MEETING NOTICES -

- FOR WEEK ENDING: 2/7/86 r/. Division of Fuel Cycle and Material Safety DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 2/11-14/86 Las Vegas, To attend meeting of the Non-Destruc- D. Chapell (FC) Chapell.

MV tive Testing Management Association. B. Carrico (FC) 2/18-21/86 Project West Valley, To discuss various topics on the T. Clark (FC) Clark M-32 NY solidification of high-level waste N. Davison (FC) at West Valley. Reps'of West Valley

Division of Waste Management 2/27/86 Chicago, Illinois International Symposium.on RJStamer . RStarmer Alternative LLW Technologies REBrowning Division of Safeguards None l

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n E3 February 10, 1986 h, RII MEETING NOTICE U

DOCKET ATTCNDEES/

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 02/10/86 Montgomery, AL Meeting with senior Regional Administrator, Grace 1:00 pm representatives of the two RII staff members, AL Dept. of Health and the Director of Office of State Programs 1:00 pm RII Office Meeting with representatives Selected RII Staff Stohr of 011, Chemical, and Atmaic Members Workers International Union to discuss workers' concerns at NFS 02/11/86 RII Office Meeting with representatives Selected RII Staff Walker 10:00 am of Georgia Power Company Members to discuss improvements in SALP at Hatch Nuclear Power Plant 02/12/86 RII Office Senior Executive Vice Regional Administrator Grace 10:00 am President, Power Supply and Engineering, CP&L, will be meeting to discuss current issues pertaining to CP&L 1:00 pm RII Office Representatives of NFS Licensee, Regional. Stohr are meeting to discuss Administrator and NFS' Improvement Program Selected RII Staff Members 02/13/86 RII Office SALP Board Meeting Selected RII Staff Walker 10:30 am SCE&G's V. C. Summer' Members y, Nuclear Plant E

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1 Q, REGION III MEETING NOTICES i

WEEK Ef40!NG: February 7, 1986 DOCKET ATTENDEES /

OATE/ TIME NUMBER LOCATION PURPGsE APPLICANT NRC CONTACT 2/18/86 50-373 Glen Ellyn. IL SALP - Connonsealth Edison J.G. Keppler

1 p.m. 50-374 LaSalle J.G. Keppler & staff 2/19/86 50-255 Glen Ellyn, k SALP Consumers Power Co. J.G. Keppler 10

00 a.m. Palisades J.G. Keppler.A staff  ;

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