ML20199G722

Final Response to FOIA Request for V Stello 860204 Memo Identifying Eight Issues for Further Evaluation.Forwards App Document.Document Also Available in PDR

ML20199G722
Person / Time
Site:	San Onofre
Issue date:	03/20/1986
From:	Grimsley D NRC OFFICE OF ADMINISTRATION (ADM)
To:	Pedro J NUS CORP.
References
FOIA-86-177, RTR-NUREG-1190 NUDOCS 8604090216
Download: ML20199G722 (2)

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UNITED STATES g,

NUCLEAR REGULATORY COMMISSION l

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E WASHINGTON, D. C. 20555

% * * * * * *o March 20, 1986 Mr. Jim Pedro Licensing Engineer Licensing Information Service NUS Corporation 2536 Countryside Boulevard IN RESPONSE REFER Clearwater, FL 33575-2094 TO F01A-86-177

Dear Mr. Pedro:

This is in regard to your request, pursuant to the Freedom of Information Act, to which the NRC assigned the above number.

This is a partial response to your request. We will notify you upon completion of search for and review ~of any additional records subject to your request.

X The staff has completed the search for and review of records subject to your request, and this is the final response to your request.

The NRC has no records subject to your request.

4 Records subject to your request are available for public inspection and copying at the NRC Public Document Room (PDR),

1717 H Street, NW, Washington, DC 20555, as noted on the enclosure (s). The PDR accession number is identified beside each record description.

X Records subject to your request are being made available for public inspection and copying at the NRC Public Document Room (PDR), 1717 H Street, NW, Washington, DC 20555, in the PDR file folder under the above number and your name. These records are listed on the enclosure.

We are enclosing a notice that provides information about charges and procedures for obtaining records from the PDR.

Sincerely, is /)&

J Donnie H. Grimsley, Director Division of Rules and Records Office of Administration Enclosure (s): As stated 0604090216 060320 PDR FOIA pDR PEDRO

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Re:

FOIA-86-177 APPENDIX i

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1.

2/4/86 Memorandum for Harold R. Denton from Victor Stello, Jr.,

subject: STAFF ACTIONS RESULTING FROM THE INVESTIGATION j

OF THE NOVEMBER 21 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 1 EVENT (NUREG -1190).

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-l WASHINGTON, D. C. 20555 FEB 04 W MEMORANDUM FOR:

Harold R. Denton, Director, NRR James M. Taylor, Director, IE John B. Martin, Regional Administrator, Region V FROM:

Victor Stello, Jr.

Acting Executive Director of Operations

SUBJECT:

STAFF ACTIONS RESULTING FROM THE INVESTIGATION 0F THE NOVEMBER 21 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT I EVENT (NUREG-1190)

An advance copy of the subject report was transmitted to you by memorandum dated January 20, 1986 from the San Onofre Team Leader, Thomas T. Martin. The report documents the Team's efforts in identifying the circumstances and causes of the November 21, 1985 event, together with findings and conclusions which fom the basis for identifying follow-on actions.

You will note from the report that the licensee has not completed troubleshooting and the determination of root causes for all equipment failures or malfunctions. Consequently, the results of future troubleshooting or analysis activities may form the basis for additional follow-on actions.

The identification of these additional actions is a responsibility of the nomal program office. The responsibility for the followup and reporting on the licensee's continued troubleshooting and determination of root cause for equipment failures is Region V.

The purpose of this memorandum is to identify and assign responsibility for generic and plant-specific actions resulting from the investigation of the San Onofre event (documented in NUREG-1190).

In this regard, you are requested to review the enclosure which specifies staff actions resulting from the investigation of the San Onofre event.

You are requested to determine the actions necessary to resolve each of the items in your area of responsibility and, where appropriate, identify additional staff actions or revisions as our review and understanding of this event are refined. Plant-specific actions required for plant restart should receive priority attention.

In view of the importance of this subject, I intend to closely monitor the resolution of these items.

By March 1,1986, please provide a written summary of the schedule and status of each item within your responsibility listed in the enclosure or that you have identified.

Further, I request that you prepare a written status report on the disposition of your items (and anticipated actions for uncompleted items) within three to six months. Every effort should be made to dispose of these items promptly.

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'o, The enclosure is based on the Team's report and its presentation to the Commission on January 22, 1986. Accordingly, it does not include all licensee actions, nor does it cover NRC staff activities associated with normal event followup such as authorization for restart, plant inspections, or possible enforcement items. These items are expected to be defined and implemented in a routine manner. Overall lead responsibility for staff actions relating to facility restart is separate from this effort and rests with Region V.

Additionally, RV is responsible for coordinating and promptly communicating the staff's requirements which must be resolved before operations at San Onofre may be resumed.

Original signed by' Victor Stello..-

Victor Stello, Jr.

Acting Executive Director for Operations

Enclosure:

As stated cc w/ enclosure:

J. Davis, NMSS T. Murley, RI J. N. Grace, RII J. Keppler, RIII R. Martin, RIV Distribution:

VStello JRoe TRehm JSniezek

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EDO NAME :JHeltemes;pv:HDenton

JTaylor

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DATE :1/29/86

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2/ y /86 OFFICIAL RECORD COPY l

STAFF ACTIONS RESULTING FROM THE INVESTIGATION OF THE NOVEMBER 21 SONGS-1 EVENT

(

Reference:

NUREG-1190) 1.

Item: Adequacy of feedwater check valves to perform safety function.

(

References:

Commission briefing, Sections 6.2.4, 6.4, 6.7, and Principal Finding)

Action Responsible Office Category Implement and coordinate IE Plant-specific the staff and industry actions Generic necessary to assure the reliability of safety-related check valves.

Other offices to assist as requested. Areas to be evaluated include:

licensee's engineering report on root cause analysis and proposed corrective actions 1

adequacy of check valve design for this applica-tion adequacy (of Inservice Testing IST) Program and i

, procedures to detect degraded and failed valves adequacy of check valves (and related testing programs) in other systems such as RHR system 2.

Item: Completeness of resolved USI A-1, " Water Hammer".

(

References:

Findingnumbers1,2,3,8and9)

Action Responsible Office Ca tegory Assess the need to re-NRR Generic evaluate USI A-1 to specifically address the potential for and prevention of condensation-induced water hammers in feedwater piping (assume the issue concerning check valve integr ty will be resolved in item 1.

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Item: Adequacy of San Onofre Unit I design.

(Commission briefing, Finding numbers 11 and 13)

Action Responsible Office Category Implement and coordinate NRR Plant-specific the staff's actions to re-evaluate the following San Onofre design features:

manual loading of the diesel generators follow-ing a loss of power event manual actuation of steam line isolation valves and assurance of steam generator availability to remove decay heat lack of steam generator blowdown status in control room adequacy of the licensee's design change to eliminate spurious SI indication on loss of power 4.

Item: Adequacy of post-trip review.

(

References:

Sections 6.6 and 7.2.2.4 and Finding number 17)

Action Responsible Office Category a.

Evaluate NRC require-NRR Generic ments for ensuring that sufficient event data are retrievable to accurately reconstruct the event following a loss of offsite power.

b.

Evaluate the licensee's Region V Plant-specific process for post-trip review and evaluation, including the thoroughness of review and oversight provided by the onsite and offsite nuclear safety review groups.

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Item: Adequacy of licensee's recordkeeping practices.

(

References:

Section 6.5 and Finding number 20)

Action Responsible Office Category Evaluate the adequacy of Region V Plant-specific the licensee's maintenance records.

6.

Item: Adequacy of operator training and/or procedures.

(

References:

Section 7 and Finding numbers 14,15 and 16)

Action Responsible Office Category Review the implementation Region V Plant-specific of the training program regarding operator under-standing and actions in the area of electrical systems, and invoking technical specification action statements.

7.

Item: Adequacy of emergency notifications and NRC response.

(

References:

Section 7.3 and Finding number 22)

Action Responsible Office Category a.

Verify the adequacy of Region V Plant-specific the licensee's procedures and training for reporting of events to NRC Operations Center.

b.

Evaluate the need for IE Generic changes in NRC policy or guidance regarding:

the use of the ENS line; the use of NRC personnel as ENS communicators; and

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possible approaches to improve the ability to determine the overall plant status.

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8.

Item: Significance of backlog of license amendments.

(

Reference:

Commission briefing)

Action Responsible Office Category j

Evaluate whether a backlog NRR Plant-specific of license amendments and i

technical specification

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changes contributed to delays in approving the licensee's l

IST program.

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ILLINOIS SAFE ENERGY ALLIANCE adEEI 53 West Jackson Boulevard, Room 343

• Chicago, Illinois 60604 * (312) 663-1667 February 6, 1986 Director FREEDOM OF INFORM ATION 1CT RFD!'FST Division of Rules and Records United States Nuclear Regulatory Commission

[dTM -[h-N Washington, D.C. 20555 FREEDOM OF INFORMATION ACT RSQUEST: High Burnup Fuel Experimentation in Commercial Lightwater Reactors i

To the Director:

This is a r3 quest under tha ?r3edom of Information Act, 5 U.S.C. #552, as amended, and the regulations of the Nuclear Regulatory Commission implementing the Act, 10CFR Part 9, Subpart A.

This request is made on behalf of the Illinois Safe Energy Alliance.

i This request seeks all records, as defined in 10CFR, Part 9, Subpart A, 3ection 9 3 a (b), which refer to or are related to the performance of high burnup fuel and high burnup spent fuel in commercial nuclear i

power reactors and spent fuel pools in the United States and other i

countries. High burnup experimentation is also known as " uranium utilization" and " extended burnup."

The records sought are all of those dated or which refer to the period from 1975 to and including the present date.

The enclosed list details scme, (but, by no means all), of the records sought.

Because none of the statutory exemptions from the Act's mandatory i

disclosure provisions applies, access to the requested records should be granted within ten (10) working days.

In the unlikely event, i

l however, that access is denied to any part of the requested records, please describe the deleted material in detail and specify the statutory basis for the denial as well as your reasons for believing that the I

alleged statutory justification applies in this instance.

Please I

separately state your reasons for not invoking your discretionary powers to release the requested documents in the public interest.

I anticipate that you will make the requested materials available within the statutorily prescribed period.

I also request that you waive any applicable fees since disclosure meets the statutory standard for waiver of fees in that " furnishing the information can be considered as primarily benefiting the general public.", 5 U.S.C.A.

1. 552 (a)(4)(A), since the Illinois Safe Energy Alliance is a public interest organization.

Sincerely, 7

O J

g(, o '/ d# o 3 7 q Catherine yuigg, Research Director (312/381-6695)

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Welcorne: M. F. Sankovich.

M M Kadman. N %sout H 3 MkawnWm@ % M General Chairman (Babcock a Arabek (CCA-f ranceL M Daron J 5

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Chasuman (D&W)

Measurements H Or men. D Franni.n 4 NRC Assessment of E siended Dumop l

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(Ehtr c Power Hesean.n insidule) tscernmg L S Hubenueen (USNHC) 1 Estended Burnup - Perspectives &

6 ti t usso) Product Henavnar we Vanous PWR S B&H thqh Uurnup lscensing Assessment i spectations y

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W E Da.ly. H A Proetastle, J F Schardt unup Pedamance of PWH feet (CEA Centre l (General Electncj

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