ML13303A972

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Requests Info Explaining How 8 H Battery Performance Test Demonstrates That Battery Can Meet Two Design Requirements, Based on Review of Util 880624 Response to Insp Repts 50-361/88-10 & 50-362/88-10
ML13303A972
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 11/29/1988
From: Hickman D
Office of Nuclear Reactor Regulation
To: Baskin K, Cotton G
SAN DIEGO GAS & ELECTRIC CO., SOUTHERN CALIFORNIA EDISON CO.
References
TAC-71194, TAC-71195, NUDOCS 8812070021
Download: ML13303A972 (4)


See also: IR 05000361/1988010

Text

epJR REG(, '

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

November 29,

1988

Docket Nos.:

50-361 and 50-362

Mr. Kenneth P. Baskin

Mr. Gary D. Cotton

Vice President

Senior Vice President

Southern California Edison Company

Engineering and Operations

2244 Walnut Grove Avenue

San Diego Gas and Electric Company

Post Office Box 800

101 Ash Street

Rosemead, California 91770

Post Office Box 1831

San Diego, California 92112

Gentlemen:

SUBJECT:

REQUEST FOR INFORMATION REGARDING SAN ONOFRE NUCLEAR GENERATING

STATION, UNITS 2 AND 3 (TAC NOS. 71194 AND 71195)

In response to our Inspection Report Nos. 50-361/88-10 and 50-362/88-10, you

undertook a two phase comprehensive assessment of the Component Cooling Water

(CCW) System. By letter dated June 24, 1988 you provided the results of the

first phase of that assessment. In your letter you stated that you had con

cluded that no unreviewed safety questions were involved and that the overall

NCR as well as five individual NCRs addressed in the assessment are available

for review at the site. Because of the number of problems with the CCW System,

we request that you forward these six NCRs to us as soon as possible.

Your Licensee Event Report (LER) 88-008-01 for San Onofre Unit 2 describes the

corrective actions you have taken as a result of the CCW System deficiencies.

The two modifications and the one procedure revision which you discussed each

have the potential to be an unreviewed safety question or to require a change

to the Technical Specifications. Because of the number of changes which have

been made to the system, we request that you forward the 10 CFR 50.59 evalua

tions for these changes which determined that they were neither unreviewed safety

questions nor changes to the Technical Specifications. These changes were (1)

the addition of a seismic makeup capability to the CCW System in 1984, (2) the

reduction in the IST acceptance criterion for non-critical loop isolation valve

closure time, and (3) the removal of the thermal overload devices from the CCW

surge tank isolation valve motor operator breaker.

Your LER 88-019-00 for San Onofre Unit 2 states that the batteries are required

to operate up to six hours following an accident to support Shutdown Cooling

(SDC) valve operation. However, Section 6.3.3.4.1 of the Updated Final Safety

Analysis Report (UFSAR) states that the determination whether or not to enter

the SDC mode is made at six hours into the event, but that "cooling of the RCS.

with the steam generators continues until the SDC entry temperature is achieved.

PDR

ADOCK 05000:361

PDCA

Pro/

110

Mssrs. Baskin and Cotton

- 2 -

November 29, 1988

The HPSI pumps are then throttled until RCS pressure is reduced to the SDC

entry pressure. Next, all injection flow is shifted back to the cold legs and

SDC is initiated." Therefore, the batteries are required to operate for some

time greater than six hours to support SDC operation. It is not clear then

that the eight hour battery performance test which you described in your

corrective actions.is adequate. Also, Section 5.4.7.1.2 of the UFSAR states

that "no single active failure prevents at least one train of the SCS from

being aligned and operated from the control room either during a normal plant

cooldown or following an accident." This would include a natural circulation

cooldown following a loss of offsite power and the single failure of a diesel

generator. This event would require the batteries to operate to the point

where SDC can be initiated. The natural circulation cooldown test at San

Onofre showed that it would take 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 36 minutes to reach SDC entry

conditions from the.time that cooldown is commenced. The requirement for a

four hour soak prior to commencing cooldown would require that the batteries

operate for nearly 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Please explain how your eight hour battery

performance test demonstrates that the battery can meet these two design

requirements.

Sincerely,

Donald E. Hickman, Project Manager

Project Directorate V

Division of Reactor Projects -

III,

IV, V and Special Projects

cc: See next page

Mssrs. Baskin and Cotton

- 2 -

November 29, 1988

The HPSI pumps are then throttled until RCS pressure is reduced to the SDC

entry pressure. Next, all injection flow is shifted back to the cold legs and

SDC is initiated." Therefore, the batteries are required to operate for some

time greater than six hours to support SDC operation. It is not clear then

that the eight hour battery performance test which you described in your

corrective actions is adequate. Also, Section 5.4.7.1.2 of the UFSAR states

that "no single active failure prevents at least one train of the SCS from

being aligned and operated from the control room either during a normal plant

cooldown or following an accident." This would include a natural circulation

cooldown following a loss of offsite power and the single failure of a diesel

generator. This event would require the batteries to operate to the point

where SDC can be initiated. The natural circulation cooldown test at San

Onofre showed that it would take 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 36 minutes to reach SDC entry

conditions from the time that cooldown is commenced. The requirement for a

four hour soak prior to commencing cooldown would require that the batteries

operate for nearly 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Please explain how your eight hour battery

performance test demonstrates that the battery can meet these two design

requirements.

Sincerely,

original signed by

Donald E. Hickman, Project Manager

Project Directorate V

Division of Reactor Projects -III,

IV, V and Special Projects

cc:

See next page

DISTRIBUTION

Docket File

NRC & LPDRs

PD5 Reading

MVirgilio

JLee

DHickman

OGC (f/info only)

EJordan

BGrimes

ACRS (10)

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11O C88

11R/OP1/88

OFFICIAL RECORD COPY

Mr. Kenneth P. Baskin

San Onofre Nuclear Generating

Southern California Edison Company

Station, Units 2 and 3

cc:

Mr. Gary D. Cotton

Mr. Hans Kaspar, Executive Director

Senior Vice President

Marine Review Committee, Inc.

Engineering and Operations

531 Encinitas Boulevard, Suite 105

San Diego Gas & Electric Company

Encinitas, California 92024

101 Ash Street

Post Office Box 1831

San Diego, California 92112

Mr. Mark Medford

Southern California Edison Company

Charles R. Kocher, Esq.

2244 Walnut Grove Avenue

James A. Beoletto, Esq.

P. 0. Box 800

Southern California Edison Company

Rosemead, California 91770

2244 Walnut Grove Avenue

P. 0. Box 800

Mr. Robert G. Lacy

Rosemead, California 91770

Manager, Nuclear Department

San Diego Gas & Electric Company

Orrick, Herrington & Sutcliffe

P. 0. Box 1831

ATTN:

David R. Pigott, Esq.

San Diego, California 92112

600 Montgomery Street

San Francisco, California 94111

Richard J. Wharton, Esq.

University of San Diego School of

Alan R. Watts, Esq.

Law

Rourke & Woodruff

Environmental Law Clinic

701 S. Parker St. No. 7000

San Diego, California 92110

Orange, California 92668-4702

Charles E. McClung, Jr., Esq.

Attorney at Law

Mr. S. McClusky

24012 Calle de la Plaza/Suite 330

Bechtel Power Corporation

Laguna Hills, California 92653

P. 0. Box 60860, Terminal Annex

Los Angeles, California 90060

Regional Administrator, Region V

U.S. Nuclear Regulatory Commission

Mr. C. B. Brinkman

1450 Maria Lane/Suite 210

Combustion Engineering, Inc.

Walnut Creek, California 94596

7910 Woodmont Avenue, Suite 1310

Bethesda, Maryland 20814

Resident Inspector, San Onofre NPS

c/o U. S. Nuclear Regulatory Commission

Mr. Dennis F. Kirsh

Post Office Box 4329

U.S. Nuclear Regulatory Commission

San Clemente, California 92672

Region V

1450 Maria Lane, Suite 210

Walnut Creek, California 94596

Mr. Sherwin Harris

Resource Project Manager

Public Utilities Department

City of Riverside

City Hall

3900 Main Street

Riverside, California 92522