ML20002D560
| ML20002D560 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/16/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-08-03.A, TASK-8-3.A, TASK-RR LSO5-81-01-020, LSO5-81-1-20, NUDOCS 8101210347 | |
| Download: ML20002D560 (5) | |
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Docket JBuchanan, NRC PDR JHeltmes, AE0D LPDR GCwalina Docket No. 50-219 Central Files DPersinko 4 D -frd-Cl-C@ O NRR Reading RHermann SEPB Reading SEP File TERA DEisenhut Mr. I. R. Fi n* rock, J r.
OELD RPurple Vice President - Jersey Central I&E(3)
Glainas Power & Light CogarD' ACRS (16}
RTedesco P. O. Box 388 WRussell RDiggs Forked River, itew Jersey 08731 DCrutchfield JRoe HSmith JWetmore
Dear Mr. Finfrock:
WPaulson RScholl
SUBJECT:
SEP TOPIC V1U-3.A. BATTERY CAPACITY TESTS (Oyster Creek Nuclear Generating Station)
Enclosed is a revised copy of our evaluation of Systematic Evaluation Program Topic VIII-3.A. Battery Capacity Tests. This report has been revised to reflect the comments provided by your letter of May 25, 1979.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is co@leted.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
SEP Topic VIII-3.A I
cc w/enclost:re:
See next page 7101/103 G f
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DEisenhut Mr. I. R. Finfrock, Jr.
WRussell RPurple Vice President - Generation DCrutchfield Glainas Jersey Central Power & Light Company HSmith RTedesco Madison Avenue at Punch Bowl Road RSnaidex TNovak Morristown, New hrsey 07960 WPaulson RDiggs NSI, Buchanan
Dear Mr. Finfrock:
more RE: SEP TOPIC VIII-3.A. BATTERY CAPACITY TESTS (OysterCreekNuclearGeneratingStation)
Enclosed is a revised copy of our evaluation of Systematic Evaluation Program Topic VIII-3.A. Battery Capacity Tests. This report has been revised to reflect the coments provided by your letter of May 25, 1979.
This assessment compares your facility, as described in Docket No.
50-219 with the criteria currently used by the regulatory staff for licensing new facilities. Please inform us if your as-built facility differs from the licensing basis assumed in our assessment within 90 days of receipt of this letter.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. This topic assessment may be revised in the future if your facility design is changed of if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely, Dennis M. Crutchfield, Chief Oper ting Reactors Branch f5 a
Division of Licensing
Enclosure:
SEP Topic VIII-3.A cc w/ enclosure:
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l SEP TECHNICAL EVALUATION.
TOPIC VIII-3.A BATT".Y CAPACITY TESTS FINAL DRAFT OYSTER CREEK Docket No. 50-219 C
December 1979 o
12-20-79 i
SEP TECHNICAL EVALUATION
.I TOPIC VIII-3.A j
BATTERY CAPACITY TESTS FINAL DRAFT OYSTER CREEK Topie VIII-3.A Station Battery Test Requirements The objective of this review is to assure that all the onsite Class IE batteries have their capacity to supply all safety related D-C loads verified by periodic testing.
The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BIP EICSB 6, and the " Standard Technical Specifications for General Electric Boiling Water Rasetors" (NUREG-0123). The required tests are as follows:
(1) At least once per 18 months, during shutdown, a battery service test should be performed to verify that the battery capacity is adequate to supply and Oi maintain in operable status all of the actual emer-gency loads for two hours.
(2) At least once per 60 months, during shutdown, a battery discharge test should be performed to veri-fy that the bactery capacity is at least 80I of the manufacturer's rating.
The Oyster Creek Nuclear Station Technical Specifications include, in Sections 4.7.A and 4.7.B. the requirements that the station and DG start battery units are load tested every six months. The load test is equivalent to a battery discharge test and encompasses the battery service test. 7CP&L has requested in Technical Specification Request No. 67 to extend this period to 28 months.
The current and proposed Technical Specification battery surveil-lance requirements satisfy the current licensing requirements. No additional SEP action is required.
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n References 1.
"0yster Creek Technical Specifications", Jersey Central Power &
Light Company.
2.
Standard Review Plan, Appendix 7-A, BTP EICSB 6, " Capacity Test Requirements of Station Batteries-Technical Specifications,"
U.S. Nuclear Regulatory Commission.
3.
"IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations," Std. No. 308-1974, The Institute of Electrical and Electronics Engineers, Inc.
4.
"IEEE Reconumended Practice for Maintenance, Testing, and Replace-ment of Large Lead Storage Batteries for Std. No. 450-1975, The Institute of Electrical and Electronies Engineers, Inc.
5.
" Standard Technical Specifications for General Electric Boiling Water Reactors," NUREG-0123, U.S. Nuclear Regulatory Consnission.
O 6.
CP&L letter (Finfrock) to NRC, dated May 25, 1979.
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