ML20059E213
| ML20059E213 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/04/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E207 | List: |
| References | |
| NUDOCS 9009100091 | |
| Download: ML20059E213 (3) | |
Text
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g#*g UNITED STATES
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( j' a NUCLEAR REGULATORY COMMISSION WASMGTON, D. C. 20666 I
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED T0- AMENDMENT NO.142 TO PROVISIONAL OPERATING LICENSE NO. DP.1 16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATIJO DOCKET NO. 50-219 INTRODUCTION By. letters dated February 20, 1990 and April 11, 1990 as superseded by letter dated July 24, 1990, GPU Nuclear. requested a change to the Technical Specifications (TS) pertaining to the surveillance requirements of the Oyster Creek diesel generator and station batteries.- The revised wording would be as follows:
4.7 B.3 At least once per 12 manths, the diesel generator battery capacity shall be demonstrated to be able to supply the-design duty loads (diesel start) during a battery service test.
4.7 B.4.
At least once per 24 months'during shutdown. the following tests will be performed to verify battery capacity.:
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a.
Battery capacity shall be demonstrated to be at least 80% of the manufacturer's rating when subjected to a ba tery capacity' discharge test to be considered operable.
b.
Any. battery which is demonstrated to have less than 85% of manufacturers ratings during a capacity discharge test shall be replaced during the subsequent refueling outage.
c.
Station battery capacity shall be demonstrated to be able to' supply-the design duty cycle loads during a battery service test.
d.
Battery low voltage annunciators are verified to pick up at 115 volts i 1 volt and to reset at 125 volts i 1 volt (Diesel; 112 volts i 1 volt).
9009100091 900904 DR ADOCK C9000219 PDC 1
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The Basis section of the TS would also be changed to reflect the changes in the battery tests.
EVALUATION:
The present TS 4.7 B.3 and 4.7 A.5 requires static,n battery and diesel generator battery capacity testing at least once per 18 months during shutdown and requires that the battery capacity be at least 80% of the manu"acturers's rating.
Veri-fication of the battery low voltage announciators are also conducted on an 18 month cycle.
The proposed TS would relax the testing interval <from 18 months to 24 months, but would require replacement of the battery iuring the subsequent J
refueling outage if the battery capacity becomes less than 85% of the manufac-turer's rating, or immediate replacement if the battery capar.ity becomes equal or less than 80% of the manufacturer's rating.
l The proposed TS adds a requirement to conduct a station btttery service test every 24 months and a diesel generator battery test every 12 months:to demon-strate the batteries' capacity to supply the design duty cycle loads.
This represents a significant addition to the present TS which does not require a service test for either battery.
The NRC staff concludes that the requirement to replace the battery during the subsequent refueling outage, once the battery capacity becomes less than 85%
of the m ufacturer's rating, appropriately compensates for the extension from 18 months to 24 months of batt wy capacity testing and low voltage annunciator verification.
Also, the additional service tests that are required under the proposed TS should add significantly toward assuring that the battery can per-form its safety function. We therefore find the proposed TS changes to be acceptable.
A proposed change to the Oyster Creek station battery and diesel generator battery Technical Specifications would add battery service tests and lengthen the interval between battery capacity tests and battery low voltage announciator verifica -
tion.
However, if the battery capacity becomes less than 85% of the manufac-turer's rating, the battery would be replaced during the next refueling outage.
The staff has reviewed the proposed TS changes and concludes that they should result in an increase in the assurance of the batteries to perform their sa'ety function. We therefore find the proposed TS changes to be acceptable.
ENVIRONMENTAL CONSIDERATION The aaendment changes a requirement with respect to the installation or use of a t acility component located within the restricted area as defined in 10 CFR Part 20. We have determined that the amendment involves ~no significant increase in the amount 3, and no significant change in tha tyoae, of any effluents that may be released offsite, and that.there is no signif -
icant increase'in individual or cumulative occurGional radiation exposure.
The staff has previously issued a proposed finding that this amendment involves no significant hazards considerat'on and there has been no public comment on such finding.
Accordingly, the amendment meets the eligibility i
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criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuancelof this amendment.
CONCLUSION The staff has concluded, based on the consideration', discussed above, that (1) there is reasonable assurance that the health r,ci safety of the public will not be endangered by operation in the proposec manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security nor to the health and safety of the public.
Dated:
SP9'*~5er 4, 1990 Principal Coraren; tor:
A. Toalston i
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