ML20008G094
| ML20008G094 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/29/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008G093 | List: |
| References | |
| TASK-08-03.A, TASK-8-3.A, TASK-RR NUDOCS 8107020226 | |
| Download: ML20008G094 (1) | |
Text
E CLOSURE TOPIC: VIII-3.A STATION BATTEF.Y CAPACITY TEST REQUIREMENTS I.
INTRODUCTION h
To assure that the onsite Class 1E battery capacity is adequate to supply de power to all safety related loads required by the accident analyses and is verified on a periodic basis, we reviewed the Technical Specifications, including the test program, with regard to the require-ment for periodic surveillance testing of onsite Class 1E batteries and the extent to which the test meets Section 5.3.6 of IEEE Std 308-1971 to determine battery capacity.
This effort is needed to ensure that the test to determine battery capacity includes (1) an acceptance test of battery capacity perform-ed in accordance with Section 4.1 of IEEE Std. 450-1975, (2) a per-formance discharge test listed in Table 2 of IEEE Std. 308-1971, performed according to Section 4.2 and 5.4 of IEEE Std. 450-1975; and (3) a battery service test described in Section 5.6 of IEEE Std. 450-1972, to be performed during each refueling operation.
II. REVIEW CRITERIA The review criteria are prasented in EG&G Report 1321 F, " Battery Capacity Tests."
III. RE dTED SAFETY TOPICS AND INTERFACES None IV. REVIEW GUIDELINES See Introduction V.
EVALUATION The Oyster Creek Nuclear Station battery surveillance requirements are included in Sections 4.7. A and B of the station Technical Speciff-cations. These requirements are in agreement with the staff's requirements.
VI. CONCLUSIONS The staff finds that the testing of the tm teries is in encordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BTP EICSB 6, and the " Standard Technical Specifications for General Electric Boiling
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Water Reactors" (NUREG-0123); and is, therefore, acceptable.
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