ML17257A513
| ML17257A513 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/31/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-08-03.A, TASK-8-3.A, TASK-RR LSO5-81-07-097, LSO5-81-7-97, NUDOCS 8108050191 | |
| Download: ML17257A513 (12) | |
Text
1 July 31, 1981 Docket No. 50-244 LS05>>81<< 07-097 Mr. John E. Maier, Vice President Electric Im Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York-14649
Dear Mr. Maier:
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SUBJECT:
SAFETY EVALUATION FOR SEP TOPIC VIII-3.A, STATION BATTERY CAPACITY TEST REQUIREMENTS (GINNA)
As requested by your letter of July 10. 1981, a copy of report 1315F is enclosed.
Please note that this report was copied almost verbatilm in the original staff SER that was transmitted on April 18, 1979.
joe April 1P, 1979 SER was reissued on June 12, 1981, in order to achieve a more consistent format to ease the preparation of the integrated assess-ment.
We regret that our evaluation did not adequately reflect the concerns of our original SER and necessitated your letter.
We have revised our SER to more clearly express our concern, Our revised report is enclosed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 Division of Licensing
Enclosure:
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Docket Ho. 50-244 LS05 Mr. John E. Maier Vice President Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Maier:
SUBJECT:
SAFETY EVALUATION FOR SEP TOPIC VIII-3.A, STATION BATTERY CAPACITY TEST RE(UIREMENTS ((GINNA)
As requested by your letter of July 10, 1981, a copy of report 1315F is enclosed.
Please note that this report was copied almost verbatum in the original staff SER that was transmitted on April 18, 1979.
The April 18, 1979 SER was reissued on June 12, 1981, in order to achieve a more consistent format to ease the preparation of the integrated assess-ment.
We regret that our evaluation did not adequately reflect the concurrence of our original SER and necessitated your letter.
We have revised our SER to more clearly express our concern.
Our revised report is enclosed.
Sincerely,
Enclosure:
As stated Dennis M. Crutchfield, Chief Operating Reactors Branch ¹5 Division of Licensing cc w/enclosure:
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Yir. John E. Maier
. CC Harry H. Yoigt, Esquire
- LeBoeuf, Lamb, Leiby and NacRae 1333 Hew Hampshire
- Avenue, N. M.
Suite 1100 Mashington, D. C.
20036 Nr. Nichael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center Hew York, Hew York 10047 J effrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223
- Director, Bureau of Nuclear Operations State of Hew York Energy Office Agency Building 2 Empire State Plaza
- Albany, Hew York 12223 Rochester Public Library 115 South Avenue Rochester, Hew York 14604 Nr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, H.
W.
Suite 600 Mashington, D. C.
20006 U. S. Environmental Protection Agency Region II Office ATTN'IS COORDINATOR 26 Federal Plaza Hew York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comaission Washington, D. C.
20555 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R.
E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519
1315F SEP TECHNICAL EVALUATION TOPIC VIII-3.A BATTERY CAPACITY TESTS FINAL DRAFT R. E.
GINNA Docket No. 50-244 December 1979 E.
W. Roberts 12"20-79
4 1
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P TECHNICAL EVALUATION TOPIC VIII-3.A BATTERY CAPACITY TESTS FINAL DRAFT R. E.
GINNA Topic VIII-3.AStation 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, BTP EICSB 6, and the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (NUREG-0452).
The required tests are as follows:
(1)
At least once per 18 months, during shutdown, a
batter service test should be performed to verify that the battery capacity is adequate to supply and 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 battery capacity is at least 80! of the manufacturer's rating.
The R. E. Ginna Nuclear Station battery surveillance requirements, are included in Section 4.6.3 of the station Technical Specifications'hese specifications require a battery rated load discharge test at each refueling outage;
- however, they do not require a battery service test.
Therefore, the R. E. Ginna Nuclear Station deviates from current'icensing requirements in that its Technical Specific'ations do not require a battery discharge test and these specifications do not indi-cate that the battery load test verifies that the battery capacity is adequate to supply and maintain in operable status all of the actual emergency loads for two hours.
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This deviation will e evaluated in the context of the Design Ba'sis Events (DBE) that rely upon these components for mitigating <he consequences of the DBE. If this deviation is determined to be unac-
- ceptable, thy Technical Specifications..will be appropriately revised.
References 1.
"Ginna Technical Specifications,"
Rochester Gas 6 Electric Company.'.
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.
"IEEE Recommended Practice for Maintenance,
- Testing, and Replace-ment of Large Lead Storage Batteries for Std.
No. 450-1975, The Institute of Electrical and Electronics Engineer's, Inc.
5.
"Standard Technical Specifications for Westinghouse Pressurized Water Reactors,"
NUREG-0452, U.S. Nuclear Regulatory Commission.
~To ic:
VIII-S.A STATION BATTERY CAPACITY TEST REOUIRENENTS INTRODUCTIOH To assure that the onsite Class lE battery.capacity is adequate to supply dc power to all safety related loads required by the accident analyses and is verified on a periodi'c basis, we reviewed the Tech-nical Specifications, including the test program, with regard to the
'equirement for periodic surveillance testing of onsite Class lE batteries and the extent to which the test meets Section 5.3.6 of IEEE St.
308-1971, to determine battery capacity.
This eff'ort is needed to ensure that the test to determine battery capacity includes (1) an acceptance test of battery capacity performed in accordance with Section 4.1 of I'EEE Std.
450-1975, (2) a performance discharge test listed in Table 2 of IEEE Std. 308-1971, and (3) a battery service test described in Section 5.6 of IEEE Std. 450-1972, to be performed during each refueling operation REVIEW CRITERIA The review criteria are presented in EGEG Report 1315F, "Battery Capaci ty Tests. "
'ELATED SAFETY TOPICS AND INTERFACES None IV.
VI.
REVIEW GUIDELINES See Introduction EVALUATION The R. ED Ginna Nuclear Station battery surveillance requirements are included in Section 4.6.2 of the station Technical Specifications.
There is no periodic battery discharge, test required.
Therefore, the Ginna Nuclear Station does not comply with the current licensing requirements for station battery capacity tests.
It is the staff's position that the battery discharge test is a more severe test than that being used presently and should be adooted.
CONCLUSIONS The staff proposes 'that the testing of the batteries be in accordance with IEEE Standa'rd 450-1975, IEEE Standard 308-1974, BTP EICSB 6, and the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (HUREG-0452).
The proposed tests are as follows:
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tes't should be performed to verify that the battery caoacity is adequate to supply and maintain in operable status all of the actual emergency loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2.
At least once per 60 months, during shutdown, a batter dischar e
test should be performe'd to verify that the battery capacity is at least 80% of the manufacturer's rating.