ML13333A437
| ML13333A437 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/07/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | James Drake Southern California Edison Co |
| References | |
| TASK-08-03.A, TASK-8-3.A, TASK-RR NUDOCS 7911270508 | |
| Download: ML13333A437 (4) | |
Text
0I D
BUTION Local PDR ORB #2 Reading NRR Reading Docket No. 5U-206 DGEisenhut HRVollmer DLZiemann HSmith PWO'Connor OELD Mr. James H. Drake I&E (3)
Vice President DCrutchfield (2)
Southern California Edison Company JRBuchanan 2244 Walnut Grove Avenue TERA Post Office Box 800 ACRS (16) kosemead, California 91770
Dear Mr. Drake:
RE:
CUNPLETION OF SEP TOPIC VIII-3.A Your letter dated December 21, 1978, indicated that you have examined our draft evaluation of the subject topic dated November 24, 1978. You suggested editorial or corrective changes to the assessment to make it more accurately reflect your facility design.
We have incorporated your suggested modifications in the enclosed assessment. With these modifications our review of SEP Topic VIII-3.A is complete and will be a basic input to the integrated assessment of your facility.
The subject assessment compares your facility design with the criteria currently used by the staff in licensing new facilities. This assessment may need to be re-examined if you modify your facility or if the criteria are changed before we complete our integrated assessment.
Sincerely, Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosure:
Completed SEP Topic VIII-3.A cc w/enclosure:
See next paye PISULATO RY ncKET FILE COPY DOR:ORB #2 DOR:SEPB aDOR DOR:ORB #2 OFFICE SURAM ~PWO'Connor:ah JKnight 9 DCr t~f~dDLZiemann SU R N A M E DT.10/ /7.9 1
/79 1 / -7 /79 14 /5/79 1el o e
NRC FORNM38?-6 R h"3?.
GO\\/V E N T( -D;NTING OFF-ICE: 1979-289-369
Mr. James H. Drake 2 -
November 7, 1979 cc w/enclosure:
Charles R. Kocher, Assistant General Counsel Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Samuel B. Casey Chickering & Gregory Three Embarcadero Center Twenty-Third Floor San Francisco, California 94111 Jack E. Thomas Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 U. S. Nuclear Regulatory Commission ATTN:
Robert J. Pate P. 0. Box 4167 San Clemente, California 92672 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 K M C, Inc.
ATTN:
Richard Schaffstall 1747 Pennsylvania Avenue, N. W.
Suite 1050 Washington, D. C. 20006
SYSTEMATIC EVALUATION PROGRAM BATTERY CAPACITY TESTS SAN ONOFRE DOCKET NO: 50-206 Topic VIII-3.A Station Battery Test Requirements The objective of this review is to assure that the onsite Class IE battery capacity to supply all safety related 0-C loads is verified by periodic testing.
The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, 8TP 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 battery service test should be performed to verify that the battery capacity 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 battery discharge test should be performed to verify that the battery capacity is at least S0%
of the manufacturer's rating.
The technical specifications for the San Onofre Nuclear Station include in Section 4.4 0 the required battery service and discharge tests at the required intervals.
Therefore, the San Onofre Nuclear Station battery tests comply with current licensing requirements.
No additional SEP action is necessary.
November 7, 1979 Complete
References
- 1. "San Onofre Technical Specifications",Southern California Edison Company.
- 2. Standard Review Plan, Appendix 7-A, BT? 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 Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Std. No. 450-1975, The Institute of Electrical and Electronics Engineers, --Inc.
- 5.
"Standard Technical Specifications For Westinghouse Pressurized Water Reactors", NUREG-0452, U. S. Nuclear Regulatory Commission.