ML19317G986
| ML19317G986 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/18/1978 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020646 | |
| Download: ML19317G986 (2) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOt1ING MATERI AL 50-312 REC: REID R W ORG: MATTIMOE J J DOCDATE: 07/18/78 NRC SACRAMENTO MUN UTIL DIST DATE RCVD: 07/19/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL O REQUEST AUTHORIZATION FOR FULL OPERATION AT 100% FULL POWER OF SUBJECT FACILITY.
PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XRS DISTRIBUTOR INITIAL:
- o************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOO1)
FOR ACTION:
BR CHIEF ORB #4 BC**LTR ONLY(7)
INTERNAL:
(pm - n mi m Y(1)
NRC PDR**LTR ONLY(1)
I & E**LTR ONLY(2)
OELD**LTR ONLY(1)
HANAUER**LTR ONLY(1)
CORE PERFORMANCE BR**LTR ONLY({
AD FOR SYS & PROJ**LTR ONLY(1)
ENGINEERING BR**LTR ONLY(1)
REACTOR SAFETY BR**LTR ONLY(1)
PLANT SYSTEMS BR**LTR ONLY(1)
EEB**LTR ONLY(1)
EFFLUENT TREAT SYS**LTR ONLY(11 J.
MCGOUGH**LTR ONLY(1)
EXTERNAL:
LPDR'S SACRAMENTO, CA**LTR ONLY(1)
REGION V**LTR ONLY(1)
TERA **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT B**LTR ONLY(16)
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CONTROL NBR:
782 DISTRIBUTION:
LTR 41 ENCL O SIZE: 1P i
CC**c******************************
THE END 8004020by5
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$ SACRAMENTO MUNICIPAL UTILITY DISTRICT O 62 SMUD 95813; (916) 452-3211 July 18,1978 Director of Nuclear Reactor Regulation Attention:
Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket No. 50-312 Small Break Analysis Rancho Seco Nuclear Generating Station, Unit No.1 r U 9) W M I O 2 Y.' '
Dear Mr. Reid:
[15:
On July 7,1978, the Sacramento Municipal Utility District requested authorization for the operation of Rancho Seco Nuclear Generating Station, Unit No.1, at 100% full power based on a Babcock
& Wilcox Company analysis of a small break loss of coolant accident.
This analysis was based on three proposed model changes to their small break ECCS evaluation model.
Since our request of July 7,1978, the Babcock & Wilcox Company has reanalyzed the snall break loss of coolant accident incor-porating only two of the three proposed model changes.
The revision to the subcooled discharge correlation was not incorporated in this second analysis to avoid concerns expressed by the NRC staff.
This reanalysis has been submitted to the NRC by the Babcock & Wilcox Company in a letter dated July 18, 1978.
The District has reviewed this submittal and finds the conclusions acceptable and applicable to Rancho Seco Unit No.1.
Additionally, by letter dated July 13, 1978, the District has requested a revision to the Rancho Seco Unit (b.1 Technical Specifications to assure that adequate operating procedures remain in effect until plant modifica-tions can be completed to eliminate their necessity.
Based on the Babcock & Wilcox analysis and procedure changes discussed above, we feel we are in full compliance with the criteria of 10 CFR 50.46 and Appendix K of 10 CFR 50 to a steady state power level of 2772 MWt.
In view of this information, we respectfully request you authorize operation of Rancho Seco Nuclear Generating Station, Unit No.1 at 100% full power.
Sincerely yours, 2n.1&A i
J. J. Mattimoe Assistant General Manager and Chief Engineer
- 73;eze27e
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AN ELECTRIC SYSTEM S E RVI N G MORE THAN 600,000 IN THE HEART OF
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