ML19317G768
| ML19317G768 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/02/1978 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004010596 | |
| Download: ML19317G768 (1) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
~...DISTRIBUTION FOR INCOMING MATERIAL 50-312 REC: STELLO V ORO: MATTIMOE J J DOCDATE: 03/02/78 NRC SACREMENTO MUN UTIL DIST DATE RCVD: 03/07/78' DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 0 RESPONSE TO NRC"S LTR DTD 01/25/78... FURNISHING INFO RE APPLICANT"S INTENTION TO PROCEED ' ETH AN EVALUATION OF THE ASYMMETRIC LOSS OF COOLANT ACCIDENT LOAD..
1 PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITI AL:
oo*oo************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOO1)
FOR ACTION:
BR CHIEF REID Y(7)
INTERNAL:
REG FILE **LTR ONLY(1)
NRC PDR**LTR ONLY(1)
& E**LTR ONLY(2 OELD**LTR ONLY(1)
HANGUtnewLaM UNLY(1)
CHECK **LTR ONLY(1)
EISENHUT**LTR ONLY(1)
SHAO**LTR ONLY(1)
BAER**LTR ONLY(1)
BUTLER **LTR ONLY(1)
GRIMES **LTR ONLY(1)
J COLLINS **LTR ONLY(1)
J.
MCGOUGH**LTR ONLY(1)
EXTERNAL:
LPDR'S SACRAMENTO, CA**LTR ONLY(1)
REGION V**LTR ONLY(1)
TIC **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT B**LTR ONLY(16)
DISTRIBUTION:
LTR 41 ENCL O CONTROL NBR:
vvvvvv038 Af
- d l SIZE: 1P T!
- kk d
oo**oo***e*************************
THE END 8004010576
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$~- SACRAMENTO MUNICIPAL UTILITY DISTRICT 0 SMUD g
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1 s street, Box 15a30, sacramento, California 95813; (916) 452-3211 March 2, 1978 Director of Nuclear Reactor Regulation
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Attention: Mr. Victor Stello, Jr., Director V
$' 86s,M4R Division of Operating Reactors 7 @8
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V. S. Nuclear Regulatory Commission Washington, D. C.
20555 3
g Docket No. 50-312 Rancho Seco Nuclear Generating j0 6
Station, Unit No.1
Dear Mr. Stello:
Your letter of January 25, 1978 requested information regarding our intention to proceed with an evaluation of the asymmetric loss of coolant accident (LOCA) loads.
The Sacramento Municipal Utility District is presently formulating plans for addressing this issue; however, it is too early at this time for these plans to be definitive.
We have been working in the asymmetric LOCA loads subject areas since being notified i'n October 1975, by the NRC, of a potential safety question and look forward to a complete and orderly resolution of this issue on operating plants. As a result of receiving the above letter on February 6,1978, we met with the other members of the B&W Owner's Group to discuss the contents of the letter. This meeting led us to believe that further NRC clarification of the various requirements of the letter is necessary before proceeding with the development of a dehiled schedule and work scope.
In order for the members of the Owner's Group to obtain the s
desired clarification, it is requested that a NRC-0wner's Group meeting
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be scheduled in March.
Mr. Lou Lanese of GPU Service Corporation, Chairman of the B&W Owner's Group Committee on Reactor Vessel Supports, will be contacting you in the near future to discuss the details of the requested meeting.
Sincerely yours, b
J. J. Mattimoe Assistant General Manager and Chief Engineer l
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