ML19317G938
| ML19317G938 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/11/1976 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020596 | |
| Download: ML19317G938 (2) | |
Text
____ _ ___ ___ __ _________ ________ - _ __ __ -_ - -_-____ _
.U.O. NUCLE AN REGULATcMY COMMIP."N DOCKET NUMBER NHC penM 196 q
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50-312 u r::...
- NRC DISTRIBUTION rOR PART 50 DOCKET MATERI AL TO:
FROM:
DATE OF DOCUMENT Sacramento Municipal Utility Dist.
8/11/76 Mr. Robert W. Reid Sacramento, California oATE RECEivEo J. J. Mattimoe 8/16/76 MLETTER ONoToRIZED PROP INPUT FORM NUMBER OF COPIES PECEIVED One Signed gORIGIN AL NC LASSIFIE D OcoPy DESCRIPTION ENCLoSU RE Ltr. re our 6/30/76 ltr...concerning the reactor coolant system pressure temperature limits contained in tech specs.
PLANT NAME:
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Rancho Seco SAFETY FOR ACTION /INFORMATION ENVTRO 8/18/76 R TL ASSIGNED ADr l ASSIGNED AD:
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BRANCH f'HTEFe K BRANCH CHIEF:
Reid PROJECT MANAGER:
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g-SACRiMENTo MUsuuo DISTRICT C 6201 S street, Box 15830, Sacramento, California 95P13; (916) 452 3211
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gb August i1,1976 Y
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s Director.of Nuclear Rd$ tor Regulation g*
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Attention: Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 e um%
U. S. Nuclear Regulatory Commission E%
Washington, D. C.
20555 50-3Ia
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Dear Mr. Reid:
1 In your letter of June 30, 1976, you requested a review of the reactor coolant system pressure-temperature limits contained in the Technical Specifications to determine if they are in full compliance with Appendix G.
Our review indicates that the reactor coolant system pressure-temperature limits contained in the Technical Specifications were not prepared in accordance with Appendix G, 10 CFR 50. However, the current operating limitations have margins of safety equal to or exceeding those required by Appendix G to 10 CFR 50, for the period of operation to the removal and the completion of testing of the first reactor vessel sur-veillance capsule.
The previous statement is justified by comparison of the present limits of the Technical Specifications with the limits calculated in accordance with Appendix G for a typical Oconee plant.
The Appendix G limits for the typical plant are presented in Topical g
Report 10046P. At the completion of the examination of the capsule data, i
new reactor coolant system pressure-temperature limitations will be established which will be in full compliance with the requirements of Appendix G,10 CFR 50. The methods of compliance are presented in Topical Report BAW 10046P.
,1 Sincerely yours,
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J. J. Mattimoe Assistant General Manager and Chief Engineer 0h J
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