ML19317G961
| ML19317G961 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/20/1976 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020621 | |
| Download: ML19317G961 (2) | |
Text
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U.s. NUCLEAR r+EEULATCGY COMMISP N DOCKET NUMSEO ss m SO - 3 I 2.
v NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL
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FROM:
e DATE OF DOCUMENT
- Mr Reid Sacramento Municipal Util.
9-20-76 Sacraimento, Calif oATE RECEivEe J J Mattimoe 9-24-76 CLETTE R O NOTORIZED PR OP INPUT FORM NUMBER OF COPIES RECEIVED cot,10lN AL SUNcLASSIFIED OCOPy 1 signed DESCRIPTION ENCLOSU RE Ltt re our 6-9-76 ltr...... furnishing addl info concerning reaccor vessel
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cupport system.....
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Rancho Seco #1 DISTRIBUTION FOR REACTOR VESSEL SUPPORT INFO
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FOR OPERATING REACTORS PER MR. TRAMMELL 7-12-76 SAFETY FOR ACTION /INFORMATION 9-27-7b ehf ASy1GriED ADr BRANCH CHTEFt E 4. t d
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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 s street, Box 15830, sacramento, California 95813; (916) 452-3211 September 20, 1976 Ql h (k IQ7 (h
r Director of Nuclear Reactor Regulation
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Attention: _ Mr. Robert W. Reid, Chief eQ g
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Operating Reactors, Branch #4 U. S. Nuclear Regulatory Comission
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20555
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Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Reid:
Your letter of June 9, 1976 expressed concern relative to the reactor vessel support system and requested additional design evaluation of this system. The District, in cooperation with other B&W users, has been reviewing the reactor vessel support concern in separate meetings with our NSSS vendor and several other consultants.
We have also reviewed
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the probability study which was developed by the Combustion Engineering users group and presented to the NRC staff.
l Based on this study and other information currently available, we believe the probability of the occurrence of this particular incident of concern is acceptably remote and no further analysis is necessary.
In order to evaluate and quantify this probability the District, as a part of the B&W users group, plans to have a study perfonned on the probability of a failure of the reactor coolant system in the annular region between l
the reactor vessel and the cavity shield wall. The study is expected to be completed by mid-December and we will at that time discuss the results with your staff.
Sincerely yours, u..^ M ~
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. Mattimoe I
Assistant General Manager and Chief Engineer i
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