ML19317H010
| ML19317H010 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/21/1977 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020687 | |
| Download: ML19317H010 (2) | |
Text
_ _ -.
w NR 196 U.s. NUCLEAR EE!ULATMY Cop poM oOCKg NUMBE R 3O=jl1 1246) p NRR. DISTRIBUTION rom PART 50 DOCKET MATERIAL TO:
FROM:
oats OP oOCUMENT Sacramento Municipal Utility Dist.
10/21/77 Mr. Robert W. Reid Sacramento, California oATE RECEivEo J. J. Mattimoe 10/27/77 ggTTER O NOTORIZEo PROP
!NPUT PORM NUMSER OF COPIES RECEIVEo hRlGINAL U NCLAS$lPIE o OCoPv l
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p.e o u.r Consists of info re. NRC request for info.
concerning the adequacy of the Rancho Seco Unit No. I reactor vessel supports.........
4 PLANT NAME: Rancho Seco Unit No.1 RJL 10/28/77 (1-P)
DISTRIBUTION POR REACTOR VESSEL SUPPORT INFO FOR OPERATING REACTORS PER MR. TRAMMELL 7-12-76 O
SAFETY FOR ACTION /INFORMATION ASSIGNED ADt M lif tr RRANCH CMTRFt ANI d PROJECT MANAGERr E PIf KSOM LIC. ASST:
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BOSNAK ROSZTOCZY CHECK C. TRAMMELL SHAO P. BARAN0WSKY P. NORIAN R. BOSNAK V. NOONAN EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR
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. sMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 s street. Box 15830, sacramento, Califomia 95815; (916) 452-3211 October 21, 1977 fib) 8!cy)g0 Director of Nuclear Reactor Regulation
[N 007 Attention: Mr. Robert W. Reid, Chief D $77 j Operating Reactors, Branch 4 u,,,,,,c,@m,2,%
U. S. Nuclear Regulatory Comission I
c hf Washington, D. C.
20555 6t
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Docket No. 50-312
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Rancho Seco Nuclear Generating
'!/I iOV Station, Unit No. 1
Dear Mr. Reid:
Your letter of June 9,1976 addressed concerns relative to the reactor vessel support system assuming an instantaneous double-ended guillotine break of the primary system piping inside the reactor cavity.
Our letter of September 20, 1976 informed you that the District was participating in a Babcock & Wilcox Ownbrs Group to evaluate the prob-ability of a failure of the reactor coolant system within the cavity to determine if the probability of occurrence of this particular incident is acceptably low that further analysis of the vessel support system is not warranted.
The results of this probability study were submitted to Dr. Charles Trammel, Project Manager, Division of Operating Reactors, on September 27, 1977 by Science Applications, Incorporated as Topical Report No. SAI-050-77-PA, "An Analysis of the Probability of Pipe Rupture at Various Locations in the Primary Cooling Loop of a Babcock
& Wilcox 177 Fuel Assembly Pressurized Water Reactor - Including the Effects of a Periodic Inspection." This analysis is similar to that in a report submitted by the Combustion Engineering Users Group but has taken advantage of experience gained in preparation and NRC review of that report and appropriately expands the depth of analysis.
By this letter, the District endorses the SAI Topical Report and it's conclusions.
We believe that it fully satisfies your request for information concerning the adequacy of the Rancho Seco Unit No.1 reactor vessel supports.
We are available to discuss the features of this report with you as required.
Sincerely yours, bbf Q
d
. Mattimoe Assistant General Manager and Chief Engineer h e 1xtua 1rA m m a se r e m,.~
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