ML19319E075
| ML19319E075 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/20/1976 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19319E076 | List: |
| References | |
| NUDOCS 8003310586 | |
| Download: ML19319E075 (3) | |
Text
MRC DISTRIBUTION FOR PART 50 DOCICFT MATER!AL, (TEMPORARY FORM)
CONTROL NO: 1105 3
FILE:
FROM: SM5D DATE OF DOC D ATE REC'D LTR TWX RPT OTHER Sacramento, Calif. 95813
__.I A Mattimoe 1-20-76 2-5-76 XX g
TO:
ORIG CC OTHER SENTURC PDR Mr. Robert Reid 1 signed 39 SENT LOCAL PDR-XX___
CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-312 DESCRIPTION: Ler trans the following:
ENCLOSURES: Addenda to Proposed Teach Spec Amdt #38 in re to hydraulic snubbet (40 cys enc 1 rec'd).
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. PLANT NAME: Rancho Seco
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SAyETy FOR ACTION /INFC RMATION pmr 9n DHL 2-6-76 A$~SIGNEO AD ASSlCEED BRANCl! ClllEF kMANCllClllEF REID (6)
PROJECT MANAGER
@ROJECT MANAGER ROONEY LIC ASST.
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INTERNAL DISTfflI3UTION 6EG P11D SYSTEMS S AFETY Pl./.?:T SYSTFMS SITE SAFLTY & ENVIRO ANALYSIS Wj! RG r u.(
llEINEMAN TEr4'SCO DENTON MULLER guELD SCllROEDER BENAROYA dOSSICK/ STAFF LAINAS ENVIRO TEC!!.
SrrE ANALYS)S M&E (2)
ENGINEEl:1NG IPPOLITO ERNST VOLLMER MlPC MACCA!!Y BALLARD EUNCll KNIGi!T OPERATINO REACTO'IS SPAUGLER J. COLLIN3 PROJECT MANAGEME!TT SlHWEIL STELLO KRECER BOYO PAWLICKI SI,T]E TECll.
P. COLLINS OPER AT11:G TECII.
GRCIILL AT61 IIOUSTON REACTOR SAFETY d.lSEN110T STEPP SALTZMAN PETERSON ROSS
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NOVAK WBAER I!ELTEMES ROSETOCZY ESCIINENCER MISCELLANEOUS CllECK dRIMES EXTL'r<NAL DISTRIBUTION M.OCALPDR Sacramento, Calif.
NATIONAL LAB U/
CYS BR00RllAVEN NAT. LAB sff1C g/IIECJON V-1&E-(W/sLUUT CREEK)
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Regu atory Docket Fila 3.'
uuo SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830, Sacramento, California 95813: (916) 452-3211 January 20
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Robert W. Reid, Chief I
Operating Reactors Branch No. C d,
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N Re:
(1) Robert W. Reid to E. K. Davis Letter dated December 19, 1975 (2) Proposed Amendment to Rancho Seco Unit 1 Technical Specification, No. 38
Dear Sir:
In reply to the above referenced letter, enclosed is the addenda to our proposed Technical Specification Amendment No. 38, based on the requirements stated in the model specifications.
However, some state-
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ments are necessary in order to describe the hydraulic shock suppressors at Rancho Seco and the high reliability we have observed in order to justify the contents of the proposed Technical Specification Amendment.
The hydraulic shock suppressor system at Rancho Seco consists of 97 Bergen-Patterson and 38 Grinnell units on Class I components. All suppressors have been inspected, tested and altered according to previous IE Bulletins Nos. 73-3, 73-4 and 75-5.
A technical specification was added to the Rancho Seco license requiring specific testing requirements.
The tests to date include sixteen complete inspections of the accessible units totaling 928 individual inspections and six complete inspections of-the inaccessible units totaling 962 individual inspections. Of the 1390 total inspections, only four snubbers have been found to have a film of oil around the reservoir seal.
None of the suppressors indicate oil leakage through the plunger seals.
All inspections have concluded that there have been no failurec at Rancho Seco since initiating the surveil-lance program.
The surveillance program required by Paragraph 4.14. " Safety Systems Hydraulic Snubbers", of our Technical Specifications provides for routine inspection of all units for evidence of hydraulic fluid leakage and a periodic evaluation of seal condition.
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Robert W. Reid, Chief
' Operating Reactors Branch No. 4 January 20, 1976
.We do not propose to institute a test program requiring the rceoval of suppressors for bench testing to verify the ability of the unit to " lockup".
It is our opinion that the design of the
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hydraulic control device is such that it is not subject to setpoint drift without a related breakdown or failure of components. The shop testing verified the proper selection of orifice sizes and poppet valve spring rates.
If any-component degradation is occurring it j
will be detected.during the inspections required by our current sur-veillance procedure which will remain in effect until NRC approval' of proposed addenda to Technical Specification Amendment No. 38, which is attached to this letter.
Respectfully,
&.'A /J!,jn t L A A
. Mattimoe Assistant General Manager and Chief Engineer 1.
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