ML19319D907
| ML19319D907 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/09/1977 |
| From: | Kaplan D, Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19319D908 | List: |
| References | |
| NUDOCS 8003270574 | |
| Download: ML19319D907 (3) | |
Text
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e N R C '* '.. 195 U.S. NUCLEAR REGULATORY C ** MISSloN COCKET NUM BE R 50-3/2.
2 3ss
'NRC DISTRIBUTION roR PART 50 DOCKET MATERI AL TO:
NRC FROM:
Sacramento Munigipal Utility DATE oF OoCUMEfGt).77 Sacramento, Calif J J Mattimoc /
DATE RECEIVED 2-14-77
/
YNoToRIZE D PROP INPUT FORM NUMBER oF CoptES RECEIVED
'%rirTE'R
(
YomGINAL
)(UNCLASSIFIE D 3 signed
{ COPY OSSCRIPTioN ENCLOSURE Ltr notarized 2-9-77....trans the following:
Proposed N.1dt to OL/ Change to Tech Specs ii32, Revision #2: Consisting of revisto is bringing facility ventilation systems into agreement with standard' tech specs..........
(40 cys enc 1 rec'd)
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PLANT NAME:
Rancho Seco SAFETY FOR ACTION /INFORMATION vmrTun z-i*-//
ent ASSIGNED AD:
ARRTCMUD An.
/ BRANCH CHIEFr N C # #4
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RRANFR PMTTU.
/ PROJECT MANAGER:
12 a o r 4 *4 PROJECT MANAGER:
/JJC. ASST. :
1 ri3km LIC. ASST._:
J INTERNAL DISTRIBUTION M2EG FTTS)
SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &-
( NRC PDR, HEINEMAN TEDESCO ENVIRO ANALYSTS
/ I & E ('k/
SCHROEDER BENAROYA DENTON & MUTUR
/ OELD T.A T'IA R
/ GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH.
MIPC MACARRY KIRKWOCD ERNST CASE KNIGHT BALLARD HANAUER SIHWEIL OPERATING REACTORS SPANGLER HARLESS PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH.
GAMMILL BOYD ROSS
/
EISENHUT STEPP P., COLLINS NOVAK
/
SHAO HULMAN HOUSTON ROSZTOCZY
/
BAER PETERSON CHECK
/
BITTLER SITE ANALYSIS l
MELTZ
/
GRIMES VOLLMER HELTEMES AT & I BUNCH l
SKOVHOLT SALTZMAN
/
J. COLLINS
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RUTBERG KREGER l
EXTERNAL DISTRIBUTION CONTROL NUMBER l
/ LPDR: 5A( w a M 6 A NAT. LAB:
BROOKHAVEN NAT. TAR, S 0 0 3 2'T 0 E7
/ TICt
/
REG V.IE ULRIKSON (ORND
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CONSULTANIS:
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a' -SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento, California suu 95813; (916; 452 3211 Feb ru a ry '), IS'7
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Director, Reactor Licensing
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Office of Nuclear Reactor Regulation H;Q bE5.Q gg
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U. S. Nuclear Regulatory Commission 7'
Uashington, D.C.
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Docket Mo. 50-312
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Proposed Amendment Ho. 32, f_,
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Revision 2 Rancho Seco fluclear Generating
[ -
Station, Unit No. 1 I
Dear Sir:
d in accordarce with 10 CFR 50.59, the Sacramento i icipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco !!uclear Generating Station, Unit ilo. 1, by submitting forty (40) copies of Proposed Acendment flo. 32, Revision 2.
This proposed amendment brings the facility ventilation systems into agreement, wherever possible, with the latest Standard Technical Specifications and applicable standards.
You will notice in the attached replacement pages, which comprise Proposed Amendment No. 32, Revision 2, that the title of Specification 4.11 has changed f rom " Reactor Building Purge Filtering System" to
" Auxiliary and Spent Fuel Building Filter System".
This constitutes deleting the current specification on the Reactor Building Purge Filter.
The reason is that this filter is not used or required for any analyzed accident at the facility.
In addition, if any release of radioactive j
material should occur during a Reactor Building Purge, the Reactor Puilding high radiation interlock to the purge fan would terminate the discharge.
The Reactor Building Purge System penetration valves are Safety Features closed in the facility design accident.
Their testing is covered by a separate section in the Technical Specifications. While deletion of this system from the Technical Specifications is justified by its non-safety related function, the system will still be maintained and operated to insure the requirements of Regulatory Guide 1.112 are met.
In addition, the environmental effects of a dropped spert fuel assembly in the Reactor Building were analyzed, without taking credit for this filter, and reported as the Class VI accident in the Mncho Seco Envi ronmental Report.
1' dub
e D i rec to r,
Reactor Licensing February 9, 1977 The other significant change by Proposed Amendment No. 32, Revision 2, is deletion of the requirement to perform an in place leakage test on the Reactor Building Emergency Filtering System.
Since this system is fully contained within the Reactor Building, where it provides recirculation ai r cleanup in the post-LOCA atmosphere, it satisfies the conditions of ANSI N510-1975, Table 1, for which such testing is unnecessary.
Added to the existing license are new and specific requirements on the Auxiliary and Spent Fuel Building Filter System.
The Auxiliary Building service provided by this system had not previously been considered as being safety related.
A detailed review of the potential non-LOCA design accidents has revealed that credit has been taken for this filter system in those analyses.
Hence, it is now proposed to add requirements to the facility license which will Insure that tiie assumed effectiveness of the filters will be available.
Respectfully submitted, SACRAMENTO MUNICIPAL UTILITY DISTRICT i
OY DA FIL 1 Le al Counsel fJgJ.Mattimoe Assistant General Manager Sacramento Muni ipal an e Engineer Utility District Subscribed and sworn to before me this /M day of February,1977 1
i
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.y Jean Heslep, Notary Public in and for the County of Sacramento, State of California My Commission Expi res March Ii, 1978 JJM:DDW:Im1 4tnummmet:.uncumr:mm.m,,---
Enclosure g
JEAN HESLEP I
i NOTARY PUBLIC-CAllMRNIA 5 lfpA.
PellNCIPAL OFFICE IN gj u
j SACRA.\\ LENTO COU.\\ TY y
@ My Cem. mission Expires furch 11. 1073 )
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