ML19317G824
| ML19317G824 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/20/1978 |
| From: | Zwetzig G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004010652 | |
| Download: ML19317G824 (5) | |
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2 September 20, 1978 p
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Docket No. 50-312
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_ LICENSEE: SACRA'4 ENTO NUNICIPAL UTILITY DISTRICT FACILITY: RANCHO SECO NUCLEAR GENERATIHG STATION
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t-SulmARY-0F HEETING HELD ON SEPTEMBER 14,"1973 TO DISCUSS DETAILS OF CERTAIN
@ Pft0 POSED FItE PROTECTION HOBIFICATIONS:
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2 Introduction
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' Arendment.No. 19'to th5 Facility Operating' License, dated February 23. 1978, identified a_ number of modifjcations to be impleraented at the F.ancho Seco Nuclear Generating Station,to-improve'.the protection afforded against M.
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ffres. -Certain of these modifications,'as listed in15ection.3.1 of the i Fire Protection. Safety;E nluation Re usre' marked with an asteriski :1Mr, port;soporting Amendmentkne. -19C....
s asterisk identrfied modifications where ~
the. staff needed addftiemal daformattee Me the form of design -detai.1s.;
-to assure that the dest y was; acceptable"prfor te actual-implementation..?
. The princ.ipal purpose C this meeting was te discuss the licensie's submittal coverirg several of-these asterisked modifications with a view toward determining the acceptability of the proposed detailed design.
In addi-
~ tien, the licensee wished to discuss:the acceptability of a proposed deviation from a previously approved c:odification. All of these issues had been previously submitted to the staff for review t,y'the licensee's letter of-August 28, 1978. ~
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A further satter considered at the meetin was a proposed varici.icn.in the
, modificatfor, described in Section 3.1.35(g) of the Fire Protection ' Safety 1
~JEvaluation' Report.
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.The asterisked rodifications addressed in the licensee'c letter cf /wgust 23, 1970, ud comidore:: at this oceting, are the fallcwin; (nuders refer to the sections of the Safety Evaluation Report):
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THIS DOCUMENT CONTAINS 8004010 $ b POOR QUALITY PAGES
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3.1.1(1). Install-thermal insulation on"func~tionally redundant
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- Channel A,-C'and D conduits (in the Coruputer-Control
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the.high pressure injection syste.: to' prevent, loss'due -.
a 7to fires in cabinet HlRC.
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3.1.1(9).Develcpment of procedure for placing the diesel generators in operation locally' for fires in control room panel'
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3.'T.23(2) and/3.b 24(2)1 Provide 1forTirippfng of tn fu~el cil T E h ' N d;"
n +,MaC* ' & e E : pumps by. actuatten.~. e.f.the;COqq.deee(two.d
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-.further cleriffcation provided at tMs meeting, we a(v.ised the licensee 7.
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that his proposed designs for implementinr the above" modifications were p'
acceptable..
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?The proposed deitation from a previousifiapproved reedification?. dis ~ cussed /
~in' the :1fcansee?s August,23,197bsvlinittalp related toithe pr,ovisieny @g l
of themal insulation for' copper piping tithizing silvdr toldered.!)eints j
^ D widevist. tom ises to set gewide thiedn(1)).;..The"lice
.in fire areas 40, 49, 50-and 58<(Sec..341.31 A
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- :sesyice' raw tieter"crossitie.pipingiin firCereeW71meti.the'auclsarslbdcthe h n
.lieehsee.would. alter the Eplanti conf:tysrstioM te' mahtiin this dess ~L W_
l tie isolated _ at both' ends,,.except when the reactor coolant sistesu makeup'l
- pumppwas ' acting asJa high pressure injection pump due to an '6vtage eft one of the two high pressure injectica pucps.' The lic~ensee bases his '
l request for this deviation on.the high radiation levels present in ~
fire area 50. and the high radiation exposure.that would be incurred-
-(estimated 80 man 2ren) in' implementing the criginally proposed modifi-
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j Based on-the information supplied by the licensee in bis submittal, review
_.of the ef~cctEd piping drawings, additional. clarification pj ovided by;the u
~ DMeensee attthis sonettefa4 the fact"that a f tre in th4s1 areatwoend niet.
cause lossicf'capah114ty to previt%catqup water te_ the, reactor the Jtiff concluded that the requested deviatiori%. Lac'ceptidle and so adItsed the
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g The final ~r.ztter considerdd at the reating dealt With tbc Mar.ncf of provi-ding a low pressure alara en hy @ ogen supply piping in tFe Turnica Buildine (Sec. 2.1.35(1)I.
Ncause the licorsae novt propses to isolete the supply i,,
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pipinrj at a point further upstream (a safer condition) the affected
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i section of the line.would gradually depressurize when isolated, thereby providing a nomal low pressure condition and an alarm. ' To correct this condition the' licensee proposes'a rate-dependent alarm which will_only
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be activiated by greater. than nomal ' leakage rates.. The ~ staff reviewed the design concept for the rate-dependent alarm and advised the licensee that this method for providing'a low pr. essure alam was acceptable.
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m 2 V.. Jerald 8. Zwetzig, Project Manager ;_, A 7
.h; Operating Reectors Branch f4
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GZwetzig:dn ainas f&i6@
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9ll9/78 9'l&l78 9/N/78 n,a w
.s NRC FORat 318 (9 76) NRCat 0240 D u. s. oovsammanr emnymo orricas sete -eae.ea4
ATTACHMENT LIST OF ATTENDEES MEETING ON RANCHO SEC0 FIRE PROTECTION MODIFICATIONS (SEPT. 14,1978)
SMUD Dallas Raasch Robert Daniels NRC James E. Knight
- Gerald B. Zwetzig
- Through previous contact, Mr. Knight also presented the comments and questions of Mr. H. George, also a member of the Rancho Seco Fire Protection Review Team and of the consultant to the Review Team. These other members of the team were subsequently apprised of the additional information provided by the licensee and concurred in the conclusions presented at the meeting by the NRC staff representatives.
~.
o HEETING NOTICE OPSTRIBUTIOil ORBf4 Docket File' NRC PDR L PDR ORBf4 Reading NRR Reading E. G. Case V. Stello D. Eisenhut B. Grimes T. Carter A. Schwencer D. Ziemann T. Ippolito R. Reid EB: DOR P. Check G. Lanis G. Knighton Projectfianaaer Attorney, OELD Ol&E(3)
B. Faulkenberry, I&E R. Ingram Receptionist, Bethesda R. Fraley, ACRS(16)
Meeting flotice File NRCParticipant(s)
H. George g
J. Knight Program Support Branch
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