ML18079A433
| ML18079A433 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/15/1979 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906200394 | |
| Download: ML18079A433 (4) | |
Text
Frederick W. Schneider Vice President Pub I ic Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201 /430-7373 Production
- \\
June 15, 1979 U. s. Nuclear Regulatory Commission Director, Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D. C.
20555 NRC IE BULLETINS NO. 79-01 AND 79-0lA NO. l UNIT SALEM GENERATING STATION SUPPLEMENTAL RESPONSE Pursuant to our initial response dated March 6, 1979 on IE Bulletin No. 79-01, the following supplemental information is hereby submitted, including the results of our.investigation concerning IE Bulletin No. 79-0lA:
As noted in our response of March 6, 1979, a detailed list of qualification documentation and other data in response to Item 3 of IE Bulletin No. 79-01 was to be submitted when your staff had agreed on our data submittal made pursuant to the Salem No. 2 Unit docket.
It is our present understanding that this review is still pending on No. 2 Unit; however, in order to meet the required 120 day response requirement of the subject bulle~.
tin, copies of the appropriate tables and responses of the FSAR are attached.
The data is applicable for both units, except as noted on Table Q7.30.
Copies of the referenced qualification reports are available for review at the PSE&G General Offic~s.
In addition, we have reviewed the recent addendum to this bulletin
( 79-.0lA) concerning solenoid valves, "Environmental Qualification of Class lE Equipment (Deficiencies in the Environmental Qualifi-.
cation of ASCO Solenoid Valves).
11 The safety-related solenoid _.
valves used in the Salem containments have been replaced with the
- new -A-SGG "NP 11 -series solenoid valves as described in PSE&G re-sponse to tbe NRC on March 6, 1979 concerning Bulletin No. 79-01.
PSE&G will follow the recommended maintenance procedure of ASCO concerning the 11NP" series solenoid valves.
Director, Div. of Operating Reactors 6/l5/79 We are presently reorganizing our information regarding environ-mental qualification of Class lE equipment to a standard EPRI format.
This task will be completed within 30 days.
Attachment CC Mr. B. H. Grier NRC, King of Prussia, Pa.
Mr. L. J. Norrholm NRC, Hancocks Bridge, N. J.
'J'Al\\II. 07. JO "n"anmil tter11 Rr0'11 Solenoid Valves Limit Switches lfydl"O'Jen R!oarblners Pan Cboler l't>tor InstrlJllent Panels r.lectrlcal Penctrat ions Electrical Cable ~lice11 H 1'79 B 56 1/2
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Barton l'tldel 763, 764 lt>fl810Ul t l'tlde 1 115 3A R:l6em':lul t l'bdel 176 KF, 176 KS
/\\9::0 NP Serles valves NNrn l'txle l EA-1 BO W?s t ing tx>we fU.lCTICN -
run111um OP!mATICN
("UA!.IFllATICN N\\'17\\
Pressurizer level Stsn. Gm. r.cvel RCS Pressure
- l<<A ( S'!') /l'ISLll (!.T)
MSl.n (l,T)
MSIJ\\ (LT)'
Steam Flow MS!.J\\ ( S'!')
Pressurizer Preesurc -
IJXA (ST)
RCS 'll!nperature
- HSU\\ (LT)
Cllntairwnent Isolation - to:A (ST) and Various Safety-Felated Valves Cbntairrnent Isolation -
TIX.A (LT)
R>st UXA tfydrogen
- to:A (LT)
Cbntrol Cbntairrnent Abmsphere - to:A (LT);11SLR (1.T)
Cboling fhclosure for Transmi ttere anc'I Solenoids Prov lries for ln')ress & Ftjrees of rJectrlc11l I.ables to the Pr lmary Cbntairwnent LOCA (LT);11SI.R (LT) llX:A (LT)/l'ISLn (I.Tl Cbnnection/'llmnlnation -
UX:A (LT)/t'1Sl.n (!.T) of f'Jectrlcal C".llbles
//J/JLC tP :730
.5,1/e:d I 320°F peak 75 j1ftig 3o;o*r peak 120 pslq peak 340°F peak 66 psi')
34fi°F peak 349°F peak 125 pslq peak 3'i0°F pe11k 43.2 PRl'l rrcr...340"F MS!.B-442°F 360°F pe!'k Weetlnghow!e !.11tter Ferort NSJJll-1950 (J>roprletary)
(9/29(78) lb Be11101X1 t Report It>. 37Rll (l/78) 1-.\\!stinghouse Feport 1-K'AP 9157 Propl"ietllry (9(77)
ASCO Feport Arfl2167R/I'R NllMCO Report (9/5(7Rl lo.\\!11til'l<)hou.'le Report
"'°'" 7R20
"'1stinghouse Report WCN> 7R2'1 Response to 11.4.11(4)
PSr.i.r. Panel 'n!st Plan Report (!liter)
C\\til\\X T~R Prototype
'l\\!Rt leport.
C'CNl\\X letter daterl l/9(79.
Franklin Institute Rep;> rt f'-C4 n 33-l
\\olef\\t ll'l<Jhoooe ~
11 flea t ion Pro-qr11111 (323-1971),
f;iwne tr11nfWllitter11 utillzerl on N:>rth Anna, Heets/F.lc~s IF:r.'P. 323-1971
- !<<Jul remen 1:11,
Westll'l<)house ~liflcation Prr>-
qram (l23-1Q71 ),
!'are RTn'" utlll-1 on N:>rth /Vina 11n<l fcxm acceptable.
Heets/f)(~s IFY.P. 323-1971 Requ i rernen tR,
Meets/F:.cee<ls Ir:r.P. ~lJ-lQ7l requ I rements.
Refer to resfXJl'lllC to f'\\Jestion 7. J'i.
Jleport qenerlc11lly approved hy NRC.
Westll'Y]house has perfonne<l 11nalysls on fan cooler rootor am fomcf the 110tor hot spot tl!fTllCr11ture lOWP.r as COl1"'red to actual qua! lflerl tl'st t~ratur<?.
~stlnqhouse letter SP.~"llI!-AfiA rlate<l 3/13(79.
'J'ests planned wi 11 rnPet/ellceerl IFY.P.
323-1971 !<<julrcment.q.
Jlevlewl!<'l durinq NRC Inspect ion 50-311(7R-l 5.
Trlent lc11l CT'NAX feeilthrouqhe 11!'1ed 11t VP.Pf.0-N-'~ 1100 foum accl'f't11hle by NRC.
~r"G t~rature prof i 14*
lower peak th11n vm-:o.
W Jlev iewe<l ancl fomrl acceptahl e by NRC inspection report ~O-Jll(7A-15. Will
!!W!et/ellceed Ifl':f. 323-1971,
TABLE 07.JO (Cbnt'dl El ectr lc-.al ontnnina l IUodts Electrical Cable11 l"btor-Qle rated Valves Varioue Limlton]Ut! SMB type Qx>r4' tors ll! ! lance
~tors Class H Insulation IVI'E:
loi?stln<Jhruse Analysis LCCA - 271°F
~ 43.2 psig HSUI - ))J.5°F ~ 42.B psig NIC Cbnfit'm'1tory KSLB - 350°F H P79 8 56 3 ti N:'I'ICN -
RFX;U I RF.O OPP.!U\\TICN Cbnnection of Electrical Oihles Various t.IX:A (LT),h1SU\\ (!,T)
Cbntainnent Isolation - rr£A (ST)/MSLA (ST)
(UAl,IFICJ\\TIOO l'll\\TA 1.riCA-;>A Ii* P M::;f,fl-350°P J40°F ( 3 lbursl.
340°f' RP.F
- OOCI t1F"Nm rowc Report IPS-400 See Response to fiection R'. 4.R ( 2)
Westing~e letter
- ierort f'&CF>-692 (7/10/751 C(H1f'Nffi CftW( test report is be l 1¥1 pl"epll t'ef1, l)(!ntinq test OOcll!lentiltlon revllNl!d by mte Refs Inspection Report 50-311/78-15.
'lllet1Ml analysis wa11 perfo~ 1111lng the iwne rroclP. l 118 VEPCO-NJ\\PS wh lch had prnvlounly ~
11ccepterl hy the nu.H,
'Ille pellk 11urrace t~rnture or the.
cahle wa11 cal'culate<l to he 333 *fl'.
'lllet1Ml analysis 1o11111 perfol11'1!<! 1111il'IC) the same rrc:xlel ae ~l\\PS which 1\\1111 previously heen accepted by the
- staff, 29l"F was the calculate<'I peak surfM:e tentlf!rature of the ll'Otor operate<'! valve 1 imi t switch OCl!llllt"t-ment.
In addition, these are ~
MrN's used by lt>rth hma.
'W' The Barton transmitters installed in Unit 1 are from LOT 2.
These transmitters are similar in design to the LOT 1 Barton transmitters (installed on Unit 2) but have a different amplifier and a modified circuit board.
Changes implemented in the LOT 2 transmitters are limited to modifications in the unit electronics.
The sensing unit, cas~ng, sealing mechanisms etc. re-main unchanged.
Preliminary tests by Barton have indicated that the modifications introduced tJ to not detract from the performance capabilities demonstrated for the LOT 1 transmitters.
The LOT 2 transmitter tests performed sofar have indicated errors within acceptance levels when subje~ted to accident environment.
The complete acceptance test program is scheduled for completion in September, 1979.
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