ML18078B119
| ML18078B119 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/30/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904020117 | |
| Download: ML18078B119 (21) | |
Text
~---
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 March 30, 1979
~.'.*... *:* ::..
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Gentlemen:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-3ll Public Service Electric and Gas Company hereby transmits 60 copies of its revised responses to your requests for additional information related to Questions 7.29 (Seismic Qualification),
7.30 (Equipment Qualification), 8.4.8(4) (Qualification of Fan Cooler Motor), position 40 (Fire Protection) and l4.31.
The information contained herein will be incorporated into the Salem FSAR in an amendment to our application.
Also included is the Unit 2 program for the inspection of steam generator cladding.
Should you have any questions, please do not hesitate to con-tact us.
Enclosure Very truly you~s, f/;1b~L R. L. Mi::r
... General Manager -
Licensing and Environment Engineering and Construction 7904020111
Seismic Qualification of Class I Electrical Equipment and Instrume~tation.
Identify and provide the method of seismic qualification for electrical equipment and instrumentation for BOP scope of supply required to reach the hot stand-by and cold shutdown condition from full power operation under a postulated SSE event.
A review of this equipment will be performed by the Seismic Qualification Review Team (SQRT).
A site visit at some future date will be necessary to inspect and otherwise evaluate selected equipment after our review of the equipment list.
The attachment describes SQRT and its procedures.
Provide your response in accordance with these SQRT requirements~
ANSWER Refer to the response to Question Q7.l8.
Table Q?.18-l has been updated to include the information requested concerning type of test/analysis and appropriate natural frequencies where available.
No distinction is made between hot standby or cold shutdown for the equipment listed in the table.
For the most part, the equipment is utilized for maintaining/achieving both of the conditions specified.
SNGS-FSAR Units 1 & 2 Q7.29-l Amendment 45
Control Console Nucle11.r Instrument-at ion System Process Control
~:quipment C'nbinels
~olid fitate Protection Actuation Vital Instrument Bus Static Inverters Auxiliary Control
~:ysL~m Terminnl and B<>l11y Cablnl'tS Relay Racks Loc11.tion Aux. Rldg.
El. 122' Aux. Rldg.
El. l ,,
Aux. Rldg, El. l ')-.,I Aux. Bldg.
El. 122' Aux. Bldg.
El. 100' Aux. Bldg.
El. 100' Aux. Rldg.
1':1. 100' S<'ism1c 1
.Q_e_~_11~13.!._!
- o. 36 g
- o. 36 g
- o. 36 g
- o. 36 g 0.25 g 0.25 g 0.25 g TA!lf.I*: err. 18-1 Sl!MMAHY OF' SE1::M1r. QllALIF'ICA1'TON l*'l)H r.ArF;Tv-1n:1.llTElJ EQ\\IIl'MEN'l' Type of
~~a__1-_U
.!_~_at 1 on Test llinxial Test f.1 n,.i:le Ax ls
'!'er, t Single Axis Test Slnii:le Axis T<>st Sinp:le Axis T<'st SlnglP Axis Dynnmlc Analysis Multiple Axis Hemnrks Simultaneous Time History Test?
producing nccelernLlons greater than design hns\\s earthquake (DHE).
Test results were accept-able.
f.lne Beat Test with penk accel-eration of 0.7g.
Test results were acceptnblP.
Sine Rent Test with peak accel-eration of 0.7g.
Test results were ncceptnhle.
f.lne Bent Test with peak accel-eration of o.7g, Test results were ncceptnble.
Uniaxis Time History Test 2 with peak accelerntion of 0.7g.
Test results were acceptable.
llniaxis Time History Test 2 with pPak 11ccelerntion of 0.7g.
Test results were acceptable.
I\\ finite element computer analy-sts wns performed.
Results of Lhe nnnlysis wrre acceptable.
There were 10 nnturnl frequen-cl.e s under 110 Hz with the first mode at ~.41 Hz.
Table Q7.18-l Sheet 1 Manufacturer/
!'.lode_!__# __ _
PSF:Pc1; Control Consoles Westinghouse Nuclear InstrumPnta-tlon System Cabinet Hng11n Process Control & Protect-J on Cabinets Westinghouse Solid State Protection System Cabinets Garrett Static Inverter '1.nd Power Supply Antley Meter Co.
System 660 PSF:.'.t} Relay Rneks Report #/Dnte
- Wyle L11hor11tories Test Heport
- 4:*4hl-l 11/9/? 3 WCAP-'f817 Suppl-ement -
? 12/71; WCAP-8830 (11/76)
WCAP-7817, SupplPment l U/?l; WC/\\P-883?
( u/7(, l wr11r-1R17 Supplrment U/?l W I,etter llS-CE-692 (7 /77)
Ai research Mnnufncturing Co.
Ro-port. #71-8040 1~'/10/71 l*Rttelle Summary Reports 5/6/71 -
~/25/71 l\\11ttelle
~:ummary Rqiort 12/.'l/73
_F~~l'lll~~
l;*~v nnd :>Bv nc Distribution Cnldn.,1.s Te rm! nnl Cn\\* i 1wts D ! e se 1 Control Cal*lnets Control Room Recorder Panels So 11<1 :;tate
!'rote ct.I on *)ut.put Te t 11nrl Interface Cnbinets Location Aux. Hldg, F.l. 84* 1.nd 100' Aux. Bldg.
El. 100' Aux. l'ltlg.
El. 100' Aux. Bldg.
El. 122 1
Aux. Bldg.
- n. l 'l')'
fietr.mic 1
.~~~~~"..~
0,25 g 0.25 g
- o. 36 g 0.36 g 1'Atlf,1': <f7.18-1 nlJMMARY m* :;1*: I :;MI c QUA [,IFICATION i"<lR
- A~'ETY-IH
- J,A'l'l:D EQ\\JIPMF.NT TypP of qu~l.!:_I cntton.
Test lllnxlal Stntic Analysis Multiple Axis Test J1inxinl Dynnmic Analysis Multiple /\\xis Test Bl axial Remarks Slmullnneous~Time History Test'* producing nccelerat.ions greater than llJ\\E, T<'sl. results were ncceptnble.
Calculnted ( 46117.) resonant frequency nnd determined stresses uslng maximum g level at this frequency from response spectra.
Results of the an1.1lysis were acceptable.
SlmuJ,taneous Time History
'J'est'* producing accele-rntions greater thnn DBE, Test results were accept-1.1ble.
A finite element computer analysis wns performed.
Results of the analysis were accept.able.
All panels exhibited cant!-
lever mode resonances above l10hz.
Vnrious panel subassemblies/selected exhibited resonances below 40hz.
SimuJ,taneous Tlme History
'l'e st' produt:ing nccele-r1.1tions i;rellter than DBE, Test results were accept-able.
Tnhle Q7.18-l
~Hieet 2 B-K Electrical Products, Inc.
125V DC Distribution Cabinets 28V DC Distribution Cabinet.a 2UV DC Load Centers (Switchgear) 115V AC Instrument Falstrom Company Terminal Cabinets Shaft.way Cabinets Bueees Diesel Gen. Control panels:
Engine Control Panel, Gen. Control Panel, Exciter Regul-ator Panel.
Recorder Panela-RP 2 &
RP 5 Annunciator Fascia; RP1,RP\\,RP4,RP6,RP7,RP8, RP9 (Structural Only)
Panel Control Inc.
SSPS Test Cabinets Wyle Laboratoiles Test Report
- l1;!)h'/-l -
l? /H1/'72 PSE&G Engineering Dr.pt. Report 11/7 /'13 Wyle Lat,oratori.
Test Report
/lli;'551-l 11/8/73 RRttelle Summary Reports 5/lii/'lli, 12/21i/75, 12/1/75 Wyle L~~orRtorles Test RPport
- 4;*7f'.n-1 7 /,*(,/7li r
~....,
Hndint.lon Moni-Lnrln~~ Cnblnet.s and Components Safeguards Equip-ment Control Control Centers Location Aux, l\\ldg.
f:l.
l.~~**
rind Various other arens Aux. Bldg, El. 100' Aux, Hldg,
- El. l;!? I
!~elsmic 1
_!l_"_:"._!_~*n
!1~:1_!:!.
- o. 16 g 0.25 g
- o. 36 g
'l'Allr.F: '17.18-1
SUMMARY
OF' ::1*:r::Mrc C!llA[,JF'fC:A'l'ION
!'OR SM'Jo:TY-HJ*:l.A'l'E!J I*:QUJPMJ-:NT
'l'ype of
_q~a_l_I,!~. c_n_t~ i_()".
'l'e st.
Bl ax l Rl Test Single Axls
!Jynamlc Analysis Multiple Axis Test Single Axis Remarks Rn.ndom multifrequency test productn" nccelerntlons
,.;renter th1tn l>BJ*:.
Tr.st results were ncceptnble.
An analysis was performed on the ent.ire assembly to demonstrnt.e its capability to withstand the specified seismic forces supported by sine sweep, sine dwell and shock test.in,.; of cn.binet.
Electronic subnssemblies and components were vibration tested nt nn.tural frequencies n.s determined by sine sweep n.nd compared to dn.ta from the analysts.
Results of the anyalysis and tests were acceptable.
Sine sweep test in the three orthogonnl axes.
0.5g main-tained from 10-500 Hz.
Loll frequency ( 5-lO!lz region) justified by combinntion test and analysis.
The test results were acceptable.
'l'nble Q.7.18-1
!~heel. 3 Un 1 t l:
Trncerlnb/Trapelo,Control Cah!nrts, Area Monitors TA6<'/AX22Vl' rM,2/Ax;>;*
PRrtic:ulal.f-' & *;as flnmpler Housing, Pnrt!culate DetrcLor M0-5tt, GRB Detector M!J-12C, F'ilter Sampler MQ-228 llnl t 2:
V!ct.oreen Inc.
Digital Radiation Moni-toring System Process and Area Monitors Vitro Laboratories Safeguards Equipment Control System Cabinets General Electric 7700 Line Motor Control Centers Wyle Lahoratorles Te"t. R<'port
- 43166-l - 4/1/76 Wyle LAbcratorles T~s\\ R<!port 111,:ir.10-1 5/u/1B
- 44040-1 5/16/78 VI t ro T.t1borato1A
- ler,
'W' Annlys\\s Report 4/74
,;cnf"' r'\\ l Electr i e Test llPport ll7c1TCS100 I\\/ ;'1/7*'
llnl t :;ul*st.nt lons and D\\~
~iwitch~enr 5 kV !;wltchgenr Diesel,;enerator and A~ce.ssorles Trny nnd H!lngers
!l!lttery Ch!lrger 125V
~"ttery Ch!lrgl!r
~*ti';
!.oc!ltl on Aux. lll<lg.
- Fl. 12.
Aux. Bldg.
El. 100' Aux. Bldg.
El. 100' Aux. Bldg.
El.
l~;.~*
Aux. l'ldg.
- El. l?;l*
Aux. Hldg.
- El. i; 1? I
!'e1nm!c 1
!'.~:'-!.~H_llnsi*
- o. 36 g 0.25 g 0.25 g
- o. 36 g
- o. 36 g
- o. 36 g Tnlilr 07.111-1 S\\I MMAR Y 01*' :H; I ::MIC QllA l.J I' ICA1' I ON r'OH :;AJ'F:'l'Y-Hl*:(.1\\'l'Ell l*:l.(llIPMr:N'l' 1'ype of
~u~!.J. 1: ~".~~.!.(l.11 Test.
!\\lngle Axis
!;tnt.lc Analysis Multlple Axis Stntic Analysis f.lngle Axis Dynnmic Annlysis Multiple Axis Test Ill axial Test.
'-Ingle flxir.
HemRrkB The unit wns shock tested nt res\\1lt.Rnt 11c~elcrntlons grent.er t.hRn the design basis f'arlhqunke ( Ul<Jo:) Rt the nRturnl frequencies.
Test rl!-
nult* nccept.n!Jle.
Cnlculnted resonant frequency (17.~Hz) and determined stresses using mnximum g level nl t.hls frequency from the response spectra.
Results of the analysis were acceptahle.
Calculnted stressee on all vital component.a using peak nccelerat\\on of l.Og horizon-tnlly nnrl 0.67g vertically.
Renults of the analysis were ncceptable.
Analysis performed by comp-uting the dynnmlc response pnrameters utilizing the response spectra.
Results of the Rnnlysis were acceptable.
A resonant eenrch was per-rormed.
The unit wns then subjrcted to n resultant nccelerA.Llon Kreater than the design hnsls earth-qunke (nHE) at the deter-mlnrd nnt.urnl frequencies.
'l'~~l results were accept-alilf*.
H1*sunanc* search from 1-351tz
- t11<\\ n t.lm** hl Rt.Pry test. wl I h pettk R.C~f'lerntions of 0.'{ 111':
ho r l :'.on t. n l n n d C1 * 'i p: v e rt 1 c 1.
'l't1e te~t rest1lt.s were acce11t.-
nl1le.
Tnl*1** l/'I. Ul-1
~: ll 1' (' !.
l1 Mnnufacturer/
Mo<!_<" ]:_JI_ ____ _
I.T.E. Imperial Corp.
6oov Swtlchgenr I.T.E.
Dw~. No'e 83708~', ;>119096 General Electric M6?!1 Metalclnd Switchgear White Industrial Power Alco Engine Division DF.-35245 T ** r. Cope Exide lJSF-130 250 r&n llattrriPS AHR ;:t\\J!/K\\"lH'3 I.T.f:. Report
/IR-8792 (F.TL l7H\\)
7/ltl/69
-,.1 r;enernl Electric
!>eism\\c Analyels Report Dated
- '/2/1 l Alco
!;e 1 r.mi c Cn.lcu-ln t 1 ons 101?/'fO NPS Report /10801-1 l/ 11\\/'fh Fx l de R**rort llQCC-10
.. ! 11/7.'
1'.'l l I*' l le l-lt,\\'1l,)
l.' ll
L~i pment
,tteriee 2RV &
'5V
'ttery Racks
.. ctrlcal
- nctrRtions
<x. !<ldp,. Vent.
111 Motors Locntlon Aux. Hldg.
- El. 122' Aux. i'ldg.
tit: l
- l ;: ~l I Contnlnment El. 78' Aux, !Hdg.
El. 1 ;:->.~'
- 0. 36 g 0.?3 g
- o. 36 g TA II[,]*: err. lfl-l
SUMMARY
tJlo' :a:r::MJC: (/,llAl.H'TGA'l'ION
~'OH ::11J*'ETY-JH:Lll'l'J*:D Jo:QllIPM~~NT Type 01*
gti.!.'.1_11~ !__c:ll t !_l)f!
'l't* st 11 i nxi al Stntic llnnlysls Pseudo-Dyn11mi c
/\\nnlysis Multiple /\\xis Stntic Analysis Remnrks Simultaneous horizontal nnd Vertical componrnts nppllrd with peak RccPleratlons KrenLer than the desl~n b11:;Js enrthquake
( JllW) at. the nnturi*l frequen-cies.
'reRL results were nccept-al>le.
- ubsequent testr. have bPen performed hy C&ll on rqul-v11lent bnt.Lerles referPnclng IEEE 344-1975 criterin.
Calculated resonant frequency and determined stresses using maximum g level nt this fre-quency from the response apec-t.ra.
Results of the analysis were acceplnlile.
Calculated resonant frequency of ttnlt. and components.
~~trcsst*s were then detf'rmtned at thene frequencies using maximum K level o\\Jt1lined from r<'sponE;e spectra..
Hesults of the nnnlysis were acceptable.
Cnlc11l11ted stresses us[np:
mrixtmt1m
~ level from rC>~;ponse spectrn.
The n.n11.lysis :;\\1h-sLnntl11tPs lhat the motnr will f11nctlon loulh mech11nlcally flnd rlectrlcnlly under UHE condi-t.l ons.
- rable Q7.1B-l
- hee t 5 Manufacturer/
~~-<:..:_l_# ___ _
C&O J\\Rtteriee LCIJ-33 KCll-21 C&D Batteries R
- D. - 1105 Er R,D,-;>l10EP Con Rx Su\\Jllssem\\Jly
- ~'3'<'5-7971-03 Allis Chalmers RG-J6l1TS: 60HP, 1800HPM
!H;- 1:>l1T: l10llP, 1800HPM
_Re po rt #/Oat"-
Wyle Laboratories neport #l1-co7I1-l 3/29/71 Wyle La\\Jorstoriee Report #43291-1 and
- 113450-l C&D Seismic Deeign Co.lculations
?/71 Conax ER1104 F:Rll04 7/6/71 ER1093 9/ 2 3/70 Rev.A 3/l?/70 Allis Chalmers Stress Calculations
& Seismic Shock 8/11/70
- t**&.*
Service Wnter Pump Motors Aux. reedwRter Pump Motors Engineered Snfeguards Motors HeRt tracing TRpe mounting and connections Location Service Water Intake Structure El. 90.9' Aux. Bldg.
El. 84' Aux. Bldg.
El. 84* and 45*
Aux. Bldg.
- El. 12::
f.eiRmic 1
.!l_"._Sl_~n__l!_~sis 0.25 g 0.24 g
- o. 24 g
- o. 36 g
- rA 11u: Q'f. lfl-1 SllMMAHY 01" st:r;.MJC l!lll\\T.TFICllTTON FPR :1Af'1':TY-HELl\\'n:!J t:Q.UIPMENT Type of
~U. ~l_!_!"_~'.'_n_t_!~~
[;tnt le Analysis Static Analysis Analysis 1'PS t Sin"le Axis &
Stntic Annlys:s Remarks Cnlculnted stresses using max-imum g level from response spectra.
The nnalysls sub-stnntiates that the motor will function both mechanically and electrically under DBE conditions.
Calculated stresses using mnximum g level from response spectrR.
The nnnlysis sub-stantintes Lhnt the motor will function both mechni-cnlly nnd electrically under DBE conditions.
Pump Motors Supplied by Westing-house with Seismic Qualification.
Heater t.Rpe was mounted on a one Inch pipe nnd vihrRted at 4 inch double amplitude from t to 5hz,
~ Inch double nmplltude from 5 to ;'Ohz Rnd 4r,, from ?O to l OOhz In ench of the three orthogonal plRnes.
Mounting connections were nnalyzerl by cnlculatlng the resonnnt frequency (10.Bhz) and determined st.resses using mnx1-mum g level from the response spectrn.
Results of the trst nnd analysis were acceptable.
Table 07. 18-1 Sheet 6 Manufacturer/
1:10.d!'_l._ll ____ _
Allis-Chalmers A-COl-0500-42471 1000 HP, 1200RPM Allis-Chalmers 588US-RG-3600RPM 600llP Chemelex lOPTV PVl-)00 Bracket Alli s-Chnlmers Cnlculntiona for Selsmlc Acceler-11 t lone 5/ 2;' /70 A 111 s-Chn lmera Rotor Shaft Deflections, f>t.ress Cnlcula-
!.lons f>e!smlc Shock 8/7/70 AnRmet T.11.horR-torles Fpt II 973. *.1hlOA Dated 10/5/73 nnd Ann.met I.1thora-toriPs Rpt II 77~).~lrJ DatP<l }/2'i/75
Equ.iprent Heat Tracing Tellp! ra ture Ccntrollers Heat Tracing Tellp!rature Crntroller Heat Tracing and Radia-ti <rl 1'tlno-toring Trans foilll!rs Location Aux. Bldg.
El. 100' Aux. Bldg.
El. 122' Aux. Bl<i;J.
- El. 122' Sei!llllic1 Design Basis 0.25 g 0.36 g
- o. 36 g TABLE Q7. 18-1
SUMMARY
OF SEISMIC QUALIFICATION FOR SAFETY-RELATED EQUIPMENT Type of Q.Jali ficatioo Test Single Axis Test Single ms Test Bi-axial Remarks
'the unJt was vibrated in the three orthoqrnal axes fran 5-50 hz resultin:1 in acoeleratirns qreater than the DBE.
The test results were J\\ccEptable.
Sine ~
test in the three orthoqrnal axes.
The test results were acceptable.
Jesonanc:JO! seardi f ran 1-40 hz was perfomed with input test le"°"'l of 0.15g.
Seismic ran<hn 11Dtion was app-lied for 30 seconds to eadi horizontal axis sinrultaneaISly with the vertical.
Seisnic resrx:nse spec-tra analysis was per-fomed qenerat]ng the maximlJTl response arn-p li tude s over the frequency ranqe of 1.1 to 100 hz.
'!lie re-sults of the tests were acceptable.
Table 07.18-1 Sheet 7 Manufacturer/
l'bdel
- Love Centrals Corp.
l'bdel 68-1 United Elec-trical Controls Type 802P l'txlel 600 Teledyne Crit-tendon Style # 15049
~
f/Oate AnarEt Labora-tories Rpt
- 975.417 Dated 9/30/75 Anim:!t Labora-tories Jeport
- 672.78
!lJ\\te 6/8/72 lt{le Laboratcu-ies, Report I 54096, Dated 1/27/75
Equ.ipnent Heat Tracing and Radia-tion l'hli taring Systen Cir-cuit Break-er Panel-boards Heat Tracing Control Panel with Crnµr nents Location Aux. Bldq.
El. 100' Aux. Bldq.
El. 100' Seismic1 Design Basis 0.25 g 0.25 g TABLE Q7.18-l
SUMMARY
OF SEISMIC QUALIFICATION FOR SAFETY-RELATED EQUIPMENT
'fypc of Quali fi caticn Test Sirqle Axis Dyn<mic Analysis Multiple Axis
'M1e unit was vibrated in all of the three orthocional axes fn:rn 5-50 hz result.inq in acceleratiCIIS qreater than the OBE.
The results of the test were accepta-ble.
Analysis perfonned by can-puting the dynamic respcnse par11reters uti 1 i zing the response spectra.
Results of the analysis were acceptable.
Table Q7.18-l Sheet 8 Manufacturer/
f>bdel
- Time-Trol f>bdel
- 73071-2 I-bf ftnan NEMI\\ 12 enclooure a:.l--
tai niJ1g IDve TenJlerature Controller l't:xlel 6 9-1
- Budlanan Tenni-nal Block Cat I 2Bll2N and cut-ler ll<mtrer 2 Pole A.C.
oontactore NEMI\\
Size 1 Report t/Date Ananet Labora-tories
~port
- 375.47 Dnted 3/25/75 NPS leport I foUB-02 Dated 10/76
'I'll nu: WI. lB-1 i;llMMllHY lH' ::n:;Mrt: <!llAJ,Jl*'TC/\\'l'TON
~*oH :;11n:TY-HJ-:[,/\\'l'l*:D EQUil'MJ*:N'I' Safety-rel~ted Instruments, instr111nrnt. panPls nnd enclosures u::ed In vnrlous Iocntlons of' t.he plant wer** qunlll ll'd by vnrlous I.est proeeclures select.ed to meet or <'XC!'ed the r<'quirem!'nts al' n:1rn 3lil1-1971.
Te,;t mi*Lh<>tls usrd lnclucied unl11xlnl,;tnr bel\\t, testinv, pcrf'ormed on orl.ho1;onnl nxes, rer.onnnt srarch mulLl-oxlo time hl*lory and multl-nxls rnnrtom multifrequency.
Test results wrre acceptnhle.
The followin~ Is a summnry listing or thP components:
Manufnctur~r/Model N Fox~oro, Fischer & Porter Rnrt.o>n PrPss11rP & Uifferential Pr!'osure Trnnsmitters WCAP-7817 12/'/ 1 WCAP-'(817 Supplement 8 l 7 /'15)
Fischer & Porter, Leeds & Northrup Pressure & Temp. Transmitters Jo' I scher & Port.er, [,eeds & Northrup E/P Converters llonrywcll Pneumatic Controller 6ol11*r, l!oneyw<'ll Pneum,.tic Ther-mos*." t. s Tl"J70 Moorr J3 PnPumatlc Transmitter Moore
~5 T 1neumatlc Controller ASCO Soenoid Valves, Various Models 8nrton Differential Pressure f)witch Fincher R/P Converter flscher IV. Porter Level Tr11nsml tter Fisr.her & Porter Flow Con-troller rt "-hc<*r P, Porter Set.point Stntlo11, ATC Timer Le<"dr; IV. Northrup Pressure Transmitter IV. Power Supply United fl!'ctric Pressure Switch SEf: NOTES ON Nf:Y.1' PAr;;:
!jNti3-P~iA B Un 1 \\. G 1 & ;'
Wyle Laboratories Test Report
- 42987 2/7/75 Wyle Laboratories Test Report 1111*1166-1 4/i/76 Jo'ischer & Porter IndicatinK Stntions Mrrcoid & United Electric Pressure Switches fiocher & Porter Power Bupply ~ Squnreroot Rxtractor A~CO Solenoid Valves (Vnrious Models)
Moore Auctioneer Mnsonellnn Pressure Regulator Imperial Valve Mnnifolds Instrument Psnel (Including tubing, fittings, terminal wire, lugs, etc.), constructed per PSR&G Spec. 72-8007 Aux. Equipment Cabinets (PSE&n)
Terminal lllocks CMC Gwlt~hes nnd Indicators NEMA 12 Enclosures (PSR&U)
Vnrlous ASCO Solenoid Valves Moore r,Bs lll1:h ~;elect, 52l1T:', 173S, 91F60 foxhoro llDM-J\\~'1, 13A-MSI, 1311-MSI, 13A-llSI Instrument Rnck (PSE&r;)
NEMA 12 Enclosure (PSE&C:)
Nupro Meterin1; Vnlve -
B4MU NEMA 12 Enclosure (PR~&U) ln ii Jo'lscher & Porter lOJ\\~496 Dlff. Press. Transmitter NEMA 12 Enclos\\lre (Pfa:&n)
Vnr1 ous J\\!>CO
~~olenolll VnlvPr.
Florher Typr 546 E/P Converter Mnsunrilnn 77-l Hegulntor, '/'/-Ii Regulator llflrton :JB6 Dlff'. Press. Tr11nsmltter
'l'ILI> le (/_'(. lB-1
- ~Ill' I' L q
- blocks,
~-------
Bsttelle f.ummnry Report 4/;~7/7 l Wyle Test Lnhorntories Report //4:*~9';-1 11/1:'/7 3 Wyle Lnborntorles Test Rrport 1144~15-l 9/ l6/7t\\
Wyle Ln~orn\\.orles Test Report /143932-1 3/17/7P.
Wyle Lnhorntorles
'i'Pst Heport /14-i*lj:'-2 J/.;! f'fi\\
Wy.le l,a\\iornt.orit*~~
'I'~,, t I! e po rt /111.n.' R-1 11/<'/7?
TAllT,f: C/7.Ul-1 GUM MA BY lli" ::1*: I :;MJ C ClllA [, T f'ICAT ION 1.-ll I! f, A Jo' 1-: 'I' Y - IH'. [,ATE JJ f:Q.11 [ PMJ*:N'l' A~r0 f.olenolrl Vnlves
.'Ot*- 181-(,F
,'t1(,_ *1111_ ff A~cn TesL RPporL A4~ 21678/TH (3/7HI l!onemount Trnnsmltters Model ll5~A ;.erle*
. '06-.l!I0-6F Nrtl n65ln:
N 1'!1 l l(iA74F.
N l'tl.il1l1A7 4 E N PH.14 4A 76 E NPB3li4A78E
~nrton Pressure Transmitter 763
~'rton Diff. Press. Transmitter 764 NAMCO Limit f>witch f:A-180 W lleport WS-TM~-1950 (9/29/78) 1 Peak horizontal accelerntion of the floor as n result of the Desi,,n !Iasis F.nrthqunke.
Rosemount Hrport RMT //Hllfl (1/;**!/7HI Acme-<;levelnnd Uevelopment Co. Report 9/5/?ll 2All time history tests were performed using the \\.lmP history response spectrn or floor elevnt.ion l:': in the Auxllinry ~ulldin>-'..
- ~quipment wns qualified for this elevntion althouKh nctunlly locnted nt n lower elevation in the nuxlllnry building.
- .r1 ;
- :- F;.AR
- Jn i Ls
!.~.*
Tnbl<' Crf. 18-l
- 11eet 10
Question 7.30 Identify safety-related instrumentation and control equipment (e.g., sensors, limit switches, connectors, instrument cabinets, cables) inside the containment which are required to function during and/or following the Design Basis Accident (LOCA as well as MSLB).
Provide environmental qualification documentation for each piece of equipment including:
(1)
Manufacturer (2)
Model number (3)
Specified environmental conditions and location (4)
Required duration of operation of Design Basis Accident (5)
How the equipment was or will be qualified (6)
If qualification tests were performed, provide the test plan, test set-up, test procedures and test results (7)
If analysis is used for qualification, justification of all analysis assumptions must be provided Reference may be made to identified Class lE equipment qualification programs found acceptable by the staff on previous operating license reviews provided the same documentation is available at a Public Service Electric and Gas Off ice for NRC audit and a statement of this affect is documented in the FSAR.
SNGS-FSAR Units 1 & 2 Q7.30-l Amendment 45
Answer Table Q7.30 lists the safety-related instrumentation, control and electrical equipment which are located inside the containment and must function during and/or following a LOCA or main steam line break.
The table presents the type of equipment, manufacturer, environmental conditions, qualification test data, reference documentation and applicable comments.
The reference documentation will be available for audit at the PSE&G offices.
Additional data regarding Environmental Qualification is presented in the response to Q7.41.
The environmental parameters for a main steam line break accident at Salem are provided in the response to Question QS.82.
These parameters are also noted in Table Q7.30.
SNGS-FSAR Units l & 2 M P79 2 23 1/2 Amendment 45 Q7.30-2
TARLE Q7.30 Transmitters RTD's Solenoid Valves Limit Switches Hydrogen R:!canbiners Fan Cboler l'btor Instrunent Panels Electrical Penetrations Electrical Cable Splices M P79 8 56 1/2 MANUFAC'IURER Barton Model 763, 764 lbserount M:xle l 115 3A Jbsenount l'bdel 176 KF, 176 KS l\\SCO NP Series Valves NAMCO l'bdel EA-180
\\oestinghouse
\\oestinghouse PSF'..&G Sufl'.ll ied
!eychffil INSIDE ccm'AINMFm' SAF'F.T'i-RF.LATP.D FnJIFMFNI' F'UNCTICN -
RE('UIRED OPERATICN
<Xll\\LIF'IC.ATICN IYITA Pressurizer r.evel Stin. cen. Level RCS Pressure
- IJX'.A (ST)/MSLR (LT)
- MSLR (LT)
- MSLR (LT) steam Flow
- MSI.Jl (ST)
Pressurizer Pressure - I.JX:.A (ST)
RCS Tunperature
- MSLR (LT)
Cbntainment Isolation - I.JX:.A (ST) and Various Safety-Rllated Valves Cbntainment Isolation - I.IX.A ( f,T)
R>st UXA Hydrogen Cbntrol I.JX:.A (LT)
Cbntairrnent Atmosphere -
I.JX:.A (LT)/MSLR (LT)
Cboling Eh closure for I.JX:.A (LT) /MSLR (LT)
Transmitters and Solenoids Provides for I.JX:.A (LT)/MSLB (LT)
Ingress & Fl:jress of Electrical Cables to the Primary Cbntainment Cbnnection/Turmination - I.JX:.A (LT)/MSLR (f,T) of Electrical Cables U8t.C' tP 7 3o S/lc:c-r 1 320°F' peak 75 psig 350°F peak 120 psig peak 340°F peak 66 psig 346°F peak 349°F peak 125 psig peak 350°F' peak 43.2 psig UJCl\\-340°F MSL&-442°F 360°F peak Westinghouse r.etter Rlport N8--'ll1-1950 (Proprietary)
(9/29/78)
Jbserount Rei:ort No. 3780 (3/78)
Westinghouse Rlp:lrt WC.AP 9157 Proprietary (9/77)
ASCO !Eport A('.621670/TR NAMOO Report (9/5/78)
Westinghouse !Ep:lrt WCAP 7820 Westinghouse Rlport WCAP 7R29
!Esponse to 8.4.8(4)
PSF.&~ Panel 'Jest Plan Rlport (Later)
CXJNAX TR-8 Prototype
'Jest Rlport.
O'.l'IAX letter dated 1/9/79.
Franklin Institute Report F-C4033-3 ccmrnrs WeRtinghouse llequalification Pro-gram (323-1971).
Same transmitters utilized on N:>rth Anna.
Meets/Exceeds IF.F.P. 323-1971
!Equirements.
Westinghouse Requalification Pro-gram (323-lq71).
Same Rl'D's utilized on lt:>rth Anna and found acceptable.
Meets/f)(ceeds rr.r.r. 323-1971 Requirements.
Meets/Exceeds rr.r.r. 323-1971 Jlequirements.
Rlfer to response to OJestion 7.35.
Rlport generically approved by NRC.
Westinghouse has performed analysis on fan cooler motor ana found the motor hot spot terrperature lower as CCJl1l"'red to actual qualified test tP.mperature.
Westinghouse letter sr.~SAII-R6R dated 3/13/79.
Tusts planned will meet/exceed IP.Er.
323-1971 Requirements.
Rlviewed during NRC inspection 50-311/78-15.
Irlentical <Xl'IAX feedthrolX}hs used at ~NAPS and found acceptable by NRC.
PSF.&G temperature profile.A lower peak than VEFCO.
ieviewed and found acceptable by NRC inspection report 50-311/78-15.
Will meet/exceed IF.Er. 323-1971.
~:fP'.'I*~***
.v' TABLE Q7.30 (Cbnt'd)
TYPE Electrical
'l\\mninal Blocks Electrical Cables 1-btor-QJerated Valves MANUFAcruru:R Buchanan Various Limi torque 9'1B type
~raters !Eliance fobtors Class H Insulation
~= ~stinghouse Analysis IJ:1:.A - 271°F
@ 43.2 psig M.SI.B - 333.5°F@ 42.8 psig NRC Cbnfirmatory M.SI.B - 350°F M P79 8 56 3 FlJNCTIOO -
REQJIRF.D OPERATICN Cbnnection of Electrical Cables Various
- LOCA (LT)/MSLR (LT)
Cbntairurent Isolation - UXA (ST)/MSLB (ST)
OOAf,IFICATIOO l"Y\\TA LOC'.A-286°F MSLR-350°F 340°F (3 lburs) 340°F U8~cp.73o s//c:e--r z..
REF. OCCl11FNTS CillAX Report IPS-400 See !Esponse to Section R.4.R(2)
Westinghouse If!tter Report NS-CFr-692 (7/10/75)
CrMMmrs CfJIAX test report is being prePared.
F.xisting test docurrentation reviewed by NRC R:!f:
Inspection !Eport 50-311/78-15.
'lhermal analysis was performed using the same nonel as VEPCo-NAPS which had previously been accepted by the staff.
'Ille peak surface temperature of the cable was calculated to he 333°F.
'lheanal analysis was performed using the same !00001 as VF.PCcrNAPS which had previously heen accepted by the staff.
291°F was the calculated peak surface tempP.rature of the IOCJ~tor operated valve limit switch ment.
In addition, these are MOil' s used by ltlrth Anna.
(4) Fan Cooler Motor Westinghouse has performed an analysis for the reactor fan coolers and found the motor hot spot temperature acceptable for the environmental qualification for Salem Units l & 2.
The following surrnmizes the analysis; The calculated steamline break containment conditions contained a short term peak temperature of 355.1°F.
Using this limiting temperature transient in the SLAB2 computer code, a peak temperature of 266°F was calcu-lated for the fan cooler motor surface.
To determine the potential effects of the steam line break conditions on the motor inlet and outlet air temperatures, T. J.
Fagan (W R&D) was requested to run his code using the peak surface temperature of 98.8°F and a maximum air outlet temperature of 127.9°F.
This information was sent to R. J. Smalter
(~ LMD) who calculated the poten-tial rise in the motor windings to be be 109°F at an operating power of 300 HP, and 90.8°F at 100 HP.
Added to the maximum air outlet temperature, the motor winding temperature reach 237op (300 HP) and 219oF (100 HP).
The test motors have been qualified to oper-ate with hot spot temperatures in the winding reaching 122°c (251°F) during design bases event operation (Letter NS-SS-78006) which is above the calculated temperatures.
M P79 5 18 15 8.4Jl(4)
SALEM GENERATING STATION RESPONSE TO FIRE PROTECTION POSITION 40 NRC LETTER DATED JAN. 19, 1979 There exists no logical method of predicting the effect of fire on electrical equipment (i.e., open-circuit or short-circuit).
An open circuit is considered the more probable occurrence.
These conditions can be detected by the re-sponse of smoke detectors and loss of control voltage alarms for the affected equipment.
A maintained short-circuit condition which results in the operation of equipment is considered highly improbable when addressing the problem of damge due to fire.
However, the postulated occurrence of a maintained short-circuit condition was considered.
Coolant pressure boundary valves found to be susceptable to a fire induced long-term short-circuit were 2PR1, 2PR2, 2PR47, and 2PR48.
In the event any of these valves open due to a sustained short-circuit, the reactor coolant pressure boundary would not be jeopardized.
Sufficient time is avail-able to correct the condition while the pressurizer is relieving to the pressurizer relief tank.
One method available to the control room operator to correct any problem would be to attempt to close either motor operated valve 2PR6 or 2PR7 (in series with 2PR1, 2PR47 and 2PR2, 2PR48 respectively).
In the event this method were to fail, 2PR1, 2PR2, 2PR47, or 2PR48 may be closed by de-energizing the appropriate 125V d.c. supply to the affected valve control circuit.
QUESTION 14.31 Provide the following plant parameters used in the LOCA analysis and indicate whether the parameters used are nominal, minimum or maximum values.
a)
Cold Leg Accumulator water volume temperature line resistance b)
Initial Core flow rate temperature pressures Provide the range of these variables that should be considered in the Technical Specifications or preoperational tests.
Discuss why the value chosen for each of these parameters is conservative or appropriate.
ANSWER The cold leg accumulator and initial core parameters used in the ECCS analysis will be reported at the same time as will the results of the analysis.
The values used will be:
a)
Cold Leg Accumulator water volume temperature line resistance b)
Initial Core flow rate nominal minimum nominal calculated (average of three highest line resistances) minimum temperature (inlet) minimum pressure maximum The net effect of the above input parameters is conservative for the LOCA analysis for the following reasons:
- 1)
Initial system conditions are chosen so as to maximize the stored energy in the RCS and fuel.
SNGS-FSAR Units l & 2 Ql4.3l-l Amendment 45 P78 136 4l I
INSPECTION OF STEAM GENERATOR CLADDING NO. 2 UNIT SALEM NUCLEAR GENERATING STATION Liquid penetrant examination of the No. 2 Unit steam gener-ator channel head cladding referenced in QAD report of NRC Inspections 50-272/79-06 and 50-311/79-06 was completed on January 19, 1979 following hot functional testing.
On that date the third part of a three part inspection was per-formed, the other two parts having been completed prior to and subsequent to cold hydrostatic testing.
Other portions of the inspection program, including metallographic exami-nation of surface replicas, are still under evaluation by both Westinghouse and PSE&G.
Results of the first liquid (red dye) penetrant examination performed prior to cold hydro were reported in our letter of August 23, 1977 to NRC Region I.
Dye penetrant examinations performed in August, 1978 after cold hydro revealed the following changes:
- 1.
Significant increase in the number of linear indications in #23 cold leg but still very faint (light penetrant bleedout).
- 2.
New indications in a small area in t21 cold leg, also very faint.
Dye penetrant examinations on January, 1979 after hot func-tional test provided the following information:
- 1.
New and expanded areas of linear indications accompanied by an increase in the amount of bleedout in both cold and hot legs of 123 steam generator.
- 2.
Many new areas of linear indication in 121 cold leg with greater bleedout than f 23 steam generator.
- 3.
Several areas of linear indications in t21 hot leg, with moderate bleedout.
- 4.
A few new linear indications in 124 hot leg.
'. S.
All of the indications found in the Unit No. 2 steam generators were of a lesser size (length of individual indication) and intensity (amount of bleedout) than those observed in the tl4 steam generator of Unit No. 1.
Additionally, the metallurgical evaluation undertaken on the No. 2 Unit identifies that the cladding indications are sim-ilar to those evidenced in No. 1 Unit.
Based on the liquid penetrant examinations and metallurgical information on the No. 2 Unit it is the position of PSE&G that the lllOst meaningful information can be derived from a continued ultrasonic inspection of the No. 14 steam gener-ator cold leg in No. 1 Unit.
These indications, for which a base line has already been established, represent a worse condition regarding penetrant bleedout and are located near the channel head-to-shell weld, an area of high stress.
Ultrasonic examination of the No. 14 steam generator, cold leg is scheduled for the forthcoming refueling outage and planned for the next two refueling outages to BK>nitor the cladding condition.
HS 1 1/2