ML17334A945

Requests Hydrostatic Testing of Identified Inservice Insp Class 1 & 2 Piping at Lower Pressures than 1974 ASME Code Criteria.Avoidance of Unnecessary Personnel Exposure to Radiation Hazards Cited.Fee Paid

ML17334A945
Person / Time
Site:	Cook
Issue date:	02/03/1986
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0070V, AEP:NRC:70V, NUDOCS 8602100174
Download: ML17334A945 (22)

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REGULATORY IlO~MATION DlSTRIBUTION SYST~(RIDS),

ff I'~CEQE/Jl, I&I:8602100174 DOC. DATE: 86/02/08. NOT RAZED: NO DOCKET FACIL: 50-31& Donald C. Cook Nuclear Power Planti Unit 2i Indiana 8< 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICHiM. P. Indiana Zc Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION DENTONi H. R ~ Office of Nuclear Reactor Regulationi Director (post 851125

SUBJECT:

Requests hydrostatic testing of identified Inservice Inop Class 1 5 2 piping at lower pressures than 1974 ASME Code criteria. Avoidance of unnecessary personnel exposure to radiation hazards cited. Fee paid.

DISTRIBUTION CODE: A047D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: OR Sub mi t ta 1: Inservi c e In spec t i on/Test in g NOTES 05000316 OL: 12/23/72 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PWR-A PD4 PD 01 5 5 PWP,-A EB 1 1 WIGGINGTONi D 1 1 INTERNAL: ACRS 16 10 10 ADM/LFMB 1 0 ELD/HDS3 1 0 NRR BWR ADTS 1 1 NRR BWR EB 1 NRR PWR-A ADTS 1 1 NRR PWR-A EB 1 1 NRR PWR-B ADTS 1 1 N EB 1 1 NRR/TAMB 1 1 04 1 1 RGN3 1 1 EXTERNAL: 24X LPDR 03 1 1 NRC PDR 02 NSIC 05 1 1

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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 February 3, 1986 AEP:NRC:0070V Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50.-316 License No. DPR-74 INSERVICE INSPECTION PRESSURE TEST CODE RELIEF Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This submittal and its attached flow diagrams are made pursuant to 10 CFR Section 50.55a(g)(6)(i). The piping sections listed below are classified as ISI Classes 1 and 2 and are subject to hydrostatic testing during the 1986 Refueling Outage and the subsequent 10-year ISI outage for Unit 2 in accordance with Articles IWB-5000 and IWC-5000 of the ASME Code,Section XI, 1974 Edition. These sections of piping cannot be tested to the code requirements without modifying the systems and/or exposing personnel to unnecessary radiation hazards. We are therefore requesting code reliefs to test the, piping at a lower pressure.

1. Emer enc Core Cooling S stem, Flow Dia ram 2-5143 (Attached)

Pi in Boundaries (a) Accumulator No. 1 Discharge Piping Valves IM0-110, SI-166-1, IRV-155, SI-168-1 (b) Accumulator No. 2 Discharge Piping Valves IMO-120, SI 166 2~ IRV 165'I 168 2 (c) Accumulator No. 3 Discharge Piping - Valves IM0-130, SI 166 3g IRV 175'I 168 3 (d) Accumulator No. 4 Discharge Piping - Valves ZM0-140, SI-166-4, IRV-185, SI-168-4 k

ISI Code Class-2 Requirements:

For a system design pressure of 2485 psig, Article IWC-5000 of Section XI code requires the piping to be tested at a pressure of 3106 psig and temperature not less than 100 F.

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Mr. Harold R. Denton AEP:NRC:0070V Code Relief Re uest:

We propose to test the above sections of piping at a pressure of 2280 psig at a temperature above 100 0 F. The test will be performed during Mode 3 with the0 Reactor'oolant, System (RCS) pressure at 2280 psig and 7y 500 F. The RCS pressure will be used to block the check valves (SI-166-1, SI-166-2, SI-166-3, SI-166-4) closed, thus limiting maximum pressure to 2280 psig.

Basis For Relief Re est:

The section of piping upstream of check valves SI-166-1 through 4 cannot be tested at a pressure of 3106 psig without making extensive temporary modifications to keep the valves closed. The modifications would require: (1) disassembly of the valves, (2) welding of temporary blocks (on the downstream side) inside the valve bodies to hold a "jack screw" type arrangement to keep the valve closed, (3) removal of the temporary blocking devices from the valves after testing, and (4) performing necessary non-destructive testing to ensure the integrity of the valve bodies before returning'hem to service. The piping downstream of these valves is part of the RHR System and carries radioactive fluid

~ during normal operation. Therefore, plant personnel would be

'ubjected to substantial radiation exposure and radioactive contamination in order to carry out any modifications for the test.

We believe this to be a reasonable code relief request, since the proposed test pressure is, in fact, higher than the 2235 psig nominal operating pressure in the short sections (less than 5 feet) of the piping systems for which the relief is requested.

2. CVCS - Reactor Letdown and Charging, Flow Diagram 2-5129 (Attached)

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Pi ing Boundaries:

(a) 2-Inch Aux. Spray Piping Valves QRV-51, CS-325 (b) Normal Charging Loop 4 Cold Leg-QRV-62, CS-328-L4, CS-326 and CS-327 (c) Alternate Charging Line to Loop 1 Cold Leg-Valves QRV-61, CS-328-Ll ISI Code-1 Re uirement for Item .(a):

For operating pressure of 2235 psig, Article IWB-5000 of Section XI code requires the piping to be 0 tested at a pressure 2458 psig and temperature not less than 100 F.

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Mr. Harold R. Denton ISI Code Class-2 Re uirement for Items (b) and (c):

For a design pressure of 2735 psig, Article IWC-5000 of Section XI code requires the piping to be tested at a pressure of 3418 psig at temperature not less than 100 0 F.

Code Relief Re uest:

We propose to test the above sections0 of piping at a pressure of 2280 psig at a temperature above 100 F. The test will be performed during Mode 3 with the RCS pressure at 2280 psig and 0

500 F. The RCS pressure pCS-329L1, will be used to block the check valves CS-329L4 and CS-325 closed, thus limiting maximum pressure to 2280 psig.

Basis for Relief Re uest for Items 2(a), 2(b) and 2(c):

This is a similar situation to Relief Request No. 1. Check valves CS-328L1, CS-328L4, and CS-325 are located on the charging lines to the RCS System. These valves must be disassembled and temporarily modified to block them closed in order to perform the required hydrostatic tests and plant personnel would be exposed to high radiation and radioactive contamination during the modification.

We believe this to be a reasonable code relief request, since the proposed test pressure is, in fact, higher than 2235 psig nominal operating pressure in the sections of piping between 23 to 115 feet long for which the relief is requested.

3. CVCS Reactor Letdown and Char ing, Flow Diagram 2-5129 (Attached)

Pi in Boundaries:

Letdown Lines Valves QRV-112, QRV-160, QRV-161, QRV-162 ISI Code Class'-2 Re uirement:

For a design pressure of 2485 psig, Article IWC-5000 of Section XI code requires the above piping to be tested, 0 at,,a pressure of 3106 psig and temperature not less than 100 F.

Code Relief Request:

We propose to test the above section 0 of piping at a pressure of 2280 psig at a temperature above 100 F during Mode 3 using RCS pressure. Valves QRV-111 and QRV-112 will be opened with QRV-160, QRV-161 and QRV-162 closed.

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Mr. Harold R. Denton AEP:NRC:0070V Basis for Relief Request:

The above section of piping cannot be tested at a pressure of 3106 psig without modification since no test connection exists.

This piping carries radioactive fluid during normal operation.

Therefore, plant personnel would be subjected to substantial radiation exposure and contamination in order to add a test connection. I As an alternative, extending the test boundary to QCR-301 was considered. This would involve using QPX-301'ocated on the downstream piping outside the regenerative heat exchanger room as a test connection. This. consideration was also rejected because valve QCR-301 and the flange bolted to the inlet flange of safety valve SV-051 are 600-lb. class, which cannot withstand the above test pressure.

We believe this, to be a reasonable code relief request, since the proposed test piessure is, in fact, higher than 2235 psig nominal operating pressure in the sections of piping approximately 65 feet long for which relief is requested.

4~ Emergenc Core Cooling System (SIS), Drawing 2-5142 (Attached)

Piping Boundaries:

IM0-51, SI-142Ll

'alves Boron Injection Loop No. 1 Valves IM0-52, SI-142L2 Boron Injection Loop No. 2 Valves IM0-53, SI-142L3 Boron Injection Loop No. 3 Valves IM0-54, SI-142L4 Boron Injection Loop No. 4 ISI Code Class 1 Re uirement:

For an operating pressure of 2235 psig, Article IWB-5000 of the ASME Code,Section XI, requires that the piping be tested at a pressure of 2458 psig and a temperature not less than 100 0 F.

Code Relief Re uest:

We propose to test the above section of piping at' pressure of 2280 psig and a temperature above 100 F. The 0

test'ill be

'performed during Mode 3 with the RCS pressure at 2280 psig and 0

7y 500 F. The RCS pressure will be used to block check valves SI-142L1 through L4 closed, thus limiting maximum pressure at 2280 psig.

Basis for Relief Request:

This is a similar situation to Relief Request No. 1. The sections of the piping system upstream of check valves SI-142L1 through L4 cannot be tested at a pressure 2458 psig without making temporary modifications (blocking the valve disc) to keep

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Mr. Harold R. Denton the check valves closed. Since the piping sections are part of the primary system, plant personnel would be subjected to substantial radiation exposure and contamination in order to carry out such modifications for the test.

We believe that this is a reasonable code relief request, since the proposed test, pressure is in fact higher than the 2235 psig nominal operating pressure in the sections of piping, each approximately 44 to 55 feet long, for which code relief is requested. I

5. Auxilia S ray to Reactor Coolant System and Pressurizer, CVCS-Reactor Letdown and Charging System, Drawin 2-5129 (Attached)

Pi in Boundaries:

Valves QRV-51 CS-326 Valves QRV-61 CS-322 Valves QRV-62 ISI Code Class 2 Re uirement:

For a design pressure "of 2735 psig, Article IWC-5000 of the ASME Code,Section XI, requires that the piping be tested at a pressure of 3418 psig, and a temperature not less than 100 0 F.

Code Relief Request:

We propose to test the above section of piping at a pressure of 2800 psig.

Basis for Code Relief:

I In order to perform the pressure test in this ISI Class 2 Sections of piping, valve QRV-51 has to be used as an isolation valve. This 1,500-lb. class, air-operated control valve is designed to withstand test pressure of 3418 psig in the open position. However, it cannot be used as an isolation valve because it was designed for a differential pressure of 1200 psig.

The valve cannot be kept closed, dur'ing pressure testing at 3418 psig without extensive temporary rigging. The modification would require: (1) removal of the air operator and installation of a "strong back" to keep the valve closed during the testing, (2) removal of the "strong back" after the testing, and (3) re-installation of the air operator on the valve and restoring the valve to operable condition before returning to service. The valve is located inside the regenerative heat exchanger room, which is a very high radiation area and plant personnel would be subjected to radiation exposure of 5 to .7 man rems.

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As an alternative, the possibility of using a freeze seal plug downstream of QRV-51 was considered. This would involve extensive working time close to the pressurizer spray valves, which are in a high radiation area. This alternative was rejected because plant personnel would be subjected to an even higher radiation exposure of 8.5 man rems during formation, monitoring and removal of the freeze seal plug.

We believe that this is a reasonable code relief request, since the proposed test pressure is in fact higher than the normal operating pressure of 2235 psig in the approximately 30 feet long section of piping for which code relief is requested.

The NRC granted these code reliefs for Unit No. 1 hydrostatic testing in 1985 (reference NRC's letters dated June 28, 1985 and August. 13, 1985).

Attached to. this letter are the following flow diagrams:

1) Dwg. No. 2-5143-29, "Emergency Core Cooling (RHR)," Unit No. 2

2) Dwg. No. 2<<5129-28, "CVCS Reactor Letdown and Charging."

3) Dwg. No. 2-5142-26, "Emergency Core Cooling (SIS)," Unit No. 2 In order to avoid unnecessary delays and to restore the unit to power on time as scheduled, we are requesting a response from the NRC by February 20, 1986. If you have any questions or concerns about the material contained herein, please do not hesitate to call us.

Although these code relief requests have been reviewed by appropriate technical and managerial personnel at both AEPSC and the Plant, this document has not yet been reviewed by our Nuclear Safety and Design Review Committee. It will be reviewed by them at their next scheduled meeting.

A check in the amount of $ 150.00 is attached with this letter for the NRC processing of the aforementioned requests.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, V

M.. Al xich )g vice president eL~)d" Attachments cc: John E. Dolan (w/o attachments)

W. G. Smith, Jr. - Bridgman (w/attachments)

R. C. Callen (w/o attachments)

G. Bruchmann (w/o attachments)

G. Charnoff (w/o attachments)

NRC Resident Inspector Bridgman (w/attachments)

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Mr. Harold R. Denton bc: J. G. Feinstein/K. J. Toth/W. E. Harvey S. H. Horowitz/T. 0. Argenta/R. C. Carruth J. J. Markowsky/S. H. Steinhart/J. A. Kobyra R. W. Jurgensen R. F. Kroeger M. L. Horvath Bridgman J. F. Stietzel Bridgman F. S. VanPelt, Jr.

J. B. Shinnock D. L. Wigginton, NRC - Washington, D.C.

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Iso ro rr c CHE.IO) alla >I>w lb FKACC)R CCOLAIIT CTCLSI TK. Iltt HCCC SKC btt4 58%,!fL 5'.C ORV ILIp TA 5

r lsotaHH w.

TEST CCSN t Dtl)11 F.O CiSSI

~

~ CSSLO FOR VALVE. IHSTRUMKNT, CALIFVHO, PIPE SCATERIAL AHD OTHCR SVSISCLS HOT X

ALh'Tssstscsslr Lblc CSSNLI 2 cooociftoec tCDCCCt LO>4 LETCOTCH OPKKES tltt FRCIC Ksc)TSL

~IRAZ TO REACTOR EAPLAHIKD CN THIS bvCS AHO FOR SCARF, HCSetSCR lD LOCPJ COLD LEG SKE DRG.GAtb>CI5 C)b +142 OTSJCIL ILS OP% 5145>ttb COOLANT FILTER CCOCS CKE Dvcb SO4.

SEK OTIC 5129A)tt l F.a~ csw rv F.C assi FL KL. 4 l)10 SEISLIK CLASS I ISRV~Z TO Pt KSSURIZER NORMAL CSCLRGCHG UNE Cct $ 00 SO TO LOOP H COLD LKG assai RELIEF TAIIILSEE SEK DTIG KO 5125.CAS, I 4C>T +CD. <<H Dstb.SIKSAKCb. VALVE HDTEO A'/O C)RV.C SO vtvt cFS)s At aco palo ALAX.SPRAT TO REACTOR aSSILC 4Stc 'O 5COCK COOLANT STSTESA DH DVTCL ~

PRKSSVlg2XR. SEE SK'G>S Htfa'A 5I?bl,tt)4.

?

OCVCI CPN 35 1st ttCSPCCllCSI TO CL t lD VOLUSAE CONTROL I, TANK. SEE DWG, 5129 A 0/4 ROCAZC)H VlLVC 1$ 1 IHSFKCBOH TD CL. 2 Q CXCCCT SV WESTINGHOUSE AS HOTCO CL40%&'

CCCCSSttt OCTO) AU. VAl.VE5 K OISTRU IttlCCOCHCC>CLSKK DWi SHSA>C)CC MKHTATON DCAPF>LIRD

~;12- I RKGK)RRATIVK HEAT KXOVICER 10 IEACIOCC CQOEAC 1st Dose>CCTSO>e IAK'~FtOH SAllttIHS Crs)KK IPMEHT SVPPLIED SY 5 LKT DOIVN FROLC LOOP 4 DRVHII Isa.12) DRAIN TAHK SCC SKK 5%4. S41 ~ Ials- AS NOTED SEE DvvG NO oftb>CCA4.

OWC 5147 4> C)CX Nr>re ocs o>ec> %>%2 > IQ 3 Ltsr CCOC aASS CLSIISSOD>CNI

~

F C. F.C ELEV. 612% CO>reccflor>L,SNC 1$ 1 Oev>oeof cxITNos oo r>>o INcle>ocs TNC lll SPIN SI ~ IS> SNC tie>ee roof >1aer>c LCCO COOL CLI>I to>S VDITS 4 Iill SSI Orer>S TNC COOSOOD. SCC CSTSNot SO li>I>vcr'NC tPIC> tSICOIOCS tool Nor>wells closcO \NLvc 4' F.csst asoo g RR tHCICATES REACH RCO CS OSC ItbOU! KD I)40-910 FROM REFUEUNG MATER cssoc iORV-ZSI STORAGE TANK. SEE cs Save DVCG. ICO 5144 CIo.lsl Ilts OCAICC INSPCCT ION IO CSStl Q

1NSIDE REACTOR COICTAINSAENT 3 O'FICOC PRSCLCT lTATtk 2 bOCUC b FROII RKSOUAL OUTSIDE REACTOR COHTAINICENZ HCLT ESCIVHCCR ~ ~

~ ~~ AGO FRTCRS,NS DTCO.SIStW5 ODG 5143.HIS E'KK astor asso Fsosc cHcscrAL Hccscc lscsc. Habltr CPCAOSS-TIE, R ZKO.SCI

'll Sta DVCC. 512%A> K/Ca SKL OHC.514'2 HIS 3>

I CIICI ICITIOP IO>P OS r FRcsl IDIOKco ssstt)l 2 'lO aCSL WATS l AttCJJI ceav Itoccr vllvc IAI4cccr 4I llOS OIIIOVIO. KC CA]R9 Stt CICC45ISI,PCS Hll'f KSCHAHGS R.

Sat DHG.S>2%A> ~RLLCCF 10 PRESCUCCIZKR TAHr

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4 FRCN VOLACHC ARTCC CKE DOC.SltSA Dla t)co>ISD

'sic'A>Icos HcoPlEI tca cist As roLtoos:

SCC Oa>CNII ISA SVISO Stf sic Oe'I+SWtC4%

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~ TTLOHÃf NADOI:

lO, csr. CSSSl tccc slpat srccKvl tCO SILKS IOCLN:VSPC~

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lD REACT>>t COOLANT.PVLAPS SEAL WA ER CCCCCVCT (4 PUMPS)

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~ cs lese Ie ~ aei L X

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'W')0 GPM DESIGN 5CH 1'l socrAousctc) acsLsctf PUMP aE 5500FK HEAD STH SV I )

Oaf CSO SQ) eecacoHsct COoLIIIC$ WIT Q rh~~~~.

fogtOCOI tLIOO CO>VS COOL! a

~r t ~ parrae p ar ~

P PWP r PN> aa r Pr ra M >P~

Paar ra eaaar p NO ~ I > pppc ew ea SSOGPM SIA)L OctccotERS.atcoccAScsLccr. 5 0 HO K DOCS. 5155> OV'OCISI PlrtfCTD>l eprpp WWI>S>~

SIST. CitS, 650HP I PP SO)

SSCC Nll.OOCH FOISON KSSO t)CG e IHC OOOCAVINO C>aero>NI Orrr o ocNINL ~ eoceoo>N aL LUISE ON INSTRUSIIENTATION AT CCNTRIFVGAL CHAICGIHO PUHIP5 I

SGK .

ttt 50) csoo trr~S) rsl Nc>D IOTCI DONALD C. COOK SI %His oloa Nooc UIUOUL NACICAR tlAHT IHSFRINab'T Hct FUNCTION SC 4 Sr ETCH atty '

FOR SCOC PIPHIG AT PUVCNA 1.~> 557 0 POR UH PSASCSC5 OICA.

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It CAST Ltb t OA

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T blbltiltl

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Ttcv>CCS

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3/4 3/

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~

I oueeAIRY LXTEH05 To 4 PPAIHARY WAIIR lal VC.

340'IK'A OAIFI(t, R010S FLUSHOAIIICT'N Stt DWG 91144 LTI 260 LTI-262 'W OL CCOLKA DSCHARK 1(AICFCCD, 30 240 P AANSS 1st CL.'t SN54 LTTL24I IIOTC OI LT1 LP(~262 263 CN THRUST BKAANG AT TH IEI)50IG,SO 240 F AAIRIE T BEAA046 HOUSING OL RLET.0.30 PSI C4456 DEAUCS TEIG,ZSE OOIIDIEY t IKNI5I BET RCCIQC. SIT SS I CFTCEA39 TO INCLUDES TUK Stt THIS DNCaK/I 511M KVCS HOLD UDIAEIKS FECST HOZEOILL'f-CECKCD StK DSIG.5I3IISC/G. VILVC.

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\Illa 250 IIV251 FQ..~.L IRV 25'OSVE91 XIIII)35

~TO bORIC 513).

SEE DW6 ACID TANKS 0/S

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'203 4

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BORON INJKCTICN TANK 4'4/DEA XI(<'HIGH (OVERALL)

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T NN 51lttc rr r r FROM BORIC ACID TRANSFER PUMPS SEEING 5131, K/5 IAV '253 IOCHTEFECITEO<<

5 Cla.v laacUE YALYE MINStas IEUN WS 4TR)OI CNARGIN(a 5 l ee N FC IFFEIA CH IHa oalreL Stt, 250 251 Stotaatt VALVE 10trtrCATKII PUDIP CROGrr TIE 51 205 TMD.256+ I ~HEAT TRACEHce 51ST Feat ECUETALCÃT CESNH STTOP5 HERE 5KK DVI(tb)29,G/4 to 2.

INCAI IUNCEAS.

TAC'AIStas NCOEFIED Fta rl FROM REFUELIISG WATER 0aAWSEC USE AS FOLLOWS:

T40 Hl: S.H5WICISDW Itst CEEN. STORAGE TANK. OR RESIDUAl- AS: HSWECOW SET)IT I 51ltC Slit t NEAT EXCHANGERS THRU S.aaIAUSIEHT ACCT VSLVE NARK 4 CHARGING PUMPS DISCI(. HTS IAT OSOWN CN oarsaatt 4'EADER. SEE DWG 5129, F/5 VALVE 10EHIPICATIOH LNT):

1st CUE INO I'lf CAooCOCOTOI~ ICH SEHIKE SrcteYI DRAIN~

P ~ CSI 0CCet ~vllostateet0

t. SIUS S~KTHIS'(IV%VX/3 Irt cl. t C HEAT TYCACENCE Sll Sletl esltOPS HERL FOE NICROIllr Stltla Stt EL 612 0 10 tECSCEaeaneae SHÃ~

WCETEF Taeae COI Caaa SE SEAT AEC 200 51115 .EL GI2'-o 3 SF Z-$ '6 ROSUCH IECCSD FOA INC 0WC

~

TO pAKssuAIKKA Sl Ca 2 CPN 43 SV BBD RELIEf TANK SKE IMPS NS243

~~~

IKG5) TARU )TIDING PROM EKSESIIK mhT KXmHlGER 1514:l 2 (COLD

~

W'EE See VENT jjOT BY Q 4

n50 PS 10(TYW>

Or 3/4'YKNT 511155 cat

'SKI AT '220 I

DWC.

f SIRBA,SC.YTS'V-SC.

5 INO~

I loa IND.2GI FROM REFUELING

'eae wwe 4 aa lUcgc fwla ewNTT N w ~

aeaeeet eao eN w New

~

,ew 4 4 w N N Nwaaw N elect 4 alai ea N eeet la ew Sea ew waee eaeeeew 'N EN weaN

~

Ilg IITIO ECTR WATER STORAGE ~ aew aaaaee N w.M at ala Naeaa eeaaN eaaeaeeee Ta aol cw'l

%Mt 5INt F I TANK. SEE DWG w a Ta N Neeaw oea 5I44, E/0 F rceEIHI ~ NEONEOIH ttscYHEc Fge SKE THPS Di/Ga D/3 SIEITS S4TCSTUTEE ICI M att Ct Silat ~ftlaCIACULKDON LINE OEt 04EOa Naa TO REFUELING WATER (IDHALD c. CD()K I'~mIKRIOR @40 E)(g 01 4'alt ~ <<TEOT N OEL STORAGE TANK.SEE IIUCIKAAFIAKF TETCT FAOM RESIDUAL f/7 2'2'r NTCaleaEA DWG. 5144,

~CRINE 51lel DXIDON HKAT KXQIANCIR a

'fe E Icat TN Stt DIIC.

FLOW Iee(VLHT Ro'454 5 L 5143.uf DIAGRA/EL 4 TOLODPS II 4(K'OLD Ltd THAB,PIPING FAO14 RLSISQL ICM KCQ RIOT banc F ENO 510

'SI.KeCNy 04~ 4 ME TOS 61'1046 6

eat 201 cLC ERGE CORE COOKING 5 UNIT NR2 HEAT 'EXCHANGER. K . SKK RO EOC N SIK 50 DWG. SICK e)B l 'Ill la

'llI TNT Le BACK4ID CROSS-IIK

~ 'I T444 I

I lal Cl..t 2" Sl CCD H 2-5 )4 2-26 IO 4 FAON CKNIAIFUCAL I SIIII CFHCC I ION IA CHIRCIHC DUEIOS SUCIIUN 'TTC FDEE TteeoaaaaT 55 DRAIII erTT Tare NIADCR Stt, DTIC.SII9 JIC 4 aaeeecR TTTN ia Ce

>>II" SEEFIT (2. SAFETY INJKCTION PUMPS PD.26 e ~ee aae c ae. 54 AE LERT +c~N ccas 400 Bole( ICRSICH) 2000 FI IDH (01 SICH) 3510 ROM GSOGDM (MAX) 1535 DSI (SHUT CFF) '400 NP Q 54lai QWG MA'OE UICTC)VK FOR

~ SSLDE RKSCIO/t CONIAINMKNT OUTSIDE REACTOR CONIAIKMKNT MAX. DISCHARCK ORESSUIES I'729 PSIC UOCIT 42 AND SUPERSEDES DWG NT ~eeeeaeea teactaec loata IDITTct ce'

( NCIK: FOR MISC; PIPING AT DUMPS SKF. SK'M-2') I C55142 RCV 16. aoeoa le eo Teal O I' N M N

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