ML16306A078

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Updated Safety Analysis Report (Usar), Revision 18, Chapter 3 - Design of Structures, Components, Equipment, and Systems, Figure 3.6-1, Sheet 63 of 111 to 3.6-1, Sheet 69 of 111
ML16306A078
Person / Time
Site: Clinton Constellation icon.png
Issue date: 10/31/2016
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16305A350 List: ... further results
References
RS-16-196
Download: ML16306A078 (7)


Text

? .ta £ J.DHI 1813-0003 14 St40 C.f> '"'" .. w(" B l 40CP ei t06CP ! " I) IJ IJ !: IJ * ... :c z i !! '!! !!! LW , L. 730'.: 11* 4crf I! u 0 " ! ! Ill o.'l ._ f .. 5EE FIE.LO II l! NO TE. '-POOL !" n n p 1 813*0003 REACTOR ffi:SSURE V£SSEL. K-2801 IE12C003 \'ATER LEG PUM" K*2826 1El2C002C RHR PU MP IC .K...::.2..BQ!

1[120331 ECCS SUCTIOO STRA I NER *-28888 VALVE NuMBER I E 12F 025C 1E 1 2F 10 1 R E V I S I ON 18 OC TO BER 2 016 R E LI EF VALVE D ATA MAKE & T Y PE S I Z E V AU,£ SET CAPK;I TY.

GPM 1/2 x 1 4 B4 PS I G G(; GPfl..t OFESSER-1-1 97*0-2 (3*1*1* 2) '/ 2 x 1 1 00 PS I G 30 G PM XF:A ... -. *-----CL INTON POWER STATION UPDAT ED SA F E T Y ANALYS IS RE POR T

-JO UJHS 0 c B 8 8 FIL:-ER DEMI ..

  • IRTOSCB 4 ENGHER"K.

NOTES : 1. WHEREVER POSS181.£, VENT, ORAIN l RELIEF V*LVE DISCHAR<;E PIPtN' SH>LL DISCHAR'E INTO ClDS*D DRJ>l<S. 2. 0 MINI....,..

DISTANCE" MEANS 1HAT THE PIPIN' DES1'NER SHOULD HOLD THE INOIUfEO DISTANCE TO BE AS ""'llAU" AS PRKTICAI LY POSSIBLE v.tTH CONSIOERATION FOil JS! ACCE\'5. ' 3. CONNECTIONS ARE PR0\11()£0 FOR OECONTAll

.. ATION OF SYSITM EOUIPMFNT . 4

  • SlllllUSS STEE\. RWCU Pf'lt;G SHALL NOT BE BENT* STAMJAl<O ATTll<<; SHALL BE VSEO. 5. FUR SA>f'l.E PRO& RECi.JIREMENTS SEE '.E. DOC. NO. Z2A2708 . F1' .2 &. ?RESSUF?E.

TAP SH1'1_L E>E O FF BoTTOM OF PIPE... IG}3*COOIB JG.H-COO!A IG338001B 3 IG33B002A

&. IG33B002.B NON-REGENERATIVE HEM EXOiANGERS 2A &. 28 REVISION 16 JANUARY 2014 FIELD NOTES: I. AU. All CPERATED WVES,EXCEPT

!HOSE US!EO IN NO!E N(). 2, SHALL BE INSTALLED WITH PROCESS FLUID FLOW FIRST ENTERING J\BOVE \Al.VE SEAT. Z. AIR CPERA!ED VALVES IC:l<;FOO, lf.3<>F002, 1'3<0F003, K&FOOS lb3'FOOl4 1

&. 1'36f02.l SHAU. BE INSrAL.lfO Willi FLOW FIRST fNTEH!N' UNOCR VALVE SEAT. 3. STRAM:R 01FFE.REt**ff"lprr.,L P'<ES.SUR.t GAU'E AS SHOWN .. STAU.ED FOR PRE-OP. & INITIAL srART-IJ' TESTWG CRY. RE>IJVE lllR NOllMAL OPERMION. 4. FOR RWCU LOGIC SEE G.E. OWG: 7"2E*07. 5. ALL HANO SWITCHES ON MOS*107" SHI> 2 L 3 ARE ON PANEL 1Gy;*P002 UNLESS OTHERWISE NOTED. !;,, RESTRICTNG SIZES INOICAT£0 ARE FCR INITIAL SYS fEM START* LP ONLY. ADJUST AS NECESSARY TO MEET SYHEM HYDRAULIC REQUIRDAEN!S.

1* 'JI; FURNISHED WITH ASSOCIATED EQUIPMENT 3 K-2801 *PANE L CRAIN 633800IA & IG33BOOIB REGENERATIVE HEAT FXCHMK"-.E:RS IA & IB RELIEF VALVE DATA MAKE

  • SIZE VALVE SET '( PSIG) TYPE INCHES) cRo::>e'{

1Y2 x 2 1410 t 1 k.FL.J:;;;-4SW cRo::;oy 1Vzx z 1410 1\.lzF2 J'0*4 5 ZX3 150 Jo-2.S cR o:.e'( 1 1/i, h!:> JO*'?.S> 1V2x 3 150 c.Ro::.ey

.3/1-1 JO*Z.S 3X4 150 Cl?OSe>Y 3X 4 ISO J0-2.S DR E'bSE..R 3X4 150 3-lSIOK*l(I-1-e--2..)*Xf,._b NUCLEAR SAFETY RELATED TEMS ARE SHOWN ON THIS DllAWING I IOI SAflfY ClASSIFICAUON SH ....... IO&WMINT.

YMVI. oa INStllUMINl usn. I NOif: lME P,. I b!C & I OIAG:IAMS fOI tHI C & I PUNCTabN SYM-S --N ON DIAWING MIO-'1076 UNllSS OT..:IWISI 1tOTIQ. SHER NUMIH & DIAGIAM __ _ lffHINCI AH SHOWN .. THE fUNCrtON SYIMOI.. CLINTON POWER STATION FINAL SAFETY ANALYSIS REPORT FIGURE 3.6-1 DIVISIONAL SEPARATION AND HIGH-ENERGY REACTOR WATER CLEAN-UP SHEET 66 OF 111 E 0 8