ML21055A393

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3 to Updated Final Safety Analysis Report, Drawing 6M721-5859, Reactor Core Isolation Cooling System
ML21055A393
Person / Time
Site: Fermi, 07200071  DTE Energy icon.png
Issue date: 02/02/2021
From:
DTE Electric Company
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21055A091 List: ... further results
References
NRC-21-0002
Download: ML21055A393 (1)
v • d • e


Text

8 7 6 5 4 3 2 1 RF"F::::?ENrE _IDCUMi::NT MPL ITEf1 NO.

,.,scE*i...AflfM INFQIMIT~ 1. liUCLEAR BOILER SYSTEM PROC. DIAG - - - - - - - - 821-1020

t. 0£St(,U PIIES~IAlt"S - 1'£MP£1fA1\llllS 61VSI B(LI)ol N!£ f'OR H INf~TION ONt.> NG AIIE TltE &<SIS foQ DfSIGH OF >l'ED

~ I ED [QUI Pl't:llf. H LOCATION 0 I- Z 3- 31 311-4 7- l. 8-9 10*11 3-12 ll.-13 13-14 15 17 IS-2 19*t9r 1')11-G 20 l.O*I

  • THE PRESSURE AT THIS LOCATION DEPEfJDS CN PiPING ARRAflGE~ENT, OESIGN PIIESS (I) AND MAY BE VARIED 1./!T~IN THE F LLO'wlNG LIMITS.

IN ~ . .- 18 128() 12 5 1250 150 1?80 1?5 125 75 15 12.S 121!() 125 1280 ll.~

LOCATION DESIGN TEM"'

IN *f 12.0 170 (2) '170' ':>15 267 170 170 170 250 1';10 190 170 tit 100 100 NOTES,

~

MINIMUM NPSH AT PUMP SUCTI N = 20 FEET.

. ~) *. ATMOSPHERIC PRESSURE OF 14.7 PSIA WAS USED IN CALCULATIONS .

Ct> ot:Slf.M PA£SSU'I£ S~J't.L ll ~S,.-

()N FE£o,J*T(~ SYSTD4 >i<UT-OFf MEAi> If THIS CCll'<)ITIOt excEEos 12eo rs14.

12110 PSIG OIi D!:P(><<Nr M,AXIMUM PRESSURE RISE ACROSS PUMP 2915 FEET FOR MODES A & C 525 FEET FOR MODES 3 & D.

2.

3.

IJATER FLO'dS ARE SHOI./N IN GPM STEAM FLOIJS IN 1000 LB/HR THE MAX!HUM POOL \./ATER TEMPERATURE FOR CONTrnuous SYSTEM OPERATION

\./ILL NOT EXCEED 140'F. HOIJEVER, DUE TO POTENTIAL SHORT TERM G) MAXl~UM PRESSURE DRCP BETI./EEN LOCATION OPERATION AT HIGHER TEMPERATURES, PIPING EXPANS!DN SHALL BE BASED

~

r-(l) f'IW(ESS DIAl'."JlN4. ,.,L foll OeSIG/11 TENl'ERATUI!£ Jll:f(R fO HUCll,*R tlOILE!li 5YSTOI ll.il *10W. © AND 0 = 15 PSI. 4, ON !70"F.

THE UNRECDVERED FLO'd NOZZLE PRESSURE DROP OF 4.5 PSI IS A FIXED LOSS C<N:fttSATE STCIR"(J[

I@ MAXIMUM PRESSURE ALLOIJED = 25 PS!A, 5,

BETI./EEN LOCATIONS@) AND©*

THE LUBE OIL CDOLX' PRESSURE DROP OF 3.0 PSI IS A FIXED LOSS BETI./EEN T- (ij) MAXIMUM PRESSURE ALLOI./ED = 75 PSIA. LOCATIONS @ AND Q_'.1.1 .

6. THE CONTROLLING MODES FOR LINE SIZING AND ARRANGEMENT ARE,

@J SUFFICIENT VACUUM TO PREVENT TURBINE SUCTION FROM COND STORAGE* - - - - - - MODE A & B SHAFT-OUT *LEAKAGE.

SUCTI N FROM SUPPRESS!DN POOL- - - * - MODE C & D G (D @ MAXIMUM PRESSURE AVAILABLE = 25 PSJA, PUMP DISCHARGE * * - - - * * - * - -

  • MODE C & D

@ @) STEAM SUPPLY * - - - * - * - - * * - - MODE A & B G

' MAXIMUM PRESSURE AVAILABLE = 50 PSJA. TURBiNE EXHAUST * * - - - * *

  • TEST LINE * * - * * - - * - - -

MODE MODE A, C & D F

@ SUFFICIENT PR[SSURE TO RETURN TO SUPPRESSION POOL. COOLING SYSTEM * * - * - - - - - - * - MODE A I?) SUFFICIENT PRESSURE TO RETURN TO COND. STORAGE. 7. THERE ARE OTHER POTENTIAL OPERATING MODES VHICH DD NOT CONTROL t--- ..,._____,...___......._ - - _..__.._ ... --- PIPE OR VALVE SIZING OR SYSTEM OPERATION AND NO DATA IS SHOI./N; I,!>

' @'1110t2LE

10. FLOIJ VALUES SHOI./N IN MODES C&D ARE BASED UPON SUCTION PIPING DESIGN PERMITTING THE MINIMUM REQUIRED NPSH TO CONTINUE TO BE PROVIDED TO THE RCIC PUMP \./HEN THE SUPPRESSION POOL SUCTION STRAINER JS 50% PLUGGED.

8.

AMONG THESE MODES JS OPERATION 1./ITH INTERMEDIATE PRESSURES IN THE REACTOR VESSEL AND SUPPRESSION PCOL.

PUMP MINIMUM FLO\./ REQUIREMENT MAY OCCUR DURING ANY OPERATING MODE. FLO\./ REQUIREMENT IS 75....G.PM MINIMUM, DURING MODE A.

- 11. MAXIMUM LINE LENGTH BETI./EEN POSITIONS 5 AND 22 EQUALS 60 FT.

THE INTERNAL CROSS SECTIONAL AREA OF THE VACUUM BREAKER PIPING

9. DELETED REAC. TO!\

...3/4 THAT JS SHARED BY RCIC AND HPCI SHALL BE EQUAL TO OR GREATER THAN THE COMBINED J~TERNAL CROSS SECTIONAL AREAS OF THE INDIVIDUAL RCJC AND HPCJ VACUUM BREAKER LINES, CONT.

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., f £. _________.'v NOTE 11 ~ ' FLOW -S\".E i'IOTC l - 600 Gil', GOO - - 0 - 9.10 9.15 9.15 Ho 10 IG 0.15 - 0.01 16+ - 0

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' T/INI( Vi'C.UUM I.. ~ I--'---"---*' - PUMP OIL MIN FLOW \.IN£ lb----,-----. COOi.CR

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$'1$1EM TEST \.INE ~,------ ' .

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..... A.MB 11116 AM8 56 /27 %0 AP!&

56 AM& AMII, 111'111, ~l'IB 1111& AMII, 11.M& IIM& AMI AMII, THIS IS A MICROSTATION PRODUCED DRAWING.

TE.~PE:RAl\lRE 0 1' - CHANGES OR REVISIONS MUST BE BROUGHT

"-v---1 TO THE ATTENTION OF THE PLANT ENGINEERING llt1£Rl'\111Etll Fl.OW DESIGN GROUP TO ENSURE THAT CONFIGURATION THRO\.IC.H ORAi I,& CONTROL IS MAINTAINED.

lAAP !i1':i T EM 10 5uPP THIS DRAWING WAS REFORMA'rfED BY E-8 M!CROSTATJON AT REVISION "E". ALL INC CODE Detroit Edison Fermi 2 POOL E loco*s INCORPORATED:

PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM IN DOCUMENT CONTROL PREPARED BY u

DATE TITLE REACTOR CORE ISOLATION A PORTION OF THIS DR.\WING IS AFFEC'tED BY THE FOLLOWING:

TSR 35664. i'IEV. A. COOLING SYSTEM A ............... --****-*****.. " ................................................. "*" *" . . . . . ....................................... ..... _............._....................................................................... --......... .............. ... .............................. .........,_ ...................................................... ".... *. . . * ......".""* "_......... "........................................ *. ""* .. "**** ........... **................................:. . . . . . .:. . . 1-.Q--TH__E__E__.. O__

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CHECKED BY DATE

....I PRC~~"n°IAG-- IDC . CORE .is61 COOL, sis " A I "I ..

.Af'i:f'R_QYED 1:3Y DATE I PLAN'f lOENTlFICATION SYSTEM NuMBER AR~ RECIPIENT #

E5100 PREPARED BY DATE CH~ DATE DOCUMENT TYPE CODE NUC OPS flLE NO. OAT~ ISSUED TO IS D ,A.KOCZKI 9/16/09 -,c 1 /(,, 0 .. OTHER APPROVAL.S DATE DDD11EC 1601 'f-1'?-D'I APPROVED BY -,.,, ff,<.} ~ ,$'"..--,..

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DATE J..,;. EDP POSTING ENTRIES REQtJlRE THE ADDITIONEITHER OF THE ARMSORSTATUS "ASB" CODE:

DRAWING NUMBER 61/f 7 21 5 8 5 9 REV.

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