ML21055A393

3 to Updated Final Safety Analysis Report, Drawing 6M721-5859, Reactor Core Isolation Cooling System

ML21055A393
Person / Time
Site:	Fermi, 07200071
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: ML21055A061 ML21055A062 ML21055A063 ML21055A064 ML21055A066 ML21055A067 ML21055A068 ML21055A069 ML21055A070 ML21055A072 ML21055A073 ML21055A074 ML21055A075 ML21055A076 ML21055A078 ML21055A079 ML21055A080 ML21055A081 ML21055A083 ML21055A100 ML21055A101 ML21055A102 ML21055A103 ML21055A104 ML21055A105 ML21055A106 ML21055A107 ML21055A108 ML21055A109 ML21055A110 ML21055A111 ML21055A112 ML21055A113 ML21055A114 ML21055A115 ML21055A116 ML21055A117 ML21055A118 ML21055A119 ML21055A120 ML21055A121 ML21055A122 ML21055A123 ML21055A124 ML21055A125 ML21055A126 ML21055A127 ML21055A128 ML21055A129 ML21055A130 ... further results
References
NRC-21-0002
Download: ML21055A393 (1)

Text

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TO HPCI VACUUM C<N:fttSATE STCIR"(J[

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LOCATION 0 I - Z 3-31 311-4 7-l. 8-9 10*11 3-12 ll.-13 13-14 OESIGN PIIESS 18 128() (I) 12 5 1250 150 1?80 1?5 125 IN

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DESIGN TEM"'

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190 170 1')11-G 20 125 1280 tit 100 OIL COOi.CR t,.P " ~ P'!II 5

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2 RF"F::::?ENrE _IDCUMi::NT MPL ITEf1 NO.

1.

liUCLEAR BOILER SYSTEM PROC. DIAG -

821-1020

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

LOCATION

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MINIMUM NPSH AT PUMP SUCTI N = 20 FEET.

M,AXIMUM PRESSURE RISE ACROSS PUMP 2915 FEET FOR MODES A & C 525 FEET FOR MODES 3 & D.

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MAXl~UM PRESSURE DRCP BETI./EEN LOCATION I@

(ij)

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© AND 0 = 15 PSI.

MAXIMUM PRESSURE ALLOIJED = 25 PS!A, MAXIMUM PRESSURE ALLOI./ED = 75 PSIA.

SUFFICIENT VACUUM TO PREVENT TURBINE SHAFT-OUT *LEAKAGE.

MAXIMUM PRESSURE AVAILABLE = 25 PSJA, MAXIMUM PRESSURE AVAILABLE = 50 PSJA.

SUFFICIENT PR[SSURE TO RETURN TO SUPPRESSION POOL.

SUFFICIENT PRESSURE TO RETURN TO COND. STORAGE.

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.

11.

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

THE INTERNAL CROSS SECTIONAL AREA OF THE VACUUM BREAKER PIPING 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,

NOTES, ATMOSPHERIC PRESSURE OF 14.7 PSIA WAS USED IN CALCULATIONS.

2.

IJATER FLO'dS ARE SHOI./N IN GPM STEAM FLOIJS IN 1000 LB/HR

3.

THE MAX!HUM POOL \\./ATER TEMPERATURE FOR CONTrnuous SYSTEM OPERATION

\\./ILL NOT EXCEED 140'F. HOIJEVER, DUE TO POTENTIAL SHORT TERM OPERATION AT HIGHER TEMPERATURES, PIPING EXPANS!DN SHALL BE BASED ON !70"F.

4, THE UNRECDVERED FLO'd NOZZLE PRESSURE DROP OF 4.5 PSI IS A FIXED LOSS BETI./EEN LOCATIONS@) AND©*

5, THE LUBE OIL CDOLX' PRESSURE DROP OF 3.0 PSI IS A FIXED LOSS BETI./EEN LOCATIONS @ AND Q_'.1.1.

6.

THE CONTROLLING MODES FOR LINE SIZING AND ARRANGEMENT ARE, SUCTION FROM COND STORAGE* -

MODE A & B SUCTI N FROM SUPPRESS!DN POOL- -

MODE C & D PUMP DISCHARGE

• MODE C & D STEAM SUPPLY * -

- MODE A & B TURBiNE EXHAUST * * -

• MODE A, C & D TEST LINE * * -

- MODE F COOLING SYSTEM

• - MODE A

7.

THERE ARE OTHER POTENTIAL OPERATING MODES VHICH DD NOT CONTROL PIPE OR VALVE SIZING OR SYSTEM OPERATION AND NO DATA IS SHOI./N; AMONG THESE MODES JS OPERATION 1./ITH INTERMEDIATE PRESSURES IN THE REACTOR VESSEL AND SUPPRESSION PCOL.

8.

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

9.

DELETED CONT.

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lAAP !i1':i T EM TSR 35664. i'IEV. A.

THIS DRAWING WAS REFORMA'rfED BY M!CROSTATJON AT REVISION "E". ALL PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM IN DOCUMENT CONTROL A PORTION OF THIS DR.\\WING IS AFFEC'tED BY THE FOLLOWING:

PREPARED BY INC CODE u

DATE TITLE 6:tv1721-- 5859 LATEST REVISION E

NUCLEAR SAFE'fY RELATED

~------------ *--------

THIS IS A MICROSTATION PRODUCED DRAWING.

CHANGES OR REVISIONS MUST BE BROUGHT TO THE ATTENTION OF THE PLANT ENGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION CONTROL IS MAINTAINED.

Detroit Edison Fermi 2 REACTOR CORE ISOLATION COOLING SYSTEM H

G F

E ID C

B TC C:-IANGE DOCUMEt<"l' CHECKED BY DATE I

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.Af'i:f'R_QYED 1:3Y AR~ RECIPIENT #

DATE I PLAN'f lOENTlFICATION SYSTEM NuMBER E5100 PREPARED BY DATE CH~

DATE DOCUMENT TYPE CODE NUC OPS flLE NO.

OAT~ ISSUED TO IS D,A.KOCZKI 9/16/09

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.. OTHER APPROVAL.S DATE DDD11EC 1601

'f-1'?-D'I APPROVED BY

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~ill DATE EDP POSTING ENTRIES REQtJlRE THE DRAWING NUMBER REV.

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ADDITION OF THE ARMS STATUS CODE:

61/f 7 21 5 8 5 9 eJµ.,,_,,'°'7,'f'1'~-'5, 9//

EITHER "AFC" OR "ASB"

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