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3 to Updated Final Safety Analysis Report, Drawing 6M721-5860, Process Diagram High Pressure Coolant Injection System
	ML21055A383
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: ML21055A383 (1)
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7 MISCELLANEOUS INFORMATION,

1. DESIGN PRESSURES AND TEMPERATURES GIVEN BELO',/ ARE FDR INF RMATI N NL Y, AND ARE THE BASIS FDR DESIGN OF APED SUPPLIED EQUIPMENT.

LOC.6TION 6

5 4

---"--"'i 3

2 1

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NOTES,

,-t. l!-tl 14-4Al4A-511-z. ls-'!) ~o-11 p2-11A112A-6p3-13AIJ3A-11 1+ I 15 IHi>-tln-i,kt-?O

,-PSIG l'Z5 4"° ~,o (I) l'l5 1250 185 13,0 l'Z5 1330 12.5 50 15 l'l5 IZ5 1'25

~~~RATIIR~"F 100 140 1'10 l?.l 110 575 ?."'- 110 111. 110 100 l'i\\8 ZOO '1.00 110 110

-TtiE -ss..-it l,T T~IS l.OCl,T!ON Dl!PalOS IJPOH PIPINc. ~~~.

ANO MAY fl( VAAIEI> WIT!HII Tl!ls PQl.t.OWIM; Ll/,lll"S.

I.

ATMOSPHERIC PRESSURE OF 14,7 PSIA wAS USED IN CALCULATIDNS, CD DESIGN PRESSURE SHALL BE EITHER 1330 PSIG DR DEPENDENT ON FEEDl,IATER SYSTEM SHUT-OFF HEAD IF THIS CONDITION EXCEEDS 1330 PSIG.

(2)

FDR DESIGN TEMPERATURE REFER TO NUCLEAR BDILER SYSTEM PROCESS DIAGRAM, MPL #B21-1020, I

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CONDENSATE

!:>TORAGE TAN~

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!.UPPRE55ION POOl..

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CORE SPRQy TE~T ~E Mltf FLOW LIii&[

<ip 19

4 I RO I 1

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FEEOWATE.R TVR81N( b RO

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&IIJJI~ NPSH AT 1'14\\fP.svcr10N # ;21 FEe'r MN:1-P1'!SS~l< RISI " 2915 f£ET O HIGH ""'1:SS. "1llP£ 525 FEIT

LOIi PRE!>S MOPE!;

owe,_ PIIESSIIRE Dl'()I' ll(l'Mal!N LOC:.. nOHS @ANO@* 15 PSI.

M>" ~RE

65 PSIA SI/FPIClfNT PRESStJRf TO PfTl.t<N TO 51.)Pf'ROSION f'OOc.

SUFflC1£NT J>ffSSOl!f TO IIETURN TO COND. 5TOMGE HMI-_PRiSSIJIIE AV,.llAlllE - 65 1'51A SI/Ff'ICIENT PllES:IURE TO R(TURN Tll l'U<PSUCTION ~1116 0f'ERA1'10N

REFERENCES, I.

NUCLEAR BDILER. PD -----B21-1020

2.

DELETED

2.

\\,/ATER FLOl,IS ARE SHOl,IN IN GPM, STEAM FL ws IN 1000 LB/HR..

3, THE MAXIMUM POOL \\,/ATER TEMPERATURE FDR CONTINUOUS SYSTEM OPERA TIN ',/ILL NOT EXCEED 140'F, HOwEVER, DUE TD POTENTIAL SHORT TERM OPERATION AT HIGHER TEMPERATURES, PIPING EXPANSI N SHALL BE BASED ON 170T, 4,

THE F LLwING ADDITIONAL ACCIDENT OPERATING MODES ARE POSSIBLE*

SUCTION FROM CONDENSATE STORAGE, SUPPRESSION POOL AT LOI,/ PRESSURE, REACTOR AT HIGH OR LOI,/ PRESSURE, SUCTION FROM SUPPRESS! N POOL, SUPPRESSI N POOL AT HIGH PRESSURE. REACTOR AT HIGH DR LOI,/ PRESSURE.

THESE POTENTIAL OPERATING MODES DD NOT CONTROL PIPE DR VALVE SIZING DR SPECIFICATION, AND ND DATA IS SHO'wN.

5.

THE CONTROLLING MODES FOR LINE SIZING AND ARRANGEMENT ARE*

SUCTIDN FROM C ND, STORAGE ------MODE A & B SUCTION FROM SUPPRESSION POOL ---MODE C & D PUMP DISCHARGE -----------------MODE C & D STEAM SUPPLY -------------------MODE A & B TURBINE EXHAUST ----------------MODE A, C & D TEST LINE ----------------------MODE E CODLING SYSTEM -----------------MODE A

6.

THE PRESSURE AT LOCATION@ IS ESTIMATED FROM PRELIMINARY PUMP DATA,

7.

PUMP MINIMUM FLO\\,/ REQUIREMENT MAY OCCUR DURING ANY OPERATING MODE. FLO\\,/ REQUIREMENT IS 500 GPM MINIMUM, DURING MODE A.

MOOE, A IICCOENT MO()(, 5uCTICllt FROM {QIUNSl,f~ 5TOl!lluE, REKTOII AT Hlr.H PRESSURE. !:>UPPRES~ IOOOL AT HIC.H PRE~

LOC,TION 0 I

2 J,

4

I "

1 8

9 10 II

12.

I!>

14 IS '"

17 Ill 19 20 21 FLOW -SEE NOTE t -

5000 5070 5000 5000 -

0 -

210 209.5 209.5 -

0 0.5 0.05 20+

70 70 20 50 -

OPERATING

-t==

PRE':>$URE - p S 1" 14.7 11 280

1140 -

1135 -

51.9 * -

14,5 14,9

,rt 75 -

45 50 --

&"-P CTEO OF 100 100 100 100 100 - -

565 SAT SAT 283 100 --

240 200 200 100 130 130 130 140 TEI\\APERATURE MA'Ajl\\lllN rn,9;; 10]-; 1~ !OJ:;: rn,?;,-

5~0 5% 2~ 2':-9; TEMPERATURE o~

40 40 40 40 40 -

70 70 10,9;;-

40 -

2~

4[ 12,9,,;

40 l2J,,;

40 103,;;

40 1~

40 13,:k 40 13~

40 17,:k 40 MOOE II

~IOENT MOOE, !.UCTIQN ~DA C()t()(N5ATE SlOIIK.E. REAC'ltllt AT l.Off PRESSURE. SUPPRE'.>51011 POOL Al H01 PRESS.

, /

U,0,.TION o*

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J, 4

!l "

1 8

9 10 II ll I!>,..,s IC.

17 111 13 20 21 FLOW -5l llOTf. t -

5000 5070 5000 5000 -

0 -

116.5 116.0 116.0 -

0 0.5 0.05 20 + 70 70 20 50

--P.SIA 14.7..

85 Ill 170 -

165 *..

51.8 * -

14,5 14.9

75 ** 45

50 c-100 100 100 100 100 - -

366 SAT SAT 283 100 -

240 200 200 100 130 130 130 140 TEMPf:RATU

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10_9{. 10_9;;'

10,9.:.

10,9;:, 10,9;:,

3~ 3~ 25,.%-0 2~0 !O_?a; 2~ 12.9,;; 12% 10;!_;, 13;!_;, 13,J; 133,;; 17J:;:

TE-.iPE ATIIRE °F 40 40 40 40 40 - -

7' 40 40

40 40 40 40 40 40 40

S.

MOOE D KCIOENT MOOE. 5UC.TION rlOM 5UPPl!ESSION flOOL. REACTOII AT UlW PR£~. ~N POOL AT lDW 1'!1£55.

LOCATIOI\\I 0 I

J, 4

I "

l II g

10 I I IZ.

13 14 15 1(,,

17 18 19 20 21 FLOW-SEE NOTIE t -

5000 5070 5000 5000 -

5000 -

75.0 74.5 74.5 -

0 0.5 0.05 20' 70 70 20 50 -

I 85 170 19.2 18.0 165 *..

PRES~E -PSI"- -

16.6 * -

14.5 14.9

75

45

14,7 E'kPECTE.0 RE°F -

140 140 140 140 140 140 366 SAT SAT 219 140 240 200 200 140 170 170 170 140 re.MP Mil.,_

I TEMPERATURE °F 10,9;;

40

17J, 40 17_9:,

40 17]-;

40 l 7},

40 17;,l; 40 17]-;

40 36.%:

70 36j;-

70 2~

70 25~ 171 2~ 19_3; 19,%-

17% 17,9;-;: 17J:;: 17_3,;,

17J.,:

40 -

70 40 40 40 40 40 40 40 40 MOOC E lE'!>T MOO£: SVC:TIOI\\I FIU!II COIIOENS,,_l£. STOII.Ni( 11l£H.l'O<< Al Hl61t Pfl£S$,.SUPPll£.SSIOII POOi... Al LOW PRES$.

LOCATION. 0 I

2..

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4 5 "

FLOW - 5£ NOT£ l -

5000 5070 5000 0 -

~-PSI"-

14.7..

255 * - -

E'kl'£C:TEI:>

°F 100 100 100 100 - -

'TE1,AP£RA'TU M.1..,._11.inw 10~ 10_9,;-

10% 10_9;'.

'TEM~TIIRI,. °F 40 40 40 40 -

IIAOOE S 5TANO*B't 1...0CATIOI\\I 0 I

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FLOW-5eE NOTE2 0

0 0

0 "' "'

0 wz PRE':> ::.URE* ~A STATIC STATIC HEAD HEAD

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"- u TEMPERATURe -°'F AMB AMB AMB AMB AMB

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14 15 '"

0 -

155 154.5 154.5 -

5000 0,5 0.05 20 1045 *..

16.7 *..,

14.5 14,9 11:

545 SAT SAT 219 100 100 240 200 200 54);- 5~ 2~ 2~ !DJ;'. 10,9:, 2~ 1~ 12.9,;:

70 70 70 70 40 40 40 40 40 EQUIPMENT NOT OPERA.TING 1

6

'!I 10 0 -

0 1000 1000 AMB 56J; 70 56x 70 AMB INTERMITTENT FLO\\,/ THRU DRAIN TRAP SYSTEM II 12 I!>

I~

15 I" 0

0 0

0 AMB AME AME AMB AMB AMB TIIIS DRA'WING lfJ,S REFORMATI'ED BY MICROSTATION AT REVISION ny. ALL PREVIOUS APPROVAL SIGNATURES ARE ON FILE ON MICROFILM IN DOCUMENT CONTROL.

F loco*s INCORPORATED:

TSR-35395 REV.¢ A PORTION OF THIS DRAWING 1S AFJ'KCTED BY THE FOLLOWING:

TC CHANGE DOCUMENT 17 Ill 19 70 70 20 75

45 100 130 130 10.9,;:

40 13J.,:

40 13_9{,

40 17 18 I '!I 0

0 0

AME AMB AMB PREPARED. BY 20 21 50 -

]4,7 130 140 13_9,;:

40 17_9,;:

40 20 21 0

AMB AMB INC.CODE u

DATE TITLE 6M721-5860 LATEST REVISION F

NUCLEAR SAFETY 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 PROCESS DIAGRAM HIGH PRESSURE COOLANT INJECTION SYSTEM G

F E

D C

B CHE~Ig!:p BY DATE OTHER REVISIONS:

I APERTURE CARD TITLE I A PREPARED BY D.STEFFKE APPROVED BY

~?.V,.._,,,

DATE CHECKED~~

-I A;;.;~

2-26-0fil.,P',<, -*

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.sy4 _ _ f!eH,r r,:::r--

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3

-¢08 EDP POSTING ENTRIES REQUIRE THE ADDITION OP THE ARMS STATUS CODE:

EITHER "AFC" OR "A2'o APPROVED BY PLANT IDENTIFICATION SYSTEM NUMBER E4100 ARMS RECIPIENT#

HPCI SYSTEM UFSAR FIG.. 6.3-1 OTHER

OVALS DATl!l DOCUMENT TYPE CODEDDDMEC NUC OPS FILE NO.I DATE ISSUED TO lS

'"°'

3-5-o-t DRAWING NUMBER 6M721-5860 REV. F 2

1

ML21055A383

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