ML21286A370

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Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Figure 7.4, Emergency Core Cooling Control
ML21286A370
Person / Time
Site: Browns Ferry  
Issue date: 10/04/2021
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21286A574 List: ... further results
References
Download: ML21286A370 (31)
v • d • e


Text

{{#Wiki_filter:BFN-18 Figure 7.4-1a (Deleted by Amendment 18)

BFN-22 Figures 7.4-2a through 7.4-2h (Deleted by Amendment 22) \\.," ~ :. I

BFN-22 Figure 7.4-3 {Deleted by Amendment 22)

BFN-19 Figure 7-4-4 (Deleted by Amendment 17)

BFN-22 Figures 7.4-5b and 7.4-5c (Deleted by Amendment 22) ~.

BFN-22 Figures 7.4-5e through 7.4-5h (Deleted by Amendment 22)

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  • ~74-1378 4-1378 IL-74-1378 ROOM TEMPERATURE AND HUMIDITY FOR RHR PUMP ROOMS A AND B FROM FCV-74-100 I

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1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE DRAWING 2-47E2610-74-J.
2. CIRCUIT BREAKER IS NORMALLY OPEN EXCEPT FOR TESTING OR WHEN RHR IS BEING OPERATED IN THE SHUTDOWN COOLING MODE. INDICATING LIGHTS AND CONTROL SWITCHES ARE NORMALLY DEENERGIZED.

J. ALL COMPONENTS PREFIX IS *2-11 UNLESS OTHERWISE NOTED.

4. A. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED AS SHOWN BELOW IN THE EXAMPLE TO MEET SPACE CONSTRAINTS.

REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT 2 AND SYSTEM 74 UNLESS OTHERWISE NOTED. FOR ADDITIONAL GUIDANCE REFER TO NEDP-4. EXAMPLE: MEL UNID BFN-2-ZI-074-0048A BFN-2-FCV-074-0053 DRAWING UNID ZI-74-48A FCV-74-53 B. ALL VALVES IDENTIFIED AS *rev* HAVE VALVE OPERATORS. THE MEL UNID FOR THE VALVE OPERATOR IS DEVELOPED AS FOLLOWS: VALVE DRAWING UNID FCV-74-61 FROM RECIRC PUMP A SUCTION HEADER L----< 2-47E2S1D-74-1. D1 I VALVE OPERATOR MEL UNID 2-MVOP-074-0061 74-9j 74-9,,4 FROM SHUTDOWN SUPPLY ~--11---- ---------<< 2-47E2S10-74-1, E2 I 6 ~~--- FROM SYS VENTS 2-47E2610-74-1, AB("P"), 85("D").A4("F") LOG I LOG I 9-~ @ I I I -@- ~ J 7447A 01 7447A CLI HS HS I CISS I r;\\_ I XS ~ ..:. ~ 1 1 74-47A 74-47B 11 A 1 ~BAI 74-48 -~a*c ~ iD 2-47E2610-74-1. DJ CISS I CISS I I I

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7 5 ~-~+~ :~:.::1~i:~ttt1Jftf ~j!,l @-:~~ H ~'..L_,:~.~- ~ii'...., 4 3 AMENDMENT 27 POWERHOUSE UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT G D c B RESIDUAL HEAT REMOVAL SYSTEM A MECHAN I CAL CONTROL DI AGRAM FIGURE 7.4-6b SH 3

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BFN-22 Figures 7.4-7c through 7.4-7h (Deleted by Amendment 22)

BFN-22 Figures 7.4-7j through 7.4-7n (Deleted by Amendment 22) -~~ ~ ' z ~

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BFN-16 Figure 7-4-8 Deleted by Amendment 9.

BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22)

BFN-22 Figure 7.4-9 (Deleted by Amendment 22)

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