ML23129A464

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1 to Updated Safety Analysis Report, Drawing 730E149BB, Sheet 1, Functional Control Diagram Nuclear Boiler
ML23129A464
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/20/2023
From:
Nebraska Public Power District (NPPD)
To:
Office of Nuclear Reactor Regulation
Shared Package
ML23129A261 List: ... further results
References
NLS2023022
Download: ML23129A464 (1)
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Text

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I SEAL*IN INITIATION SIG.

WffE"I AUX, RELAY IS ENERGIZED RELA TRIP LOGIC 11W" CONTACT AUX. RELAY "flt.A\\NG DEVICE.

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TRIP LOGIC "A" LOW REACTO WATER LEVEL

  • 2A LP NOTE 3 TRIP LOGIC "c" REF. 1.........____

LOW REACTOR

---.., WATER LEVEL LP TRIP ILOG!C "A" TRIP LOGicc"'

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120 SECONDS AFTER INITIA110N 01' TIM<.R

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TRIP LOGIC"B" TR.IP!.Ot,IC:. "f,"

IDENTICAL. 'TO Tll;IP 1.0GI'- "A" E1ttE?I' FMT

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TIMER TIMER

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TRIP LOGIC "o" "m1P LOf,,t,C. *o*

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SIJFFIKE~ NC' AI..A'tM FIJNC.TION DEVIC.E CR 10 SEE TABLE I -~

TABLE I ALMIM NICT f ~

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-ll,ICI I.TOil 730E149BB TITLE FUNC CONT DIAG CONT ON SHEET 2 SH NO. 1 NUCLEAR BOILER FIRST MADE FUR COOPER NOTES:

1.

REMOVED

2.

RELIEF VALVE MAY BE MANUALLY OPENED AT ANY TIME BY CONTROL SWITCH OR AUTOMATICALLY BY REACTOR HIGH PRESS VALVES CLOSE WHEN SWITCH IS IN AUTO POSITION EXCEPT WHEN AUTOMATIC BLOW DOWN OR REACTOR HIGH PRESSURE SIGNALS ARE PRESENT.

3.

AUTOMATIC SLOWDOWN TRIP LOGIC CIRCUITS A&C SHALL BE POWERED FROM STATION BATTERIES "A" TRIP LOGIC.

CIRCUITS B&D SHALL BE POWERED FROM STATION BATTERIES "B" WITH AUTOMATIC TRANSFER TO BATTERY "A" ON LOSS OF POWER.

4.

AUXILIARY RELAYS AND DEVICES ARE NOT SHOWN ON FCD EXCEPT WHERE REQUIRED TO CLARIFY FUNCTION.

5.

ISOLATION VALVE CLOSURE SIGNALS SHALL BE SEALED IN UNTIL MANUALLY RESET FROM THE CONTROL ROOM PANEL.

6.

REMOVED

7.

WHEN TEST SOLENOID PILOT IS ENERGIZED, THE MAIN STEAM ISOLATION VALVE OPERATOR IS SLOWLY EXHAUSTED (60 SEC CLOSURE TIME)

WHILE VALVE IS CLOSED BY ACTION OF THE VALVE SPRING WITHOUT AID OF THE AIR PRESSURE.

8.

THE ALARMS AND VALVE INDICATING LIGHTS SHOWN ON THE FCD ARE SYSTEM REQUIREMENTS IN ADDITION TO THOSE SHOWN ON THE SYSTEM P&ID"S a:,

ADDITIONAL INFORMATION ON ALARMS, VALVE POSITION INDICATING LIGHTS, AND PROCESS INSTRUMENTATION NOT SHOWN ON THIS FCD MAY BE OBTAINED FROM REF 1, 2, 3, 4, 5, 6, 13 AND 14.

9.

MAIN STEAM LINE ISOLATION VALVE TRIP LOGIC CIRCUITS A, B, C, & D SHALL BE POWERED FROM REACTOR PROTECTION SYS M-G SETS.

TRIP ACTUATOR CIRCUIT I SHALL BE POWERED FROM ANY RELIABLE AC SOURCE.

TRIP ACTUATOR CIRCUIT II SHALL BE POWERED FROM STATION BATTERIES.

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10.

TIMING DEVICES SHALL BE OF THE lYPE THAT AUTO. MECHANICALLY RESET TO ZERO, UPON LOSS OF POWER TO THE TIMING DEVICE OR UPON LOSS OF THE INITIATION SIGNAL, OR UPON PUSHING THE PB TO RESET.

11.

FOR LOCATION AND IDENTIFICATION OF INSTRUMENTS SEE INSTRUMENT DATA SHEET LISTED IN MPL FOR EACH INSTRUMENT.

12. THE NUCLEAR BOILER SYSTEM SHALL BE DESIGNED IN ACCORDANCE WITH "PROPOSED CRITERIA FOR NUCLEAR POWER PLANT PROTECTION SYSTEM IEEE 279" IN SO FAR AS PRACTICABLE.

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~OT REQUIRED OIJ RV Z:*71, 0 lj, F" r.==:::> EXHAUST CR

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LIEF VALVE OPENS WHEN A PILOT IS ENERGIZED OR B STEAMLINE PRESS IS HIGH T..:1P AC.TUAiOR I L_..

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T'l'PIC.1\\1.. FOR V. AV/ 2-71B,C,E,G & H TYPl(./\\L FOR RV 2-71D & F EXCEPT A.'::. NOTED J.__ ________ AUTOMATIC BI..OWDOWW SYGTEM-----------'1 2

3 REQUIRES COINCIDENT TRIP OF SWITCH 2-3-101A & 101C OR 1018 & 101D LOW REACTOR WATER LEVEL TRI7 7

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WATER LEVEL WATER LEVEL I

LIS LIS I

I 2-3-101A LP 2-3-101E LP I

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LOW REACTOR LOW REACTOR I

WATER LEVEL WATER LEVEL I

LIS LIS I

I 2-3-101<

LP 2-3-101r LP I

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______ j REQUIRES COINCIDENT TRIP OF SWITCH 5-12A OR 5-12C AND 5-128 OR 5-12D TO PRODUCE HIGH DRYWELL PRESS TR:z I

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HIGH DRYWELL HIGH DRYWELL I

PRESSURE PRESSURE I

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HIGH DRYWELL HIGH DRYWELL I

PRESSURE PRESSURE I

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REQUIRES COINCIDENT TRIP OF SWITCHES 57A OR 578 AND 58A OR 588 TO PRODUCE LOW REACTOR WATER LEVEL TRl:.z I

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LOW REACTOR LOW REACTOR I

WATER LEVEL WATER LEVEL I

LIS LIS I

I 2-3-57A LP 2-3-578 LP I

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LOW REACTOR LOW REACTOR I

WATER LEVEL WATER LEVEL I

LIS LIS I

I 2-3-58A LP 2-3-58B LP I

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SEE REF DWG 5 & 11 LOW REACTOR FOR ADDITIONAL FUNCTIONS LOW REACT WATER LEV OR~

EL

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PERFORMED BY THIS WATER LEVEL SET OF SWITCHES

    • HIGH DRYWELL PRESS (SCRAM PRESSURE)

Al..lV.S'l.!o I. M<~YS 'It lll~R, l"UIIAP IS Q,1Jt,,1i...,1t.JG:

13.

FOR TRIP SETTINGS SEE REF 18.

14. THE DEVICES IN THIS LOGIC ARE ESSENTIAL AND MUST MEET THE REQUIREMENTS OF IEEE 279.

REF DOCUMENTS

1.

P&ID NUCLEAR BOILER VESSEL INSTRUMENTATION ________ 2 -

3

2.

P&ID NUCLEAR BOILER _______________________ 2

3.

P&ID RHR SYSTEM-------------------------- 10

4.

FCD HPCJ SYSTEM-------------------------- 23

5.

!ED REACTOR PROTECTION SYSTEM*---------------* 5

6.

JED PROCESS RADIATION MONITOR----------------* 17

7.

FUNCTIONAL CONTROL DIAGRAM RHR SYSTEM ___________ 10 -

202

8.

FCD REACTOR WATER CLEAN-UP SYSTEM ------------ 202

9.

FCD RADWASTE SYSTEM _______________________ 20 -

703

10.

DESIGN SPEC FOR CONTAINMENT ISOLATION SYSTEM ______ 1 -

157

11.

FCD RECIRC FLOW CONlROL SYSTEM -------------- 184 -

5

12.

FCD NEUTRON MONITOR SYSTEM----------------- 2

13.

P&ID RADWASTE SYSTEM ______________________ 20

14.

P&ID REACTOR WATER CLEANUP SYSTEM------------- 12

15.

SCHEMATIC CONTROL DIAGRAM ___________________ 175A9560

16.

LOGIC SYMBOLS--------------------------- 209A4756

17.

P&ID CORE SPRAY SYSTEM ---------------------14

18.

TURB GEN STEAM BYPASS SYS ___________________ 1 -

139

/

PROCESS RADIATION MONITOR SYSTEM TRIP (HIGH RADIATION REACTOR BLDG VENT EXHAUST PLENUM)

LOW REACTOR WATER OR HIGH DRYWELL PRESSURE REF 6 SCRAM REACTOR SEE REF 5 LOW REACTOR WATER OR HIGH DRYWELL PRESS r1 SEAL-IN 11 SEAL-IN ~ -

I

  • OR HIGH RAD REAC BLDG VENT DUCT (NOTE 5)

(NOTE 5)

CLOSE DRYWELL EQUIP ~

I SEAL-IN~

DRAIN VALVES REF 13 (NOTE 5)

CLOSE DRYWELL FLOOR CLOSE DRYWELL ATMOSPHERIC CONT !SOL VALVES F 9 DRAIN VALVES REF 13 INCLUDING 02 ANALY2ER VALVES REF BY A.E.

LEGEND

  • -SWITCH GEAR DEVICE FUNCTION NO'S USAS SPEC C-37.2

-*- - FURNISHED AS PART OF VALVE OR DEVICE ASSEMBLY.

WITHDRAW TIP SYSTEM PROBES REF 12 CLOSE REACTOR BLDG (SECONDARY CONTAINMENT)

CLOSE RHR/SHUTDOWN COOLING ~

VENTILATION DUCT ISOLATION VALVES REF BY A.E.

ACTIVATE STANDBY GAS TREATMENT REF 6 BY A.E.

RIT3 1 RIT7 CLOSE REACTOR WATER CLEAN-UP SYS !SOL VALVES REF 14 ~

ACTIVATE CREFS REF 8 INITIATE ISOLATION VALVE CLOSURE (EXCEPT MAIN STEAM LINE)

INFORMATION ONLY

6.

to FOR PREVIOUS REVISIONS, SEE SUPERSEDED CARDS. 45 2 0 0 5 0 40 REVISIONS BY N.P.P.D.

NO.

REVISIONS DFT CKD APP DATE NOS CED 6014280 DCN 04-1263 RAC RHG KG 8-18-05 i!"

12 13 SCAN CADD DWG DO NOT REVISE MANUALLY CADD FJLE: C0054654 730E149BB CONT ON SHEET 2 SH NO. 1 CI.

REV N05:__

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