ML20205S301

Rev 0 to Alternative Safe Shutdown Procedure ASSD-06, Reactor Bldg South

ML20205S301
Person / Time
Site:	Brunswick
Issue date:	04/04/1988
From:	Bishop E CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20205K904	List: ML20205K902 ML20205K907 ML20205K913 ML20205S261 ML20205S267 ML20205S272 ML20205S277 ML20205S283 ML20205S286 ML20205S293 ML20205S296 ML20205S301 ML20205S306 ML20205S310 ML20205S315 ML20205S332 ML20205S335 ML20205S339 ML20205S344 ML20205S350 ML20205S355 ML20205S362 ML20205S369 ML20205S390 ML20205S400 ML20205S405 ML20205S414 ML20205S419 ML20205S429 ML20205S438 ML20205S452 ML20205S471 ML20205S478 ML20205S492 ML20205S504 ML20205S508 ML20205S511 ML20205S516 ML20205S522 ML20205S532 ML20205S536 ML20205S541 ML20205S545 ML20205S557 ML20205S560 ML20205S565 ML20205S571 ML20205S577 ML20205S582 ML20205S586 ... further results
References
ASSD-06, ASSD-6, NUDOCS 8811110015
Download: ML20205S301 (23)

Text

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC F'LANT UNIT 1 PROCEDURE TYPE: ALTERNATIVE SAFE SHUTDOWN PROCEDURE NUMBER: AS$0-06 PROCEDURE TITLE: REACTOR BUILDING SOUTH Rev. O V 3 g t3,j 4/4/88 4 g. p-V

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O l APPROVED BY: )" m-/ ~ hf

• Gen e rilla na g e eftfa*na g eE0 e r aD o ns Date:

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BSEP-1/A550-06 Page 1 of 23 Rev. 0~

8841110o15 001025 PTA ADOCK 05000324 P PDR

LIST OF__ EFFECTIVE _PAGES ASSD-06

.P,a ge ( s ) Revision 1-23 o R. G.

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A. TITLE Reactor Building South B. REFERENCES

1. Per 10CFR50 Appendix 'R' sections ll!.G & L.

2. Per 10CFR50 Appendix 'R' section !!!.J.

C. ENTRY C0fsDIT!0,fi This procedure is entered from Alternative Safe Shutdown Index AS50-01.

1. A fire has occurred in an area containing Alternative Safe Shutdown Train B equipment, AND

2. The Shift Foreman has determined that the reactor is to be brought to Cold Shutdown using Alternative Safe Shutdown Train A. '

The purpose of this procedure is to provide supplemental actions to be used concurrently with E0P'S and other operations procedures to achieve R 8.1 and maintain Cold Shutdowci coincident with or without a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> loss of off-site power.

D. OPERATOR ACTIONS

1. IF while executing this procedure, the fire is extinguished AND  !

tEc the Shift Foreman determines that no action is required, l

THEN EXIT this procedure.

2. OBSERVE the following parameters on instruments indicated while performing actions to achieve and maintain cold shutdown.

l Instrumcnl Location l 1-CAC-TR-4426-1 Suppression Pool Temp. (Pt. l') Control Room Panel l 1-CAC-LR-2602 Torus Level Control Roon Panel .

l 1-C32-PI-R605A Reactor Pressure Control Room Panel i 1-C32-L1-R606A Reactor Water Level Control Room Panel

3. If diesel generator building _AND/OR_ reactor building ANDf04 service water building entry is required to restore Ofmoliitor equipment THEN

._ a . DISPATCtl the following minimum manpower for performance of this procedure.

Reactor Building - 1 Auxiliary Operator service Water Building - 1 Auxiliary Operator Diesel Generator Building - 1 Auxiliary Operator l

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9 a

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b. OBTAIN the following keys from the Shift Foreman's Key Locker

~(1) ASSO Equipment Cabinet Key #148 (1) AS50 Flashlight Tool Box Key #160 ,

~

c. OBTAIN Security Access Keys from SAS Security Officer located in the Control Roxn AND PROCURE the following equipment from the ASSD Fqliipment Cabinet:

For Reactor Building .;

(1 Flashlight (1 Sound powered phonc

_ ,, ( 1 Twenty-fiv/ foot sound powered phone extension cord (1) Copy of this procedure (6) Remote Shutdown Keys, serial T112

_(1) Security Access Key R Servico , Water Buildi,nq (1) Flashlight

1) Sound powered phone

'((1) Twenty-five foot sound pwered phone extension cord R B..f (1) Copy of this procedure (1) Security Access Key F o r_ _D i es el_G e ne r a t o_r_ _B u i_1_d _i ng (1) Flashlight (1) Sound powered phonc

_ (1) Twenty-five foot sound powered phone extension cord

~~

(1) Copy of this procedure

^(1) Security Access Key (14) Door Wedge Blocks

_d. USE appropriate figures in this procedure to provide access / egress routes, equipment and comunication locations.

4. IF Diesel generator operation is required THEN BLOCK OPEN bTesel Generator Building doors, as indicated on Attachment 1, to establish ventilation for Diesel Generator operations.

BSEP-1/AS50-06 Page 4 of 23 Rev. O

1 F

• • .........*** ... ** **********..*****. .................****i. *** ....... .

CAUTION Cooldown rates above 1000 F/hr (RPV cooldown rate LCO) may be required to accomplish this step.

I 5 ENSURE Safety Relief Valve (SRV) high/ low pressure interf ace is  ;

provided by performing the following:

~~~~~~

a. OPEN ADS Relay logic A and B Control Panel, H12-628, Circuit Breaker at 125/250V DC Distribution Panel 3B Ckt No.11.

b. PLACE ASSO ADS /RHR Logic Power Supply Isolation Switch on panel H12-P617 to ASSD-2 position.

6 ENSURE Main Steamline Isolation Valve (MSIV) high/ low pressure interf ace is provided by performing the following:

a. PLACE Inboard MS!V AC Power Isolation Switch /t 25.1 -

(keylock) on panel H12-P622 in ISOL position.

b. PLACE Outboard MSIV AC Power Isolation Switch i (keylock) on pane) H12-P623 in ISOL position.

c. OPEN the following 125V DC breakers:

(1) Inboard Isolation Valve Logic Control  !

Panel H12-P622 Circuit Breaker at 125V DC Distribution Panel 3A Ckt 12 (2) Outboard Isolation Valve logic Control Panel, H12-P623, Circuit 3rraker at 125V DC Otstribution Panel 33 Ckt 12, i l ,

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CAUTION _

Performance of the following defeats HPCI high area temperature logic.

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • +***************

7 ,IF,HPCI F operation is required, THEN

a. PLACE HPCI Logic A Switch, B21-56A on panel H12-P614 in TEST position.

b. PLACE HPCI Logic B Switch, B21-568 on panel H12-P614 in TEST position. ]

c. OPERATE HPCI per OP-19,

~

8. IF operation of HPCI Steam Supply Inboard Isolation Valvo, R 41-F002, is required AND 1-E41-F002 CANNOT be operated from the RTGB, M power is NOTTvailable frexTMCC~1XD, THEN_

a. IF MF 1XD is NOT accessible due to fire, THEN the Urcuit breaker cor. trol svitch in the OFF position for Reactor Building MCC 1XD at 4BOV Unit Substation E8 compartment A08 l

l b. IF MCC IkD IS ac essible. THEN PLACE the circuit breaker control switch in th'e OFF position for HPCI I Steam Supply Inboard Isolation Valve, 1-E41-F002, at M, S.J MCC 1XD compartment DW1.

c. PLACE the circuit breaker control switch in the ON position for HPCI Steam Supply Line Isolation VaTie, 1-E41 F002, (ASSD Feed) at MCC 1XC compartment 051.

d. IF 1-E41 F002 is required to be Open, THEN PLACE the

~

ESDKeylockCcitrolSwitchintheOPEY"5sition,at MCC 1XC compartment DSI.

e. IF 1-E41-F002 is required to be Closed, THEN PLACE We ASSD Keylock Control Switch in the Cl.'65ID position, at MCC 1XC compartment 051.

9 IF operation of HPCI Turbine Exhaust Vacuum Breaker Yalve, R41-F079. is required AND 1-E41-F079 CANNOT be operated from the RTGB $ power is N0f7 val 14ble f romWTXB,3

a. IF MCC 1XB is NOT accessible due to fire, THEN PLACE We circuit breaker control switch in the W position for Reactor Building MCC IXB at 4T07 Unit Substation E6 compartment AW0 BSEP-1/ASSD-06 Page 6 of 23 Rev. O

8 4

b. IF MCC IXB IS accessible, THEN PLACE the circuit '

Ereaker control switch in tff0FF position for HPCI ,

Turbine Exhaust Vacuum BreakerTive,1-E41-F079, at  !

MCC 1XB compartment DQO.  ;

~ ~ ~

c. PLACE the circuit breaker control switch in the ON position for HPCI Turbine Vacuum Breaker Valve, ~~ ,

1-E41-F079, (ASSD FEED) at MCC IXC compartment DT2. {

d. IF 1-E41-F079 is required to be Open, THEN PLACE the [

ESO Keylock Control Switch in the OPEN pos1 tion, at .

MCC 1XC conpartment DT2. l I

4 e. IF 1-E41-F079 it required to be Closed THEN PLACE He ASSD Xeylock Control Switch in the CF0W position, at i:CC IXC compartment OT2.  ;

IF operation of Suppression Pool Suction Valve,1 E41-F042 is

10. Wquired and 1-E41-F042 CANNOT be operated from the RTGB due to l;

HPCI logic interlocks, THEN

}

a. PLACE Valve E41-F042 Interlocks Bypass Switch, l E41-SS-5401 keylock swltch on panel H12-P601 in  !

BYPASS position, j

b. OBSERVE anber indicating lamp above keylock switch A S.i [

illuminated. j E

c. OPERATE l-E41-F042 as required f rom the RTGB.  !

11. PERFORM the following to ensure suppression pool level f indication is available. (

l

a. PLACE keylock Isolation Switch for Valve . l CAC-SV-1219C, Y9A-151, at Junction Box Node Y9A;  !

Reactor Building North Wall, El 20' in lSOLATE j

position.  ;

i

! b. Pt. ACE keylock Isolation Switch for Valve CAC-SV-4344, i Y9A-IS2, at Junction Box Node Y9A, Reactor Building  !

North Wall, El. 20' in ISOLATE position.  !

1 12. VERIFY a flow path DOES NOT exist from the nuclear to I conventional header throTgE Conventional Service Water Pumps lA I j

AND_IC Discharge Valves by performing the following

[

a. Pt. ACE the circuit breaker control switch in the 0FF position for Conventional Service Water Pump 1 A  !

Discharge Valve To Conventional Header,1-SW-V13, at j MCC 2PB compartment E45.

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BSEP-1/ASSD-06 Page 7 of 23 Rev 0

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b. PLACE the circuit breaker control switch in the OFF position for Conventional Service Water Punp 1A Discharge Valve To Nuclear Header,1-SW-V14, at '

MCC 2PB compartment E44

c. VERIFY Closed OR Manually CLOSE Conventional Service Water Pump 1A UTscharge Valve to EITHER the Nuclear Header, 1-SW-V14 O_R, Conventional Header, 1-SW-V13 l

d. PLACE the circuit breaker control switch in the OFF position for Conventional Service Water Pump IC ~ ~

Oischarge Valve To Conventional Header, 1-SW-V17, at MCC IPB compartment BXB.

~

e. PLACE the circuit breaker control switch in the OFF position for Conventional Service Water Pump 1C Discharge Valve To Nuclear Header,1-SW-V18, at MCC IPB compartment BX9.

f. VERIFY Closed OR Manually CLOSE Conventional Service Water Pump IC UIscharge Valve to EITHER the Nuclear Header, 1-SW-V18 M Conventional Header, 1-SW-V17

13. PERFORM the following to prevent spurious operation of safe shutdown service water valves fed f rom MCC IX9 RB

a. IF MCC IXB is NOT_ accessible due to fire, THEN PLACE tIIe circuit breaker control switch in the DC position for Reactor Building MCC IXB at 4EY Substation E6 compartment AW0 0,3,

b. IF MCC IXB 15 accessible. THEN (1) PLACE tne circuit breaker control switch in the OFF position for RHR Heat Exchanger B Service Header Outlet Valve.

l-E11-POV-F0688, at MCC 11B compartnent DN1.

(2) PLACE the circuit breaker control switch in  :

the OFF position for RRR Service Water Booster Pumps B and 0 Inboard Isolation Valve,1-SW V105, at MCC IXB compartment DMI.

(3) PLACE the circuit breaker control switch in the OFF position for Service Water to RHR Service Water Header Cross-tie Valve.  ;

1-SW-V102, at MCC IXB compartment DM6.

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I BSEP-1/ASSD-06 Page 8 of 23 Rev. O  ;

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~ (4) PLACE the circuit breaker control switch in the OFF position for Nuclear Service

, Water to Vital Heade- Inboard Isolation Valve, 1-SW-V117, 4 MCC IXB compartment OP2.

c. Manually CLOSE RHR Heat Exchanger B Service Header Outlet Valve 1-E11-PDV-F0688.

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FIGURE 1 Control Building 23'0' and 49'0" Elevations Access / Egress i and Sound Powered Phone Con,unications r e BSEP-1/A550-06 Page 17 of 23 Rev, 0

CIESEL GENERATOM BUILDING &

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1 Unit 1 Reactor Building 20'0" Elevation Access / Egress and Sound Powered Phone Comunications BSEP-1/A550 06 Page 19 of 23 Rev. O

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BSEP-1/A550-06 Page 20 of 23 Rev. O

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Page 21 of 23 Rev. O l BSEP-1/A550-06 l

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DIESEL CENERATOR VENTILATION

1. OPEN/ BLOCK ODEN doors identified on drawing below.

2 BLOCK OPEN doors using door wedge blocks.

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BSEP-1/A550-06 Page 23 of 23 Rev. O L ,