ML20196J568
| ML20196J568 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/17/1997 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20196J565 | List: |
| References | |
| 2ASSD-05, 2ASSD-5, NUDOCS 9708050002 | |
| Download: ML20196J568 (83) | |
Text
_ _ ___ _ __ _______ _____-_- _ _
C (Nb CAROLINA POWER & LIGHT COMPANY BRUNSWICK NUCLEAR PLANT continuous Use PLANT OPERATING MANUAL VOLUME XXIll ALTERNATIVE SAFE SHUTDOWN PROCEDURE UNIT RCCEIVED BY BNP
]
i JUL 181997 NUCLEAR DOCUMENT CONTR'A 2ASSD-05 REACTOR BUILDING NORTH REVISION 21 8 N P REClPlENTID EFFE TlVE DATE COMEROTTRr) Yi I4] ,
Sponsor 6 -
7-I7-97 Date Approval M -/b }
anag[ Operations Date D[ kDO 05 0 324 F PDR 2ASSD-05 Rev.21 Page 1 of 83
TABLE OF CONTENTS Section .P_ age A. TITLE , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 B. ENTRY CONDITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . 3 C. OPERATOR ACTIONS . . . . . . . . . . . . . . . . . . . . . . . . . 3 Section "A" . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Unit 2 SCO Actions Section "B" . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Unit 1 BOP Reactor Operator A tions 1
Section "C " . . . . . . . . . . . . . . .. . . . . . . . . . . . . 24 j Unit 2 RSDP/PMI Reactor Operator (Remote Shutdown i Panel Operator) Actions j Section "D " . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 Unit 2 Rx Bldg MCC Operator Actions l Section "E" . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 Service Water Building Operator Actions 1
l Section "F" . . . . . . . . . . . . . . . . . . . . . . . . . . . . 68 )
l Emergency Switchgear Operator DG Bldg Actions Section "G" . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 i
Diesel Generator Operator Actions i
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- . BSEP-2/ASSD-05 Page 2 of 83 Rev. 21 4
5.
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i A. T[TLE :
)
Reactor Building North B. ENTRY CONDITIONS i I
- 1. This procedure is entered from Unit 2 Alternative Safe Shutdown <
Index ASSD-01.
1
- 2. . Unit SCO has determined that the Reactor is to be brought to ,
, cold shutdown from outside the Control Room using Alternative l Safe Shutdown Train B. )
C. OPERATOR ACTIONS .
i g NOTE I
i The following minimum manpower is required to
(_ perform this procedure.
i j 1 Unit SCO 1 Unit 2 RSDP/PMI Reactor Operator 1 Unit 1 BOP Reactor Operator 1 Unit 2 Rx Bldg MCC Operator 1 Diesel Generator Operator ,
j 1 Emergency Switchgear Operator DG Bldg '
j 1 Service Water Building Operator i
- 1. CONTINUE implementation of this procedure by performing the steps in Section "A."
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SECTION "A" I UNIT 2 SCO ACTIONS l ****************************************************************************** l l CAUTION l Interlocks that would normally prevent inadvertent draining of the reactor l coolant to the suppression pool, due to improper valve positioning, are 1 l
bypassed when operating the valves manually or with the ASSD switches selected .
for local operation. Caution must be exercised when performing RHR valve operations in this procedure to ensure that each valve operation is fully ,
completed prior to performing the next sequential operation. j (This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel !
, to suppression pool at BWRs", and may not be removed without concurrence of '
l Regulatory Affairs.)
l ******************************************************************************
I !
l 1. OBTAIN the ASSD equipment cabinet key from the Unit SCO key '
locker.
l
- 2. OBTAIN seven (7) security access keys from the CAS locker. l
- 3. PROVIDE the Unit 1 BOP Reactor Operator with the following.
- a. Security access key
- b. Section "B" of this procedure
- 4. DIRECT the Unit 1 BOP Operator to PERFORM Section "B" of this procedure.
- 5. DIRECT Unit 1 RSDP PMI Monitor to ESTABLISH communication with Unit 2 Remote Shutdown Panel using phone jack labeled " REMOTE l
SHUTDOWN TRAIN 'B' (UNIT #1) SOUND POWERED PHONE CKT." located l
on Unit 1 RTGB.
6 NOTIFY all personnel that in the event the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the plant Gai-tronics system to establish communications. j l
- 7. DIRECT the following personnel to OBTAIN their security access !
key and equipment from the ASSD equipment cabinet for implementation of Unit 2 ASSD-05.
i a. Unit 2 RSDP/PMI Reactor Operator (Remote Shutdown l Panel Operator)
- b. Unit 2 Rx Bldg MCC Operator j c. Service Water Building Operator
- d. Emergency Switchgear Operator DG Bldg l
- e. Diesel Generator Operator BSEP-2/ASSD-05 Page 4 of 83 Rev. 21 l
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- 8. PROCEED to AND OPEN the ASSD equipment cabinet.
- 9. PLACE the security keys on the key holder in the ASSD equipment cabinet.
- 10. OBTAIN a security access key and equipment from ASSD equipment cabinet.
- 11. USE appropriate figures in the back of this section to provide access / egress routes, equipment, and communication locations AND PROCEED to Unit 2 Remote Shutdown Panel.
- 12. ESTABLISH communication with other remote shutdown stations using the "ASSD UNIT 2 TRAIN B SOUND POWERED PHONE CKT." on the RSDP.
- 13. If the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the plant Gai-tronics system to establish communications.
14 OBSERVE parameters on instruments listed below while performing actions to achieve and maintain cold shutdown.
Instrument Location 2-C32-PI-3332 Reactor Pressure Remote Shutdown Panel 2-B21-LI-R60*BX Reactor Water Level Remote Shutdown Panel 2-B21-LI-5977 Reactor Level Remote Shutdown Panel 2-CAC-TR-778 Drywell Temp (Pts. 1, 3, and 4) Remote Shutdown Panel 2-E51-FIC-3325 RCIC Flow Controller Remote Shutdown Panel 2-E11-FI-3338 RHR System B Flow Remote Shutdown Panel 2-CAC-TR-778 Suppression Pool Water Temp. Remote Shutdown Panel (Pt. 6 and 7) 2-CAC-LI-3342 Suppression Pool Level Remote Shutdowr Panel 2-CAC-PI-3341 Drywell Pressure Remote Shutdown Panel 2-CO-LIT-1160 CST Level CST 2-SW-TI-808 RHR HX B Service Water Reactor Bldg-El. 20' Outlet Temp Ind South 2B RHR HX Koom
- 15. IE any of the following conditions should occur THEN rapidly DEPRESSURIZE the reactor vessel using Attachment 1.
- a. IE reactor water level cannot be maintained above 10 inches.
- b. IE drywell temperature monitored on CAC-TR-778, Point 1, is higher than reactor temperature AND i r: tor water level cannot be maintained l above 20 inches.
- c. lE average drywell air temperature cannot be maintained below 300*F as determined by Calculation Sheet 1.
j BSEP-2/ASSD-05 Page 5 of 83 Rev. 21
NOTE The loss of drywell cooling can be confirmed by monitoring Points #1, #3 and #4 on recorder CAC-TR-778 located on the Remote Shutdown Panel. The time the event occurred can be determined from the chart paper speed.
- d. IF average drywell temperature cannot be calculated AND (1) A loss of drywell cooling has occurred AND (2) Reactor vessel cool down rate of 100*F/hr or greater has NOT started within one hour of the loss of drywell cooling.
- 16. WHEN:
- a. RCIC is operational AND ,
i
- b. N, Backup Switch and circuit alignment for l SRV operation is complete AND 1 1
- d. Reactor water level is being maintained greater than 20 inches, THEN
- e. DIRECT Unit 2 RSDP/PMI Reactor Operator to START l reactor depressurization and cooldown using SRVs and l RCIC.
E0_.TE l
The RSDP and Emergency Switchgear Operators will direct most activities in this procedure.
- 17. MONITOR communications AND VERIFY the following conditions and events take place: l
- a. Conditions do not approach rapid depressurization requirements.
- b. . Reactor water level is being maintained I above 20 inches by RCIC.
l
- c. WHEN RCIC and SRV pneumatics are available, reactor depressurization and cooldown have been initiated.
- d. INFORM the RSDP and MCC Operators WHEN 4 KV Buses E2 and E4 are energized from the diesel generators.
BSEP-2/ASSD-05 Page 6 of 83 Rev. 21
- e. Nuclear service water is made available,
- f. Suppression pool cooling is placed in service.
- g. 4 KV Bus E3 is deenergized AND Diesel Cenerator 3 is stopped, if running.
- h. Suppression pool cooling is stopped when reactor pressure has decreased to 120 psig.
- i. l'hutdown cooling is placed in service when reactor pressure has decreased to 120 psig.
- 18. CONTINUE shutdown cooling as required to achieve and maintain reactor pressure at 0 psig until an alternate method of determining reactor 'iater temperature is provided.
- 19. DIRECT the Unit 1 PJP Reactor Operator to manually CLOSE HPCI and RCIC Combined iuction From CST Isolation Valve, 2-CO-V127, i locally at Unit 2 CST. !
I
- 20. RETURN plant to general operating condition as directed by plant management.
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BSEP-2/ASSD-05 Page 7 of 83 Rev. 21
ATTACHMENT _1 A. TITLli UNIT 2 REACTOR. VESSEL RATID DEPRESSURIZATION B. ENTRY CONDITION
- 1. If any of ths followins conditions should occur THEN rapidly DEPRESSURIZF the recetor vessel,
- a. IE reactor water level cannot be maintained above 10 inches.
- b. IE drywell temperature monitored on CAC-TR-778, Point 1, is higher.than reactor temperature AND reactor water level cannot be maintained above 20 inches.
_ c. lE average drywell air temperature cannot be
! maintained below 300*F as determined by calculation Sheet 1.
NOTE l
l The loss of drywell cooling can be confirmed by monitoring l
Points #1, #3 and #4 on recorder CAC-TR-778 located on the.
l' Remote Shutdown Panel. The time the event occurred can be L determined from the chart paper speed.
l d. If average drywell-temperature cannot be calculated l- AND l.
- (1) A loss of drywell cooling has occurred AND 1
! (2) Reactor vessel cool down rate of 100*F/hr or greater has NOT started within one hour of the loss of drywell cooling.
C. OPERATOR ACTION
- 1. Inform all stations that conditions exist that require rapid i
depressurization of Unit 2 reactor vessel.
- 2. DIRECT the Unit 2 RSDP/PMI Reactor Operator to INITIATE a rapid l
depressurization using Attachment 1 of Section C. l l
- 3. If any of the entry conditions to this attachment no longer apply 6NQ NQ other conditions are present that require rapid depressurization, THEN EXIT this attachment and RETURN to Section "A" to a compatible step for plant conditions.
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BSEP-2/ASSD-05 Page 8 of 83 Rev. 21
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l l 4. WHEN reactor water level has been increased to between 200 and 210 inches and rapid depressurization or LPCI injection are no longer needed, THEN DIRECT Unit 2 RSDP/PMI Reactor Operator to ESTABLISil shutdown cooling.
- 5. EXIT this attachment AND RETURN to Section "A" to a compatible step for plant conditions.
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BSEP-2/ASSD-05 Page 9 of 83 Rev. 21
Calculation Sheet 1 Values Obtained From Recorder CAC-TR-778 80' elev PT No. 1.
x 0.14 x 0.14 x 0.14 x 0.14 x 0.14 x 0.14 x 0.14 X 0.14 A A A A A A A A 28' elev PT No. 3 l
x 0.4 x 0.4 x 0.4 x 0.4 x 0.4 x 0.4 x 0.4 X 0.4 B 'B B B B B B B 13' elev PT No. 4 x 0.46 x 0.46 x 0.46 x 0.46 x 0.46 x 0.46 x 0.46 X 0.46 l
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l C C C C C C C C i Add the numbers obtained in lines A, B, and C, to obtain average l DW temp.
I Average DW Temp i
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l BSEP-2/ASSD-05 Page 10 of 83 Rev. 21 l.
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TABLE 1 Reactor Pressure Vs Saturation Temperature 600 1
f
-o a
^ 550 se M i o a d" v ad '~
a p r
- w r x 500 _
se S
c . a?
x d '
w s .---
l a 950 f C J' i
W r l
a k z 400 O E
- ~* f H A I x f x r l
t 3 350 1 J u) A W
6- P i z 300 ,
c r l 1
J r i o !
! o ;
o 250 I
i l
l 200 ,
O se las 300 GOO 900 1200 REACTOR PRESSURE (PSIC)
BSEP-2/ASSD-05 Page 11 of 83 Rev. 21 1
FIGURE 1 Control Building 49'and 23' Elevation Access / Egress NORTH m
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a"cc"es"seon"ess" CONTROL BUILDING "cc#
A m2m esseoness "
TO UNIT NO. 2 TO UNfT NO 1 N BLDO. EL. WW
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To DeESELGENERATORBUILDNG SENCE I WATER SURDNG, REACTOR BLdDNG, nmeme suumG ANDTHE EAST YARD.
CONTROLLED ACCESS BREEZEWAY g
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LEGEND
- - - - ACESS/ EGRESS V PHONE JACK. TRAIN A OR B BSEP-2/ASSD-05 Page 12 of 83 Rev. 21 L_______
j FIGURE 2 Unit 2 Reactor Buildind 50' Elevation Access / Egress i
UNIT 2 REACTOR BUILDING i NORTH I 1 1 1 l W d U b u 5 2-F.I l-F0688 (ELEV. 45'-O") % "[
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TO & FROM "
2O'-O" EL.s '
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rm E 2-SW-V 106 2-SW-V 102 EL. 50'-O" RHRSW PUMPS LEGEND
- - -= ACCESS / EGRESS 3 VALVES e NORMAL / ISOLA 17. SWTTCHES BSEP-2/ASSD-05 Page 13 of 83 Rev. 21
FIGURE 3 Unit 2 Reactor Building 20' Elevation Access / Egress and Sound Powered Phone Communications NORTH UNIT 2 REACTOR BUILDING ,
O i i l, w J % J /-
I EE TO & s
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= =_
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a:gcc 2xo MCC 2XC STARhh - -
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ELEVATION 20W LEGEND
ACCESS / EGRESS V PHONE JACK, TRAIN AOR B BSEP-2/ASSD-05 Page 14 of 83 Rev. 21
SECTION "B" UNIT 1 BOP REACTOR OPERATOR ACTIONS
- 1. UPON receiving this procedure, PERFORM the steps in the order listed.
- 2. OBTAIN a security key from the Unit 2 SCO.
- 3. OBTAIN the following keys from the Unit SCO key locker.
1 CO Key, Key Number 202 QR 203 1 Tll2 Outboard MSIV AC Power Isolate Switch Key, Key Number 214 1 Tll2 Inboard MSIV AC Power Isolate Switch Key, Key Number 215 4 At the Unit 2 RTGB, PLACE the keylock switch to "0VRD/ RESET" for Div II Noninterruptible Instrument RNA Valve, )
2-kNA-SV-5261.
- 5. USE appropriate figures in the back of this section to provide access / egress routes and equipment. )
1
- 6. At the Control Room back panels, REMOVE power to the MSIVs and SRVs to prevent spurious operation AND REMOVE power to HPCI flow control circuits as follows:
- a. At Panel 2-H12-P623, PLACE the Normal / Isolate keylock switch to " ISOLATE" for Outboard MSIV AC Power Isolation Switch, l
- b. At Panel 2-H12-P622, PLACE the Normal / Isolate keylock switch to " ISOLATE" for Inboard MSIV AC Power Isolation Switch.
- c. At Control Building 125V DC Distribution Panel 4A:
(1) PLACE CKT 11 to "0FF" for ADS Relay Logic B.
(2) PLACE CKT 2 to "0FF" for HPCI Flow Controller, E41-F053, E41-F054, E41-F026, E41-F028, E51-F005, E51-F025.
l (3) PLACE CKT 12 to "0FF" for Inmoard Isolation Valve Logic Control Panel 2-H12-P622.
BSEP-2/ASSD-05 Page 15 of 83 Rev. 21
. . _ _ _ ~ . _ _ . . .- -
l l d. At Control Building 125V DC Distribution Panel 4B:
, (1) PLACE CKT 11 to "0FF" for ADS Relay Logic A l and B Control Panel 2-H12-P628.
(2) PLACE CKT 12 to "0FF" for Outboard l Isolation Valve Logic Control Panel 2-H12-P623.
- 7. PROCEED to the ASSD equipment cabinet AND OBTAIN the Unit 1 BOP l Reactor Operator equipment bag from the ASSD equipment cabinet.
l
[ 8. PROCEED to Unit 2 Cable Spread Room 120V AC Emergency j Distribution Panel 2D, TilEN l
l
- a. PLACE all breakers to the "0FF" position. !
J j b. VERIFY reset OR RESET the main power supply breaker. I l
- c. PLACE CKT 25 to "0N" for Div II PNS/N2 Backup Valves 2-RNA-SV-5261, 5251, and 5481.
l.
- 9. PROCEED to 2B Battery Room AND PERFORM the following: l
- a. OPEN Battery Charger 28-1 transfer switch cover,
- b. PLACE Normal / Emergency switch for' Battery Charger 2B-1 to " EMERGENCY."
. c. OPEN Battery Charger 2B-2 transfer switch cover.
- d. PLACE Normal / Emergency switch for Battery l Charger 2B-2 to " EMERGENCY." !
- 10. PROCEED to Unit 2 Turbine Building 4 KV switchgear room.
l 11. REMOVE the control power fuses, THEN manually TRIP the l following breakers using mechanical trip push button.
1 At 4 KV Switchgear Bus 2B I
__ a . Compt AB3 (Row S), MG Set 2A Drive Motor l
l
- c. Compt ACl (Row KK), Condensate Booster Pump 2A j d. Compt AC2 (Row LL), Condensate Booster Pump 2C
- e. Compt AC7 (Row QQ), Condensate Pump 2B t
BSEP-2/ASSD-05 Page 16 of 83 Rev. 21
-. , . - - . - _. . _ . - . . . . _ - .. - . - . . _ . - _ . - . _ ~ ~ . . - . . - . -
At 4 KV Switchgear Bus 2D
- f. Compt AD9 (Row J), Condensate Booster Pump 2B
- g. Compt AD3 (Row D), Condensate Pump 2A-
- h. Compt AD2 (Row C), Condensate Pump 2C
- 12. PROCEED to Unit 2 Remote Shutdown Panel AND INFORM Unit 2 SCO that the following actions have been completed.
- a. Power has been removed to MSIVs and SRVs to prevent spurious operations AND power has been removed to HPCI flow control circuits,
- c. The N2 Backup Switch AND circuit alignment has been ,
completed for continuous SRV pneumatic supply. )
i
- d. Power has been removed-to Recirculation Pumps, Condensate, and Condensate Booster Pumps, i
- 13. E not in progress, T]M PERFORM Unit 2 Rx. Bldg MCC Operator's 1 Section D2 for Manual Service Water Valve Operations. l
- 14. W!iEN directed by the Unit 2 RSDP/PMI Reactor Operator, THEN PERFORM the following:
- b. MONITOR RHR HX B Service Water Outlet Temp Ind, 2-SW-TI-808.
CAUTION Failure to maintain RHR Heat Exchanger service water outlet temperature below 180*F may challenge the short term seismic qualification of the RHR Servico Water System and associated support structures.
- c. H RHR HX 2B service water outlet temperature
. approaches 180'F, THEN NOTIFY Unit 2 RSDP/PMI Reactor Operator.
- 15. ASSIST Unit 2 SCO as directed, i
.a.
BSEP-2/ASSD 05 Page 17 of 83 Rev. 21
I
! FIGUP.E 1 Control Building 49' and 23' Elevation Access / Egress mo m O =
4ev earszaway CONTROL BUILDING *** '*828 =
Acccannaeuss Accra "4 TO UNfT No. E ,o UNff NO, ,
REACTOR SLDO EL. BO'c' g , , g , RgACTOR BLDO. EL. 50'c' s 1 / 7 ??$ ~s
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LEGEND ACES 5/EORESS PHONE LACK, TRAIN A OR B i
l BSEP-2/ASSD-05 Page 18 of 83 Rev. 21
I FIGURE 2 l
l Turbine Building 20' Elevation Access / Egress TURBINE BUILDING 20' ELEV. Nonrn 1 w i l
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\ concatra UNIT 2 TURBINE BLOG.
BEAnt 4.I6KV SWITCHGEAM OUS 20 E* \ I CONO. PUhnP 2C AIR 2 cow pump 2A COM g yg gggy 3 CONO. DSTM. PtAh0F 20 SANPLE \ 4.16KV SWITCMGEAR Ot/S 20 STATION \ @ Q 4 S
NG SET 28 DMtW MOTOR MG SET 2A DMtW MOTOM REC
\ m o rana,. 4.iexv smranEAn a ac 6 CON. BSTW. PtAh9 2A
__ 1 0 7 a
Coho. BSTR. Ptn9P 2C C0m. mar ts !
l rs. utsvAT0n~'% UNIT / TUtBINE BLOG.
2 I
N <wKy surcueEAn esis la l hi 9 MG SETIA DMtVE N0 TOW 10 MG SET 10 DMtVE NOTOR
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<lexv swircseEAn esis 10 II COND. BSTM. PUMP 10
I f ! SKY SWITGNCEAR..._ nil 21C
<14 CON. RSTW. PUnaP IA BREEZEWAY IS C0 m. sSrM. Pune IC 4.- + - - - , A\ Q .16_COM.+ PUh0F p, IB t n 4 a LEGEND ACCESS /E0 NESS - ~ ~
l BSEP-2/ASSD-05 Page 19 of 83 Rev. 21 l
.-. .- - - .. ._. _ . - . . _ - _ . _ . - - . - - . _ . . . . , _ = . - . . . . . _ .
r i
' FIGURE 3 l l
- Unit 2 Reactor Building 50' Elevation Access / Egress i
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- UNTT 2 REACTOR BUILDING f NORTH r r l T 1 l[W d U L w I
2-El 1-F0 6 8 B (ELEV. 45'-O") % j[
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TO & FROM 33 j 20' O' EL. s ' 3!
M) m m
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M DFhWELL
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2-SW-V 105 /*~% '2-RNA-CSCO I N f 7
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-AND 2-RNA-CS-OO2 m a rROM 61 20'-O' EL.
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rm l'" 3 m E
2-sW-V I Oe 2-SW-V I O2 EL. 50'-O" RHRSW PUMPS LEGEND
- - - ACCESS / EGRESS E VALVES S NORMAL / ISOLATE SWITCHES BSEP-2/ASSD-05 Page 20 of 83 Rev. 21
FIGURE 4 Unit 2 Reactor Building 20' Elevation Access / Egress and Sound Powered Phone Communications NORTH UNir 2 REACTOR BUILDING I
a ~
E
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= :
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50'-0'bb INVERTER (HIK)/y lg,,, j
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.jl'-0*hbb /A E:gcc axo I MCC 2XC 2-SW-Tl408 - -
N[ -
ELEVATION 20'O' STARhhf trocso
ACCESS / EGRESS V PHONE JACK, TRAIN AOR B b TEMPERATUREINDICAiOR
'BSEP-2/ASSD-05 Page 21 of 83 Rev. 21
l FIGURE 5 Unit 2 Reactor Building -17' Elevation Access / Egress UNIT 2 REACTOR BUILDING NORTH b
/ s DRYWELL
\ /
1
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708 FMON EL EVATION 20'- 0" l
N / '
RCIC PUMP
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l 9 EL V T/0 20'- 0"
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EL . 9'- 0" N
5\ [tgoogg LEGEND GRATING " /
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- - - - ACCESS / EGRESS , l ~f l
/ I \ \ ,
L LADDER j 2-SW-Vil7 } { 2-SW-Vil8
~
l EL .(APPROX.) - 2'. 0" EL. (APPROX.)-2'- 0" r
EL. 9' O" 1
BSEP-2/ASSD-05 Page 22 of 83 Rev. 21
FIGURE 6 East Yard Structures and Equipment Iocations EAST YARD AREA NORTH RADWASTE BULONG
-Is.- l q- _j s "
- ^ REACTOR BLOG. g REACTOR BLOG.
yl UNIT NO.2 UNIT NO. I DIESEL GENERATOR BUILDING E
2-CO-V127 l-CO-V127 y LOCAL CST LOCAL CST LEVEL INDICATOR LEVEL INDICATOR l '
7 CONDENSATE STORAGE CONDENSATE STORAGE UNIT NO.2 / \ IAVIT NO.I FUt?L OIL STORAGE TANK SERVICE WATER INTAKE STRUCTURE .
wh U V-BSEP-2/ASSD-05 Page 23 of 83 Rev. 20
I SECTION "C" UNIT 2 RSDP/PMI REACTOR OPERATOR (REMOTE SHUTDOWN PANEL OPERATOR) ACTIONS CAUTION Interlocks that would normally prevent inadvertent draining of the reactor coolant to the suppression pool, due to improper valve positioning, are bypassed when operating the valves manually or with the ASSD switches selected for local operation. Caution must be exercised when performing RHR valve operations in this procedure to ensure that each valve operation is fully completed prior to performing the next sequential operation.
l (This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel I to suppression pool at BWRs", and may not be removed without concurrence of Regulatory Affairs.)
- )
- 1. OBTAIN a security access key from the ASSD equipment cabinet.
- 2. USE appropriate figures in the back of this section to provide access / egress routes, equipment, and communication locations ]
=
AND PROCEED to the Unit 2 Remote Shutdown Panel. '
- 3. ALIGN switches on RSDP listed in table below as follows:
1
- a. PLACE control switch in position, THEN l
- b. PLACE Normal / Local switch to " LOCAL" OR Isolation Switch to "ISOL".
EQUIPMENT DESCRIPTION CONTROL NORMAL / LOCAL NUMBER SWT POS OR ISOLATION SWT POS 2-SW-V143 Well Water Supply Valve CLOSED LOCAL 2-E51-RS-SS RCIC Turb Trip Logic N/A LOCAL l
Train "B" (Unit 2) Control N/A ISOL Rm Isolation Sw.
2-B21-F013E Manual Relief Valve E OFF LOCAL 2-B21-F013G Manual Relief Valve G OFF LOCAL 2-B21-F013B Manual Relief Valve B 0FF LOCAL 2-B21-CS-3345 Reactor Water Level N/A LOCAL 2-SW-V141 Well Water to Vital Header CLOSED LOCAL BSEP-2/ASSD-05 Page 24 of 83 Rev. 21
. .- ._- , - . ~ _ - . . - _~. _ - - - - . - - - - - _ . . . . - - ~ _ - _
l I
l 4 OBSERVE parameters on instruments listed below while performing I actions to achieve and maintain cold shutdown.
Instrument Location 2-C32-PI 3332 Reactor Pressure Remote Shutdown Panel 2-B21-LI-R604BX Reactor Water Level Remote Shutdown Panel B21-LI-5977 Reactor Level Remote Shutdown Panel 2-CAC-TR-778 Drywell Temp (Pts. 1, 3, and 4) Remote Shutdown Panel 2-E51-FIC-3325 RCIC Flow Controller Remote Shutdown Panel 2-E11-FI-3338 RRR System B Flow Remote Shutdown Panel 2-CAC-TR-778 Suppression Pool Water Temp. Remote Shutdown Panel
, (Pt. 6 and 7) 2-CAC-LI-3342 Suppression Pool Level Remote Shutdown Panel 2-CAC-PI-3341 Drywell Pressure Remote Shutdown Panel l 2-CO-LIT-1160 CST Level CST 2-SW-TI-808 RHR HX B Service Water Reactor Bldg-El. 20' Outlet Temp Ind South 2B RHR HX Room l l
- 5. ALLOW SRVs to operate at their mechanical setpoint to conserve pneumatics.
0 E0_TE To save time, establishing communications with !
other operators on the ASSD sound-powered phone i system can be performed simultaneously with the implementation of other steps in this procedure.
- 6. ESTABLISH ASSD sound-powered phone communications as follows:
- a. PLUG a Y-jack into the ASSD Unit 2 Train B Sound Powered Phone Ckt.
- b. PLUG the sound-powered phone into the Y-jack ;
installed in the ASSD Unit 2 Train B phone jack. j
- 7. If the ASSD sound-powered phone system fails to operate, THEN i USE hand-held portable radios or the plant Gai-tronics system to establish communications. I
- 8. lE directed to perform a rapid depressurization, THEN ESTABLISH sound-powered phone communication AND PROCEED to Attachment 1 of this section.
l i
I i
BSEP-2/ASSD-05 Page 25 of 83 Rev. 21
1 l
l 4
NOTE 1 RCIC Steam Supply to Turbine, E51-F045, may have closed due to I high reactor water level.
)
l NOTE 2 !
1 RCIC Trip and Throttle Valve, E51-V8, may have tripped closed on turbine overspeed. If this has occurred, the RCIC Turbine l Trip light will NOT be illuminated and the valve will still ;
indicate open at MCC 2XDB. RCIC Turbine Trip light will only '
be illuminated if actuated by depressing manual " TRIP" push i button, or a RCIC Pump Suction Low Pressure and/or a i RCIC Turbine Exhaust Diaphragm High Pressure trip signal. The !
valve motor must be run fully closed to reset the actuator to )
enable reopening the valve. i 1
- l CAUTION If the RCIC Turbine trips on an actual overspeed condition, the Turbine Trip ;
and Throttle Valve, E51-V8, should not be reset until RCIC flow is at minimum.
- 9. WHEN informed RCIC is ready for startup, THEN:
- a. PLACE the Normal / Local switch to " LOCAL" for the RCIC Flow Controller.
- b. RESET RCIC and VERIFY the RCIC turbine trip light is extinguished. ,
I
- c. VERIFY reactor water level is less than or equal to 200 inches.
1
- e. If RCIC does not start, THEN DIRECT Unit 2 Rx Bldg MCC Operator to RESET RCIC Trip and Throttle Valve, E51-V8.
- f. WHEN informed RCIC is reset and ready for startup, THEN DIRECT Unit 2 Rx Bldg MCC Operator to START RCIC.
- g. If RCIC is running, THEN adjust the RCIC flow controller as necessary to maintain reactor water level between 170 and 200 inches.
l h. INFORM Unit 2 SCO of RCIC status.
- 10. WHEN directed, THEN START reactor depressurization and cooldown at areater than 100*F/hr using SRVs and RCIC as follows:
l l
BSEP-2/ASSD-05 Page 26 of 83 Rev. 21 l
\
NOTES When cycling SRVs, sequence E, G, and B should be used to evenly distribute heat load to the suppression pool.
Cool down rate is determined by obtaining reactor coolant temperature using Temperature vs Pressure curve on Table 1 of this section. Temperature is then plotted on Table 2 of this section for temperature vs time to derive the cooldown rate.
- a. OPEN ss many SRVs as is necessary to achieve a cooldown rate treater than 100*F/hr.
- b. MAINTAIN reactor water level greater than 20 inches,
- c. PLOT cooldown rate on Table 2 of this section.
- d. IF reactor water level approaches 20 inches during depressurization, THEN CLOSE as many SRVs as necessary to maintain reactor water level greater than 20 inches.
NOTE RCIC suction should not be transferred from CST to suppression pool if suppression pool temperature is greater than 140*F.
- e. If suppression pool level increases to -2 feet AND suppression pool water temperature is less than 140*F, THEN DIRECT Unit 2 Rx Bldg MCC Operator to TRANSFER RCIC suction from CST to suppression pool.
- 11. WHEN informed the switch lineup on the MCCs is complete, THEN DIRECT Unit 2 Rx Bldg MCC Operator to:
- a. PERFORM Section D2, Manual Service Water Valve Operations, AND
- b. PERFORM Section D3, Establishing Service Water Flow through RHR HX 28.
- 12. WHEN informed service water flow has been established through RHR Heat Exchanger 2B, THEN DIRECT Unit 2 Rx Bldg MCC Operator to START suppression pool cooling in accordance with Section D4.
- a. WHEN RHR System B flow indicates 9,500 to 10,000 gpm, THEN DIRECT Unit 2 MCC Operator to STOP THROTTLING OPEN E11-F0243.
- 13. WHEN reactor pressure indicates les. than 120 psig, THEN INFORM Unit 2 SCO.
BSEP-2/ASSD-05 Page 27 of 83 Rev. 21
- 14. DIRECT Unit 2 Rx Bldg MCC Operator to STOP suppression pool cooling in accordance with Section DS.
- 15. If the reactor vessel level is less than 200 inches or decreases to less than 200 inches anytime during shutdown cooling, THEN DIRECT Unit 2 Rx Bldg MCC Operator to ADD makeup water to the reactor vessel.
- a. WHEN reactor water level has been raised to between 200 and 210 inches, THEN DIRECT Unit 2 Rx Bldg MCC Operator to STOP ADDING water to the reactor vessel.
.,_16. WHEN informed suppression pool cooling is stopped, THEN DIRECT Unit 2 Rx Bldg MCC Operator to START shutdown cooling in accordance with Section D6.
I ******************************************************************************
CAUTION An RHR Pump should not be operated with a discharge flow rate of less than 500 gpm for more than one minute with the RHR pumps minimum flow bypass valve closeo.
- a. WHEN RRR System B Flow indicates 1000 to 1100 gpm, THEN DIRECT Unit 2 Rx Bldg MCC Operator to STOP l THROTTLING OPEN Ell-F0488.
- b. MAINTA1N 1000 to 1100 gpm flow through RHR system for 15 minutes to warm up system piping. l
,,c. DIRECT Unit 2 Rx Bldg MCC Operator to THROTTLE OPEN Ell-F048B to establish 5,000 to 10,000 gpm RHR flow rate.
- d. WHEN RHR System B Flow ind'.stes 5,000 to 10,000 gpm, THEN DIRECT Unit 2 Rx Bldg H00 Operator to STOP THROTTLING OPEN Ell-F048B.
CAUTION Failure to maintain RHR Heat Exchanger service water outlet temperature below 180*F may challenge the short term seismic qualification of the RHR Service Water System and associated support structures.
- x+***********n***+*********xt*+++*********************.******************
l e. DIRECT the Unit 1 BOP Reactor Operator to monitor RHR HX 2B service water outlet temperature on i 2-SW-TI-808.
l BSEP-2/ASSD-05 Page 28 of 83 Rev. 21 l
l l
CAUTION RPV cooldown rate, RHR Heat Exchanger service water outlet temperature, and RHR System flow requirements must be monitored once E11-F048B and Ell-F003B are throttled.-
- 17. INCREASE E DECREASE cooldown rate as necessary to achieve 45 to 50*F/hr cooldown rate by directing Unit 2 Rx Bldg MCC Operator to PERFORM one g more of the following:
NOTE Use pressure vs temperature curve on Table 1 of this section to monitor reactor cooldown,
- a. THROTTLE RHR Hx B Service Water Discharge Valve, Ell-PPV-F068B, while maintaining nuclear service water header pressure at 40 psig or greater.
- 18. WHEN reactor pressure has decreased to 60 psig, E EN:
19, MONITOR reactor vessel cooldown using Table '. and 2 of this section AND ASSIST Unit SCO as directed.
- 20. WHEN reactor pressure has decreased to O psig, THEN INFORM Unit SCO.
BSEP-2/ASSD-05 Page 29 of 83 Rev. 21
- ATTACHMENT 1 ,
l A. TITLE Unit 2 Reactor Vessel Rapid Depressurization B. ENTRY CONDITIONS WHEN directed by the Unit SCO to initiate a rapid depressurization C. OPERATOR ACTIONS l 1. DIRECT Unit 2 Rx Bldg MCC Operator to INITIATE Section D9 for l LPCI Injection.
- 2. WHEN informed LPCI is running, THEN
- a. OPEN -11 SRVs.
- b. WHEN F:!R flow starts to increase THEN MAINTAIN flow at the desired rate to increase vessel level to 200 inches by directing Unit 2 Rx Bldg MCC Operator to THROTTLE RHR HX 2B Byp Vlv, Ell-F048B. i
- 3. IE increased RHR flow is desired THEN DIRECT the Emergency l Switchgear Operator DG Bldg to START RHR Pump 2D.
- 4. WHEN reactor water level has been increased to between 150 and 160 inches, THEN DIRECT the Emergency Switchgear Operator DG Bldg to STOP RHR Pump 2D.
l
- 5. WHEN reactor water level has been increased to between 200 and 210 inches, THEN:
- 6. WHEN it is determined that LPCI injection is no lo7ger needed, THEN:
( a. DIRECT Unit 2 Rx Bldg MCC Operator to CLOSE RRR HX 2B l Byp Viv, Ell-F048B. (
l l
- b. DIRECT Unit 2 Rx Bldg MCC Operator to START shutdown cooling in accordance with Section D6.
- c. EXIT this attachment AND return to Section C to a compatible step for plant conditions.
BSEP-2/ASSD-05 Page 30 of 83 Rev. 21 4
TABLE 1 Reactor Pressure Vs Saturation Temperature 600
^ ~"
a 550 _se-o a d' v ,# P' s
$ 500 '"'
f
? s a r a r x s Y 450 r y l
y s
- r I 900 o x
& A T y
& W D 350 e ,
a J u) A W
w y z 300 ,
C r J r o
o u 250 ;
200 ', ,
O se see 300 600 900 1200 REACTOR PRESSURE (PSIC)
BF3P-2/ASSD-05 Page 31 of 83 Rev. 21
l I
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i 8 8 8 8 o o
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I ELBAT MORF ERUTAREPMET TNALOOC ROTCAER D s
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FIGURE 1 Control Building 49' and 23' Elevation Access / Egress NORTH m
- # BREEZE W CONTROL BUILDING " " M EZE W AccesseoRe88 ACCES863RESS TO UNIT NO. 2 TO UNIT NO.1 REACTOR BLDO. EL W#
,,,,9~75 [
~, h ,,,,,,-,,,,,
[ ,, , , , ,
[ ,,,,r,",W :REACTOR ELDO. EL W#
- ~ ~,'*~ , , , ,
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N g___-,w _ . -) ,
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, , , , , ,I V , , /, , , , , ,\, , , \, , , , , , , , , , , , , , , , , , -
EL49' 0" TO 'MESEL GENERATOR BUILDING SERVICE WATER BUILDING REACTOR BUILDING, TURBINE SUILDedo ANDTHE EAST YARD.
CONTRO'd.ED ACCESS BREEZEWAY 00** Do**
.____ ___g-;n._______________________- __ ___
3 C-
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V EL23*-0" LEGEND
- - - - ACCESS / EGRESS V PHONE JACK. TRAIN A OR B BSEP-2# idL-05 Page 33 of 83 Rev. 21
FIGURE 2 ,
Unit 2 Reactor Building 50' Elevation Access / Egress UNIT 2 REACTOR BUILDING NORTH I '
1 l U b h.d 2-E l 1 -FO68B j (ELEV. 45'-O') %
TO & FROM 20'-O' EL.N
% > e--
- ~
a ,
~
M DRWVELL
^2-RNA CS-OO 1 2-Sw-v i 05
/
/*~] _; YR 'A-CS-OO2 TD & FROM N 20'-o' EL.
I ( ( g
---n f/
rn T' 3 "
E 2-SW-v i Oe 2-S W-v i O 2 EL. 50'-O" RHRSW PUMPS LEGEND i - - - ACCESS / EGRESS 3 VALVES S NORMAL / ISOLATE SWITCHES l
l BSEP-2/ASSD-05 Pcge 34 of 83 Rev. 21
. . . _ , - . _ . . ... ... . . - ~ ._-.. . . . = - . . . . . . - . - - . _ . ~ . _ . . - - . . - , . . -
FIGURE 3.
Unit 2 Reactor Building 20' Elevation Access / Egress and Sound Powered Phone Conununications NORM UNIT 2 REAC10R BUILDING I
2 t-.
E
{/ ,
- ==
TO & s
- EE ^* EE -
s%
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's s cmWEU.
l MCC 2XB- =#
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- MCC 2XA MCC 2XDQ j y,')d l _ _
l
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W -0' M ,.
- 4. ..
f s' l l r-INVERTER (HIK)< ,_. ;m, '
i
-1T-O' k b cm )
- MCC 2XC 2-SW-TI408 -
g"E
--4f -
ELEVATION 20'-O' l STAR J)
LEGEND l
L
ACCESS / EGRESS T PHONE JACK, TRAIN AOR B l
' 8 TEMPERATUREINDICATOR 1 4 i a I
il t
i i
j BSEP-2/ASSD-05 Page 35 of 83 Rev. 21 4
l t
SECTION "D" UNIT 2 RX BLDG MCC OPERATOR ACTIONS l
INDEX l
D1 Initial Actions and RCIC Operations D2 Manual Service Water Valve Operations D3 Establishing Service Water Flow Through RHR HX 2B l D4 Placing Suppression Pool Cooling in Service D5 Removing Suppression Pool Cooling From Service D6 Placing Shutdown Cooling in Service D7 Removing Shutdown Cooling From Service l
D8 Adding Makeup Water to the Reactor Vessel l
l D9 LPCI Inj ection i
l l I
i l
I i
l l
l i
i ;
BSEP-2/ASSD-05 Page 36 of 83 Re t . 21 i
l SECTION D1 l
INITIAL ACTIONS AND RCIC OPERATIONS
- A***************************************************+*****************
CAUTION
, Interlocks that would normally prevent inadvertent drnining of the reactor l coolant to the suppression pool, due to improper valve positioning, are bypassed when operating the valves manually or with the ASSD switches selected for local operation. Caution must be exercised when performing RHR valve operations in this procedure to ensure that each valve operation is fully completed prior to performing the next sequential operation.
(This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel to suppression pool at BWRs", and may not be removed without concurrence of Regulatory Affairs.)
- 1. OBTAIN a security key from the ASSD equipment cabinet.
l
- 2. USE appropriate figures in the back of this section to provide access / egress routes, equipment, and communication locations.
- 3. PROCEED to Unit 2 Reactor Building AND PERFORM the following at MCC 2XD
! NOTE I
l Power is considered available to an MCC when ;
( indicating lights are illuminated at that MCC. l
- a. At Compt DW2 (Row E3) for RCIC Turbine Vacuum Breaker l Valve, E51-F062:
l (1) PLACE breaker to "0N" AND (2) II power is available, THER 7 PEN valve.
- b. At Compt DW1 (Row F3) for HPCI Steam Line Isolation Valve, E41-F002:
l (1) PLACE Normal / Local switch to " LOCAL" AND (2) IE power is available, THEN CLOSE valve.
BSEP-2/ASSD-05 Page 37 of 83 Rev. 21
- .-.~ . -. . - - - - - .. - . ... - - . . - . - ~ . . . .
NOTE I l
Communication may be established any time using the ASSD Unit ' Train B Sound Powered Phone Ckt l at MCC.2XB Compt D3Z (Row C2). In the event the ASSD sound-powered phone system is inoperable,
. hand-held portable radios or the plant Gai-tronics system may be used. l
- 4. PERFORM the following at MCC 2XDB.
t
- a. For items that have maintained contact control switches (switches without an
- or a #):
(1) VERIFY QE PLACE the control switch to the position indicated on the table, THEN (2) VERIFY QR PLACE Normal /L: cal switch to i
" LOCAL." ,
- b. For items that have sprine return to "NEUT" or "0FF" control switches (switches that have an
- or #):
(1) VERIFY QR PLACE Normal / Local switch to "LDCAL," THEN (2) OPERATE the control switch of the item with l an
- or # as required to line up the item to the position indicated on tha table.
l NOTE
- Control switches for these items are spring return to "NEUT" or "0FF" 6NQ l have a seal in. Momentarily placing the switch to the position indicated on i the table will line up the valve.
]
l
- Control switches for these items are spring return to "NEUT" or "0FF" AND QQ HQI have a seal in. The control switch must be held in position until the valve is fully stroked to the position indicated on the table.
CONTROL NORMAL /
ConPT/ EQUIIMENT SWT/VLV LDCAL CKT DESCRIPTION NUMBER POS SWT POS MCC 2XDB Reactor Building El 20' LOCATION South BOC Valve 2-Ell-F009 Interlock With RRR Pumps 2B and 2D 2-Ell-F009 N/A ISOLATE (Row A3)
B36 RCIC Barometric Condenser 2-E51-C002-START LOCAL (Row B3) Condensate Pump CP B37 RCIC Turbine Trip and Throttle 2-E51-V8 CLOSED LOCAL (Row C1) Valve BSEP-2/ASSD-05 Page 38 of 83 Rev. 21 1
.. .. ~.,
CONTROL NORMAL /
COMPT / EQUIPMENT SWT/VLV LOCAL CKT DESCRIPTION NUMBER POS SWT POS B38 RCIC Condensat:e Storage Tank 2-E51-F010 *0 PEN LOCAL (Row C2) Suction Valve RCIC Cooling Water Supply Valve 2-E51-F046 *0 PEN LOCAL w D1) 1 RCIC Pump Discharge Valve 2-E51-F012 *0 PEN LOCAL w D2)
R w E1) "J"" " * "" ~ ~
l * ^
B42 RCIC Bypass to Condensate Storage Tank Valve 2-E51-F022 # CLOSED IDCAL (Row E2)
B43 RCIC Steam Supply Outboard 2-E51-F008 *0 PEN LOCAL (Row F1) Isolation Valve
, pg RCIC Turbine Steam Supply Valve 2-E51-F045
- CLOSED LOCAL B45 RCIC Suppression Pool Suction Valve 2-E51-F031
- CLOSED IDCAL (Row Cl)
B46 RCIC Suppression Pool Suction 2-E51-F029
- CLOSED LOCAL (Row G2) Valve B47 RCIC Minimum Flow Bypass t (Row H., 2-E51-F019
- CLOSED LOCAL Suppression Pool Valve a Is lat n a e -
-F0% END NL R w H2)
BS2 Hain Steam Line Drain Outboard 2-B21-F019 *CIDSED LOCAL (Row J1) Isolation Valve
- 5. WHEN switch lineup for MCC 2XDB is complete, I}{EN INFORM RSDP Operator.
- 6. VERIFY open 9B OPEN RCIC Sterm Supply Inboard Isolation Valve, E51-F007, by performing the following:
- a. At inverter Panel H1K, START the inverter for RCIC Steam Supply Inboard Isolation Valve by performing the following. l t
(1) OPEN the left side of the inverter cabinet (2) DEPRESS AND HOLD S1 push button. l (3) Confirm red lamp DSl cycles ON, then OFF.
f BSEP-2/ASSD-05 Page 39 of 83 Rev. 21
. . - . . . - . . . . - . - - - - . ~ _ _ . . . . . . - . ~ . _ . . _ . . . . . . - . . .
i l
l (4) Wait 5 seconds.
(5) Place breaker CB6 to "0N."
(6) Release S1 push button.
- b. At Remote Starter Panel COJ, IE RCIC Steam Supply l Inboard Isolation, E51-F007, does NOT indicate full OPEN, THEN
i
( (1) PLACE control switch for valve to "0 PEN" l for 3 to 5 seconds to partially open valve. l l'
(2) WAIT 30 to 60 seconds, to equalize pressure across valve.
! (3) Fully OPEN E51-F007.
l c. INFORM the Unit 2 RSDP/PMI Reactor Operator that RCIC
- is ready to start.
I
- a. At Compt B37 (Row Cl), OPEN RCIC Turbine Trip and Throttle Valve, E51-V8.
- b. At Compt B44 (Row F2), OPEN RCIC Turbine Steam Supply l Valve, E51-F045.
- c. INFORM Unit 2 RSDP/PMI Reactor Operator that E51-V8 M E51-F045 are open M RCIC should be running If N.QI tripped.
i
t
- +********************************************************
amsa When closing the RCIC Turbine Trip and Throttle Valve, E31-V8, hold the control switch in the CLOSE position for 5 seconds after receiving full closed I indication to ensure the latch mechanism is fully engaged. j 1
j b. At MCC 2KDB Compt B37 (Row Cl), CLOSE RCIC Turbine
- Trip and Throttle Valve, E51-V8.
l 1 c. DIRECT the Unit 2 RSDP/PMI Reactor Operator to RESET j j RCIC. l l
j
~
l 1
l BSEP-2/ASSD-05 Page 40 of 83 Rev. 21 a 1 i ;
i . , _ . . _ _ _ . _ . . _ _
i
- d. IE RCIC has tripped on mechanical overspeed (ask the Unit 2 RSDP/PMI Reactor Operator), THEN RESET the mechanical overspeed trip device locally at Trip and Throttle Valve, E51-V8, as follows:
(1) Depending on body position, either PUSH QR PULL against spring pressure the emergency connection rod in the direction of the Turbine Trip and Throttle Valve, E51-V8 (approximately one inch).
(2) OBSERVE the tappet and ball assembly, which resembles a plunger, drops into place.
(3) lE the tappet and ball assembly does NOT drop in place, THEN lightly DEPRESS the 1 assembly.
1 (4) RELEASE the emergency connection rod.
_____ e. INFORM the Unit 2 RSDP/PMI Reactor Operator that RCIC is reset and ready for startup.
(1) At Compt B37 (Row Cl), OPEN RCIC Turbine Trip and Throttle Valve, E51-V8.
1 (2) At Compt B44 (Row F2), OPEN RCIC Turbine I Steam Supply Valve, E51-F045. j (3) INFORM Unit 2 RSDP/PMI Reactor Operator j that RCIC should be running. '
l
- a. At Compt B45 (Row Gl), OPEN RCIC Suppression Pool Suction Valve, E51-F031.
- b. At Compt B46 (Row G2), OPEN RCIC Suppression Pool Suction Valve, E51-F029.
- c. At Compt B38 (Row C2), CLOSE RCIC Condensate Storage
- Tank Suction Valve, E51-F010.
- 10. WHEN directed to stop RCIC operation, THEN at MCC 2XDB Compt B44 (Row F2), CLOSE RCIC Steam Supply to Turbine, E51-F045.
BSEP-2/ASSD-05 Page 41 of 83 Rev. 21
l
[
i CAUTION Interlocks that would normally prevent inadvertent draining of the reactor coolant to the suppression pool, due to improper valve positioning, are l bypassed when operating the valves manually or with the ASSD switches selected for local operation. Caution must be exercised when performing RHR valve operations in this procedure to ensure that each valve operation is fully completed prior to performing the next sequential operation.
(This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel l to suppression pool at BWRs", and may not be removed without concurrence of
! Regulatory Affairs.)
- 11. E power is NOT available to MCC 2XB AND/OR MCC 2XB-2, THEN PERFORM the following switch lineup in the sequence indicated at the deenergized MCC(s).
- a. E power becomes available during the performance of this step, THEN EXIT this step AND PROCEED to the next step.
- b. PIACE control switch to the position indicated on the table, THEN
- c. PLACE Normal / Local switch to " LOCAL."
l NORMAL / )
CONTROL LOCAL / l COMPT / EQUIPMENT SWT/VLV ISOLATE CKT DESCRIPTION NUMBER POS SWT POS HCC 2XB Reactor Building El 20' LOCATION South RS-A-SS Suction Valve 2-B32-F023B N/A LOCAL R w Cl)
RS-B-SS Suction Valve 2-B32-F023B N/A IDCAL w C1)
S uth RHR Vent Fan 2-B-FCU-RB START IDCAL R w Cl)
DN6 RHR Pumps 2B and 2D Supp. Pool 2-Ell-F020B OPEN LOCAL (Row G1) Suction Valve DP2 Nuclear Service Water to Vital 2-SW-Vil7 N/A LOCAL (Row G2) Header Valve
[ DN9 RHR HX B Service Water Discharge 2-Ell-F002B LOCAL Valve N/A l (Row G4)
DM1 Nuclear Service Water Supply 2-SW-V105 LOCAL Valve N/A
- (Row H3)
DM6 Conventional-Nuclear Header 2-SW-V102 N/A LOCAL (Row H4) Cross-Tie Valve j DL8 RHR Drywell Spray Outboard 2-E11-F016B CLOSED LOCAL (Row I2) Isolation Valve BSEP-2/ ASS 0-05 Page 42 of 83 Rev. 21
l NORMAL /
CONTROL LOCAL /
COMPT / EQUIPMENT SWT/VLV ISOLATE CRT DESCRIPTION NUM.BER POS SWT POS DM2 RHR Suppression Pool Cooling 2-Ell-F024B N/A LOCAL (Row J2) Isolation Valve DM4 RHR Suppression Pool Spray 2-Ell-F027B CLOSED LOCAL (Row J3) Isolation Valve DN1 RHR HX B Service Water Discharge 2-Ell-PDV- LOCAL (Row K4) Valve F068B N/A DL5 RCIC Turbine Exhaust Vacuum Breaker Valve 2-E51-F066 N/A LOCAL (Row L4)
DK9 RHR Pump 2B Suppression Pool (Row M1) Suction Valve 2-Ell-F004B OPEN LOCAL RHR Minimum Flow Bypass Valve 2-E11-F007B N/A LOCAL w M2)
DLO RHR Pump 2D Suppression Pool (Row M3) Suction Valve 2-Ell-F004D OPEN LOCAL RHR HX 2B Outl c Valve 2-Ell-FC03B OPEN LOCAL R w N1)
HR E 2B Inlet Valve 2-Ell-F0M B C W ED WAL w N2)
RHR E 2B Byp Vlv 2-Ell-F048B C W ED MCAL l w N3)
D3Y Isolation Switch 2-D37-IS1 for 2-CAC-SV-N/A ISOIATE (Row N4) Valve 2-CAC-SV-1218C 1218C D3Y Isolation Switch 2-D3Y-IS2 for 2-CAC-SV- ISOIATE (Row N4) Valve 2-CAC-SV-1225C 1225C N/A D3Y Isolation Switch 2-D3Y-IS3 for 2-CAC-SV- IS01 ATE (Row N4) Valve 2-CAC-SV-4345 4345 N/A l
l HCC 2XB-2 Reactor Building El LOCATION 20' South RHR Outboard Injection Valve 2-Ell-F017B OPEN LOCAL ow C2)
RHR Inboard Inj Viv 2-E11-F015B N/A LOCAL R w D3) l DMS RHR Suppression Pool Discharge 2-Ell-F028B CLOSED LOCAL .
(Row B4) Isolation Valve l BSEP-2/ASSD-05 Page 43 of 83 Rev. 21
- 12. WHEN power is available to MCC 2XD, THEN:
- a. At Compt DW2 (Row E3), OPEN QR VERIFY open RCIC Turbine Vacuum Breaker Valve, E51-F062.
- 13. WHEN power is available to MCC 2XB and MCC 2XB-2 (in either order), THEN immediately PERFORM the following switch lineup in the sequence indicated at the energized MCC(s):
NOTE If a switch lineup was completed with no power available to MCC 2XB and/or MCC 2XB-2 (Step 11),
then only Step b.(2) below must be performed at each MCC that the initial switch lineup was completed at.
- a. For items that have maintained contact control switches (switches without an
- or a #):
(1) VERIFY QE PLACE the control switch to the position indicated on the table, THEN (2) VERIFY QE PIACE Normal / Local sattch to
" LOCAL."
- b. For items that have sprinn return to "NEUT" or "0FF" control switches (switches that have an
- or #):
(1) VERIFY QE PLACE Normal / Local switch to
" LOCAL," THEN (2) OPERATE the control switch of the item with an
- or # as required to line up the item to the position indicated on the table.
i l
4 BSEP-2/ASSD-05 Page 44 of 83 Rev. 21
l
- Control switches for these items are spring return to "NEUT" or "0FF" AND have a seal in for the position indicated on the table.
- Control switches for these items are spring return to "NEUT" or "0FF" AND _D_00 NOT have a seal in. The control switch must be held in position until the valve is fully stroked to the position indicated on the table.
NORMAL /
CONTROL LOCAL /
COMPT / j EQUIPMENT SWT/VLV ISOLATE CKT DESCRIPTION r NUMBER POS SWT POS MCC 2XB Reactor Building El 20' LOCATION South RS-A-SS Suction Valve 2-B32-F023B *CMSED LOCAL R w Cl)
RS-B-SS Suction Valve 2-B32-F023B
- CLOSED LOCAL CD i
BV9 South RHR Vent Fan 2-B-FCU-RB START LOCAL l (Row Cl)
DN6 RHR Pumps 2B and 2D Supp. Pool (Row Gl) Suction Valve 2-Ell-F020B OPEN LOCAL l
DP2 Nuclear Service Water to Vital 2-SW-V117 #0 PEN LOCAL (Row G2) Header Valve DN9 RHR HX B Service Water Discharge Valve 2-Ell F002B *0 PEN LOCAL (Row G4)
DM1 Nuclear Service Water Supply 2-SW-V105 *0 PEN LOCAL i (Row (H3) Valve DM6 Conventional-Nuclear Header 2-SW-V102
- CLOSED MCAL l (Row H4) Cross-Tie Valve l
f DL8 RHR Drywell Spray Outboard 2-Ell-F016B CMSED LOCAL (Row 12) Isolation Valve DM2 RHR Suppression Pool Cooling 2-Ell-F024B # CLOSED LOCAL l (Row J2) Isolation Valve DM4 RHR Suppression Pool Spray 2-Ell-F027B CLOSED MCAL (Row J3) Isolation Valve DN1 RHR HX B Service Water Discharge 2-Ell-PDV-
- CLOSED LOCAL
DK9 RHR Pump 2B Suppression Pool 2-E11-F004B OPEN LOCAL
- (Row M1) Suction Valve l BSEP-2/ASSD-05 Page 45 of 83 Rev. 21
l j l NORMAL /
l CONTROL LOCAL /
COMPT / EQUIPMENT SWT/VLV ISOLATE CKT DESCRIPTION NUMBER POS SWT POS R w M2)
RER Minimum Flow Bypass Valve 2-Ell-F007B *0 PEN LOCAL DLO RHR Pump 2D Suppression Pool (Row M3) Suction Valve 2-Ell-F004D OPEN LOCAL RFR HX 2B Outlet Valve 2-E11-F003B OPEN LOCAL R w N1)
RHR HX 2B Inlet Valve 2-Ell-F047B CLOSED LOCAL w N2)
RHR HX 2B Byp Viv 2-Ell-F048B CLOSED LOCAL R w N3) l D3Y Isolation Switch 2-D37-ISl for 2-CAC-SV-N/A ISOLATE (Row N4) Valve 2-CAC-SV-1218C 1218C D3Y Isolation Switch 2-D3Y-IS2 for 2-CAC-SV-(Row N4) Vale 2-CAC-SV-1225C 1225C /A S0 W E D3Y Isolation Switch 2-D3Y-IS3 for 2-CAC-SV-Valve 2-CAC-SV-4345 4345 N/A IS0 W E (Row N4)
MCC 2XB-2 Reactor Building El LOCATION 20' South RHR Outboard Injection Valve 2-E11-F017B OPEN LOCAL R w C2)
RHR Inboard Inj Viv 2-E11-F015B *CIDSED LOCAL l R w D3)
DMS RHR Suppression Pool Discharge 2-Ell-F028B CLOSED LOCAL (Row B4) Isolation Valve l
l 14. WHEN alignment of switches on the MCCs is complete, THEh INFORM Unit 2 RSDP/PMI Reactor Operator.
4 BSEP-2/ASSD-05 Page 46 of 83 Rev. 21
. . -. . . . . = .
l l
SECTION D2 ,
1 MANUAL SERVICE WATER VALVE OPERATIONS
- 1. CLOSE SW-V118 and SW-V106 as follows:
- 2. VERIFY with the Diesel Generator Operator that power has been removed from MCC 2XA. (Breaker t--i,, ped at Substation E7) i
- 3. VERIFY closed gg manually CLOSE Nuclear Header to RBCCW Heat Exchanger Isolation Valve, SW-V106. (50' el.) ,
- 4. VERIFY closed QB manually CLOSE Vital Service Water Divisional Tie Valve, SW-V118. (9' el.)
- 5. INFORM Unit 2 RSDP/PMI Reactor Operator that 2-SW-V118 and 2-SW-V106 are closed.
l i
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i I
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s i
BSEP-2/ASSD-05 Page 47 of 83 Rev. 21
SECTION D3 ESTABLISHING SERVICE WATER FLOW THROUGH RHR RX 2B
- 1. WHEN directed to establish service water flow through RHR Heat Exchanger 2B, THEN:
i
- a. PERFORM Section D2 for Manual Service Water Valve l Operations.
- b. DIRECT Service Water Building Operator to INFORM you ;
when Unit 2 nuclear header pressure de' creases I to 40 psig.
- c. At MCC 2XB Compt DN1 (Row K4), THROTTLE OPEN l j
RHR HX 2B Service Header Outlet Valve, Ell-PDV-F0688, !
until informed nuclear header pressure has decreased '
to 40 psig.
1
- d. INFORM Unit 2 RSDP/PMI Reactor Operator that service I water flow has been established through RHR Heat Exchanger 2B. i l
1 l
l 1
l
- i 1 1
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BSEP-2/ASSD-05 Page 48 of 83 Rev. 21
- SECTION D4 PLACINC SUPPRESSION POOL COOLING IN SERVICE i
- 1. WHEN directed to start suppression pool cooling, THEN:
- a. COMPLETE Section D2 for Manual Service Water Valve Operations.
- b. COMPLETE Section D3 for Establishing Service Water Flow through RHR HX 2B.
- e. WHEN informed RHR Pump 2B is running, THEN at MCC 2XB Compt DM8 (Row N3), slowly THROTTLE OPEN RHR HX 2B Bypass Valve, E11-F048B, until valve is full open.
- f. At MCC 2XB Compt DM2 (Row J2), COORDINATE with the Unit 2 RSDP/PMI Reactor Operator and THROTTLE OPEN RHR Suppression Pool Cooling Isolation Valve, E11-F0248, to establish 9,500 to 10,000 gpm flow.
(1) At Compt DM7 (Row N2), VERIFY OPEN QR OPEN RHR HX 2B Inlet Valve, Ell-F0478.
(2) At Compt DK8 (Row N1), VERIFY OPEN QR FULLY OPEN RHR HX 2B Outlet Valve, Ell-F003B.
(3) At Compt DM8 (Row N3), CLOSE RHR HX 2B Byp Viv. E11-F048B. t
- 2. INFORM Unit 2 RSDP/PMI Reactor Operator that suppression pool cooling is in service.
BSEP-2/ASSD-05 Page 49 of 83 Rev. 21
l
\
i SECTION D5 I REMOVING SUPPRESSION POOL COOLING FROM SERVICE l
- 1. WHEN directed to stop suppression pool cooling THEN: j l
- a. At MCC 2XB Compt DL3 (Row M2), OPEN Minimum l' low '
Bypass Valve, Ell-F007B.
- b. At MCC 2XB Compt DM2 (Row J2), CLOSE Suppression Pool 1
i l Isolation Valve, Ell-F024B.
l c. DIRECT the Emergency Switchgear Operator DG Bldg to STOP RHR Pump 2B.
- d. WHEN informed RHR Pump 2B is stopped, THEN at ;
MCC 2XB-2 Compt DM5 (Row B4), CLOSE Suppression Pool !
Discharge Isolation Valve, E11-F028B.
l l
l l
- f. INFORM the Unit 2 RSDP/PMI Reactor Operator that j suppres,sion pool cooling is removed from service. l l
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r BSEP-2/ASSD-05 Page 50 of 83 Rev. 21
1 i
SECTION D6 4'
a PLACING SHUTDOWN COOLING IN SERVICE l CAUTION Interlocks that would normally prevent inadvertent draining of the reactor coolant to the suppression pool, due to improper valve positinning, are bypassed when operating the valves manually or with the ASSD switches selected forLlocal operation. Caution must be exercised when performing RHR valve operations in this-procedure to ensure that each valve operation is fully completed prior to performing the next sequential operation.
(This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel to suppression pool at BWRs", and may not be removed without concurrence of Regulatory Affairs.)
- 1. WHEN directed to start shutdown cooling, THEN:
1
- a. COMPLETE Section D2 for Manual Service Water Valve Operations,
- b. COMPLETE Section D3 for Establishing Service Water ;
- c. At MCC 2XB, PERFORM the following. i (1) At Compt DN6 (Row Gl), CLOSE RHR Pump B and D Suppression Pool Suction Valve, ,
E11-F020B. I l
(2) At Compt DK9 (Row M1), CiDSE RHR Pump B !
Suppression Pool Suction Valve, Ell-F004B.
(3) At Compt DLO (Row M3), CLOSE RHR Pump D Suppression Pool Suction Valve, E11-F004D.
(4) At Compt DL3 (Row M2), CLOSE RHR Minimum Flow Bypass Valve, Ell-F0078.
(5) At Compt DL1 (Row L2):
(a) PLACE the Normal / Local switch to
" LOCAL."
(b) PLACE the breaker to "0N."
(c) OPEN RER Pump B Shutdown Cooling Suction Valve, Ell-F006B.
BSEP-2/ASSD-05 Page 51 of 83 Rev. 21
I
__ (6) At Compt DL2 (Row L3):
(a) PLACE the Normal / Local switch to
" LOCAL."
(b) PLACE the breaker to "0N."
_ _ (c) OPE.N RHR Pump D Shutdown Cooling Suction Valve, Ell-F006D. >
- d. At MCC 2XD Compt DX5 (Row F2):
(1) PLACE the breaker to "ON."
(2) OPEN RHR Shutdown Cooling Inboard Isolation ,
Valve, Ell-F009. t
- 2. At MCC 2XDB Compt B50 (Row A4): l l
(1) PLACE the Normal / Local switch to " LOCAL."
(2) Slowly THROTTLE OPEN RHR Shutdown Cooling Outboard Isolation Valve, E11-F008.
- f. At MCC 2XB, PERFORM the following:
(1) At Compt DM7 (Row N2), VERIFY closed QR CLOSE RHR HX 2B Inlet Valve, Ell-F0478.
(2) At Compt DK8 (Row N1), VERIFY open QR OPEN RHR HX 2B Outlet Valve, E11-F0035.
(3) At Compt DM8 (Row N3), VERIFY closed QB CLOSE RHR HX 2B Byp Vlv, Ell-F0488.
(4) DIRECT the Emergency Switchgear Operator DG Bldg to START RHR Pump 28. ,
I (5) WHEN informed RHR Pump 2B is running, THEN l
_at Compt DM8 (Row N3), slowly THROTTLE OPEN '
RHR HX 2B Byp Viv, E11-F048B, until dual indication is received to fill system and limit water hammer.
- h. At MCC 2XB Compt DM8 (Row N3), THROTTLE OPEN RHR HX Byp Viv, E11-F048B, until directed to stop to establish 1000 to 1100 gpm RHR flow rate, i
p f r4 A
BSEP-2/ASSD-05 Page 52 of 83 Rev. 21
CAUTION RPV cooldown rate, RHR Heat Exchanger service water outlet temperature, and RHR System flow requirements must be monitored once E11-F04SB and Ell-F003B are throttled.
- 1. WHEN directed, THEN at MCC 2XB, THROTTLE OPEN RHR RX 2B Byp Viv, Ell-F048B, to establish 5,000 to 10,000 gpm flow rate.
l
- j. WHEN directed, THEN at MCC 2XB, ESTABLISH RHR flow through RER Heat Exchanger 2B, by performing the foll ing:
(1) At Compt DK8 (Row N1), CLOSE RHR HX 2B Outlet Valve, Ell-F003B. I (2) At Compt DM7 (Row N2), OPEN RHR HX 2B Inlet Valve, Ell-F047B.
(3) WHEN directed, THEN PERFORM both of the following at MCC 2XB to establish cooldown rate and maintain desired flow rate:
(a) At Compt DK8 (Row N1), SLOWLY THROTTLE OPEN RHR HX 2B Outlet Valve, Ell-F003B.
(b) At Compt DM8 (Row N3), SLOWLY THROTTLE CIASE RHR HX 2B Byp Viv, E11-F048B.
I
- 2. INFORM the Unit 2 RSDP/PMI Reactor Operator that shutdown cooling is in service.
_ __ 3 . IF directed to change cooldown rate, THEN RTFORM one QR more of the following as directed.
l
- a. AT MCC 2XB, PERFORM the following:
(1) At Compt DN1 (Row K4), COORDINATE with the l Service Water Building Operator and THROTTLE RHR HX B Service Header Outlet Valve, Ell-PDV-F068B, to maintain the Nuclear Service Water Header pressure at l 40 psig or greater.
l l (2) At Compt DM8 (Row N3), THROTTLE RHR HX 2B Bypass Valve, Ell-F048B.
(3) At Compt DK8 (Row N1), THROTTLE RHR HX 2B Outlet Valve, Ell-F003B.
l l
BSEP-2/ASSD-05 Page 53 of 83 Rev. 21 l
i l SECTION D7 1
REMOVING SHUTDOWN COOLING FROM SERVICE CAUTION
! Interlocks that would normally prevent inadvertent draining of the reactor l coolant to the suppression pool, due to improper valve positioning, are
! bypassed when operating the valves manually or with the ASSD switches selected l for local operation. Caution must be exercised when performing RHR valve i
! operations-in this procedure to ensure that each valve operation is fully completed prior to performine the next sequential operation.
(This caution is a result of SOER 87-2 " Inadvertent draining of reactor vessel ,
i to suppression pool at BWRs", and may not be removed without concurrence of l Regulatory Affairs.) i l ****************************************cw************************************
l
- 1. WHEN directed to stop thutdown cooling, THEN:
I
- c. WHEN informed RHR Pump 2B is stopped, THEN at i
MCC IXDB Compt B50 (Row A4), CLOSE RHR Shutdown Cooling Outboard Isolation Valve, Ell-F008.
l l d. At MCC 2XD Compt DXS (Row F2), CLOSE RHR Shutdown
! Cooling Inboard Isolation Valve, Ell-F009.
- e. At MCC 2XB, PERFORM the following:
(1) At Compt DL1 (Row L2), CLOSE RHR Pump 2B Shutdown Cooling Suction Valve, Ell-F006B.
1 (2) At Compt DL2 (Row L3), CLOSE RHR Pump 2D l Shutdown Cooling Suction Valve, Ell-F006D.
(3) At Compt DN6 (Row Cl), OPEN RHR Pumps B and D Suction Valve, Ell-F020B.
I (4) At Compt CK9 (Row M1), OPEN RHR Pump B Suppression Pool Suction Valve, Ell-F004B.
(5) At Compt DL0 (Row M3), OPEN RHR Pump D Suppression Pool Suction Valvo Ell-F004D.
(6) At Compt DK8 (Row N1), VERIFY OPEN OR FULLY
BSEP-2/ASSD-05 Page 54 of 83 Rev. 21 r
(7) At Compt DM7 (Row N2), CLOSE RHR HX 2B Inlet Valve, Ell-F047B.
(8) At Compt DM8 (Row N3), CLOSE RHR HX 2B Byp Viv, Ell-F048B.
(9) At Compt DL3 (Row M2), OPEN RPP. Minimum Flow Bypass Valve, Ell-F007B.
- 2. INFORM Unit 2 RSDP/PMI Reactor Operator that shutdown cooling is removed from service.
I l
l BSEP-2/ASSD-05 Page 55 of 83 Rev. 21
l
[ SECTION D8 i ADDING WATER TO THE REACTOR VESSEL l
- 1. If directed to add water to the reactor vessel, THEN:
l l a. If in suppression pool cooling, THEN PERFORM
( Section D5 for Removing Suppression Pool Cooling From Service,
- b. If in shutdown cooling, THEN PERFORM Section D7 for Removing Shutdown Cooling From Service.
l l c. DIRECT the Emergency Switchgear Operator DG Bldg to START RHR Pump 2B.
- d. WHEN informed RHR Pump 2B is running, THEN, at MCC 2XB Compt DM8 (Row N3), slowly THROTTLE OPEN RHR HK 2B Byp Viv, Ell-F048B, until dual indication is received to fill the system and limit water hammer.
- f. At MCC 2XB Compt DM8 (Row N3), COORDINATE with Unit 2 RSDP/PMI Reactor Operator AND THROTTLE OPEN RHR HX 2B Byp Viv Ell-F048B, as necessary, to restore Reactor water level.
- 2. WHEN directed, to stop adding water to the reactor vessel, THEN:
l
Viv, Ell-F048B. ;
- d. INFORM Unit 2 RSDP/PMI Reactor Operator that the lineup for adding water to the reactor vessel is stopped AND the RHR System is ready to be lined up for:
(1) Suppression pool cooling QE l
, (2) Shutdown cooling QR I
t (3) LPCI injection BSEP-2/ASSD-05 Page 56 of 83 Rev. 21
l SECTION D9 )
LPCI INJECTION
any remaining steps for the MCC switch lineups in the l initial actions of Section Dl. l l
- b. COMPLETE Section D2 for Manual Service Water Valve I Operations. j l
- c. If in suppression pool cooling, THEN STOP suppression {
pool cooling in accordance with Section D5. i
- d. lE in shutdown cooling, THEN STOP shutdown cooling in ,
accordance with Section D7. !
- e. IE adding water to the reactor vessel in accordance with Section D8 THEN: 1 (1) CONTINUE with steps in Section D8 until RHR Pump 2B is running and injecting (start RHR Pump 2D if RHR Pump 2B will not start),
THEN (2) PROCEED to Step 1.h.(3).of this section. j
- f. ESTABLISH ASSD sound-powered phone communication with Unit 2 RSDP/PMI Reactor Operator.
- g. lE the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the plant Cai-tronics system to establish communications.
- h. IE NOT adding water to the reactor vessel, THEN:
(1) DIRECT the Emergency Switchgear Operator DG Bldg to START RHR Pump 2B (start RHR Pump 2D if RHR Pump 2B will not start).
l (2) WHEN informed RHR Pump 2B(2D) is running, THEN at MCC 2XB Compt DM8 (Row N3), slowly OPEN RHR HX 2B Byp Viv, E11-F048B, until dual indication is received to fill the system and limit water hammer.
(3) At MCC 2XB-2 Compt DL7 (Row D3), OPEN RER Inboard Inj Vlv, Ell-F015B. t (4) INFORM the Unit 2 RSDP/PMI Reactor Operator that LPCI is running, i
i
{
l BSEP-2/ASSD 05 Page 57 of 83 Rev. 21 t
l
1 (5) At MCC 2XB Compt DM8 (Row N3), COORDINATE with Unit 2 RSDP/PMI Reactor Operator AND l THROTTLE OPEN RHR HX 2B Byp V1v, E11-F048B, ,
as necessary, to rest. ore Reactor water l level.
(6) At MCC 2XB-2 Compt DL7 (Row D3), WHEN directed, THEN CLOSE RHR Inboard Inj Vlv, E11-F015B. )
1 (7) At MCC 2XB Compt DM8 (Row N3), WHEN l
directed, THEN CLOSE RHR HX 2B Byp Viv, l E11-F048B.
- 2. EHEN directed, THEN START shutdown cooling in accordance with Section D6.
1 l
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4 BSEP-2/ASSD-05 Page 58 of 83 Rev. 21
l l
l l
l FIGURE 1
)
4 Control Building 49' and 23' Elevation Access / Egress j NORTH m l
1 1
- '# "m" CONTROL BUILDING *#=nmv I ACCESSEORESS ACCES8/EORESS TO UNIT NO. 2 TO UNIT NO.1 naAcTonat.oo.a. w e
,,, n:- ,=.. g@y gp nEActon stoa. EL. we
,,,,,,,,, ,, ,,,,. s.----- ,,,.
[lXIC)<]l ,
=r %_
y jl ~-
./ -z-l J _ - . _ Y - ~r3_\ %.b 1
- VV S 4 -
l
-:/
ser --
\: l l
/
, , , , , , , , .IV. ,/, , , , , ,\ , , , , , , , , , , , , , , , , , ,
EL4F# 1 To: osesEL GENERATOR SUM.ONO SUMCE WATER BULDMO REACTOR BUILDNG.
TUPENNE DUILDMG AND THE EAST YARD.
CONTROLLED ACCESS BREEZEWAY
.____ __ _~ __ ___
rnou nEv. ' rnou Euv.
we ' O J we
==O -
y Q c=c--
1 _ S- Ir--
Il V I l-EL23'#
t.EGEND
- - - - ACESS/ EGRESS V PHONE JACK, TRAIN A OR B f BSEP-2/ASSD-05 Page 59 of 83 Rev. 21
. _ . . _ . . . . - - - . _ . - . - . _ - . - = . . ...-. _..-..- - ..- . . . - - - . .. . - . . . - --- .-
FIGURE 2 Unit 2 Reactor Building 50' Elevation Access / Egress UNIT 2 REACTOR BUILDING NORTH m
l 1 1 W d d b w 2-El 1-F068B (ELEV. 45'-O') % "[
l W
TO & FROM l 20'-O' EL.N 3 N a$ -
a ,
M DRWVELL 2-SW-V i 05 /*~% '2-RNA-CSCO I I -AND f
j _ _
2-RNA-CSCO2 To a rROM 1 -
20'-O' EL.
( ( g A l' /
rm T' h "E 2-Sw-V i Oe 2-SW-v i O2 EL. 5O'-O" RHRSW PUMPS LEGEND
- = = ACCESS / EGRESS E VALVES S NORMAL / ISOLATE SWITCHES i
i BSEP-2/ASSD-05 Page 60 of 83 Rev. 21
l 1
FIGURE 3 )
l Unit 2 Reactor iuilding 20' Elevation Access / Egress !
and Sound Powered Phone Comnunications l
l NORTH l
UNIT 2 REACTOR BUILDING
- V l
, , L 4
- < ~ s- i I
I ^*
TO&F N N ELEVATION %
n W2XI Q ,-
' Ads - -
MCC 2XDA l
MCC 2XB . , -/ - MCC 2XA MCC 2XDB -- -
,l __
! MCC 2XB 2 RSD" r y )' -
l SHb p 50'-0"hkbh$
k INVERTER (HIK)/
,,%..,[,'_s/
l l _
}".
i m.y l
17'.0"hkbh$ ~~ -'
- gcc 2xo g Mcc axc STARhh - - - -
4p -
ELEVATION 20'O' l LEGEND
ACCESS / EGRESS V PHONE JACK, TRAIN A OR B 4
BSEP-2/ASSD-05 Page 61 of 83 Rev. 21
l FIGURE 4 tnit 2 Reactor Building -17' Elevation Access / Egress UNIT 2 REACTOR BUILDING NORTH n -
lI V i
/ w DRYWELL
\ \
/
~ ~
roe enou EL EVA7t0N 20'= 0*
\ /
RCIC PUMP
. r- TO 9 FROM
""" PU"f#
,1 9 ELEVATION 20'-0" 9
/
~
-EL -17*-0"
,. o SEE DETAIL \
EL . 9'- 0 "
~
K l% N [ LADDER LEGEND
- ~ ~ ACCESS / EGRESS gg,7,,g .
7 N~~S) f _
Y P ;-t :ii
/ I \ \
l l 'LLADDER 2- SW- Vil7 - ! L 2-SW- Vil8 EL.(A PPROX.) - 2'- 0" EL.(A PPROX.)- 2'- 0" EL.9'-O" BSEP-2/ASSD-05 Page 62 of 83 Rev. 21
, . . . _ _ _ . _ _ _ _ _ _ _ . _ . _ _ . ___ . . _ . _ _ _ . . _ . _ _ . ___.-m_ _ _ . _ _ . _ _ _ . _
f SECTION "E" ,
SERVICE WATER BUILDING OPERATOR ACTIONS
- 1. OBTAIN a security access key from the ASSD equipment cabinet. ;
- 2. USE appropriate figures in the back of this section to provide j access / egress routes, equipment, and communication locations. ^
- 3. REPORT to Service Water Building AND ESTABLISH communications with any available station usind either-
- a. 20' elevation ASSD Unit 2 Train B sound-powered phone ekt located near the center of the west wall close to MCC 2PB 98
- b. 4' elevation ASSD Unit 2 Train B sound-powered phone ekt located near the center of the east wall.
- c. IF the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the !
plant Gai-tronics system to establish communications. ,
l EDIE l
Continuous communication should be maintained except during electrical and manual valve lineups. ,
- 4. At MCC 2PA, PLACE the following breakers to "0FF."
l
- a. At Compt E07 (Row E2), Conventional Service Water Pump 2A Discharge Valve to Conventional Header, i 2-SW-V13.
l b. At Compt E08 (Rew E3), Conventional Service Water
- Pump 2A Discharge Valve to Nuclear Header, 2-SW-V14.
l l S. At MCC 2PB, PLACE the following breakers to "0FF."
l l a. At Compr E37 (Row E4), Conventional Service Water Pump 2B Discharge Valve to Nuclear Header, 2-SW-V16.
- b. At Compt E36 (Row F3), Conventional Service Water Pump 2B Discharge Valve to Conventional Header, 2-SW-V15.
- c. At Compt E38 (Row F4), Nuclear Service Water Pump 2B Discharge Valve, 2-SW-V20.
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BSEP-2/ASSD-05 Page 63 of 83 Rev. 21 l
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i 6. At MCC 1PA, PLACE the following breakers to "0FF."
- a. At Compt BU9 (Row El), Conventional Service Water Pump 2C Discharge Valve to Nuclear Header, 2-SW-V18.
- b. At Compt BVO (Row F1), Conventional Service Water Pump 2C Discharge Valve to Conventional Header, 2-SW-V17.
- 7. IF Nuclear Service Water Pump 2B is running, THEN VERIFY open QR manually OPEN its discharge valve, 2-SW V20.
NOTE The purpose of the next step is to ensure that the nuclear header is not crosstied to the conventional header through the conventional service water pump discharge valves. If both discharge valves are found open, then it is preferable to close the conventional header valve.
- 8. VERIFY closed QB manually CLOSE each conventional service water pump discharge valve to the conventional header.
- a. Conventional Service Water Pump 2A Discharge Valve to ,
Conventional Header, 2-SW-V13 l
- b. Conventional Service Water Pump 2B Discharge Valve to Conventional Header, 2-SW-V15 I
- c. Conventional Service Water Pump 2C Discharge Valve to Conventional Header, 2-SW-V17
- 9. INFORM the Emergency Switchgear Operater DG Bldg that the service water valve and electrical lineup is complete.
- 10. WHEN directed, THEN VERIFY closed QR manually CLOSE Nuclear Service Water Pump 2B Discharge Valve, 2-SW-V20.
- 11. WHEN 2-SW-V20 is closed, THEN INFORM Emergency Switchgear Operator DG Bldg. I
- 12. WHEN directed, THEN manually OPEN Nuclear Service Water Pump 2B Discharge Valve, 2-SW-V20.
- 13. WHEN 2-SW-V20 is open, THEN INFORM Emergency Switchgear
, Operator DG Bldg.
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BSEP-2/ASSD-65 Page 64 of 83 Rev. 21 i
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- 14. VHEN directed, THEN INFORM Unit 2 Rx Bldg MCC Operator when I nuclear header pressure decreases to 40 psig as read on i 2-SW-PI-145, located on Nuclear Service Water Pump 2B discharge line.
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- 15. PERFORM duties as directed by the Unit SCO. ;
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l BSEP-2/ASSD-05 Page 65 of 83 Rev. 21 l
1
FIGLTE 1 Control Building 49' and 23' Elevation Access / Egress NORTH -
i
&# BREmWAY CONTROL BUILDING *#mm=
ACCESSE.ORESS ACCE88EORESS TO UNGT NO. 2 TO UNrT NO.1 )
REACTOR 94.DO. EL. 5&#
, , ,, , - , , , , + n ,/,
7
[ ,,
[ +1 - _,,-,-,w REACTOR BdXL EL. 60'#
- =r ~ l fM S '
- _ _ ' -, . T - ' + %. . t ze
- 6 ,
- Ya7A /
l egy' --
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)
- l
- - 1
/
~ . , , , , , ,,,,,,,-
[ /, , , , , ,\, , , , , , , , ,
EL45r 0*
TO: DIESEL GENERATOR BUILDNG SERVICE WATER SUILDING. REACTOR SUILDING, TURBINE DUILDING AND THE EAST YARD.
CONTROLLED ACCESS BREEZEWAY P9* m **
- I 8 PROM ELEV, PytOW ELEV.
er O J ee
.'=O -
y , y ==c---
'l Assosaurunwr
- f N
V l
l EL23'.F LEGEND
- - - - ACESS/ EGRESS i
V PHONE JACK TRAIN A OR B BSEP-2/ASSD-05 Page 66 of 83 Rev. 21 l
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FIGURE 2 Service Water Building Access / Egress Routes and Sound Powered Phone Cotmnunications j SERVICE WATER BUILDING _Nonq risra wr 1 - 1, j 3,_,,, ,q - - - - - - - - - - - - - - - - - - - - .
g ,,
.g ,',
jffgR P 2B <j_t__ n _-___
g.Sy.py.f4g N m __4 __;
16
> o ol/
,Joo O O O O O O O l C / / // / / lvi sisisis sii / ////7/ // /// / /
L 2-SW-PI-145 l-SW-PI-143 \
20 '- O' EL f* V.
LEGENO
- - - - ACCESS / EGRESS QPHONE ./ACK, rRAIN A oR B
= vAi.vE n enESSunE luciCAron o Srnainen
,1111111111,111111111111111111/11 ,
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k A2 E A }0 L ~\'\\'\W ftbd#l-l-H,ErAM , I LLh '
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'////KM/FAA/VAM///XXX/YXXX/A / ///>
2-SW-V2O l-SW-Vl9 2-SW-VI9 l-SW-V20 2-SW-vl0 l-SW-Vl3 l 2- S W-Vl7 l-SW-Vl4 2- SW- V16 l-SW-VIS
! 2- S W- Vl3 4LO' EL EV l-SW-Vis l 2- S W-VI4 l-S W- VIT l 2. S W-Vl3 1-SW- vie I
l
{
l BSEP-2/ASSD 05 Page 67 of 83 Rev. 21
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i SECTION "F" I l
EMERGENCY SWITCHGEAR OPERATOR DG BLDG ACTIONS
- 1. OBTAIN a security access key from the ASSD equipment cabinet.
- 2. USE appropriate figures in the back of this section to provide access / egress routes, equipment, and communication locations.
- 3. REPORT to 4 KV Bus E2 AND ESTABLISH communication with Unit 2 RSDP/PMI Reactor Operator and the Diesel Generator Operator as follows:
- a. At Compt AHO (Row G), PLUG a Y-Jack into the ASSD Unit 2 Train B Sound Powered Phone Ckt.
NOTE l i
The next step will tie Unit 1 and Unit 2 ASSD Train b sound powered phone circuits together and allow Unit 2 SCO to talk with Unit 1 Control Room Operator.
NOTE The jumper cord and both Y-Jacks must remain connected throughout the performance of this procedure to allow ccmmunications with all Unit 1 and Unit 2 stations. I
- b. At Compt AHO (Row G), PLUG a Y-Jack into ASSD Unit 1 Train B Sound Powered Phone Ckt.
- c. PLUG the jumper between the two Y-Jacks.
HOIE Performance of the following step provides communications to support operations on 4 KV Buses El and E2.
- d. PLUG the sound-powered phone into either of the j remaining Y-Jack connections on Compt AHO AND i ESTABLISH communications with the Diesel Ge.serator Operator.
- 4. IF the ASSD sound-pawered phone system fails to operate, THEN USE hand-held portable radios or the plant Gai-tronics system to establish communications.
- 5. At PT Compt AGS (Row B), PLACE Normal / Local switch to " LOCAL".
! 6. DIRECT Diesel Generator Operator to REMOVE Diesel Generator Z l from service, i
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BSEP-2/ASSD-05 Page 68 of 83 Rev. 21 i
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NOTE Performance of the following step provides communications to support operations cn 4 KV Buses E3 and E4.
- 7. When actions are required in the area of 4 KV Bus E4, THEN j ESTABLISH communications with the Diesel Generator Operator '
using ASSD UNIT 2 TRAIN B SOUND POWERED PHONE CKT located i on 4 KV Bus E4 Compartment AK6 (Row H). l l
l l 9. WHEN informed Diesel Generator 2 has been removed from service, l THEN DIRECT the Diesel Generator Operator to REMOVE Diesel Generator 4 from service.
l 10. PLACE the following Normal / Local switches to " LOCAL."
l a.
At Compt AK3 (Row E), RHR Pump 2B.
I b. At Compt AK4 (Row F), RHR Serv Wtr Pump 2B.
- c. At Compt AK7 (Row I), Unit Substa E8.
l l d. At Compt AK8 (Row J), CRD Hydraulic Pump 2B.
- e. At Compt AL1 (Row M), Nuc Serv Wtr Pump 2B. ,
l
- 11. VERIFY open og manually TRIP the following breakers using the control switch 23 the manual trip push button.
i l a. At Compt AK3 (Row E), RhR Pump 2B. i
- b. At Compt AK4 (Row F), RHR Serv Wtr Pump 2B.
l
- c. At Compt AK8 (Row J), CRD Hydraulic Pump 28.
- d. At Compt AL1 (Row M), Nuc Serv Utr Pump 2B.
- 12. REMOVE control power fuses AND open QR manually TRIP the following breakers using the manual trip push button. ,
- a. At Compt AK5 (Row G), RX Core Spray Pump 2B.
- b. At Compt AL2 (Row N), Cony Serv Wn: Pump 2B.
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i BSEP-2/ASSD-05 Page 69 of 83 Rev. 21 l
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- 13. WHEN informed:
- a. Service water valve and electrical lineup is complete AND l b. Diesel Generator 4 has been removed from service.
i THEN DIRECT Service Water Building Operator to VERIFY closed QR CLOSE Nuclear Service Water Pump 2B Discharge Valve, 2-SW-V20.
l
- 14. At Compt AK7 (Row I), VERIFY closed QB CLOSE Unit Sub E8 breaker.
- 15. VERIFY reset OR RESET the following Lockout Relays.
- a. At Compt AKl (Row C), Switch 86Ds.
- b. At Compt AK2 (Row D), Switch 86DP.
- 16. WHEN informed 2-SW-V20 is closed AND Diesel Generator 4 is ready to start, THEN COORDINATE to place Diesel Generator 4 in service as follows .
I
- a. At Compt AJ9 (Row A), REMOVE control power fuses from j Incoming Line from Swgr 2C breaker. )
- b. DIRECT Diesel Generator Operator to START Diesel Generator 4.
- c. At Compt AJ9 (Row A), WHEN informed Diesel !
Generator 4 is running, THEN VERIFY open QB TRIP Incoming Line from Swgr 2C breaker using the manual trip push button.
- d. DIRECT Diesel Generator Operator to CLOSE Diesel Generator 4 circuit breaker.
1
- e. At Compt AL1 (Row M), WHEN informed Diesel Generator 4 breaker is closed, THEN START Nuclear Service Water Pump 2B.
- f. DIRECT Service Water Building Operator to l
OPEN 2-SW-V20.
- 17. INFORM the Unit 2 RSDP/PMI Reactor Operator and Unit 1 RSDP PMI Monitor that E4 is energized and Nuclear Service Water Pump 2B is running.
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l BSEP-2/ASSD-05 Page 70 of 83 Rev. 21 1
- 18. PROCEED to 4 KV Bus E2 AND PLACE the following Normal / Local switches to " LOCAL."
- a. At Compt AG8 (Row E), RHR Serv Wtr Pump 2D.
- b. At Compt AG9 (Row F), RHR Pump 2D.
- c. At Compt AH1 (Row H), Unit Substa E6.
l 19. VERIFY open QR manually TRIP the following breakers using the l control switch QR the manual trip push button.
I
- a. At Compt AG8 (Row E), RHR Serv Utr Pump 2D.
- b. At Compt AG9 (Row F), RHR Pump 2D.
- 20. DIRECT Service Water Building Operator to VERIFY closed QR CLOSE Nuclear Service Water Pump 1B Discharge Valve, 1-SW-V20.
l
- 21. At Compt AH1 (Row H), VERIFY closed gg CLOSE Unit Sub E6 breaker.
l 22. VERIFY reset QE RESET the following Lockout Relays.
I
- a. At Compt AG6 (Row C), Switch 86DB.
l
- b. At Compt AG7 (Row D), Swicch 86DP.
- 23. WHEN informed 1-SW-V20 is closed AND Diesel Generator 2 is I
ready to start, THEN COORDINATE to place Diesel Generator 2 in service as follows:
( a. At Compt AG4 (Row A), REMOVE control power fuses from l Incoming Line from Swgr 1C breaker.
- b. DIRECT Diesel Generator Operator to START Diesel Generator 2.
l
- c. WHEN informed Diesel Generator 2 is running, THEN at Compt AG4 (Row A), VERIFY open QE manually TRIP Incaming Line from Swgr 1C breaker using the manual trip push button.
- d. DIRECT Diesel Generator Operator to CLOSE Diesel l
Generator 2 circuit breaker.
- e. WHEN informed Diesel Generator 2 breaker is closed, THEN DIRECT the Unit 1 RSDP PMI Monitor to START Nuclear Service Water Pump 1B.
l BSEP-2/ASSD-05 Page 71 of 83 Rev. 21 l
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l' 24. INFORM the Unit 2 RSDP/PMI Reactor Operator and Unit 1 RSDP PMI
! Monitor that 4 KV Bus E2 is energized and Nuclear' Service Water
- l. Pump 1B is running.
- 25. PROCEED to Emergency Bus E3 AND COORDINATE with Diesel Generator Operator to ISOLATE Emergency Bus E3 AND STOP Diesel l Generator 3 II operating as follows:
- a. At PT Compt AI3 (Row B), PLACE Normal / Local switch to !
- " LOCAL."
l
- b. DIRECT Diesel Generator Operator to REMOVE Diesel Generator 3 from service,
- c. At Compt A12.(Row A), WHEN informed Diesel Generator 3.has been removed from service, THEN !
REMOVE the control power fuses AND VERIFY open E manually TRIP Incoming Line from Swgr 2D breaker by {
depressing the manual trip push button. !
Compt AK3 (Row E) AND INFORM Unit 2 Rx Bldg MCC Operator.
- 27. If directed, IHEE. START E STOP RHR Pump 2D at 4 KV Bus E2 at Compt AG9 (Row F) and INFORM Unit 2 Rx Bldg MCC Operator.
)
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l BSEP-2/ASSD-05 Page 72 of 83 Rev. 21 b :
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FIGURE 1 Control duilding 49' and 23' Elevation Access / Egress NORTH m m -
CONTROL BUILDING ** maernw
- "es"emo"s"es *^Y Acc Accesseoness TO UNIT NO. 2 TO UNIT NO.1 REACTOR BLD 3. EL W#
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[ ,,,,,u,
[, _,,____,,,,,'0*
REACTOR BLDG. EL 60-IlXJNl l ;_ _ _ }a _jl_ h=w_
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b: h VsV4 l .. cy -- -
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EL49'M l 1 l l TO DIESELGENERATORBUILDNO SERVICE l
WA1ER SulLDING, REACTOR BUILDNG, ,
TURelNE BUILDMG AND THE i EAST YARD. J l
CONTROLLED ACCESS BREEZEWAY I l
.____ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ noww __ ____
encueLEv._./
we ' 0 l, l J Y 'aou ae euev.
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LEGEND
- _ - - ACESS/ EGRESS
+ V PHONE JACK, TRAIN AOR B l BSEP-2/ASSD-05 Page 73 of 83 Rev. 21
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l FIGURE 2 Diesel Generator Building Access / Egress Routes ;
and l Sound Powered Phone col.anications l
! \
l l OESEL GEhERATOR BNDNG m "Y_ \
1 ss rrrr rrrrr rrs/L v//s.'r rrrrir//f r///firrr r rr rr rr rr rrrrrrrf //sstrriss F
WN I swds r4l Isn@r 13] la erI s
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s,,t - --3 , 7 i v 3 r - L" "J
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FR0et , ) . , n FR0nt ,
23' ON W 23 0' b.......M..b. . . . . . .M. .b..R.b.......fL_ .... {
EL. 60' l
90 4 90 2 D0 2 90 1 LOCAL LOCAL LOCAL CoffrNOL COArrNCL COAmIOL \ ,gi LOCAL M
PANEL PAnK PAnK
,,,,,,,,,,,,,,,,n ,,,,,,,,,,v ,,,,,,,,,,r ,,,,: ,,,,\,9AnEL , , , , , , , , , , , , , , , , , , , , , , , , , ,
l 2
_c_
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- J %.l-}_ _ _ f _ _-i ddi-d.nwa [']- .Irrs --! a
- .I
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w FmF 11 sg i
Fe $ " Ir m .r] t i w l w I w i
g $ I $ ~
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$ kg f *l) ewer $ari i [::- i
$ I:T i
$ [:T i j I:] '
j
! $ Yl8 " M ::T sl l l l lswer tsj i
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1,11,sississi, sis m iussisi,- ///////s m isisiss ' ,///////////
h wh M y,un C mewves Cc-swveso ,.3, "7,"
[C reeveam tomme % i-sw-veer e-seves s -seveso 1 -sw-ve70 EL 23' LEGEND l -_--- Accessasares [ PNomr acc raast AM l ,Q PNonar act sawT t & 2 i
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( BSEP-2/ASSD-05 Page 74 of 83 Rev. 21
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SECTION "G" l l
DIESEL GENERATOR OPERATOR ACTIONS j
- 1. OBTAIN a security access key from the ASSD equipment cabinet.
l
- j. 2. USE appropriate figures in the back of this section to provide access / egress routes, equipment, and communication locations AND PROCEED to 480V Substation E7 switchgear.
l
- 3. At 480V Substation E7 Compt AY2 (Row Cl), TRIP the breaker for MCC 2XA.
l 4 PROCEED to Diesel Generator 2 Control Panel H55 AND ESTABLISH 1 l communications with Emergency Switchgear Operator DG Bldg using L the ASSD Unit 2 Train B Sound Powered Phone Ckt.
- 5. If the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the plant Gai-tronics system i
to establish communications.
l .
I
- 6. WHEN directed to remove Diesel Generator 2 from service, THEN:
- a. IE closed, THEN TRIP ene Generator Circuit Breaker.
t l
j b. IE operating, THEN STOP Diesel Generator 2 using the l EMERGENCY STOP push button.
l L
I CAUTION i There are seven (7) keylock normal / local switches located on Diesel i l Generator 2 Control Panel. Six (6) of these are located in a row. The l seventh switch is located in the row above the six switches. The six switches ;
in a~ row must be placed in local before placing the seventh switch in local.
l
- k*******************************
l l
l c. PLACE the six keylock Normal / Local switches to !
l " LOCAL."
l l d. Located in the row above the six keylocked Normal / Local switches, PLACE the seventh keylock Normal / Local switch to " LOCAL."
- e. IN10RM the Emergency Switchgear Operator DG Bldg that l Diesel Generator 2 has been removed from service.
- 7. PROCEED to Diesel Generator 4 Control Panel H57 AND ESTABLISH communication using the ASSD Unit 2 Train B Sound Powered Phone Ckt.
- 8. lE the ASSD sound-powered phone system fails to operate, THEN i USE hand-held portable radios or the plant Gai-tronics system 2
to establish communications.
BSEP 2/ASSD-05 Page 75 of 83 Rev; 21
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- 9. WHEN directed. to remove Diesel Generator 4 from service, THEN
- a. IF closed, THEN TRIP the Generator Circuit Breaker.
- b. IE operating, THEN STOP Diesel Generator 4 using the EMERGENCY STOP push button.
CAUTION There are seven (7) keylock normal / local switches located on Diesel Generator 4 Control-Panel. Six (6) of these are located in a row. The-seventh switch is located in the row above the six switches. The six switches in a row must be placed in local before placing the seventh switch in local.
- c. PLACE the six keylock Normal / Local switches to
" LDCAL. "
- d. Located in the row above the six keylocked Normal / Local switches, PLACE the seventh keylock Normal / Local switch to " LOCAL."
- c. INFORM the Emergency Switchgear Operator DG Bldg that Diesel Generator 4 has been removed from service.
- 10. lE the ASSD sound-powered phone system is being used for l
communications, IHEN REMOVE the headset AND PERFORM the following lineup. I
- a. At MCC DGD, PERFORM the following:
(1) At Compt EF7 (Row G2), PLACE breaker to j "0FF" for DG 4 SW TO JKT WTR CLR SPLY ISOL l VLV, 1-SW-V682.
j (2) At Compt DS9 (Row G3), PLACE Normal / Local switch to " LOCAL" AND Start /Stop control l
switch to " START" for Diesel Generator i Cell 4 Exhaust Fan, H-EF-DG. l (3) At Compt EF6 (Row II), PLACE breaker to "0FF" for DG 4 SW TO JKT WTR CLR INL ISOL VLV, 2-SW-V682.
- b. VERIFY open QE manually OPEN Diesel Generator 4 Unit 2 Service Water Supply Valve, 2-SW-V682.
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l BSEP-2/ASSD-05 Page 76 of 83 Rev. 21
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- c. At 480V Substation E8,. TRIP the following breakers. J (1) At Compt AZ6 (Row B3), Reactor Building MCC 2XH breaker.
(2) At Compt A04 (Row D3), Reactor Building MCC 2XF breaker.
(3) At Compt A07 (Row E2), Reactor Building MCC 2XM breaker.
l (4) At Compt A09 (Row E4), Control '
Building MCC 2CB breaker.
(5) At Compt AI2 (Row F3), Emergency 120/208V AC Distribution Panel 2E8 breaker,
- d. At 480V Substation E8 Compt FN2 (Row A1), PERFORM the following: ,
i (1) PLACE Normal / Local switch to "LDCAL" AND (2) VERIFY closed OR CLOSE Sub. E8 480V Main Breaker (breaker indication is on Compt AZ5 (Row B2). ;
1
- 11. IE the ASSD sound-powered phone system is operable, THEN PUT ON the headset AND INFORM the Emergency Switchgear Operator DG Bldg that Diesel Generator 4 is ready to be started.
- 12. WHEN directed, THEN START Diesel Generator 4 using the EMERGENCY START push button,
- 13. WHEN the Unit Available Running light illuminates, THEN INFORM the Emergency Switchgear Operator DG Bldg that Diesel l Generator 4 is running.
- 14. WHEN directed, to close Diesel Generator 4 circuit breaker, THEN:
- a. PLACE the Synchronizing Generator Switch to "0N."
- b. CLOSE the Generator Circuit Breaker.
- c. PLACE the Synchronizing Generator Switch to "0FF. "
l j d. INFORM Emergency Switchgear Operator DG Bldg that
- Diesel Generator 4 circuit breaker is closed.
l l
- 15. At Diesel Generator 4 Control Panel, OBSERVE service water pressure is greater than 25 psig on SW-PI-153-4.
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BSEP-2/ASSD-05 Page 77 of 83 Rev. 21 I
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- 16. PROCEED to blesel Generator 2 Control Panel H55 AND ESTABLISH communications using the ASSD Unit 2 Train B Sound Powered-Phone Ckt.
- 17. lE the ASSD sound-powered phone system fails to operate, THEN USE hand-held portable radios or the plant Gai-tronics system to establish communications.
- 18. REMOVE headset AND PERFORM the following lineups:
- a. At MCC DGB, PERFORM the following:
(1) At Compt D09 (Row G3), PLACE the Normal / Local switch to " LOCAL" AND Start /Stop con:rol switch to " START" for i Diesel Generator Cell 2 Exhaust Fan, 1 F-EF-DC. I 1
(2) At MCC DGB Compt EC3 (Row H2), PLACE breaker to "0FF" for SW to Jacket Water Cooler Isolation Valve, 2-SW-V680.
(3) At MCC DGB Compt EC4 (Row H3), PLACE breaker to "0FF" for Jacket Water Cooler Isolation Valve, 1-SW-V680.
- b. VERIFY open QR manually OPEN Unit 2 Service Water Supply Valve, 2-SW-V680.
- c. At 480V Substation E6, TRIP the following breakers:
(1) At Compt AW1 (Row D2), Reactor Building MCC 2XK breaker.
(2) At Compt AW4 (Row El), Off-Gas Building MCC 20G breaker,
- d. At 480V Substation E6 Compt FNO (Row A), PERFORM the following:
(1) PLACE the Normal / Local Switch to " LOCAL" AND (2) VERIFY closed QR CLOSE Sub E6 480V Main Breaker (Breaker indication is on Compt AV4
[ Row B2]).
- 19. lE the ASSD sound-powered phone system is operable, THEN PUT ON the headset AND INFORM the Emergency Switchgear Operator DG Bldg that Diesel Generator 2 is ready to be started.
- 20. WHEN directed THEN START Diesel Generator 2 using the i EMERGENCY START push button.
- 21. WHEN the Unit Available Running light illuminates, THEN INFORM i the Emergency Switchgear Operator DG Bldg that Diesel l Generator 2 is running.
BCEP-2/ASSD-05 Page 78 of 83 Rev. 21
- 22. WHEN directed to close Diesel Generator 2 circuit breaker, THEN:
- a. PLACE the Synchronizing Generator Switch to "0N."
- b. CLOSE the Generator Circuit Breaker.
- c. PLACE the Synchronizing Generator Switch to "0FF."
- d. INFORM Emergency Switchgear Operator DG Bldg that Diesel Generator 2 circuit breaker is closed.
- 23. At Diesel Generator 2 Control Panel, OBSERVE service water pressure is greater than 25 psig on SW-PI-153-2.
NOTE Service Water Pressure should be periodically monitored on SW-PI-153-2 and SW-PI-153-4 at Diesel Generator 2 and Diesel Generator 4 Control Panels while these diesels are operating.
< 24. IE the ASSD sound-powered phone system is being used for communications, THEN REMOVE the headset AND BLOCK OPEN Diesel Generator Building doors, as indicated on Attachment 1, to establish ventilation for continuous diesel generator operations.
- 25. WHEN ventilation has been established for diesel generator operation, THEN PUT ON the headset AND INFORM the Emergency Switchgear Operator DG Bldg that diesel generator ventilation has been established.
- 26. WHEN directed to remove Diesel Generator 3 from service, THEN PERFORM the following at DG 3 Control Panel,
- a. If closed, THEN TRIP the Generator Circuit Breaker.
- b. If Operating, THEN STOP Diesel Generator 3 using the EMERGENCY STOP push button.
- c. PLACE the six Normal / Local keylocked switches to "LDCAL."
- d. INFORM the Emergency Switchgear Operator DG Bldg thst Diesel Generator 3 is removed from service.
- 27. IF the ASSD sound-powered phone system is being used for communications, THEN REMOVE the headset and PERFORM the following:
- a. VERIFY closed QR manually CLOSE Jacket Water Cooler Service Water Inlet Valve, 1-SW-V680.
BSEP-2/ASSD-05 Page 79 of 83 Rev. 21
- b. VERIFY closed OE manually CLOSE Unit 2 Service Water_
Supply Valve, 2-SW-V681.
- c. VERIFY closed QR manually CLOSE Jacket Water Cooler Service Water Inlet Valve, 1-SW-V681.
- d. VERIFY closed pH manually CLOSE Jacket Water Cooler Service Water Inlet Valve, 1-SV-V682.
- 28. E the ASSD sound-powered phone system is operable, THEN PUT ON the headset and MONITOR operation of the diesel generators.
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i BSEP-2/ASSD-05 Page 80 of 83 Rev. 21
ATTACRMENT 1 Diesel Generator Building Door Position For Diesel Cell Ventilation
- 1. OPEN/ BLOCK OPEN doors identified on drawing below.
- 2. BLOCK OPEN doors using door wedge blocks.
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ELEV 23' O' BSEP-2/ASSD-05 Page 81 of 83 Rev. 21
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FIGURE 1 Control Building 49' and 23' Elevation Accese/ Egress ,
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- m osE8EL GENERATOR BUILDING SEm4CE WATER SUtLDING, REACTOR BUILDING.
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_ _ -- ACESS/ EGRESS V PHONE JACK, TRAIN AOR B BSEP-2/ASSD-05 Page 82 of 83 Rev. 21 1
FIGURE 2 l Diesel Generator Building Access / Egress Routes and Sound Powered Phone Communications OESEL GEAERATOR Bial,ONG #
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