ML20205S272
| ML20205S272 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/05/1988 |
| From: | Bishop E CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205K904 | List:
|
| References | |
| ASSD-02, ASSD-2, NUDOCS 8811110004 | |
| Download: ML20205S272 (202) | |
Text
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT COMMON PROCEDURE TYPE: ALTERNATIVE SAFE SHUTDOWN PROCEDURE NUMBER: ASSD-02 PROCEDURE TITLE: CONTROL BUILDING L-g' Rev. 0 4/5/88 QN yrQ yos 990&s,,4# >
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APPR0VED BY: bd[f{M DatW
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General ManagsrfHanager -gperations t.) :
BSEP-0/ASSD-02 Page 1 of 202 Rev. 0 8911110004 001025 PDR ADOCK 050003.'4 P ppy
LIST OF EFFECTIVE PAGES
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ASSD-02 Page(s) Revision 1-202 0 N
\r b-BSEP-0/AS50-02 Page 2 of 202 Rev. O
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TABLE OF CONTENTS kbh i PAGE ;
A. i TITLE........................................................... 5 B. REFERENCES...................................................... 5 .
i C. E N TR Y C O ND I T ! 0 NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 i
D. OPERATOR ACT!0NS................................................ 5 i i
Section "A" .....................................................$ !
Unit 2 Shift Foreman Action Section "8".................................................... 14 [
Senior Auxiliary Operator Action Section "C".................................................... 18 ,
Unit 2 Control Room Operator (Remote Shutdown l Panel Operator) Actions :
ti it Section "0".................................................... 31 p' Unit 2 Reactor Building MCC Operator Actions a, Section "E".................................................... 62 I
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c- Service Water Building Operator Actions &.
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Section "F".................................................... 74 11 Emergency Switchgear Operator Actions 1
l Sec t i on " G " . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96 Diesel Generator Operator Actions i Section "H"................................................... 113
.1 Unit 1 Shift Foreman Actions Section "!"................................................... 117 l i Unit 1 Control Room Operator (Remote Shutdown !
- Panel Operator) Actions l 1 !
Section "J"................................................... 130 Unit 1 Reactor Building MCC Operator Actionk A pp e nd i x 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 161 Unit 2 ASSD Remote Shutdown Pendl Equipment List l
Appendix 2........'............................................ 163 l Unit 1 ASSD Remote Shutdown Panel Equipment List j e
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TABLE Or CONTENTS (Cont'd) -
PAGE l A p p e nd i x 3 . . . . . . . . . . . .'. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 164 Unit 1 Access / Egress Routes Appendix 4.................................................... 172 Unit 2 Access / Egress Routes Appendix 5.................................................... 182 Restoring DC Power Appendix 6.................................................... 189 Unit 1 Blowdown and Flood Up Appendix 7.................................................... 196 i Unit 2 Blowdown and Flood Up ,
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A. TITLE O Control Building Alternativc Safe Shutdown Procedure AS$0-02.
Fire Location: Any area in the Control Building (including Mechanical ;
Equipment Space) other than the Battery Rooms, i B. REFERENCES
- 1. Per 10CFR50 Appendix 'R' Sections lil.G & L.
- 2. Per 10CFR50 Appendix 'R' Section Ill.J.
C. ENTRY CONDITIONS
- 1. This procedure is entered from Unit 1 or Unit 2 Alternative Safe ll Shutdown Index ASSD-01. ft
- y,
- 2. Shift Foreman has determined that both Reactors are to be brought to Cold Shutdown from outside the Control Room using (V
Alternative Safe Shutdown Train B. !
D. OPERATOR ACTIONS NOTE '
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Mt#i; l (73 The following minimum manpower is required to pi ' form f!
this procedure. ;i '
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(2) Shift Foreman (one from each Unit) t!
l (2) Licensed Operators (one Remote Shutdown Panel Operator :
l foreachUnit)
(1) Senior Auxiliary Operator (2) Auxiliary Operators (one for each Unit's Reactor f l Building) j (1) Auxiliary Operator (Diesel Generators) !
(1) Auxiliary Operator (Emergency Buses) ?
(1) Auxiliary Operator (Service Water Building) j l
1 1. Use appropriate figures in Appendix 3 and 4 to provide j l access / egress routes, equipment, and comunication locations. t L
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BSEP-0/ASSD-02 Page 5 of 202 Rev. 0 ,
- e. 2. OBSERVE the following parameters on instruments indicated while GI performing actions to achieve and maintain cold shutdown.
UNIT 1 Instrument location 1-CAC-TR-778 Suppression Pool Water Temp. (Pt. 7) Remote Shutdown Panel 1-CAC-LI-3342 Torus Level Remote Shutdown Panel 1-C32-PI-3332 Reactor Pressure Remote Shutdown Panel 1-B21-LI-R604BX Reactor Weter Level Remote Shutdown Panel UNIT 2 Instrument location 2-CAC-TR-778 Suppression Pool Water Temp. (Pt. 7) Remote Shutdown Panel 2-CAC-L1-3342 Torus Level Remote Shutdown Panel 2-C32-PI-3332 Reactor Pressure Remote Shutdown Panel 2-821-L1-R604BX Reactor Water Level Remote Shutdown Panel RB.
A BSEP-0/ASSD-02 Page 6 of 202 Rev. O
h CAUTION Fire damage may result in high impedance f aults involving non-safe shutdown equipment which could cause safe shutdown power sources to be deenergized.
- 3. IF while performing this procedure, any equipment listed below Tecomes deenergized due to ELECTRICAL fault THEN REFER to the .
applicable section listed below to restore power. '
EQUIPMENT SECTION - PAGE
- a. Reactor Building MCC 2XB Sect D - 48 j,
- b. Reactor Building MCC 2XDB Sect D - 58 i s
- d. Reactor Building MCC 2XD Sect 0 - 53 y
- e. Service Water Intake Structure KC 2PB Sect E - 71 :'
- f. Service Water Intake Structure MCC 1PB Sect E - 68 yb
- g. Emergency Bus E4 Sect F - 81
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@[. h. 480V Suosta E8 Sect G - 102 fg;l '
- i. Diesel Generator Building MCC DGD Sect G - 104 g
- j. 125V DC Distribution Panel 2B Sect F - 90 T 4
- k. Emergency 120V AC D'.stribution Panel 28-DG Sect F - 87
- 1. Emergency Bus E2 Sect F - 84
- m. 480V Substa E6 Sect G - 107
- n. Diesel Generator Building MCC DGB Sect G - 100
- c. 125V DC Distribution Panel 18 Sect F - 94
- p. Emergency 120V AC Distribution Panel 18-DG Sect F - 91
- q. Reactor Building MCC 1XB Sect K - 147
- r. Reactor Building MCC IXDB Sect K - 157
- t. Reactor Building MCC IXD Sect K - 152
- u. 125/250V DC Switchboard 1B App 5 - 183
- v. 125/2'50V DC Switchboard 28 App 5 - 186
- 4. CONTINUE implementation of this procedure by performing the i steps in SECTION A.
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BSEP-0/ASSD-02 Page 7 of 202 Rev. O i
SECTION "A" UNIT 2 SHIFT FOREMAN ACTIONS
- 1. 06TAIM the following keys from the Shift Foreman keylocker.
- a. (1) Unit 2 Remote Shutdown Panel Key
- b. (1) Unit 1 Remote Shutdown Panel Key
- c. (1) ASSD Equipment Cabinet Key
- d. (1) CO Key
- 2. OBTAIN ten (10) Security Access Keys from the Secondary Alarm Station.
- 3. DIRECT the following personnel to assemble at the ASSD Equipment Cabinet for implementation of ASSD-02.
- a. Senior Auxiliary Operator
- b. Unit 1 Shift Foreman
- c. Unit 1 Control Room Operator R5.1
@) d. Unit 2 Control Room Operator
- e. (5) Auxiliary Operators
- 4. PROCEED to AND OPEN the ASSD Equipment Cabinet.
- 5. PROVIDE Senior Auxiliary Operator with the ',ollowing,
- a. C0 Key
- b. Security Access Key
- c. Copy of ASSD-02
- d. Flashlight
- e. Battery charger transfer switch cove? taal (I
BSEP-0/ASSD-02 Page 8 of 202 Rev. O
NOTE Section "B" performs the following evolutions to both Units when executed by the Senior Auxiliary Operator.
- 2. Removes power to the Condensate Pumps, Condensate Booster Pumps, Recirculation Pumps, and HPCI control circuits.
- 3. Tran*fers Battery Chargers to alternate power.
- 6. DIRECT Senior Auxiliary Operator to complete Section "B" of this procedure.
- 7. INSTRUCT the Operators that, IF an to be operated is tagged out To'r "y equipment Pre-fire that Rackout" THEN is required REMOVE the tags and operate the equipment as necessary, 8 DIRECT . personnel to PROCEED to their assigned area AND PERFORM the steps in their section of this procedure as soon as they receive their equipment.
- 9. PROVIDE Unit 1 Shif t Foreman with the following.
- a. Key to Unit 1 Remote Shutdown Panel M
- b. Security Access Key AN,D, an ASSD flashlight
- c. Equipment per Appendix 2
- 10. PROVIDE the remaining Unit 1 personnel with a security access key, AhD an ASSD flashlight AND DISTRIBUTE equipment per Appendix 2. -
- 11. PROYlDE Unit 2 personnel with a security access key, AND an ASSD flashlight AND DISTRIBUTE equipment per Appendix 1.
- 12. PROCEED to Unit 2 Remote Shutdown Panc1.
- 13. ESTABLISH comunication with other remote shutdown stations using the "Y" phone jack labeled "TIE TO UNIT 1 REH3TE SHUTDOWN PANEL SOUND POWERED PHONE" on the RSDP.
- 14. IF any of the following conditions should occur 1 HEN Rapidly W)RESSURIZE the Reactor Vessel using Appendix 7
- a. Reactor vessel level as indicated on 2-B21-L1-604BX decreased to 45 inches ~OR indication of Reactor Vessel level is lost.
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BSEP-0/ASSD-02 Page 9 of 202 Rev. O
NOTE O The loss of Drywell cooling can be confirmed by monitoring points #1, #3 and #4 on recorder 2-CAC-TR-778 located on the Remote Shutdown Panel. The time the event occurred can be determined from the chart paper speed.
- b. Loss of Drywell cooling has occurred and Reactor Vessel cool down rate of 1000 F/hr. or greater has not started within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the loss of Drywell cooling.
- c. Failure of any SRV (2-821-F013E, G, or B) to open using the local control switches on the Remote Shutdown Panel.
- d. The continuous SRV pneumatic supply is or becomes unavailable as confirmed by the following:
HOTE The Div. I and Div. !! N; Backup system isolation valves will f ail to the open polition when the Olesel Generator Operator de-energizes MCC 2CA (Section G. Step 25) and Emergency 120V AC Distribution Panel 2 E8 (Section G, Step 5.c.)
(1) Np Backup System isolation valves are open (5tep 5.c and Step 25 of Section G have been Q performed). M D.
AND (2) N2 Backup System Div. I pressuie as indicated on 2-RNA-PI-5266 is less than 70 psig.
AND (3) N2 Backup System Div. 11 pressure as indicated on 2-RNA-PI-5264 is lese than 70 psig.
- 15. WHEN the Senior Auxiliary Operator reports that Section "B" is Complete THEN INFORM Unit 1 shift Foreman that the Senior Auxiliary Operator has performed the following to Unit 1 equipment;
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- a. Removed power to MSIV's and SRV's to prevent spurious operations AND removed power to HPCI flow control circuits.
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- b. Removed powce to Condensate Pumps, Condensate Booster l Pumps, and Racirculation Pumps.
l C, c. Transferred "B" Battery Chargers to alternate power.
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BSEP-0/AS$0-02 Page 10 of 202 Rev. 0 l
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- 16. WHEN !
C)
- a. Diesel Generator Operator reports that Diesel Generator
%. 4 is ready to be started, AW b, Emergenc)' Switchgear Operator reports that Emergency aus E4 is ready to be energized, AW ,
- c. Service Water Building Operator reports that the ,
Service Water lineup is Complete, THEN t
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- d. DIRECT the Diesel Generator Operator to START AND LOAD 1 Diesel Generator No. 4. !
17 1WN informed that Diesel Generator No. 4 is tied to Emergency i' Bus E4 THEN 1 mediately DIRECT the Emergency Switchgear Operator [
to STARTTuclear Service Water Pump 28.
- 18. WHEN: (
4,
- a. Diesel Generator Operator reports tnat Diesel Generator No. 2 is ready to be started AW gi
- b. Emergency Switchgear Operator reports that Emergency Bus E2 is ready to be energized. THEN {I; .
g c. DIRECT the Diesel Generator Operator to START AND LOAD Diesel Generator No. 2.
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- 19. WHEN informed that Diesel Generator No. 2 is Tied to Emergency o, Tus't2 THEN 1 mediately DIRECT the Emergen:y Switchgear Operator to STARTTuclear Service Water Pump 18. kl.
- 20. WHEN: b; l
- a. Diesel Generators No. 4 and 2 are Running AND l
- b. Nuclear Service Water Pump 1B is Running THEN !
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- c. INFORM Unit 1 Shift Foreman of the following ;
1 (1) Diesel Generators No. 4 AW No. 2 are running !
AND supplying Emergency Tuses E4 AND E2. j (2) Unit 1 Nuclear Service Water is available.
- 21. WHEN informed by the Reactor Building MCC Operator that the !
switch lineup on the MCCs is Complete THEN DIRECT RSDP Operator l g . to COORDINATE with other operators tv 7Tt the Suppression Pool i 4
in recirculation using RHR Loop B. !
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- 22. DIRECT Diesel Generator Operator to PLACE Diesel Generator No. 3 ,
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k(, in local control, i
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- 23. WHEN informed of the status of feeder breaker from Bus 20 to h Emergency Bus E3 THEN PERFORM the following:
- a. IF feeder breaker from Bus 2D to Emergency Bus E3 is Uosed. THEN DIRECT Emergency Switchgear Operator to REMOVE the control power fuses & TRIP feeder breaker f rom Bus 2D to Emergency But E3. ,
- b. IF feeder breaker from Bus 20 to Emergency Bus E3 is I E Closed. THEN DIRECT Emergency Switchgear Operator -
to REMOVE the control power fuses for feeder breaker t from Bus 2D to Emergency Bus E3.
IF Diesel Generator No. 3 is Operating, THEN DIRECT Diesel
- 24. Unerator Operator to TRIP Diesel Generator No. 3 output breaker !
AND STOP Diesel Generator No. 3.
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- 25. DIRECT Diesel Generator Operator to PLACE Diesel Generator No.1 t in local control, j
- 26. WHEN informed of the status of feeder breaker from Bus 10 to '
Emergency Bus El THEN PERFORM the following:
IF feeder breaker from Bus 10 to Emergency Bus El is
- a. Uosed, THEN DIRECT Emergency Switchgear Operator to REMOVE the control power fuses R TRIP feeder breaker g
, g' f rom lus ID to Emergency tus E1.
IF feeder breaker from Bus 10 to Emergency Bus El is b.
R Closed. THER DIRECT Emergency Switchgear Operator to REMOVE the control power fuses for feeder breaker from Bus ID to Emergency Bus E1.
- 27. IF Diesel Generator No.1 is Operating THEN DIRECT Diesel Enerator operator to TRIP Diesel Generator No.1 output breaker AND STOP Diesel Generator No. 1.
- 28. WHEN
- a. RCIC is operational AND maintaining Reactor Vessel water level greater than +70", AW
- b. Suppression Pool is being recirculated using RHR Loop "B", THEN I
- c. DIRECT the RSDP Opera',or to BEGIN a plant depressurization and cooldown at greater than 100'F/hr using SRVs and RCIC.
- 29. DIRECT Reactor Building MCC Operator to CLOSE 2 SW-V106 AW 2-SW-V118.
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- 30. WHEN informed by Unit 2 Reactor Building MCC Operator that 4 T39-Y106 AND 2-SW-V118 are Closed THEN DIRECT Unit 2 Reactor Building C0perator to COORDINATE with Service Water Building Operator to ESTABLISH Service Water flow through RHR Heat Exchanger 28'for suppression pool cooling and shutdown cooling.
- 31. WHEN informed by RSDP Operator that reactor pressure is less tnan 125 psig THEN DIRECT RSDP Operator to STOP Suppression Pool Cooling.
- 32. WHEN informed by RSDP Operator that Suppression Pool Cooling has been Stopped THEN DIRECT RSDP Operator to COORDINATE with Unit 2 Operators andWCE RHR Loop "B" in Shutdown Cooling Mode.
- 33. IF Rapid Depressurization of Reactor was performed, THEN PLACE Tsk System in Shutdown Cooling WHEN the lineup to stop LPCI Mode is Complete by performing the f W wing.
- 4. IF service water flow through RHR HX 2B has NOT been previously established THEN (1) DIRECT Reactor Building MCC operator to PERFORM Step 6 of Section "D". (To Verify closed or manually close 2-SW-V106 and 2-SW- V118. )
Q (2) WHEN informed by Reactor Building MCC Operator that 2-SW-Y106 AND 2-SW-V118 are N
Closed, THEN DIRECT Reactor Building MCC %
Operator to COORDINATE with Service Water N Building Operator to Establish service water flow through RHR HX 2B using applicable steps of their designated Section.
- b. WHEN service water flow through RRR HX 2B is -
Tiiablished. THEN DIRECT RSDP Operator to COORDINATE with Operators to PLACE RHR Loop "B" in Shutdown Cooling using applicable steps of their designated Section.
- 34. WHEN informed by Unit 2 RDP Operator that RC!C System operation is no longer required and is being shut down, THEN DIRECT 5.A.O.
to Manually CLOSE HPCI and RCIC Combined SuetionTrom CST Isolation valve, 2-CO-V127, locally at the Unit 2 CST.
- 35. CONTINUE Shutdown Cooling operation as required to achieve AND maintain Reactor pressure at 0 psig until an alternate method of determining reactor water temperature is provided.
- 36. RETURN plant to Generai Operating Condition as directed by Plant Management.
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BSEP-0/ASSD-02 Page 13 of 202 Rev. O
SECTION "B" h $ENIOR AUXILI ARY OPERATOR ACTIONS s procedure. THEN PERFORM the following:WHQ directed by U
- 1. TII
- a. PROCEED to the Unit 2 Battery Rooms M PERFORM the following:
(1) At 2A Battery Room:
(a) PLACE RPS M-G Set A output breaker to "0FF".
(b) OPEN Control Buildine 125V DC Distribution Panel 4A Supply Breaker at 125/250V DC
$witchboard 2A Compartment G14.
(2) At 28 Battery Room:
(a) PLACE RPS M-4 Set B output breaker to "0FF". N (b) l_F 125/250V DC Switchboard 28 is W-energized due to electrical m fault, 3,N,, PERFORM Appendix 5 DO steps for Restoring Power to 125/250V DC $witchboard 79 R CONTINUE this procedure with The following step below.
(c) OPEN Control Building 125V DC Distribution Panel 48 Supply treaker et 125/250V DC
$witchboard 28 Compartment GK4.
(d) OPEN tattery Charger 25-1 AC Power Transfer Switch cover.
(e) PLACE Normal / Emergency switch for batter { charger 26-1 to "EMERGENCY position.
j (f)OPENBatteryCharger28-2AC Power Transfer switch cover.
(g) PLAct Normal / Emergency switch for batterg charger 28 2 to "EERGENCY position.
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- b. PROCEED to the Unit 1 Battery Rooms AND PERFORM the i
! @s l following:
l l (1) At 1A Battery Room:
1 (a) PLACE RPS H-G Set A output breaker to "0FF".
(b) OPEN Control Building 125V DC l Distribution Panel 3A Supply l Breaker at 125/250V DC l Switchboard 1A Compartment G16, 1
(2) At 1B Battery Room: '
1
- (a) PLACE RPS M G Set B output I breaker to "0FF". !
(b) "IF 125/250V DC $witchboard 18 is K-energized due to electrical fault, THEN PERFORM Appendix 5 sters for Restoring Power to
! 125/250V DC $witchboard 1B AND l
CONTINUE this procedure witFThe following step below.
~ ~ (c) OPEN Control Butiding 125V DC N
Dw - Distribution Panel 3B Supply Breaker at 125/250Y DC
, Switchboard IB Compartment GKS.
1 l (d) OPEN Battery Charger 18-1 AC l Power Transfer Switch cover.
1 (e) PLACE Normal / Emergency switch for batter { charger 181 to j "EMERGENCY position.
(f)OPENBatteryCharger182AC Power Transfer Switch cover.
(g) PLACE Normal / Emergency switch l for battery charger 18 2 to 1 "EERGENCY" position.
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ESEP-0/ASSD-02 ' Page 15 of 202 Rev. O
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- c. GO to the Unit 2 Turbine Building 20' elevation AND I
o (si REMOVE control fuses. THEN Manually TRIP breaker using mechanical trip push button for ths follouing:
At 4.16 KV Switchgear Bus 2C (1) Condensate Booster Pump 2A at Compartment AC1 (2) Condensato Booster Pump 2C at Compartment AC2 (3) Condensate Pump 2B at compartment AC7 At 4.16 KV Switchgear Bus 20 (1) Condensate Booster Pump 28 at Compartment AD9 (2) Condensate Pump 2A at Compartment AD3 (3) Condensate Pump 2C at Compartment AD2 At 4.16 KV Switchgear Bus 28 (1) M3 Set 2A Drive Motor at Compartment AB3 (2) MG Set 28 Drive Motor at Compartment AA9 R B . .~
(R d. GO to the Unit 1 Turbine Building 20' elevation AND v REMOVE control fuses. THEN Manually TRIP breaker using mechanical trip push button for the following:
At 4.16 KV Switchgear Bus 1C (1) Condensate Booster Pump 1A at Compartment AC1 (2) Condensate Booster Pump 1C at Compartment AC2 (3) Condensate Pump 1B at Compartment AC4 At 4.16 KY Switchgear Bus 10 (1) Condensate Booster Pump 18 at Compartment AD9 (2) Condensate Pump 1A at Compartment AD3 (3) Condensate Pump 1C at Compartment AD2 At 4.16 KV Switchgear Bus 1B (1) M3 Set 1A Drive Motor at Compartment AB3 (2) HG Set 1B Drive Motor at Compartment AA9
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BSEP-0/ASSD-02 Page 16 of 202 Rev. O
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- 2. PROCEED to Unit 2 Remote Shutdown Panel AN INFORM Unit 2 Shift h Foreman that the steps in Section "B" have both units, which performed the following:
en completed for l
- a. Removed power to MSIV's and $RV's to prevent spurious operations AND removed power to HPCI flow control ci rcuits,
- b. Removed power to Condensate Pumps. Condensate looster Pumps, and Recirculation Pumps.
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- c. Transferred "B" Battery Chargers to alternate power.
- 3. A$$1ST $hift Foreman as directed. l t
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SSEP-0/A$$0-02 Page 17 of 202 Rev. 0 l f
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l SECTION "C" Q
l UNIT 2 CONTROL ROOM OPERATOR (REMOTE SHUT 00WN PANEL OPERATOR) ACTIONS
- 1. REPORT to Unit 2 RSDP AND ALIGN switches on RSDP listed in table below as follows: ;
- a. PLACE control switch in position THEN l
- b. PL ACE Normal / Local switch to "LOCAL" !
l EQUIPMENT CONTROL NORMAL / LOCAL NUMBER DESCRIPTION SWT POS SWT POS ;
2-E51-CS-3324 RCIC Flow Controller N/A LOCAL
[
2-SW-V143 Well Water Supply Valve CLOSE0 LOCAL 2-E51-RS-SS RCIC Turb Trip Logic N/A l.0 CAL !
Remote Shutdown Train "B" i (Unit 2) Control Rm isolation Sw. N/A LOCAL lt 4,1, 2-821-F013E Manus 1 Relief Valve E *0FF LOCAL
(~ 2 821.F013G Manual Relief Valve G *0FF LOCAL l
i-2-821-F0138 Manual Reitef Valve 8 *0FF LOCAL 2-SW-V141 Well Water To Vital ' leader CLOSED LOCAL [
I 2-821 -CS-3345 Reactor Water level N/A LOCAL l
- Control switch is spring return to 0FF position.
- 2. ALLOW SRY's to operate at their mechanical setpoint to conserve pneumatics.
l NOTE To save time, establishing comunications with other operators on t,he ASSD sound powered phone system can be performed simultaneously with the implementation f of other steps in this procedure. ,
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- 3. ESTABLISri sound powered phone comunications as follows:
- a. FLUG Y-jack into sound powered phone jack on RSDP labeled REMOTE SHUTDOWN TRAIN "B" (UNIT f 2) SOUNC POWERED PHONE CKT.
- b. PLUG Y-jack into sound powered phone jack on RSDP labeled TIE TO UNIT-1 REMOTE SHUTDOWN PANEL $0U2 POWERED PHONE.
- c. PLUG 8" sound powered phone jumper cord betwen Y-jacks installed in Steps 3.a and 3.b above.
- d. PLUG sound powered phone headset into 25' sound powered phone extension cord AND PLUG sound powered phone extension cord into Y jack installed in Step 3.4 above.
- e. MAN sound powered phone headset AND ESTA81.!$H comunications with sther Operators.
Unit 1 Shift Foreman Unit 2 Reactor Building MCC Operator Service Water Building Operator Emergency Switchgear Operatur bE-Diesel Generator Operator
- 4. OBSERVE RSDP indication for RCic system status THEN INFORM Shift Foreman of one of the following conditions.
- a. RCIC is Running
- b. RCIC is NOT Running AND turbine indicates Tripped.
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- c. RCIC is NOT Running AW turbine doe 3 NOT indicate Tripped. ,
l t j 5. E RCIC is running THEN PERFORM the following:
- a. ADJUST RCIC Flow Controller 2-E51-FIC-3325 setpoint tape as necessary to enintain Reactor Yessel level between 170" and ZW as indicated on 2-821-L1604BT. at RSDP.
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- b. WHEN informed by Reactor Building MCC Operator that the
, #! switch lineup for MCC 2XDB is Complete THEN '
l (1) INFORM Reactor Butiding *CC Operator that
- RCIC System is Running. -
1 (2) DIRECT Reactor Buildi::y MCC Operator to TRANSFER 2-E51-F007 AND 2-E51-F062 from ;
normal power supply To'"ASSD power supply per Step 3 of Section D.
NOTE 1 2-E51-F045 may have closed due to high reactor water level.
NOTE 2 2-E51-Y8 may have tripped closed on turbine overspeed. if this has occurred, the RCIC Turbine Trip lignt will NOT be i,1uminated and the valve will still indicate open at MCC 2XDP. RCIC Turbine Trip light will only be illumin ted if actuated by a RCIC Pump Suction Low Pressurr, and/or a RCIC AS. l
@' Turbine Exhaust Diaphragm High Pressure trip signal. The valve motor must be run fully closed to reset tne actuator to enable reopening the valve.
............................................**... 6<....**..e..................
CAUliON If the RCIC Turbine trips on an actual overspeed condition, the Turbine Trip and Throttle Valve. E51 V8. should not be reset untti RCIC flow is at minimum.
- 4. PLACE RCIC Flow Controller 2-E51-FIC-3325 Auto /Manuai selector switch in ' MAN" A@ potentiometer output at minimum.
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g b. WHEN informed by Reactor Building EC Operator that the bd;, switch lineup for MCC 2XDB is Complete THEt!
(1) INFORM Reactor Building EC Operator that the RCIC System is NOT Running.
(2) DIRECT Reactor Building EC Operate
- to PERFORM the following per Step 4 of Section D:
(a) CLOSE 2-E51-F045 (b) CLOSE 2-E51-V8 (c' OPEN 2-E51-F019 (d) RESET mechanical oversperd trip device Socally at Trip and Throttle Valve, 2 E51-Y8.
c.1 HEN informed by Reactor Building EC Operator that:
(1) 2-E51-F045 is Closed (2) 2 E51-Y8 is Closed R 8. l (3) 2-E51-F019 is Open Si' (4) Trip and Throttle Valve, 2-E51 V8, is Reset THEN DEPRESS RCIC Turbine Reset push button on RSDP.
- d. VERIFY RCIC Turbine Trip light on RSDP is Extinguished.
NOTE 3 2 E51-F007 and 2-E51-F062 may close due to spurious operations. The valves are transferred to their ASSD power supply to prevent spurious operations and to ensure that they are open.
- e. DIRECT Reactor Building MCC Operator to TRANSFER 2-E51-F007 and 2-E51-F062 frca normal power supply to AS$D power supply per Step 4.c of Section D.
- f. WHEN informed by Reactor Building E C Operator that M1-F007 AND 2 E51-F062 are Transferred from normal power supplyTo ASSD power supply Am WHEN power is available to EC 21D THEN DIRECT Reactor Building MCC Opotator to OPEN bs M1-F007 AND 2 E51-F062 per Step 4.d of Section D.
BSEP-0/ASSD-02 Page 21 of 202 Rev. O
- g. WHEN informed by Reactor Building MCC Operator that (O 2-E51-F062 andlevel 2-E51-F007 areonOpen, THEN OBSERVE reactor water indication a M1-L1-604BX at the Remote Shutdown Panel.
- h. WHEN reactor water level is < 200" as indicated on THE fDIRECT Reactor Building 2-B21-LI-604BX MCC Operator to OPEN 2-E T P78 AND then OPEN at RSDP, 2-E51-F045.
- 1. WHEN informed by Reactor Building MCC Operator that THEN VERIFY RCIC Flow M1-V8 increases and to 2-E51-F045 minimum as directed are Open,7REIC b Flow Controller 2-E51-FIC-3325 on RSDP.
- j. DIRECT Reactor Building MCC Operator to CLOSE 2-E51-F019.
l
- k. ADJUST RCIC Flow Controller 2-E51-FIC-3325 manual pot l as necessary to maintain reactor water level between i
170" and 200" as indicated on 2-B21-L1-604BX at RSDP.
- 1. INFORM Shift Foreman of RCIC System status.
- 7. WHEN directed by Shift Foreman, THEN COORDINATE with other *I operators to place the Suppression Pool in recirculation using fjf RHR Loop B as follows:
- a. DIRECT Reactor Building MCC Operator to OPEN 2-E11-F0288.
- b. WHEN informed by Reactor Bu'lding MCC Operator that 2-EIl-F028B is Open THEP DIRECT Emergency Switchgear Operator to STARI RHli Tt , 2B.
- c. WHEN informed by Emergency Switchgear Operator that RHR Puliip 2B is Running, THEN DIRECT Reactor Building MCC 6perator to Slowly TIIMITLE Open 2-E11-F048B to fill system and limit water hamer.
- d. WHEN informed by Reactor Building MCC Operator that MT1-F048B is Open, ,THEN DIRECT Reactor Building MCC Operator to T3ROTTLE Open 2-E11-F024B.
- e. WilEN RHR System B flow indicator 2-E11-F1-3338 on RSDP indicates approvimately 1000 gpm THEN DIRECT Reactor Building MCC Operator to STOP THROTTETNG open 2-E11-F0248.
- f. DIRECT Reactor Building MCC Operator to CLOSE 2-Ell-F007B.
b.V BSEP-0/ASSD-02 Page 22 of 202 Rev. 0 j
- g. WHEN informed by Reactor Building MCC Oprator that (6 2-E11-F007B is Closed, THEN DIRECT Reactor Building MCC Operator to THROTTLE Open 2-E11-F0248.
- h. WHEN RHR System B flow indicator 2-E11-FI-3338 on RSDP indicates 6000-7500 gpm, THEN DIRECT Reactor Building MCC Operator to STOP THROTETNG Open 2-E11-F024B.
J. WHEN informed by Reactor Building MCC Operator that the lineup for placing the Suppression Pool in recirculation using RHR Loop B is Complete, THEN INFORM Shift Foreman that the Suppression Pool is being recirculated using RHR Loop B.
NOTE The Unit 2 Shift Foreman and the Unit 2 Reactor Building MCC Operator will establish Service Water flow through the Loop B RHR heat exchanger.
- 8. WHEN directed by Shift Foreman, THEN START reactor depressurization and cooldown at greater than 1000 F/hr using SRV's and RCIC as follows: g $,
nr -
D.s a. IF any of the SRVs controlled from the RSDP fails to open when the control switch is placed in the OPEN position, THEN LEAVE the control switch in the OPEN position AND TNFORM the Shift Foreman.
NOTES When cycling SRVs, use sequence E, G, B to evenly distribute the heat load to the Suppression Pool.
To determine cooldown rate, obtain reactor coolant temperature using Temperature vs Pressure curve on Section "C" Table 1.
Than plot tempe3ture on Section "C" Table 2 for Temperature
- vs Time to derive the cooldown rate,
- b. OPEN as many SRVs as is necessary to achieve a cooldown rate greater than 100 0F/hr.
- c. PLOT cooldown rate on Section "C" Table 2.
- d. IF reactor water level approaches +70 inches during
~depressurization as indicated on 2-B21-L1-604BX at RSDP, THEN CLOSE SRVs at RSDP as necessary to taaintain wa+er level greater than +70 inches,
- s. v BSEP-0/AS50-02 Page 23 of 202 Rev. 0 A M'*
o NOTE 8 Do not transfer RCIC Suction from the -
l CST to the Suppression Pool if Suppression Pool temperature is greater than 140 0F.
! e. IF Suppression Pool level increases to -24" as i Tiidicated on 2-CAC-L1-3342 AND Suppression Pool water temperature is less than 14 M as indicated on point 7 l of 2-CAC-TR-778 at RSDP, THEN DIRECT Reactor Building MCC Operator to perform steps to TRANSFER RCIC suction from CST to Suppression Pool.
l 9. WHEN Reactor Pressure indicates < 125 psig on T-U2-PI-3332 at RSDP, THEN INFORM Shift Foreman.
- 10. WHEN directed by Shift Foreman to STOP Suppression Pool cooling, TRET DIRECT Reactor Building MCC Operator to C00RDINATC with Emergency Switchgear Operator to STOP Suppression Pool Cooling.
i
- 11. WHEN directed by Shift Foreman, THEN COORDINATE with Unit 2 Operators to PLACE RHR Loop B in shutdown Cooling Mode as follows: ad (t
- a. DIRECT Reactor Building MCC Operator to COMPLETE Steps 10.6 '1),' through 10.a (14) of Section "D" to PERFORM g initial valve lineup.
- b. WHEN informed by Reactor Building MCC Operator that l Steps 10.a (1) through 10.a (14) of Section "D" are l Completed, THEN DIRECT Emergency Switchgear Operator to ,
start RHR Pump 2B for Shutdown Cooling.
- c. WHEN informed by Emergency Switchgear Operator that RHR Pump 2B is Running THEN DIRECT Reactor Building MCC ,
l Operator to:
(1) PLACE the control switch in the OPEN positin for 2-E11-F048B AND (2) Imediately THROTTLE Open 2-E11-F017B Valve to establish approximately 1000 gpm flow rate.
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 closed.
- d. WHEN approximately 1000 gpm is indicated on RHR System 8 flow indicator 2-E11-FI-3338 at RSUP THEN DIRECT O'2 Reactor Building MCC Operator to STOP ThROTrLING Open 2-E11-F017B.
BSEP-0/ASSD-02 Page 24 of 202 Rev. O
- e. MAINTAIN approximately 1000 gpm flow through the RHR h system for 15 minutes to warm up the system piping.
CAUTION The maxirr. tan RHR total flow rate of 7500 gpm should not be exceeded during the shutdown cooling mode of operation to prevent damage to the RHR heat exchanger.
- f. DIRECT Reactor Building MCC Operator to THROTTLE Open 2-E11-F017B to establish 6000-7500 gpm flow rate.
- g. WHEN 6000 to 7500 gpm flow rate is indicated on RHR THEN System B flow indicator DIRECT Reactor 2-E11-FI-3338 Building MCC Operator to STOP at RSDP, TH T0TTl!NG Open 2-E11-F0178.
CC DECREASE cooldown rate as necessary, to achieve g approximately 500 F/hr cooldown rate.
NOTE Use temperature vs pressure curve on Table 1 of Section "C" to monitor reactor cooldown.
- 12. WHEN reactor pressure decreases to 75 psig as indicated on THEN INCREASE reactor water level to 200".
M as 2-PI-3332 indicated o., at2-B21-L RSDP, T W 4BX at RSDP.
- 13. DIRECT Reactor Butiding MCC Operator to CLOSE 2-E51-F045 to ST00 RCIC operation AND INFORM Unit 2 Shift Foreman that RCIC Syster.
operation is no longer required and RCIC is being shut down, i
b BSEP-0/ASSD-02 page 25 of 202 Rev. O
1
- 14. MONITOR reactor vessel cooldown asi 19 Su. tion "C" Table i AND
'CWI- ASSIST Shift Foreman as directed.
~ ~ ~ ~
i
- 15. WHEN Reactor Pressure has decreaseo tc 0 psig at indicated en M-PI-3332 at RSDP, THEN INFORM Sh' ft Foreman.
- 16. IF makeup water is needed to raise reactor water level while in TFiutdown Cooling "OR to DECREASE Suppression Pt.ol water level.
THEN PERFORM the S lowing:
- a. DIRECT Emergency Switchgear Operator to STOP RHR Pump 28.
- b. WHEN informed by Emergency Switchgear Operator th t kHG Pump 2B is Stopped, THEN DIRECT Reactor Building i CC Operator to (1) CLOSE 2-E11-F008 (2) CLOSE 2-E11-F006B (3) CLOSE 2-E11-F017B (4) CLOSE 2-E11-F047B cd a:
(5) CLOSE 2-E11-F0488
@ c. WHEN informed by Reactor Building HCC Operator that (1) 2-E11-F008 is Closed (2) 2-E11-F006B is Closed (3) 2-E11-F017B is Closed (4) 2-E11-F047G is Closed (5) 2-E11-F048B is Closed THEN LINE UP for LPCI injection f rom the Suppression .
Foot as follows:
(1) DIRECT Reactor Building NCC Operator to (a) PLAC2 breaker for 2-E11-F007B to "0N" position (b) OPEN 2-E11-F007B (c) OPEN 2-E11-F020B
. (d)OPEN2-E11-F004B BSEP-0/ ASS 0-02 Page 26 of 202 Rev. 0
22; (2) WHEN informed by Reactor Building MCC
& Operator that (a) Breake'* for 2-E11-F007B is in the "0N" rosition (b) 2-E11 F007B is Open (c) 2-E11-F0208 is Open (d) 2-E11-F004B is Open THEN DIRECT Emergency Switchgear Operator to ITANY RHR Pump 2B, (3) WHEN informed by Emergency Switchgear Operator that RHR Pump 2B is Running THEN (a) DIRECT Reactor Building MCC 03erator to OPEN 2-E11-F0488 AND T'HROTTLE Open 2-E11-F0178.
(b) OBSERVE reactor vessel water level ~7 increasing on 2-821-LI-604BX at 00 RSDP. OC
(.9h
" (c) WHEN desired rate of water level increase is achieved THEN DIRECT Reactor Buildirs MCC Operator to STOP THROTTLING Open 2-E11-F0178.
(d) DIRECT Reactor Building MCC Operator to CLOSE 2-E11-F0078.
- 17. WHEN reactor water level has been raised using LPCI to 200" as -
indicated on 2-821-LI-604BX at R$0P, THEN PERFORM the following to return to Shutdown Cooling Mode, i
- a. DIRECT Emergency Switchgear Operator to STOP RHR '
Pump 28.
t I
B.
l
<J' BSEP-0/ASSD-02 Page 27 of 202 Rev. 0 l l
g, > b. WHEN informed by Emergency Switchgear Operator that RHR d_ Pump 2B is Stopped. THEN, DIRECT Reactor Building MCC Operator to (1) CLOSE 2-E11-F0178 (2) CLOSE 2-E11-F048B (3) CLOSE 2-011-F004B (4) CLOSE 2-E11-F0208 (5) PLACE breaker for 2-E11-F007B to "0FF" position
- c. WHEN informed by Reactor Building MCC Operator that (1) 2-E11-F0178 is Closed (2) 2-E11-F048B is Closed (3) 2-E11-F004B is Closed (4) 2-E11-F0208 is Closed g (b) Breaker for 2-E11-F007B is in "0FF" position. "
h THEN DIRECT Reactor Building MCC Operator to (1)OPEN2-E11-F006B (2)SlowlyOPEN2-E11-F008
- d. WHEN informed by Reactor Building MCC Operator that (1) 2-E11-F006B is Open
, (2) 2-E11-F008 is Open THEN DIRECT Emergency Switchgear Operator to START RHR Pump 28.
- e. WHEN informed by Emergency Switchgear Operator that RHR Pump 2B is Running, THEN Imediately DIRECT Reactor Building MCC Operator to:
(1) PLACE the contro'l switch in the OPEN position for 2-E11-F0488 AND (2) Imediately THROTTLE Open 2-E11-F0178.
- f. WHEN 6000-7500 gpm flow rate is achieved as indicated on RHR System B flow indicator 2-E11-FI-3338 at RSDP,
@ THEN DIRECT Reactor Building MCC Operator to STOP TM6TTLING Open 2-E11-F0178.
BSEP-0/ ASS 0-02 Page 28 of 202 Rev. O
SECTION "C"
{
Q'; TABLE 1 soO o o 550 .-----------
a .. .. .
i ea-n
+ -----
r--- ----
-+ --- -y ---
- y -- -- -
.- , - 2, n; ma ----.
- --- --- - -- --- ,a 500 .
l _.
.~ "~
- es aC 450 mr
.a e-as .dr ~
g 2P 2 400 f e ur
,,,, E
- / K2 t&s /
5 350
.a
- e 7 '
2 P. 3 0 0 ,
v 1
/ '
LM y EE 5 250 'J 2 El Q Et El I t t 200
O 100 200 300 400 500 600 700 800 900 1,000 REACTOR PRISSURZ (PSIG)
.c k a BSEP-0/ ASS 0-02 Page 29 of 202 Rev. 0
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S Q '
- s N e Ed /
~Q vs
/
a y / - RL
,? > ) i,,
c .. g
% / >l
' N 1 f r -
. o O
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- b. .
g SECTI:1 "0" UNIT 2 REACTOR BUILDING MCC OPERATOR ACTIONS
- 1. REPORT to Reactor Building MCC 2XB AND ESTABLISH comunications with the RSDP Operator using sound powered phone jack labeled REMOTE SHUTDOWN TRAIN 'B' (UNIT #2) SOUW POWERED PHONE CKT located on MCC 2XB Compartment D3Z.
l
- 2. PERFORM lineup of items on the following table as directed by instructions at the top of the table.
[
[
I i
Q R e,I ,
f' I
L l
i r
l l
b :
BSEP-OfASSD-02 Page 31 of 202 Rev. O
( 713 To perform lineup of the items listed on this table, do the following steps as W directed.
For items that have two-position or three-position maintained contact control switches:
PLACE the control switch to the position indicated on the table, to ensure the item will line up or remain lined up to the position indicated on the table THEN PLACE the Normal / Local switch to "LOCAL".
For items that have thr,te-position spring return to "NEUT" or "0FF" control switches (indicated by an *):
PLACE the Normal / Local switch to "LOCAL" THEN OPERATE the control switch as required to line up the item to the position indicated on the table.
NOTE: Items indicated with an (*) must be verified in position or be placed in position using control switches when power is available to the MCC.
CONTROL NORMAL / LOCAL /
CDMPT/ EQUIPMENT SWT/ ISOLATE S'4T VLV P05 POS Qj CKT DESCRIPTION NUMBER LOCATION MCC-2XDB Reactor Building El 20' South B50 Shutdown Cooling Outboard 2-E11-F008
- CLOSED LOCAL Suction Isolation Valve B35 RCIC Barometric condenser 2-E51-C002 START LOCAL Vacuum Pump B36 RCIC Barometric Condenser 2-E51-C002 START LOCAL Condensate Pump B37 RCIC Turbine Trip & Throttle 2-E51-V8
- OPEN LOCAL Viv B38 RCIC Condensate Storage Tank 2-E51-F010
- OPEN LOCAL Suction Valve
-
- Control switches for these items are spring returned to "NElfi" or "0FF".
C: .
ESEP-0/ASSD-02 Page 32 of 202 Rev. O I
h WMPT/ EQUIPMENT CONTROL NORMAL / LOCAL /
SWT/ ISOLATE SWT CKT DESCRIPTION NUMBER VLV POS POS B39 RCIC Cooling Water Supply 2-E51-F046
- OPEN LOCAL Valve B40 RCIC Pump Discharge Valve 2-E51-F012
- OPEN LOCAL B41 RCIC Injection Valve 2-E51-F013
- OPEN LOCAL B42 RCIC Bypass to Condensate 2-E51-F022
- CLOSED LOCAL Storage Tank Valve B43 RCIC Steam Supply Outboard 2-E51-F008 #* OPEN LOCAL Isolation Valve i If 2-E51-F008 is found closed on initial lineup of table, then throttle open valve for approximately 10 seconds. Wait approximately 60 seconds for RCIC steam line to repressurize then fully open valve.
B44 RCIC Steam Supply to Turbine 2-E51-F045
- OPEN LOCAL M.
B45 RCIC Suppression Pool Suction 2-E51-F031
- CLOSED LOCAL g, Valve B46 RCIC Suppression Pool Suction 2-E51-F029
- CLOSED LOCAL Valve B47 RCIC Hinimum Flow Bypass to 2-E51-F019
- CLOSED LOCAL Suppression Pool Valve B48 RWCU Inlet Outboard Throttle 2-G31-F004
- CLOSED LOCAL
! solation Valve B52 Main Steam Line Outboard 2-B21-F019
- CLOSED LOCAL Drain Isolation Valve
- Control switches for these items are spring returned to "NEUT" or "0FF".
WHEN the switch lineup for HCC 2XDB is Complete, THEN INFORM the E DF Operator.
l C_ .
BSEP-0/ ASS 0-02 Page 33 of 202 Rev. 0
1
@ COMPT / EQUIPMENT CONTROL NORMAL / LOCAL /
SWT/ ISOLATE SWT !
CKT DESCRIPTION NUMBER VLV POS POS !
TORTTUR MCC-2XB Reactor Building El. 20' South BV9 Recirculation Pump 2B 2-B32-F023B
- CLOSED LOCAL Suction Valve (2 switches)
BV9 Vent RHR HX Area 2-B-FCU-RB START LOCAL Cooling Fan DN6 RHR Pump 29 and 2D Supp. Pool 2-E11-F020B OPEN LOCAL Suction Valve DP2 Nuclear Service Water To 2-SW-V117
- OPEN LOCAL Vital Header Inboard Isolation Valve DN9 RHR HX B Service Water 2-E11-F002B
- OPEN LOCAL Discharge Valve p DN2 RHR Service Water 2-E11-F073
- CLOSED LOCAL fu r Outboard Injection Valve Q2 DM1 RHR Service Water b',ooster 2-SW-V105
- OPEN LOCAL Pumps B and D Inboard Isolation Valve
. DM6 Service Water To RHR Service 2-SW-V102
- CLOSED LOCAL Water Header Cross-Tie Valve DL8 Drywell Spray Outboard 2-E11-F016B CLOSED LOCAL
! solation Valve Dit2 Suppression Pool Cooling 2-E11-F0248
- CLOSED LOCAL Isolation Valve DM4 Suppression Pool Spray 2-E11-F0278 CLOSED LOCAL Isolation Valve DN1 RHR HX B Service Header 2-E11-POV-
- CLOSED LOCAL Outlet Valve F068B DL1 RHR Pump 2B Shutdown Cooling 2-E11-F006B CLOSED LOCAL Suction Valve
- Control switches for these items are spring returned to "NEUT" or "0FF".
O'_
BSEP 0/ASSD-02 Page 34 of 202 Rev. O I
(
l CONTROL NORMAL / LOCAL /
bsi COMPT / EQUIPMENT SWT/ ISOLATE /SWT CKT DESCRIPTION NUMBER VLV POS POS DL2 RHR Pump 2D Shutdown Cooling 2-E11-F006J CLOSED LOCAL Suction Valve DL5 Turbine Exhaust Vacuum 2-E51-F066
- OPEN LOCAL Breaker Valve ,
DK9 RHR T '.7 2B Supprescion Pool 2-E11-F0040 OPEN LOCAL Suetica Valve DL3 Minimum Flow Bypass Valve 2-E11-F007B
- OPEN LOCAL DLO RHR Pump 2D Suppression Pool 2-E11-F004D OPEN LOCAL Suction Valve DX8 RHR HX 2B Outlet Valve 2-E11-F003B OPEN LOCAL DM7 RHR HX 2B Inlet Valve 2-E11-F0478 CLOSED LOCAL DM8 RHR HX 2B Bypass Valve 2-E11-F048B CLOSED LOCAL N D3Y ! solation Switch 2-D3Y-IS1 2-CAC-SV - N/A ISOLATE g
for Viv 2-CAC-SV-1218C 1218C D3Y lsolation Switch 2-D3Y-IS2 2-CAC-SV- N/A ISOLATE for Viv 2-CAC-SV-122bc 1225C D3Y Isolation Switch 2-D3Y-IS3 2-CAC-SV- N/A ISOLATE for Viv 2-CAC-SV-4345 4345 LOCATION HCC-2XB-2 Reactor Building El 20' South ,
DL9 LPCI Outboard Injection Viv 2-E11-F017B OPEN LOCAL CL7 LPCI Inboard Injection Viv 2-E11-F015B
- CLOSED LOCAL DMS Suppression Pool Discharge 2-E11-F028B CLOSED LOCAL Isolation Valve
- Control switches for these items are spring returned to "NEUT" or "0FF".
c.
t _
BSEP-0/ASSD-02 Page 35 of 202 Rev. O
- 3. IF informed by RSDP Operator that RCIC is Running, THEN when
, CM.
~JTrected by RSDP Operator TRANSFER 2-E51-F007 AND 2 ST-F062 from normal power supply to ASSD power supply as follows:
- a. PLACE the circuit breaker control switch in the ON - '
position for RCIC Steam Supply Line Isol. Viv.
2-E51-F007 ASSD Feed at MCC 2XD Compartment DY1. ,
(Looking at the front of the panel at the bottom, it is the fourth compartment in from the right side et the bottom.)
- b. PLACE the circuit breaker control switch in the ON position for RCIC Turb. 'Vac Breaker Viv. 2-E51-FMI2 ASSD Feed at MCC 2XD Compartment DW2 (Looking at the front of the panel at the bottom, it is located four compartments in from the right side and is the second compartment up from the bottom.)
- c. PLACE the circuit breaker control switch in the OFF position for Steam Supply Inboard Isolation Valv'e7 2-E51-F007, at MCC 2XC Compartment DS4 (Looking at the front of the panel at the bottom, it T3 is located four compartments in from the left side and
- g. is the third compartment up from the bottom.)
- d. PLACE the circuit breaker control switch in the 0FF position for Turbine Exhaust Vacuum Breaker Valve, 2-E51-F062, at MOC 2XA Compartment DE4 (Looking at the bottom of the side of the panel that is facing South, it is the third compartment in from the left side at the botics)
- e. VERIFY 2-E51-F007 AND 2-E51-F062 are Open by observing valve open indicating lights illuminated at MCC 2XD AND INFORM RSDP Operator that 2-E51-F007 AND T-T51-F062 are transferred from normal power supply to ASSD power supply,
- f. COHpLETE the alignment of switches on table per Step 2.
- g. WHEN alignment of switches on the MCCs is Complete, TfiEY INFORM Unit 2 Shift Forerr :n. l l
bs .
I BSEP-0/ASSD-02 Page 3G of 202 Rev. O i
i
~ "' ""*d "S " "' ' '" " " ' '"""'"' '"'"
CM FEkFORM the following:
- a. WHEN directed by RSDP Operator, THEN (1) CLOSE RCIC Turbine Steam Supply Valve, 2-E51-F045, at MCC 2XDB Compartment B44 (2) CLOSE RCIC Turbine Trip And Throttle Valve, 2-E51-V8, at MCC 2XDB Cogartment B37.
(3) OPEN RCIC Minimum Flow Bypass To Suppression Pool Valve, 2-E51-F019, at MCC 2XDB Compartment B47 (4) RESET mechanical overspeed trip device locally at Trip and Throttle Valve, 2.!51-V8 as follows:
(a) Depending on body position, either PUSH 0_R, R PULL against spring pressure the emergency connection rod in the direction of the Turbine Trip and Throttii Valve, E51-Y8, (approximately one inch).
g
{?;- (b) OBSERVE the tappet and ball assembly, which resembles a plunger, drop into place.
(c) If the tappet and ball assembly does not drop in place, Lightly DEPRESS the assembly.
(d) RELEASE the emergency connection rod.
, b. INFORM RSDP Operator that:
(1) 2-E51-F045 is Closed.
(2) 2-E51-V8 is Closed.
(3) 2-E51-F019 is Open. .
(4) Hechanical overspeed trip device for Trip and Throttle Valve, 2-E51-V8 is Reset.
C. .
ESEP-0/ASSD-02 Page 37 of 202 Rev. O
gm c. WHEN directed by RSDP Operator THEN TRANSFER
@ 2-Eol-F007 AND 2-E51-F062 f rom normal power supply to ASSD power supply as follows:
(1) PLACE the circuit breaker control switch in the ON position for RCIC Steam Supply Line Iso 1 D iv. 2-E51-F007 ASSD Feed at MCC 2XD Cornpartment DY1.
(Looking at the front of the panel at the bottom, it is the fourth compartment in from the right side at the bottom.)
(2) PLACE the circuit breaker control switch in the ON Viv.7 position E51-F062forASSD RCIC Turb.
Feed Vac2XD at MCC Breaker Compartment DW2.
(Looking at the front of the panel at the bottom, it is located four compartments in from the right side and is the $3cond compartment up from the bottom.)
(3) PLACE the circuit breaker control switch in the OFF position for Steam Supply Inboard 3)
Isolation Valve, 2-E51-F007, at HCC 2XC G
w
. Compartment DS4 (Looking at the front of the panel at the bottom, it is located four compartments in from the left side and is the third compartment up from the bottom.)
(4) PLACE the circuit breaker control switch in the OFF position for Turbine Exhaust Vacuum Bresker Valve, 2-E51-F062, at MCC 2XA Compartment DE4 (Looking at the bottom of the side of the panel that is facing South, it is the third compartment in from the left side at the bottom.)
l (5) INFORH LDP Operator that 2-E51-F007 AND 2-E51-F062 have been transferred f rom normal power supply to ASSD power supply.
(L .
BSEP-0/ASSD-02 Page 38 of 202 Rev. O
- d. WHEN directed by RSDP Operator AND when power is h, available to HCC 2XD, THEN OPEN 2-E51-F007 AND 2-E51-F062 as follows:
(1) To repressurize RCIC steam line PLACE the Close./Off/Open Keylock Switch in the OPEN position for 10 seconds THEN PLACE the Close/Off/Open Keylock switch to the OFF position for RCIC Steam Supply Line Isol.
V1 . 2-E51-F007 ASSD Feed at MCC 2XD Compartment DY1.
(Looking at the front of the panel at the bottom, it is the fourth compartment in from the right side at the bottom.)
(2) After 60 seconds, PLACE the Close/Off/Open Keylock Switch in the OPEN position for RCIC Steam Supply Line Isol. Viv.
2-E51-F007 ASSD Feed at HCC 2XD Compartment DY1 until valve is Full Open.
(3) PLACE the Close/Off/Open Keylock Switch in the OPEN position for RCIC Turb. Vac .
Breaker Viv. 2-E51-F062 ASSD Feed at HCC 2XD, Compartment DV2 until valve is Open.
(Looking at the front of the panel at the bottom, it is located four compartments in from the right side and is the second compartment up from the bottom.)
(4) INFORM RSDP Operator that 2-E51-F007 AND_
2-E51-F062 are Open.
- e. WHEN directed Ly RSDP Operator THEN (1) OPEN RCIC Turbine Trip And Throttle Valve, 2-E51-V8, at HCC 2XDB Compartment B37 (2) OPEN RCIC Turbine Steam Supply Valve, l 2-E51-F045, at MCC 2XDB Compartment 844
- f. INFORM RSDP Operator that 2-E51-V8 ~~AND 2-E51-F045 are Open.
(./
BSEP-0/ASSD-02 Page 39 of 202 Rev. O
- g. WHEN directed by RSDP Operator, THEN CLOSE RCIC
- h. TUnimum Flow Bypass To Suppression Pool Valve, 2-E51-F019, at MCC 2XDB Compartment B47.
- h. INFORM RSDP Operator that 2-E51-F019 is Closed.
- i. COMPLETE the alignment of switches on table per Step 2.
- 5. WHEN the switch alignment of table in Step 2 is COMPLETE THEN TERTORM the following to usist in 41 acing Suppression PooTTri recirculation using RHR Loop 6.
- a. WHEN directed by RSDP Operator THEN OPEN Suppression Fo3T Discharge Isolation Valve,TT11-F028B, at MCC 2XB-2 Compartment DMS.
- b. INFORM RSDP Operator that 2-E11-F028B is Open.
- c. WHEN directed by RSDP Operator, THEN Slowly THROTTLE Open RHR HX 2B Bypass Valve, 2-ETF-T04SB, at MCC 2XB Compartment DMB. Rs.
(p"i d. WHEN RHR HX 2B Bypass Valve, 2-E11-F048B, is fully Open THEN INFORM RSDP Operator.
~
- e. WHEN directed by RSDP Operator, THEN THROTTLE Opon Suppression y ool Cooling Isolation Valve, 2-E11-F0248, at MCC 2XB Compartmer.t D N to establish approximately 1000 gpm flow rate.
- f. WHEN directed by RSDP Operator,_THEN STOP THROTTLING Open Suppression Pool Cooling Isolation Valve, 2-E11-F0248, at MCC 2XB Compartment DK.
- g. WHEN dir%:ed by RSDP Operator, THEN CLOSE Minimum Tils Bypass Valve, 2-E11-F0078, at MCC 2XB Compartment DL3.
- h. WHEN 2-E11-F007B is Closed, THEN INFORM RSDP Operator.
- i. WHEN directed by RSDP Operator,_THEN THROTTLE Open Suppression Pool Isolation Valve, 2-E11-F024B, at MCC 2XB Compartment DE to establish 6000-7500 gpm flow rate.
- j. W THEN STOP THROTTLING
_Open HENSuppression directed by Pool RSDP Operator, VaWe, 2-E11-F0248, at Isolation MCC 2X3 Compartment DM.
g, A.
BSEP-0/ASSD-02 Page 40 of 202 Rev. O
- k. WHEN directed by RSDP Operator, THEN COMPLETE the g 751 Towing steps to establish RHR TTEw through R m Heat Exchanger 28.
(1) OPEN RHR HX 2B Inlet Yalve, 2-E11-F0478, at MCC 2XB Compartment DM7.
(2) CLOSE RHR HX 2B Bypass Valve, 2-E11-F0488, at MCC 2XB Compartment DH8.
- 1. INFORM RSDP Operator that the lineup to place the Suppression Pool in recirculation using RHR Loop B is !
Complete.
- 6. WHEN directed by Shift Foreman to CLOSE 2-SW-Y106 AND 2-SW-V118 THlT STOP Service Water flow through RBCCW heat exchangers AND Toop of the Vital Service Water header by performing the l following
- a. PLACE the circuit breaker control switch in the OFF
- position for Nuclear Header to RBCCW Heat Exchanger l 1 solation Viv, 2-$W-V106, at MCC 2XA Compartment DE3. l,
- b. PLACE the circuit breaker control switch in the OFF position for Vital Service Water Divisional Tie YaTve, 2-SW-V118, at MCC 2XA Compartment DE1. M
'kh c. VERIFY Closed OR Manually CLOSE Nuclear Header to RBCCW Heat ExcTanger Isolation Valve, 2-SW-V106.
- d. VERIFY Closed OR 1Rnua11y CLOSE Vital Service Water l Divisional TieTalve, 2-SW-V118.
- e. INF0P.M Shift Foreman that 2-SW-V106 AND 2-SW-V118 are L Closed.
7 WHEN directed by Shift Foreman, THEN ESTABLISH service water ,
TT6w through RHR Heat Exchanger H as follows:
- a. DIRECT Service Water Building Operator to INFORM when .
Unit 2 Nuclear Header Pressure decreases to 40 psig. ;
- c. WHFN informed by Service Water Building Operater that !
Nuclear Header pressure has decreased to 40 psig THEN i
- STOP THROTTLING Open RHR HX B Service Header Outlet i Valve, 2-E11-PDV-F0688, at MCC 2XB Compartment. DN1. !
- d. INFORM Shift Foreman that Service Water flow has been established through RHR Heat Exchanger 28. ,
<w En l l
BSEP-0/ASSD-02 Page 41 of 202 Rev. 0 l l
t
,.. 8. IF directed by RSDP Operator, THEN TRANSFER RCIC Suction from Q;td 1TT to Suppression Pool as follows:
- c. CLOSE RCIC Condensate Storage Tank L.; tion Valve, 2-ES1-F010, at HCC 2XDB Compartment B38,
- 9. WHEN directed by RSDP Operator, THEN STOP Suppression Pool Cooling as follows:
- a. OPEN Hinimum Flow Bypass Valve, 2-E11-F007B, at HCC 2XB Compartment DL3.
- b. CLOSE Suppression Pool Cooling Isolation Valve, 2-E'41-F024B, at MCC 2XB Compartment DH2,
- c. DIRECT Emergency Switchgear Operator to STOP RhR Pump 28.
T
- d. WHEN informed by Emergency Switchgear Operator that RHR Pump 2B is Stopped THEN CLOSE Minimum Flow Bypass 4
Valve, 2-E11-F0078, at HlTTXB Compartment DL3.
- g. INFORM RSDP Operator that Suppression Pool Cooling is Stopped.
b _. .
BSEP-0/ASSD 02 Page 42 of 202 Rev. 0
q V
- 10. PERFORM the following to assist in placing RHR Loop B in Shutdown Cooling.
- a. WHEN directed by RSDP Operator, THEN CONLETE Steps 10.a(1) through 10.a(14) of Section "D" as follows:
(1) CLOFE RHR Pump 28 and 2D Supp. Pool Suction Yalve, 2-E11-F0208, at MCC 2XB Compartment DN6.
(2) CLOSE RHR Pump 2B Suppression Pool Suction Valve, 2-E11-F004B, at MCC 2XB Compartment DK9.
(3) CLOSE RHR Pump 20 Suppression Pool Suction Valve, 2-E11-F0040, a MCC 2XB Compartment DLO.
'(4) PLACE the circuit breaker control switch in the ON position AND OPEN RHR Pum ShutEwn Cooling Tiiction Valve, p 28 2-E11-F006B, at MCC 2XB Compartment DL1.
- (5) PLACE the circuit breaker control switch in 80 the ON position AND OPEN RHR Pump 2D QC ShutWwn Cooling Tiiction Valve, 2-E11-F006D, at MCC 2XB Compartment OL2.
(6) PLACE the circuit breaker control switch in the ON switE, position OPEN RHRANDSuction using Isolation keylock Valve, control 2-E11-F009, at MCC 2XD Compartment DX5.
(Lookingatthebottomofthefrontofthe panel, it is located three compartments in
- from the right side and is the third l
compartment up from the bottom.)
(7) PLACE the circuit break 9r control switch in the ON position AND Slowly THROTTLE Open ShutWwn Cooling 0iitboard Suction isolation Valve 2-E11-F008, at MCC 2XDB Compartment B50 until valve is Full Open.
(8) VERIFY Closed RH.R HX 2B Inlet Valve, 2-E11-F0478, at MCC 2XS Compartment DM7.
l (9) VERIFY Open RHR HX 2B Outlet Valve, l
2-E11-F0038, at MCC 2XB Compartment Dra.
(10) YERIFY Closed Minimum Flow Bypass Valve, 2-E11-F0078, 40 MCC 2XB Compartment OL3.
i@)
BSEP-0/ASSD-02 Page 43 of 202 Rev. O i
,p:,. (11) PLACE the circuit breaker control switch in W the OFF position for Minimum Flow Bypass Valve, 2-E11-F007B, at MCC 2XB Compartment DL3.
(12) CLOSE LPCI Outboard Injection Viv, 2-E11-F017B, at MCC 2XB-2 Compartment OL9.
(13) OPEN LPCI Inboard Injection Viv, 2-E11-F015B, at MCC 2XB-2 Compartment DL7.
(14) INFORM RSDP Operator that Steps 10.a(1) through 10.a(14) of Section "D" are Completed.
- b. WHEN directed by RSDP Operator, THEN:
(1) PLACE the control switch in the OPEN position for RHR HX 2B Bypass Valve, 2-E11-F048, at MCC 2XB Compartment DMB AND (2) Imediately THROTTLE Open LPCI Outboard 7 Injection Valve, 2-E11-F0178, at MCC 2XB-2 Compartment DL9 to establish approximately 1000 gpm flow rate.
Cl4
- c. WHEN directed by RSOP Operator, THEN STOP THROTTLING open LPCI Outboard Injection Valve, 2-E11-F0178, at MCC 2XB-2 Compartment OL9.
- d. WHEN directed by RSDP Operator, THEN THROTTLE Open ITCT Outboard Injection Valve, 2W-F017B, at MCC 2XB-2 Compartment OL9 to establish 6000-7500 gpm flow rate.
- e. WHEN directed by RSDP Operator, THEN STOP THROTTLING Open LPCI Outboard injection Valve, 2-E11-F0178, at MCC 2XB-2 Compartment DL9.
- f. When directed by RSDP Operator THEN ESTABLISH RHR flow through RHR Heat Exchanger 2B by performing the following.
_(1) OPEN RHR HX 2B Inlet Valve, 2-E11-F0478, at MCC 2XB Compartment DM7.
(2) VERIFY Open RHR HX 2B Outlet Valve, 2-E11-F003B, at MCC 2XB Compartment OK8.
- g. IF directed by RSDP Operator to increase cooldown rate, THEN THROTTLE Closed RHA HX 2B Bypass Valve, 2-E11-TUTiB, at MCC 2XB Compertment DM3 as directed by bn R50P Operator.
BSEP-O'AS50-02 Page 44 of E02 Rev. 0
a h. IF directed by RSDP Operator to decrease cooldown 7 Tate, THEN PERFORM one or more of the following actions as directed by the RSDP Operator. ;
(1) THROTTLE Open RHR HX 2B Bypass Valve, 2-E11-F048B, at MCC 2XB Compartment DMB (2) THROITLE Closed RHR HX B Service Header Outlet Valve, 2-E11-POV-F0688, at MCC 2XB Compartment DN1.
r
- 11. WHEN directed by RSDP Operator, THEN CLOSE RCIC Steam Supply to Turliine, 2-E51-F045, at MCC 2XDB Compartment B44,
- 12. IF makeup water is needed to raise reactor water level while in liiutdown Cooling, THEN PERFORM the following:
. WHEN directed by RSDP Operator THEN (1) CLOSE Shutdown Cooling Outboard Suction Isolation Valve, 2-E11-F008, at MCC 2XDB i-Compartment B50. --
e l (2) CLOSE RHR Pump 28 Shutdown Cooling Suction e Valve, 2-E11-F006B, at MCC 2XB Compartment OL1.
($ (3) CLOSE LPCI Outboard Injection Viv, 2-E11-F017B at MCC 2XB-2 Compartment OL9.
(4) ".0SE RHR ltX 2B Inlet Valve, 2-E11-F0478, at MCC 2XB Compartment DM7 (5) CLOSE RHR HX ?B Bypass Valve, 2-E11-F0488, i at MCC 2XB Compartment Ote. -
I
- b. INFORM RSDP Operator that j (1) 2-E11-F008 is Closed.
(2) 2-E11-F006B is Closed. l (3) 2-E11-F017B is Closed.
l (+) 2-E11-F047B is Closed. L l (5) 2-E11-F0488 is Closed. l l
i i
b ,
i BSEP 0/ASSD-02 Page 45 of 202 Rev. O !
t L
g c. WHEN directed by RSDP Operator THEN (1) PLACE circuit breaker control switch to the ON position for Minimum Flow Bypass Valve, FE11-F007B, at MCC 2XB Compartment DL3.
(2) OPEN Minimum Flow Bypass Valve, 2-E11-F007B, at MCC 2XB Comp trtment DL3.
(3) OPEN RHR Pump 2B and 20 Supp. Pool Suction Yalve, 2-E11-F0208, at MCC 273 Compartment D,46.
(4) OPEN RHR Pump 2B Suppression Pool Suction Valve, 2-E11-F0048, at MCC 2XB Compartment DK9.
- d. INFORM RSDP Operator that (1) Breaker for 2-E11-F0078 is in the ON position. -
cQ (2) 2-E11-F007B is Open. cc:
(3) 2-E11-F020B is Open.
({j') (4) 2-E11-F004B is Open.
! e. WHEN directed by RSDP Operator THEN:
3 (1) OPEN RHR HX 2B Bypass Valve, 2-E11-F0488,
) at MCC 2XB Compartment DMB.
i (2) THROTTLE Open LPCI Outboard Injection Viv, 2-E11-F0178 at MCC 2XB-2 Compartment DL9. *
't i
- f. WHEN directed by RSDP Operator THEN STOP THROTTLING i Open LPCI Outboard Injection Viv, 2-E11-F017B at MCC
- 2XB 2 Compartment DL7.
- g. WHEN directed by RSDP Operator THEN CLOSi Minimum Flow Bypass Valve, 2-E11-F007B, at MU,'7XB Compartment DL3.
- 13. To return to Shutdown Cooling Mode from reactor vessel makeup, PERFORM the followingt
- a. WHEN directed by RSDP Operator THEN (1) CLOSE LPCI Outboard Injection Viv, 2-E11 F0178, at MCC 2XB-2 Compartment DL9.
(2) CLOSE RHR HX 2B Bypass Valve, 2-E11-F048B, (n., at MCC 2XB Compartment DMB.
BSEP-0/ASSD-02 Page 46 of 202 Rev. 0
(4) CLOSE RHR Pump 28 and 2D Supp. Pool Suction Valve, 2-E11-F020B, at MCC 2XB Compartment DN6.
(5) PLACE the circuit breaker control switch in the OFF position for Minimum Flow Bypass Valve, 2-E11-F0078, at MCC 2XB Compartment DL3.
_ b. INFOLM RSDP Operator that (1) 2-E11-F0178 is closed.
(2) 2-E11-F0488 is Closed.
(3) 2-E11-F004B is Closed.
(4) 2 E11-F020B is Closed.
(5) Bre. er for 2-E11-F007B is in the OFF position,
- c. WHEN directed by RSDP Operator THEN N
Q (1) OPEN RHR Pump 2B Shutdown Cooling Suction Valve, 2-E11-F006B, at MCC 2XB Compartment f DL1. Y (2) Slowly OPEN Shutdown Cooling Outboard Suction Isolation Valve, 2-E11-F008, at MCC 2XDB Compartment B50.
- d. IrlFORM RSDP Operator that '
_ (1) 2-E11-F006B is Open.
(2) 2-E11-F008 is Open.
, , e. WHEN directed by RSDP Operatte THEN:
(1) PLACE the control switch in the OPEN position for RHR HX 2B Bypass Valve, 2-E11-F0488, at MCC 2XB Compartment DM8 AND (2) Imediately THROTTLE Open LPCI Outboerd Injection Valve, 2-E11-F0178, at MCC 8 8 2 Compartment OL9.
- f. WHEN directed by RSDP Operator THEN STOP THROTTLING
BSEP-0/ASSD 02 Page 47 of 202 Rev. 0
l g RESTORING POWER TO REACTOR BUILDING
'd MCC 2XB The purpose of the following steps is to restore power to Reactor Building MCC 2XB in the event that an electrical f ault causes the feeder breaker at 480V Substation E8 Compartment A02 to trip.
- 1. IF power is NOT available 'co Reactor Building MCC 2XB as Tetermined by loss of indicating lights and control for items l powered from ReAc, tor Bui'. ding MCC 2XB THEN DIRECT Diesel l Generator Operas ir to CONFIRM the following
- a. 480V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC 2XB at Compartment A02 is Tripped.
- 2. WHEN Diesel Generator Operator CONFIRMS that
- a. 480V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC 2XB at Compartment A02 is Tripped, THEN OPEN the following breakers on Reactor Building MCC 2XB.
RE EA Compartment i Number Component Description BN9 Primary Containment Atmosphere Radiation Monitor, 2-CAC-AT-1260, Circuit Breaker EF5 Reactor Suilding Personnel Decontamination Room l Hot Water Heator Circuit Breaker i
DP9 TBCCW HX Service Water Hoader Inboard Isolation Valve, 2-SW-Y3, Circuit Breaker I
DP8 Reactor Building-Off Gas Drain Tank Pump B, l 2-G16-C0408. Circuit Breaker i
DP7 Vent RHR HX Area Cooling Fan, 28-FCU RB, 1
Circuit Breaker l
i I
L
- (E I < i .
.s,' ,
BSEP-0/A350 02 Pago 48 of 202 Aav. 0 ,
l g 2. (Cont'd) -
Compartment Num>er Component Description DP3 Shutdown Cooling Inboard Suction Isolation Valre, 2-E11-F009, Circuit Breaker DK1 Recirculation Pump 28 Suction Valve, ,
2-B32-F023B, Circuit Breaker i DN3 RHR SW Inboard Injection Valve, 2-E11-F075, I Circuit Breaker ,
DP1 Recirculation Pump 2B Seal Water Injection Valve, 2-B32-Y30, Circuit Breaker DN6 RHR Pung 28 8 2D Suppression Pal Suction Valve, 2-E11-F0208, Circuit Breaker DP2 Nuclear Service Water To Vital Header Inboard i Isolation Valve, 2-SW-Y117, Circuit Breaker '
DN9 RHR HX B Service Water Discharge Valve, g*
@(
w, 2-E11-F002B, Circuit Breaker UN2 Rm SW Outboard Injection Yalve, 2-E11-F073, Circuit Breaker DH1 Rm Service Water Booster Pumps B And D Inboard !
Isolation Valve, 2-SW-Y105, Circuit Breaker DH6 Service Water To RHR Service Water Header I Cross-tie Valve, 2-$W-V102, Circuit Braaker ,
DL8 Drywell Spray Outboard Isolation Yalve, l' 2-E11-F0168, Circuit Breaker DH0 Drywell Spray Inboard I' solation Valve. l 2-E11-F0218 Circuit Breaker i i
DH2 Suppression Pool Cooling Isolation Valve, !
2-E11-F0248, CiNuit Breaker l DH4 Suppression Pool Spr z Isolation Yalve, 2-E11-F0278, Circuit . reaker ,
DM9 LPCI Injectica Check Valve Bypass Valve, 2-E11-V33, Circuit Breaker td :' _ .
t
, BSEP-0/ASSD-02 Fsge 49 of 202 Rev. 0
g 2. (Cont'd)
Compartment Number Coreponers Description DN1 RHR HX B Service Header Outlet Yalve, 2-E11-PDV-F0688, Circuit Breaker .
DQO HPCI Turt,ine Exhaust Vacuum Breaker Valve, 2-E41-F079, Circuit Breaker _
DL1 Rd Pump 2B Shutdown Cooling Suction Valve, 2-E11-F006B, Circuit Breaker DL2 RHR Pump 20 Shutdown Cooling Suction Valve, 2-E11,-F0060, Circuit Breaker DL5 RCIC Turbine Exhaust Vacuum Breaker Val /e, 2-E51-F066, Circuit Breaker DK9 RHR Pump 28 Suppression Pool Suction Valve, 2-E11-F004B Circuit Breaker DL3 RHR Minimum Flow Bypass Valve, 2-E11-F0078, (f.j Circuit Breaker DLO RHR Pump 2D Suppression Pool Suction Valve, 2-E11-F0040, Circuit Breaker DN4 RHR HX 2B Outboard Vent .:ve, 2-E11-F103B, Circuit Breaker i
DKB RHR hr 43 Outlet Valve, 2-E11-F003B, Circuit l
~~
Breaker l
DM7 RHR HX 2B Inlet Valve, 2-E11-F0478, Circuit Breaker DMB RHR HX Bypass Valve, 2-E11-F048B, Circuit Breaker DL6 RHR HX 2B Drain To Suppression Pool Valve, 2-E11-F0118, Circuit Breaker DM3 RHR KX 2B Drain to RCIG Valve, 2-E11-F0268, Circuit Breaker DN5 RHR HX 2B Inboard Vent Valve, 2-E11-F1048, Circuit Breaker Disconnect c- Switch 9KVA 38 480-208Y/120V Transformer Q.i'j BSEP-0/ASSD-02 Page 50 of 202 Rev. O
- 3. PE9 FORM switch lineup on MCC 2XB per Step 2 of Section D without N+) power available to MCC 2XB, THEN CONTINUE restoration with Step 4 below.
- 4. OlilECT Diesel Generator Operator to RECLOSE Reactor Building 2XB powca supply breaker at 480V Substation E8 Compartment A02.
- 5. WHEN informed by Diesel Generator Operator that power supply THEN CLOSE the breaker followingfor ReactortoBuilding breakers energizeMCC Safe2XB is Closed, Shutdown loaTis on Reactor Building MCC 2XB.
Tompa rtment Number Component Description DP7 Vent RHR HX Area Cooling Fan, 28-FCU-RB, Circuit Breaker DP3 Shutdown Cooling Inboard Suction Isolation Valve, 2-E11-F009, Circuit Breaker DK! Recirculation Pump 2B Suction Valve, 2-B32-F023B, Circuit Breaker
,g DNS RHR Pump 2B & 2D Sappression Pool Suction R S.l A .c Valve, 2-E11-F020B, Circuit Breaker DP2 Nuclear Service Water To Vital Header Inboard Isolation Valve, 2-SW-V117, Circuit Breaker ,
DN9 RHR HX B Service Water Discharge Valve, 2-E11-F0028 Circuit Breaker DN2 RHR SW Outboard injection Valve, 2-E11-F073 Circuit Breaker DM1 RHR Service Water Booster Pumps B And D Inboard Isolation Valve, 2-Sw-Y105, Circuit Breaker DMS Ser vice Water To RHR Serv'ce Water Header Cross-tie Valv2, 2-SW-V102, Circuit Breaker DL8 Drywell Spray Outboard Isolation Valve, 2-E11-F016B, Circuit Breaker DM0 Drywell Spray Inboard Isolation Valve, 2-E11-F021B, Circuit Breaker b
BSEP-0/ASSD-02 Page 51 of 202 Rev. O
i j ~
- 5. (Cont'd) l Q
Compartment Number Component Description DH2 Suppression Pool Cooling Isolation Valve, 2-E11-F024B, Circuit Breaker DH4 Suppression Pool Spray Isolation Valve, 2-E11-F027B, Circuit Breaker DN1 RHR HX B Service Header Outlet Valve, 2-E11-PDV-F068B, Circuit Breaker DL1 RHR Pump 2B Shutdown Cooling Suction Valve, 2-E11-F006B, Circuit Breaker DL2 RHR Pump 2D Shutdown Cooling Suction Valve, 2-E11-F0060 Circuit Breaker DL5 RCIC Turbine Exhaust Vacuum Breaker Valve, 2-E51-F066 Circuit Breaker M DK9 RHR Pump 2B Suppression Pool Suction Valve, 2-E11-7004B, Circuit Breaker DL3 RHR Hinimum Flaw Bypass Valve, 2-E11-F0078, Circuit 3reaker DLO RHR Pump 2D Suppression Pool Suction Valve, 2-E11-F0040, Circuit Breaker DKB RHR HX 2B Outlet Valve, 2-E11-F003B, Circuit Breaker DH7 RHR HX 2B Inlet Valve, 2-E11-F047B, Circuit Breaker DM8 RHR HX Bypass Valve, 2-E11-F04BB, Circuit Breaker
- 6. COMPLETE switch / valve position lineup for HCC 2XB per Step 2 of Section D with power available to MCC 2XB.
V.: ~
BSEP-0/ASSD-02 Page 52 of 202 Rev. 0 1
j
RESTORING POWER TO REACTOR BUILDING MCC 2XD T.he purpose of the following steps is to r2 store power to Reactor Building MCC 2XD in the event that an electrical fault causes the feeder breaker at 480V Substation E8 Compar*.wnt A08 to trip.
- 1. IF power is NOT available to Reactor Building MCC 2XD as Tetermined by loss of indicating lights and control for items powered from Reactor Building MCC 2XD, THEN DIRECT Diesel Generator Operator to CONFIRH the following
- a. 480V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC 2XD at Compartment A08 is Tripped.
- 2. WHEN Diesel Generator Operator C0NFIRMS that
- a. 400V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC 2XD at Compartment A08 is Tripped.
THEN OPEN the following breakers on Reactor Building MCC 2XD.
b Compartment Number Component Description DW9 Core Spray Pump B Minimum Flow Bypass Valve, 2-E21-F031B, Circuit Breaker DWB Core Spray Full Flow Test Bypass Valve, 2-E21-F0158, Circuit Breaker DW6 Core Spray Inboard Injection Yalve, 2-E21-F005B, Circuit Breaker DX8 Standby Air Compressor 2B Circuit Breaker DX2 Vent Core Spray Pump Area Cooling Fan, 2D-FCU-RB, Circuit Breaker DW3 Core Spray Pump B Suppression Pool Suction Valve, 2-E21 F001B, Cit 9it Breaker _
DW5 Core Spray Outboard Injection Valve, 2-E21-F004B Circuit Breaker (b _ -
BSEP-0/ASSD-02 Page 53 of 202 Rev. O m
- 2. (Cont'd)
Yompartment Number Component Description DX4 Suppression Pool 2 Inch Purge Exhaust Valve, 2-CAC-V22. Circuit Breaker DX9 COMPT 2-DX9 MOTOR 2-KE3 N$$$ MN STM DRN LIE VLV 2-B21-F016 A$$D FEED DYO Welding Receptacle (Elev. -17' 0") 460V 30 DX7 Reactor Building Equipment Drain Tank Pump A, 2-G16-C006A, Circuit treaker DW2 COMPT. 2-DW2 MOTOR 2-RR7 RCIC TURB. VAC Breaker VLV. 2-E51-F062 A$$D FEED DY1 COMPT. 2-DY1 MOTOR 2-K$8 RCIC STEAM $UPPLY LIE !$0L. VLV. 2-E51-F007 A$$D FEED DX5 COMPT. 2-DX5 MOTOR 2-KM2 RMt $UCTION ISOL. VLV.
2-E11-F009 A$$D FEED I[h DW1 HPCI Steam Supply Inboard Isolation Valve, 2-E41-F002, Circuit Breaker DXO Feedwater Line B Isolation Valve, 2-821-F0328 Circuit Breaker D38 COMPT 2-038 SERVICE 2-487 BATTERY CHARGER 25-2 ALTERNATE FEED DV9 Miscellaneous 120V AC Distribution 2DXS Supply treaker DX6 Welding Receptacle (Ele. 20'-0") 480V 30 DX3 Recirculation Pump 2B Motor Heater Circuit Breaker D3A COMPT. 2-D3A SERVICE 2~G86 BATTERY CHARGER 28-1 ALTERNATE FEED Utsconnect Switch 9KVA 38 480-206Y/120V Transformer bik -
BSEP-0/AS$D-02 Page 54 of 202 Rev. 0
~l
- 3. DIRECT Diesel Generator Operator to RECLO$E Reactor Building MCC
@ 2XD power supply breaker at 480V Substation E8 Compartment A08, 4 WHEN informed by Diesel Generator Operator that power supply breaker for Reactor Building MCC 2XD at Compartment A08 is Closed, THEN CLOSE the following breakers to energize safe Shutdown loads on Reactor Building MCC 2X0.
C artment Nu r Component Description DW2 COMPT. 2-DW2 MOTOR 2-RR7 RCIC TURt. VAC BREAKER VLV. 2-E51-F062 AS$D FEED DY1 COMPT. 2-DY1 MOTOR 2-K$8 RCIC STEAM $UPPLY LIE ISOL. VLV. 2-E51-F007 AS$0 FEED DX5 Co w T. 2-0X5 MOTOR 2-KM2 RHR SUCTION 1$0L. VLV.
2-E11-F009 A$$0 FEED D38 COMPT 2-D3B *.ERVICE 2-G87 BATTERY CHARGER 28-2 ALTERNATE FEED .
M' D3A COMPT. 2-03A SERVICE t-486 BATTERY CHARGER 28-1 ALTERNATE FEED 9
(h_
BSEP-0/A$$D-02 Page 55 of 202 Rev. 0
RESTORING POWER TO REACTOR BUILDING Fy HCC 2XB-2 v
The purpose of the following steps is to resture power to Reactor Building MCC 2XB-2 in the event that an electr! cal fault causes the feeder breaker at 480V Substation E6 Compartment AV8 to trip.
- 1. IF power is NOT available to Reactor Building MCC 2XB-2 as E termined by loss of indicating lights and control for items powered from Reactor Building MCC 2XB-2 THEN DIRECT Diesel Generator Operator to CONFIRM the following
- a. 480V Substation E6 is Energized AND
- 2. WHEN Diesel Generator Operator CONFIRMS that
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Reactor Building HCC 2XB-2 at Compartment AV8 is Tripped, y THEN OPEN the following breakers on Reactor Building MCC 2XB-2.
,f Compartment v#7 Number Component Description DK2 Recirculation Pump 24 Discharge Valve, 2-B32-F031B, Circuit Breaker DK3 Recirculation Pump 2B Discharge Bypass Valve, 2-B32-F032B, Circuit Breaker DL7 LPCI Inboard injection Yalve, 2-E11-F015B Circuit Breaker DL9 LPCI Outboard injection Valve, 2-E11-F0178, Circuit Brecker DMS Suppression Pool Discharge Isolation Valve, 2-E11-F028B, Circuit treaker Q ;-
- BSEP-0/ASSD-02 Page 56 of 202 Rev. O
- 3. PERFORM switch lineup on MCC 2XB-2 per Step 2 of section D without power available to MCC 2XB-2, THEN CONTINUE restoration
@' with Step 4 below.
4 DIRECT Diesel Generator Operator to RECLOSE Reactor Building 2XB-2 power supply breaker at 480V Substation E6 Compartment AV8.
- 5. WHEN informed by Diesel Generator Operator that power supply breaker for Reactor Building MCC 2XB-2 is closed, THEN CLOSE the following breakers to energize Safe Shutdowr loads on Reactor Building MCC 2XB-2.
Compartment Number Component Description DL7 LPCI Inboard Injection Valve, 2-E11-F0158 Circuit Breaker _
DL9 LPCI Outboard Injection Yalve, 2-E11-F0178, Circuit Breaker Suppression Pool Discharge Isolation Valve, M
DMS 2-E11-F0288, Circuit Breaker
/P
% 6. COMPLETE switch / valve position lineup for MCC 2XB-2 ,ner Step 2 of Section D with power available to MCC 2XB-2.
ESEP-0/ASSD-02 Page 57 of 202 Rev. O
l RESTORING POW.R iv .! ACTOR BUILDING l HCC 2XDB !
The purpose of the following steps is to restore power to Reactor Building MCC 2XDB in the event that an electrical f ault causes the feeder breaker listed below to trip.
125/250V DC Switchboard 18
- a. Compt. B30 ' incoming Feeder Breaker
- 1. OPEN the following breakers on Reactor Building itCC 2XDB.
Compartment Number Component Description ,
835 RCIC Barometric Condenser Vacuum Pump !
Circuit Breaker 836 RCIC Barometric Condenser Vacuum Tank 1r r Condensate Pump Circuit Breaker HD B37 RCIC Turbine Trip And Throttle Valve, f 2-E51-V8, Circuit Breaker :
i 838 RCIC Condensate Storage Tank Suction Valve. 2-E51-F010, Circuit Breaker !
B39 RCIC Cooling Water Supply Valve, 2-E51-F046, Circuit Breaker B40 RCIC Pump Discharge Valve, 2-E51-F012, Circuit Breaker '
I B41 RCIC Injection Valve, 2-E51-F013 Circuit Breaker 842 RCIC Bypass To Condensate Storage Tank :
Valve, 2-E51-F022, Circuit Breaker _
r B43 RCIC Steam Supply Outboard Isolation
- Valve, 2-E51-F008. Circuit Breaker !
B44 RC1C Turbine Steam Supply Valve, [
2-Es1-F045, Circuit Breaker ;
(- -
l SSEP-0/ASSD-02 Page 58 of 202 Rev. O I
I l
- 1. (Cont'd)
Compartment Number Component Description B45 RCIC Suppression Pool Suction Valve,
?-E51-F031, Circuit Breaker B46 RCIC Suppression Pool Suction Valve. .
2-E51-F029, Circuit Breaker B47 RCIC Minimum Flow Bypass To suppression Pooi Valve, 2-E51-F019, Circuit Breaker 848 RWCU Inlet Outboard Throttle Isolation Yalve, 2-G31-F004, Circuit Breaker B50 Shutdown Cooling Outboard Suction Isolation Valve, 2 E11-F008. Circuit Breaker B51 Rift To Rad 1ste Outboard Isolation Valve, 2-E11-F04' , Circuit Breaker M B52 Main Steam Line Outboard Drain Isolation Valve, 2-B21-F019. Circuit Breaker g/
i l B53 REMOTE SHUTDOWN PANEL 1R-RB-4 ALT.
- SAFE SHUTDOWN INSTRUENTS
- 2. PERFORM switch lineup on HCC 2XDB per Step 2 of section D without power availabie to MCC 2XDB, THEN CONTINUE restoration with Step 3 below.
l 3. At 125/250V DC Switchboard 18 VERIFY Closed 3, CLOSE Feeder Braaker COMPT GL3 Reactor Butiding MCC 2XDB, 4 At Reactor Building MCC 2XDB, VERIFY Closed OR ~
CLOSE Compt. B30 INCOMING FEEDER BREAXER.
. BSEP-0/ASSD-02 Page 59 of 202 Rev. 0
- 5. CLOSE the following breakers on Reactor Building MCC 2XDB.
Com>a rtment
. Num>e r Component Description B35 RCIC Barometric Condenser Vacuum Pump Circuit Breaker B36 RCIC Barometric condenser Yacuum Tank Condensate Pump Circuit Breaker B37 RCIC Turbine Trip And Throttle Valve, 2-E51-V8, Circuit Breaker I
B38 RCIC Condensate Storage Tank Suction Valve, 2-E51-F010, Circuit Breaker 839 RCIC Cooling Water Supply Valve, 2-E51-F046, Circuit Breaker B40 RCIC Pump Discharge Valve, 2-E51-F012, .
Circuit Breaker p 841 RCIC Injection Valve, 2-E51-F013 f,. Circuit Breaker b
B42 RCIC Bypass To Condensate Storage Tank Valve, 2-E51-F022, Circuit Breaker 943 RCIC Steam Supply Outboard Isolation Valve, 2-E51-F008 Circuit Breaker _
8 44 RCIC Turbine Steam Supply Valve, l 2-E51-F045, Circuit Breaker B45 RCIC Suppression Pool Suction Yalve, 2-ES1-F031, Circuit Breaker ;
B46 RCIC Suppression Pool Suction Valve, 2-E51-F029, Circuit Breaker ;
B47 RCIC Minimum Flow Bypass To Suppression Pool Valve, 2-E51-F019, Circuit Breaker B48 RWCU Inlet Outboard Throttle Isolation Valve, 2-G31-F004 Circuit Breaker i
l
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BSEP-0/ASSD-02 Page 60 of 202 Rev. O
- 5. Cont'd) m, g
Compartment Nun 6er Component Description
- 850 Shutdown Cooling Outboard Suction Isolation l Valve, 2-E11-FOO8, Circuit Breaker i 8 52 Main Steam Line Outboard Drain Isolation l Valve, 2-821-F019 Circuit Breaker i
853 REMOTE SHUTDOWN PANEL IR-R8-4 ALT.
SAFE SHUTOOWN INSTRUMENTS
- 1f the pre-fire rackout tag has not been previously removed during performance of ASSD-02, then ,0), NOT close this breaker.
- 6. COMPLETE switch / valve position lineup for HCC 2XDB per Step 2 of Section D with power available to MCC 2XDB.
N r,
O{
('s -
BSEP-0/ASSD-02 Page 61 of 202 Rev. O
\
SECTION "E"
@~
SERVICE WATER BUILDING OPERATOR ACTION
- 1. REPORT to Service Water Building AND_ ESTABLISH cor sunications with Unit 2 RSDP Operator using phone jacks listed below:
- a. 20'-0" Elev. - (F3E) REMOTE SHUTDOWN TRAIN 'B' (UNIT
9.R.
b 4'-0" i ly. - (F3G) REMOTE SHUTDOWN TRAIN 'B' (UNIT
- 2) SOCND POWERED PHONE CKT. located near center of east wall.
- 2. COMPLETE Unit 2 and Unit 1 Servica Water Building MCC breaker and switch lineup listed in Tab'- e located at the end of this section.
FAIL OPEN (Unit 2) Lube Water Supply Pressure Centrol Valve, 3.
2-SW-PV136, by performing the following:
- a. CLOSE Instrument Air Isolation Valve 2RI A-IV-U-V1, for 2-SW-PV136. g ,,g g b. OPEN Air Regulator Bleed Valve located on 2-SW-PV136.
- 4. Fall OPEN ' Unit 1) Lube Water Supply Pressure Control Valve, 1-SW-PV136, by performing the following:
- a. CLOSE Instrument Air Isolation Valve 1RIA-IV-U-Y1, for 1-SW-PV136.
- b. OPEN Air Regulator Bleed Vf de located on 1-SW-PV136.
- C .
BSEP-0/ASSD-02 Page 62 of 202 Rev. O
s NOTE Q The purpose of the rext 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.
- 5. VERIFY Closed OR Manually CLOSE one of the discharge valves for each of the CoWentional Service Water Pumps listed below:
- a. Conventional Service Water Pump 1A Discharge valve to Nuclear Header 1-SW-V14 Conventional Header 1-SW-V13
- b. Conventional Service Water Pump 1B Discharge valve to Nuclear Header 1-SW-V16 Conventional Header 1-SW-V15
- c. Conventional Service Water Fump 1C Discharge valve to
' Nuclear Header 1-SW-V18 E i C-/ Conventional Header 1-SW-Y17
- d. Conventional Service Water Pump 2A Discharge valve to Nuclear Header 2-SW-V14 Conventional Header 2-$W-V13
- e. Conventional Service Water Pug 26 Discharge valve to Nuclear Header 2-SW-Y1'3 Conventional Header 2-SW-V15
- f. Conventional Service Water Pu g 2C Discharge valve to Nuclear Header 2-SW-V18 Conventional Header 2-SW-V17
-~
6 IF Nuclear Service Water Pug 2B is NOT Running THEN VERIFY ITosed OR Hanually CLOSE Nuclear Service Water Pump 2B Discharge Valve 2 D V20
- 7. IF Nuclear Service Water Pump 1B is NOT Running THEN Vf.RIFY TTosed OR Hanually CLOSE Nuclear Service Water Pump 18 Discharge Valve 1%-V20.
(.- .
BSEP-0/ASSD-02 Page 63 of 202 Rev. O
- 8. INFORM Unit 2 Shift Foreman that Service Water systems are lined g u? for operation in accordance with this procedure. ,
- 9. PERFORM the following to help place Nuclear Service Water Pump 2B in operation:
- a. WHEN directed by Emergency Switchgear Operator, THEN VETFY Open OR Manually Open Nuclear Service Water Pump 2B DiscErge Valve 2-SW-Y20.
- b. INFORM Emergency Switchgear Operator that 2-SW-V20 is Open.
- 10. PERFORM the following to help place Nuclear Service Water Pug 1B in ope ation:
- a. WHEN directed by Eleergency Switchgear Operator, THEN VGTFY Open OR Manually Open Nuclear Service Water Pump 1B DiscErge Valve 1-SW-Y20.
- b. INFORM Emergency switchgear Operator that 1-SW-V20 is Open. '
- 11. WHEN directed THEN INFORM Unit 2 Reactor Building MCC Operator N when Nuclear Header pressure decreases to 40 psig as read on ;
2-SW-PI-145, located on 28 Nuclear Service Water Pug discharge
... line.
@D.' ' 12. _WHEN directed, THEN INFORM Unit 1 Shift Foremn when Nuclear .
Header pressure decreases to 40 psig as read on 1-SW-PI-145, located on 18 Nuclear Service Water Pump discharge line.
, 13. PERFORM duties as directed by Shift Foreman.
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BSEP-0/ASSD-02 Page 64 of 202 Rev. O i l
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SECTION "E" I TABLE 1
([
CONTROL NORMAL /
BREAKER SWT./VLV LOCAL i COWT DESCRIPT10h EQUIPMENT POS. POS. SWT.
LOCATION MCC 2PB E44 Conventional Service Water 1-SW-V14 0FF N/A N/A '
Pump 1A Discharge Valve to Nuclear Header.1-SW-V14 Circuit Breaker E29 Service Water Lube Water SW-2B ON START LOCAL i
Pump 2B Circuit Breaker E37 Conventional Service Water 2-SW-V16 0FF N/A N/A Pump 2B Discharge Valve To Nuclear Header, 2-SW-V16 Circuit Breaker E45 Conventional Service Water 1-SW-V13 0FF N/A N/A Pump 1A Discharge Valve To gg* l
.,, Conventional Header,1-SW-V13 k5 Circuit Breaker E36 Conventional Service Water 2-SW-V15 0FF N/A N/A Pump 28 Discharge Valve To Conventional Header, 2-SW-V15 Circuit Breaker E23 Nucicar Service Water Pump 28 2-SW-V20 ON N/A LOCAL Discharge Valve 2-SW-V20 Circuit Breaker LOCATION MCC 2PA E07 Conventional Service Water 2-SW-V13 0FF N/A N/A Pump 2A Discharge Valve To Conventional Header 2-SW-V13 Circuit Breaker E06 Conventional Service Water 2-SW-Y14 0FF N/A N/A Pump 2A Discharge Valve To Nuclear Header 2-SW-V14 Circuit Breaker E
BSEP-0/ASSD-02 Page 65 of 202 Rev. O
SECTION "F" TABLE 1 (Cont'd)
@ {
i CONTROL NORMAL / i l
BREAKER SVT./VLV LOCAL COMPT DESCRIPTION EQUIPMENT POS. POS. SWT.
l LOCATION MCC2PA(Cont'd) . ;
I E12 Service Water Lube Water SW-2A ON START LOCAL -
i Pump 2A ;
806 hucicar Service Water Pump 1A 1-SW-V19 ON N/A LOCAL i Discharge Valve 1 SW-V19 l Circuit Breaker ,
BU9 Conventional Service Water 2-SW-V18 0FF N/A LOCAL Pump 2C Olscharge Valve To Nuclear Header, 2-SW-Y18 Circuit Breaker BU7 Conventional Service Water 1-SW-V15 0FF N/A N/A Pump 18 Discharge Valve To gg' ;
, Wz. Conventional Header 1-SW-V15 a
i circuit Breaker i 1
808 Conventional Service Water 1-SW-V16 0FF N/A N/A Pump 1B Discharge Valve To Nucioar Header 1-SW V16 -
Circuit Breaker ,
, BVO Conventional Service Water 2-SW-Y17 0FF N/A N/A i Pump 2C Discharge Valve To Conventional Header 2-SW-V17 !
Circuit Bre6ker
! BY2 Service Water Lube Water SW-1A ON START LOCAL Pump 1A LOCATION MCC 1PB BX1 Service Water tube Water SW-1B ON START LOCAL Pump 18 f f
i BXP Conventional Service Water 1-SW-V18 0FF N/A N/A Pump iC Discharge Valve lu Nuclear Header 1-SW-V18 ;
g , Circuit Breaker t W .. )
i BSEP-0/ASSD-02 Page 66 of 202 Rev. 0 1
l l
h SECTION "E" !
p TABLE 1 (Cont'd)
CONTROL NORMAL /
BREAKER SWT./VLV LOCAL l COMPT EQUIPMENT P05. Pos. SWT.
l DESCR E ON LOCAT_._ ION MCC1PB(Cont'd) '
EX8 Conventional Service WI,ser 1-SW-V17 0FF N/A N/A I Pump 1C Discharge Valve To !
i Conventional Header 1-SW-V17 Circuit Brecker !
BYO Nuclear Service Water Pump 18 1-SW-V20 ON N/A LOCAL Discharge Valve 1-SW-V20 Circuit Breaker i
i Rs.I O !
+
tyt,
%? o BSEP-0/ASSD-02 Page 67 of 202 Rev. 0
RESTORING POWER TO SERYlCE :
g WATER INTAXE STRUr,TURE HCC 1PB The purpose of the following steps is to restore powcr to Service Water Intake Structure MCC 1PB in the event that an electrical fault causes 480V feeder breaker to MCC IPB to trip.
- 1. IF power is NOT available to Service Water Intake Structure MCC TFB as determined by loss of indicating lights and control for items powered from MCC 1PB THEN DIRECT Diesel Generator Operator to CONFIRM the following:
- a. 480V Substation E6 is Energized AND 4
1
- b. Power supply breaker to Service ttater Intake Structure '
MCC 1PB at Compartment AW3 is Tripped.
- 2. WilEN Diesel Generator Operator CONFIRMS that: ,
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Service "ater Intake Structure !
MCC 1PB at Compartment AW3 is Tripped.
THEN OPEN the following breakers on Service Water Intake N
structure MCC IPB. !
(#M Compartment Number Component Description
! BX6 Ventilation Pump House Exhaust Fan,1 A-EF-SWIS, l
! Circuit Breaker j l
4 BX4 Screen Wash Water Service Water Travtling '
Screen, SCW-18 Circuit Breaker BX3 SERYlCE 1-PR5 WELD NG RECEPTACLE 480V 38 BX1 Service Water Lube ncer Pump 1B Circuit i Breaker ;
i BY1 Conventional Service Water Puap 1C Discharge !
Strainer Motor Circuit Breaker l
BY2 Nuclear Service Water Pung B Discharge Strainer Motor Circuit Breaker i
i i BSEP-0/ASSD-02 Page 68 of 202 Rev. O
- 2. (Cont'd) g, Compartment Mus6er -
Component Description ,
BX7 Service Water To Circulating Water Pumps .
Bearing Lubricating Water supply Valve, 1-$W-Y37. Circuit Breaker BX9 Conventional service Water Puap IC Discharge Valve To Nuclear Hender,1-$W-V18 Circuit treaker 8X8 Conventional service Water Pump 1C Discharge Valve To ventional Header,1-$W-V17 Circuit s.< er BYO Nuclear Service Water Pump 18 Discharge Valve,1-$W-V20, Circuit Breaker BY9 Emergency 120V AC Distribution Panel 1B-$W Supply Breaker .
312 Service Water To Chlorination System 1n Outboard Supply Valve,1-$W-V295, C1. cult n D.
rh Breaker
- Disconnect
$ witch 9KVA 38 480-208Y/120V Transformer
- 3. DIRECT Diesel Generator Operator to RECLOSE Service Water Intake
$ttveture MCC 1Pt power supply breaker at substation E6 Compartment AW3.
i l
W-BSEP-0/A$$D-02 Page 69 of 202 Rev. O l
p 4. WHEN informed by Diesel Generator Operator that power supply (lii breaker for Service Water Intake Structure MCC 1PB at 480V Substation E6 Compartment AW3 is Closed THEN CLOSE the following breakers to energize Safe Shutdown loads on Service Water intake Structure MCC 1PB.
i Compartment Number Component Description BX1 Service Water tube Water Pump 18 Circuit Breaker ,
BY1 Conventional Service Water Pump 1C Discharge Strainer Motor Circuit Breaker BY2 Nuclear Service Water Pump 18 Discharge Strainer Motor Circuit Breaker BYO Nuclear Service Water Pump 18 Discharge Valve, t 1-SW-V20, Circuit Breaker INFORM Unit 2 Shift Foreman that MCC 1PB is Energized AND Safe !
5.
Shutdown load breakers are Closed. ,
R&l
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E 1
i I
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l kt"~ (; ) i BSEP-0/ASSD-02 Page 70 of 202 rev. 0
RESTORING POWER TO SERVICE (0 WATER INTAXE STRUCTURE EC 2PB f i
The purpose of the following steps is to restore power to Service Water Intake ;
structure MCC 2PB in the event that an electrical fault causes 480V Feeder breaker to EC 2P8 to trip.
- 1. IF power is NOT available to Service Water Intake Structure EC FB as detarmined by loss indicating lights and control for ;
items powered from E C 2PB. THEN DIRECT Diesel Generator 4 Operator to CONFIRM the following:
- a. 480V Substation E8 is Energized AND j 1 b. Power supply breaker to Service Water Intake Structure KC 2PB at Compartment A05 is Tripped. l I 2. WHEN Diesel Generator Operator CONFIRMS that:
- a. 480V Substation E8 is Encegired AND 4
l b. Po.:P supply breaker to Stryke Water Intake L Structure KC 2PB at Compartment .'S5 is Tripped. ;
THEN OPEN the following breakers on Service Water Innake '
4 TEFiicture KC 2Ps.
, , . RE ,
jUi
. Compa rtment Number Component Descriptica
]
1 i
E34 Ventilation Pump House Exhaust Fan 2A-EF-SWi$.
l Circuit Breaker s
i E32 Screen Wash Water Servise Water Traveling ;
j Screen. SCW-28. Circui', Sreaker
.1 Nuclear Service Wate', Pump 2B Discharge E39 Strainer Motor Circi,it Breaker J E44 Conventional Service Water Pump 1A Discharge i Valve Tc Nuclear Header 1-SW-V14. Circuit i treaker [
E40 Conventional Service Water Pump 28 Discharge i
- Strainer Motor Circuit treaker l I
f l
) e C; l
3 SSEP-0/ASSD-02 Page 71 of 202 Rev. 0 l i
- 2. (Cont *d)
Q l Compartment
- Number Component Dese.ription E31 2-m 5 WELDING RECEPTACLE 480V 36 E29 Service Water Lube Water Pump 28 Circuit Breaker _
l E46 Cenventional Service Water Pump 1A Discharge !
i etrainer Motor Circuit Breaker I !
E37 Conventional Service Water Pump 25 Discharge !
Valve To Nuclear Header, 2 SW V16, Circuit :
Breaker !
l E35 K) TOR 2-KY4 SERV WATER TO CIRC WTR PHP BRGS
, SEC !$0L YLY 2 SW-Y37 E45 Conventional Service Water Pump 1A Discharge f Valve To Conventional Header,1-$W-V13, Circuit Breaker
.e E36 Conventional Service Water Pug 28 Discharge n Yalve To Conventional Header, 2-5W-Y15, lq'3' Circuit treaker
- E38 Nuclear Service Water Pug 2B Discharge Valve. I 2-$W-Y20, Circuit Breaker E47 Emergency 120V AC Distribution Panel 2B-5W Supply Breaker E49 Service Water To Chlorination System Outboard Supply Valve, 2 SW-V2%, Circuit Breaker 01scannect Switch 9KVA 38 480-208Y/12CY Transformer ,
i l
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BSEP-0/ASSD-02 Page 72 of 202 Rev. O i f
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- 3. DIRECT Diesel Generator Operator to RECLOSE Service Water Intake Structure HCC 2PB power supply breaker at substation E8
@" Coepartment A05.
4 WHEN informed by Diesel Generator Operator that power supply breaker for Service Water Intake Structure MCC 2PB at 480V '
Substation E8 Compartment A05 is Closed. THEN CLO$E the following breakers to energize Safe Shutdown loads on Service ,
, Water intake Structure MCC 2Pl.
C artment :
Nu r component Description l E39 Nucitar Service Water Pump 28 Discharge Strainer Motor Clitutt treaker j t
Service Water tube Water Pump 28 Circuit E29 treaker ,
E38 Nuclear Survice Water Pump 2B Discharge Valve, 2 $W-V20, Circuit Breaker
- 5. INFORM Unit 2 shift Foreman that MCC 2PB is Energized and Safe Shutdown load breakers are Closed, g
h [
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I i BSEP-0/ASSD-02 Page 73 of 202 Rev. 0 .
l i
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i g SECTION "F" EMERGENCY SWITCHGEAR OPERATOR ACTIONS
- 1. REPORT .o Emergency Bus E1 AND ESTABLISH comunication with Unit 2 RSDP Operator using sound powered phone jack labeled REMOTE >
SHUTDOWN TRAIN 'B' (UNIT #2) SOUND POWERED PHONE CKT. located on Compartment AK6. -
- 2. M. ACE the Normal / Local switches in the "LOCAL" position for Emergency Bus E4 loads listed below.
NORMAL /
COMPT. DESCRIPTION LOCAL SWT. !
AKO P.T. Compartment Local [
I 1 AK1 P.T. Auxiliary Compartment Local l
AK1 P.T. Auxiliary Compartment knife Disconn switches under cover labeled TS-FV VAR. W/TR E8'I. l 1
AK3 R$ Pump 28 Local i
, . , ~
b AK4 Rm Serv. Wtr. Pump 28 Local f AK7 Unit Sub E8 Local AK8 CAD Hydraulic Pump 25 Local AK9 RM Serv. Wtr. Pump 18 Local l
ALO Rm Pump 18 Local ;
All Nuc Serv. Wtr. Puer 28 Local
- 3. VERIFY Closed OR CLOSE 4KV breaker to Unit Sub E8 (AK7) using control switch'Tocated on Compartment AK7.
l i
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BSEP-0/ASSD-02 Page 74 of 202 Rev. 0 (
l
t 4 REMOVE control power fuses R VERIFY Tripped 1 TRIP the g following breakers using the manual trip pushbutton,
- s. Compt. AK5 - RX Core Spray Pus,25
- b. Compt. AK6 - Cony. Serv. Wtr. Pump 1A
- c. Coset. AL2 - Cony. Serv. Wtr. Pusp 28
- d. Compt. AL3 - Fire Pump Feed
- 5. l_F Emergency tus E4 is energized from 4KV Dus 2C, EN VERIFY Tw th the Diesel Generator Operator that the seven m-Normal / Local switches on Diesel Generator No. 4 Control Panel are in local control before completing step 6.
- 6. REMOVE control power fuses from 4KV breaker Cosuartment Alg. .,
Incoming Line Swgr. 2C. A!gt VERIFY tripped & TtlP 4KV breaker using mechanical trip puTsbutton.
- 7. INFORM Unit 2 Shift Foreman that Emergency Bus E4 is ready to be energized. E,
- 8. EN directed by shift Foreman to START Nuclear Service Water Pump 28 THEN PERFORM the following:
- a. START Muclear Service Water Pusp 28 at Emergency tus
() E4 Compartment All by placing the local control switch in the *5 TART" position.
- b. DIRE 0T Service Water Building Operator to VrRIFY Open 3, Manually OPEN 2 5W-V20.
- g. W N informed blr Service Water Building Operator that 2 5W-V20 s pen iTN IN r0RM Unit 2 Shift Foreman that Nuclear Service Water Puey 75 is Running.
- 10. RE-LOCATE phone comunication from Emergency tus E4 to Emergency tus E2. RE-ESTML15H coeuunication with Unit 2 R$DP Operato.'
using sound powered phone jack labeled RENOTE SHUTDOWN TRAIN "l" (UNIT #2) $0VNO POWERED PH0E CET. located on compartment AMO.
l b
BSEP-0/A550-02 Page 75 of 202 Rev. 0 l
i
- 11. COMPLETE the Norm 41 c' veal switch lineup for Emergency Bus E2, !
listed in the table below, g+ i NORSL/
COMPT. DESCRIPTION LOCAL SWT.
i AGS P.T. Compartment Local AG6 P.T. Auxiliary Compartment local _
AG6 P.T. Auxiliary Compartment knife Disconn switches undercover labeled i TS-FV VAR. W/TR !
AG8 RHR W rv. Wt*. Pu g 2D 1.oc al ;
AG9 RHR Pump 2D Local AH1 Unit Sub E6 Local AH2 C on y. Serv. Wtr. Pug IC Local AH3 CRD Hydraulic Pug Il local :
y AH4 RHR Serv. Wtr. Pug 10 Local !
t.d " I AH5 R R Pump 1D Local I i
AH6 Nuc Serv. Wtr. Pug 1B 1,0 cal i
- 12. VERIFY Closed OR CLOSE 4KY breaker to Unit tub E6 (AH1) using control switch Tocated on Compartment AH1.
- 13. REMVE control power fuses AND VERIF.* Tripped OR TRIP the !
following breakers using f.he manual trip push Etton. !
- a. Compt. AHO - R1 Cree Spray Pug 1B j
- b. Coa 9t. AH7 . F'.re Pump Normal Feed
- 14. Eth the Diesel Generator Operator that the sevenIF Emergency lus [2 l l
Normal / Local switches on Diesel Generator No. 2 Control Panel !
are in local control before completing Step 15.
l
- 15. RENVE control power fuses from 4KV breaker Compartment AG4, !
Incoming Line Swgr.1C AND YERIFY tripped OR TRIP 4KY breaker using mechanical trip pH button.
{. ;
BSEP 0/ASSD-02 Page 76 of 202 a.ev. O f i
l . . ___, - - _ - ~ ~ , _ _ _ _ _ _ _
- 16. INFORM Unit 2 Shift Foreman that Emergency Bus E2 is ready to be bc.? energized.
- 17. WHEN directed by Unit 2 Shift Foreman to START Nur. lear Service V H er Pump ll THEN PERFORM the following:
- a. START Nuclear Service Water Pum 18 at Emergency tus E2 Cort.partment AH6 by placing tw local control switch in the "START" position.
- b. DIRECT Service Water Building Operator to VERIFY Open OR, Manually OPEN 1-SW-Y20.
- 18. WHEN informed by Service Water Building Operator that 1-SW-V20 Ts~Tpen THEN INFORM Unit 2 Shift Foreman that Nuclear Service Water Pu'mp TB is Running.
- 19. WHEN directed by Unit 2 RSDD Operator THEN START RHR Pump 28 at Tiiie'rgency Bus E4 Compartment AK3,
- 20. WHEN RHR Pump 2B is running,2E.N,, N INFORM Unit 2 RSDP Operator.
- 21. WHEN directed by Unit 1 Shift Foreman, THEN START RHR Pump 10 at Tiiiergency Bus E2 Compartment AHS.
- 22. WHEN Rift Pump 10 is running, THEN INFORM Unit 1 Shift Foreman.
- 23. PLACE the Normal / Local switches in the "LOCAL' position for Emergency tus E3 loads listed below:
NORML/
COWT. DESCRIPTION LOCAL SWT.
A13 P.T. Compartment Local AJ4 P.T. Auxiliary Compartment local A14 P.T. Auxiliary Compartment knife Disconn I switches under cover labeled TS-FV VAR. W/TR MO Unit Substa E7 ._m....
Local l M2 CRD Hydraulic Pump 2A loca) l M3 Nuc Serv. Wtr. Pump 2A Local l
M4 Cony. Serv. Wtr Pump 2A local 1
1
- ' s BSEP-0/ASSD-02 Page 77 of 202 Rev. O l
- 24. DETERMINE the status of Emergency Bus E3 using 4KV breaker
/n position indication listed below AND NOTIFY Unit 2 Shift W Foreman,
- a. Compt. A12 - Incoming Line Swgr 2D OPEN CLOSED
__, _ b. Compt. AIS - Diesel Gen. No. 3 OPEN CLOSED
- 25. VERIFY Diesel Generator No. 3 is in Lacal control before completing Step 26,
- 26. WHEN DIRECTED by Unit 2 Shif t Foreman, THEN REMOVE control power fuses AND TRIP 4KV breaker AI2 using the manual trip push button at Incoming Line Swgr 20, Compartment Al2.
- 27. PLACE the Normal / Local swis 'es in the LOCAL position for Emergency Bus El loads list ( below.
NORMAL /
COMPT. DESCRIPTION LOCAL SWT.
AE7 P.T. Compartment Local k,dl AE8 P.T. Auxiliary Compertment Local AE8 P.T. Auxiliary Compaitment knife Disconn switches undercover labeled TS-FV VAR. W/1R AF3 CRD Hydraulic Pump 1A Local ,
AF8 Ur.it Sub E5 ,
Local _
AF9 Nuc Serv. Wtr. Pump 1A local
' h$)-
BSEp-0/ASSD-02 Page 78 of 202 Rev. 0
7.
7
- 28. DETERH1NE the status of Emergency Bus El using 4KV breaker position indications listed below AND NOTIFY Unit 2 Shift O*.. Foreman. .
- a. Compt. AE6 - Incoming Line Swgr ID Open Closed 6 Compt AE9 - Diesel Gen. No. 1 Open Closed
- 29. VERIFY Diesel Generator No.1 is in local control before completing Step 30.
- 30. WHEN directed by Unit 2 Shift Foreman, THEN REH0VE control power f uses AND TRIP 4KV breaker AE6 using the manual trio push button at Inclim'Tng Line Swgr 10, Compartment AE6
- 31. WHEN directed by Unit 2 Reactor Building MCC Operator, _THEN STOP WPump 2B at Emergency Bus E4 Compartment AK3 to stop Supprossion Pool Cooling.
- 32. WHEN R4R Pump 2B is Stopped. THEN INFORM Unit 2 Reactor Building Operator.
g'
- 33. WHEN dire:ted by Unit 2 RSDP Operator, ,THEN START RHR Pump 2B at
@u Emergency Bus E4 Compartment AK3 for Shutdown Coolin: AR INFORM Unit 2 RSDP Operator.
- 34. IF maktup water is needed to raise reactor water level while Unit 2 is in Shutdown Cooling, THEN PERFORM the following
- a. WHEN directed by Unit 2 RSDP Operator, THEN STOP RHR Pump 2B at Emergency Bus E4 Compartment AKY to stop Shutdown Cooling AND INFORM Unit 2 RSDP Operator,
, b. WHEN directed by Unit 2 RSDP Operator, THEN START FHR Pump 2B at Emergency Bus E4 Compartment Ax3 for makeup AND INFORM Unit 2 RSDP Operator.
- 35. To return Unit 2 to Shutdown Cooling from reactor vessel makeup, PERFOR>i the following
- a. WHEN directed by Unit 2 RSDP Operator, ~THEN STOP RHR Pump 28 at Emergency Bus E4 Compartment XU to stop makeup AND INFORM Unit 2 RSDP Operator,
- b. THEN START RH1 WHEN Pump 2Bdirected by Unit at Emergency Bus 2E4RSDP Operator, T to start Compartment Shutdown Cooling AND INFORN Unit 2 RSDP Operator.
hf? l BSEP-0/ASSD-02 Page 79 of 202 Rev. O
~ _
- 36. WHEN directed by Unit 1 Shift Foreman, THEN STOP RHR Pump 1D at C;) Emergency Bus E2 Compartment AHS to stop Suppression Pool w Cooling.
- 37. WHEN RHR Pump 1D is stopped, THEN INFORM Unit 1 Shift Foreman.
- 38. WHEN directed by Unit 1 Shift Foreman, _THEN START RHR Pump 1D at Emergency Bus E2 Compartment AH5 for Shutdown Cooling AND INFORM Unit 1 Shift Foreman.
- 39. IF makeup water is needed to raise reactor watre level while in 3Tutdown Cooling, THEN PERFORM the follw
- a. WHEN directed by Unit 1 Shift Foreman THEN STOP RHR Pump 1D at Emergency Bus E2 Compartment AH5 to stop Shutdown Cooling.
- b. WHEN directed by Unit 1 Shift Foremar., THEN START RHR Tuiiip"10 at Emergency Bus E2 Compartment AH!i for makeup.
M
- 40. To return to Unit 1 Shutdown Cooling from reactor vessel makeup, PERFORM the following
- a. THEN STOP RHR WHEN Pump 10 directed by Unit at Emergency 1 Shift Bus E2 Foreman, W to stop Ccmpartment
,.. makeup.
p". ., .
- b. THEN START RHR WHEN Pump 1Ddirected by Unit at Emergency Bus 1 E2Shift Foreman, W to start Compartment Shutdown Cooling.
(T .
BSEP-0/ASSD-02 Page 80 of 202 Rev. O
[ RESTORING POWER TO EMERGENCY M BUS E4 l
The purpose of the following steps is to restore power to Emergency Bus E4 in the event that an electrical fault causes Diesel Generator Output breaker AK2 l to trip.
l 1. PLACE the Normal / Local switches in the "LOCAL" position for Emergency Bus E4 loads listed below.
l NORML/
COMPT. DESCRIPTION LOCAL SWT.
AKO P.T. Compartment Local AK1 P.T. Auxiliary Compartment Local AK1 P.T. Auxiliary Compartment kni fe Disconn switches undercover labeled TS-FV VAR. W/TR AK3 Rm Pump 28 Local AK4 Rm Serv. Wtr. Pump 28 Local O'!
MS
'A AK7 Unit Sub E8 Local AK8 CR0 Hydraulic Pump 2B Local AK9 RHR Serv. Wtr. Pump 1B Local ALO RHR Pump 1B Local All Nuc Serv. Wtr. Pump 2B Local GF u
BSEP-0/ ASS 0-02 Page 81 of 202 Rev. O
- 2. VERIFY Tripped OR Manually TRIP the following breakers using the i
- g. manu61 trip pusli~ button. l
- a. COMPT. AK3 RHR PUMP 2B
- b. COMPT. AK4 RfR SERV WTR Pump 2B
- c. COMPT. AK7 UNIT SUB E8
- d. COMPT. AK8 CRD HYDRAULIC PUMP 2B
- e. COMPT. AK9 RHR SERV. WTR PUMP 1B
- f. COMPT. ALO RHR PUMP IB
- g. COMPT. All NUC SERV WTR PUMP 28
- 3. REMOVE control power fuses AND YERIFY Tripped OR Manually TRIP the following breakers using the manual trip push button,
- a. COMPT. AJ9 INCOMING LINE SWGR. 2C
- b. COMPT. AK5 RX CORE SPRAY PUMP 28
- c. COMPT. AK6 CONY SERY l!TR PUMP 1A
- d. COMPT. AL2 CONY SERV WTR PUMP 28 N
G;'.
- e. COMPT. AL3 FIRE PUMP FEED 4 VERIFY Closed OR CLOSE COMPT. AK7 UNIT SUBSTA E8 4KV breaker using local co7itrol switch.
5 VERIFY with the Diesel Generator Operator that the seven (7)
Normal / Local switches on Diesel Generator No. 4 Control Panel are in local.
- 6. VERIFY Reset OR RESET the following 86DB LOCK 0UT Relays located on the compar7t ents listed below.
- a. COMPT. AKO P.T. COMPT.
- b. COMPT. AK1 P.T. AUXILI ARY COMPT.
E. -
BSEP-0/ASSD-02 Page 82 of 202 Rev. 0
- 7. DIRECT Diesel Generator Operator to START Diesel Generator No. 4 using the EMERGENCY START pushbutton located on the Local
(]l'} Control Panel.
- 8. DIRECT Diesel Generator Operator to CLOSE Diesel Generator No. 4 Output breaker f rom the local control panel WHEN Diesel
. Generator No. 4 has reached rated speed AND rated voltage.
- 9. START Nuc Serv. Wtr Pump 2B at 00MPT. ALI.
- 10. DIRECT Service Water Building Operator to VERIFY Open OR Manually OPEN Nuc. Serv. Wtr. Pump 2B disch. valve 2-SWTV20.
- 11. INFORM Unit 2 Shift Foreman that Emergency Bus E4 is re-energized and the necessary Safe Shutdown loads can be re-started.
- 12. The following loads are non-safe shutdown loads and should not be energized,
- a. COMPT. AJ9 INCOMING-LINE SWGR 2C
- b. COMPT. AK4 RHR SERV WTR PUMP 2B
- c. COMPT. AK5 RX CORE SPRAY PUMP 2B
c3 d. COMPT. AK8 CRD HYDRAULIC PUMP 2B 49
- e. COMPT. AK9 RHR SERV WTR PUMP IB
- f. C0liPT. AL3 FIRE PUMP ALTERNATE FEED 1
9 COMPT. AL4 TIE BREAKER EMERG SWGR E3
- h. COMPT. AL5 TIE BREAXER EMERG SWGR E2
&J BSEP-0/ASSD-02 Page 83 of 202 Rev. 0
RESTORING POWER TO EMERGENCY q BUS E2 The purpose of the following steps is to restore power to Emergency Bus E2 in the event that an electrical fault causes Diesel Generator Output breaker (AG7) to trip.
- 1. COMPLETE the Normal / Local switch lineup for Emergency Bus E2, listed in the table below.
NORMAL / COMPT. DESCRIPTION LOCAL SWT. AG5 P.T. Compartment Local AG6 P.T. Auxiliry Compartment Local AG6 P.T. Auxiliary Compartment knife Disconn switches undercover labeled TS-FV VAR. W/TR AG8 RHR Serv. Wtr. Pump 2D Local AG9 RHR Pump 2D Local N
, AH1 Unit Sub E6 Local AH2 Cony. Serv. Wtr. Pump 1C Local AH3 CRD Hydraulic Pump IB Local AH4 RHR Serv. Wtr. Pump 1D Local AH5 RHR Pump 10 Local AH6 Nuc Serv. Wtr. Pump 1B Local
(? ? BSEP-0/ASSD-02 Page 84 of 202 Rev. 0
I l
- 2. VERIFY Tripped OR Manually TRIP using manual trip pushbutton for l g, the following 4'KT breaker on Emergency Bus E2.
.a. COMPT. AG8 RHR SERV WTR Pump 20
- b. COMPT. AG9 RHR PUMP 2D i i
- c. COMPT. AH2 CONY. SERV. WTR PUMP 1C
- d. COMPT. AH3 CRD HYDRAULIC PUMP IB
- e. COMPT. AH4 RHR SERV. WTR PUMP ID
- f. COMPT. AHS RHR PUMP ID
- g. COMPT. AH6 NUC SERV WTR PUMP 1B 3 REMOVE control power fuses AND VERIFY Tripped OR Manually TRIP the following breakers using the manual trip plt 5h button.
- a. COMPT. AG4 INCOMING LINE SWGR 1C
- b. COMPT. AHO RX CORE SPRAY PUMP 1B
- c. COMPT, AH7 FIRE PUMP NORMAL FEED M y., -
4 VERIFY Closed R CLOSE COMPT. AH1 UNIT SUBSTA E6 4KV breaker (3 using local control switch.
- 5. VERIFY with the Diesel Generator Operator that the seven (7)
Normal / Local switches on Diesel . Generator No. 2 Control Panel are in local.
- 6. VERIFY Reset OR RESET the following 86DB LOCK 0UT Relays located on the compartliients listed below,
- a. COMPT. AG5 P.T. COMPT.
- b. 00HPT AG6 P.T. AUXILI ARY CDHPT.
9 b BSEP-0/ASSD-02 Page 85 of 202 Rev. 0
- 7. DIRECT Diesel Generator Operator to START Diesel Generator No. 2 using the "EMERGENCY START" push button located on the Local (deg)
Control Panel.
- 8. DIRECT Diesel Generator Operator to CLOSE Diesel Generator No. 2 Output breaker fro:n the local control panel WHEN Diesel Generator No. 2 has reached rated speed AND rated voltage.
- 9. START Nuc Sury. Wtr Pump 1B at 00HPT. AH6.
- 10. DIRECT Service Water Building Operator to VERIFY Open OR Hanually OPEN Nuc. Serv. Wtr. Pump 1B disch. valve 1-SW!V20.
- 11. INFORM Unit 2 Shift Forenen that Emergency Bus E2 is re-energized and the necessary Safe Shutdown loads can be restarted.
- 12. The following loads are non-safe shutdown loads and should not be energize 9.
- a. 00HPTs AG4 INCOMING LINE SWGR 1C
- b. 00HPT. AG8 RHR SERV WTR PUMP 2D
- c. COMPT. AHO RX CORE SPRAY PUNP 18 %
- d. 00HPT. AH3 CRD HYDRAULIC PUHF 1B
('_] .
- e. 00HPT. AH4 RHR SERV WTR PUHP 1D
- f. COMPT. AH7 FIRE PUMP NORMAL FEED
- g. COMPT. AH8 TIE BREAXER EMERG SWGR El
_ h. COMPT. AH9 TIE BREAXER EHERG SWGR E4 (iL-BSEP-0/ASSD-02 Page 86 of 202 Rev. 0
RESTORING POWER TO EtERGENCY g.) 120V AC DISTRIBUTION PANEL 2B-DG The purpose of the following steps is to restore power to EMERGENCY 120V AC DISTRIBUTION PANEL 2B-DG in the event that an electrical fault causes the feeder breakers listed below to trip. 480V HCC DGD
- a. COMPT. D49 EMERGENCY 120V AC DISTRIBUTION PANEL 2B-DG SUPPLY BREAKER E!!ERGENCY 120V AC DISTRIBUTION PANEL 2B-DG
- b. IMIN INCOMING FEEDER BREAKER
- 1. TRIP the EMERGENCY 120V AC DISTRIBUTION PANEL 2B-DG loads listed below.
Circuit Number Component Description 1 Diesel Generator Building South Airlock Door Circuit Breaker N 2 Diesel Generator Building Deluge Valve,
~
2-FP-DV15 Circuit Breaker (g, 3 Remote Shutdown Panel RCIC Flow Controller 4 Solenoid Valve, 2-FO-SV-2000 Circuit Breaker 5 Diesel Generator Building Fire Protection Annunciator 2-UA-41 Circuit Breaker 6 Solenoid Valve, 2-FO-SV-2024, Circuit Breaker 7 Diesel Generator No. 4 Engine Control Panel Space Heaters Circuit Breaker 8 Diesel Generator No. 4 Exciter Control Panel Lights And Receptacles Circuit Breaker 9 Diesel Generator Building Deluge Valve, 2-FP-DV14 Circuit Breaker 10 Diesel Generator No. 4 Exciter Panel Space Heaters Circuit Breaker (,- BSEP-0/ASSD'-02 Page 87 of 202 Rev. O
F
- 1. (Cont'd) g _.
Circuit Number Component Description 11 Diesel Generator Building Deluge Valve, 2-FP-DV13 Circuit Breaker 12 Diesel Generator No. 4 Generator Control Panel Instrumentation Circuit Breaker 13 480V Substation E6. Heater And Fan Circuit Breaker 13A Diesel Generator Building H61on Control Panel (Node H1Z) 14 Diesel Generator No. 4 Generator Control Panel Lights And Space Heater Circuit Breaker 15 RHR SW. Pp 2B CONTROL PNL H83 BUS E-4 16 Diesel Generator Building Deluge Valve RB. 2-FP-DV17 Circuit Breaker h* 17 Diesel Generator Building Deluge Valve, 2-FP-DY18 Circuit Breaker 18 RHR SW. Pp 2D CONTROL PNL H81 BUS E-2 19 Diesel Generator Building Deluge Valve, 2-FP-DV19, Circuit Breaker 20 Diesel Generator Building Deluge Valve, 2-FP-DV16, Circuit Breaker 21 Bus Duct Heater For E2-E4 Circuit Breaker 22 DIESEL GEN. BLDG. VENT CELL #2 DMPER CONT. 23 4169 Emergency Bus E4 Heater And Control Bus Circuit Breaker 24 Diesel Generator No. 4 Engine Control Panel Instrumentation Circuit Breaker BSEP-0/ASSD-02 Page 88 of 202 Rev. 0
i
- 2. At 480V HCC DGD VERIFY Closed OR CLOSE 480V breaker COMPT D49 EMERGENCY 120V AC DISTRIBUT10tf7ANEL 2B-DG supply breaker.
@) l
- 3. At EMERGENCY 120V AC DISTRIBUTION PANEL 28-DG VERIFY Closed OR CLOSE MAIN INCOMING FEEDER BREAKER.
- 4. CLOSE the following 120V hreakers to energize EMERGENCY 120V AC DISTRIBUTION PANEL 2B-DG Safe Shutdown loads listed below.
Circuit Number Component Description __ f y. Solenoid Vaive, 2-FO-SV-2000~ Circuit Breaker f, Solenoid Valve, 2-F0-SV-2024, Circuit Breaker 12 Diesel Generator No. 4 Generator Control Panel Instrumentation Circuit Breaker 13A Diesel Generator Building Halon Control Panel (Node MIZ) Diesel Generator No. 4 Engine Control Panel O' 24 Instrumentation Circuit Breaker b 5. INFORM Unit 2 Shift Foreman that Emergency 120V Distribution Panel 2B-DG is Energized. BSEP-0/ASSD-02 Page 89 of 202 Rev. (
RESTORING POWER TO 125V @ DISTRIBUTION PANEL 2B The purpose of the following steps is to restore power to 125V DC DISTRIBUTION PANEL 2B in the event that an electrical fault causes the Feeder breakers listed below to trip. 125/250V DC SWITCHBOARD 2B
- a. COMPT GL6125Y DC Distribution Panel 2B 125V DC Distribution Panel 2B
- a. Main Incoming Feeder Breaker
- 1. TRIP the 125V DC DISTRIBUTION PANEL 28 loads listed below.
Circuit Number Component Description 1 4KV Emergency Bus E2 Alternate Control Power Circuit Breaker 2 4KY Emergency Bus E4 Normal Control Power nnu Circuit Breaker . 3 Diesel Generator No. 2 Alternate Power Supply For Annunciator, Start, And Load Circuit Breaker 4 Diesel Generator No. 4 Normal Power For Annunciator, Start, And Load Circuit Breaker _ 6 Rerrote Shutdown Panel RCIC Turbine EGM Control Box Circuit Breaker 7 ESS Logic Cabinet H61 Circuit Breaker 8 Remote Shutdown Panel Safety Relief Valve Control Power Circuit Breaker 12 HI-WATER LEVEL JACKET ISOLATION PELAYS 14 4 KY Emergency Bus E4 Test Cabinet Circuit Breaker 15 480V Substation E6 Alternate Control Power
, Circuit Breaker h$b BSEP-0/ASSD-02 Page 90 of 202 Rev. 0
- 1. (Cont'd) circuit Number Component Description 16 480V Substation E8 Normal Control Power Circuit Breaker 17 Diesel Generator Building Emergency Lighting Contactor Supply Breaker 19 Flood Status
- 2. At 125/250V DC Switchboard 2B VERIFY Closed OR CLOSE Feeder Breaker COMPT GL6 125V DISTRIBUTION PANEL 287
- 3. At 125V DC Distribution Panel 2B VERIFY Closed OR CLOSE MAIN INCOMING FEEDER Breaker.
- 4. CLOSE the following 125Y breakers to energize 125V DC Distribution Panel 2B Safe Shutdown Loads.
Circuit Number Component Description
) 1 4KV Emergency Bus E2 Alternate Control Power Circuit Breaker 2 4KV Emergency Bus E4 Normal Control Power Circuit Breaker 3 Diesel Generator No. 2 Alternate Power Supply For Annunciator Start, And Load Circuit Breaker 4 Diesel Generator No. 4 Normal Power For Annunciator, Start, And Load Circuit Breaker 6 Remote Shutdown Panel RCIC Turbine EGM Control Box Circuit Breaker 8 Remote Shutdown Panel Safety Relief Valve Control Power Circuit Breaker 15 480V Substation E6 Alternate Control Power Circuit Breaker 16 480V Substation E8 Normal Control Power Circuit Breaker
- 5. INFORM Unit 2 Shift Foreman that 125Y DC Distribution Panel 2B Q}" \. is energized.
BSEP-0/ASSD-02 Page 91 of 202 Rev. 0
I i RESTORING POWER TO EMERGENCY Gj 120V AC DISTRIBUTION PANEL 1B-DG The purpose of the following steps is to restore power to EMERGENCY 120V AC DISTRIBUTION PANEL 1B-DG in the event that an electrical fault causes the feeder breakers listed below to trip. 480V HCC DGB i
- a. COMPT D89 - EMERGENCY 120V AC DISTRIBUTION PANEL 1B-DG SUPPLY BREAKER EMERGENCY 120V AC DISTRIBUTION PANEL 1B-DG
- b. MAIN INCOMING FEEDER BREAKER
- 1. TRIP the EMERGENCY 120V AC DISTRIBUTION PANEL 1B-DG loads listed below.
Ci rcuit Number Component Description 7 Diesel Generator No. 2 Engine Control Panel Space Heaters Circuit Breaker 8 Diesel Generator No. 2 Exciter Control Panel Lights y And Receptacles Circuit Breaker 9 Bus Duct Heater For Buses E2-El __ 10 Diesel Generator No. 2 Exciter Control Panel Space Heater Circuit Breaker 12 Diesel Generator No. 2 Generator Control Panel Instrumentation Circuit Breaker 13 480V Substation E8 Heater And Fan Circuit Breaker 14 Diesel Generator No. 2 Generator Control Panel Lights And Space Heaters Circuit Breaker 15 RIR SW. PP.1D CONTROL PNL H81 BUS E-2 18 RHR SW. PP. 1B CONTROL PNL H81 BUS E4 21 Remote Shutdown Panel RCIC Flow Controller Circuit Breaker h BSEP-0/ASSD-02 Page 92 of 202 Rev. 0
- 1. (Cont'd)
Circuit Number Component Description 23 4160V Emergency Bus E2 Heater And Control Bus Circuit Breaker _ 24 Diesel Generator No. 2 Engine Control Panel Instrumentation Circuit Breaker
- 2. At 480V HCC DGB, VERIFY Closed OR CLOSE 480V Breaker COMPT D89 EMERGENCY 120V AC DISTRIBUTION VINEL 18-DG SUPPLY BREAKER.
- 3. At EMERGENCY 120V AC DISTRIBUTION PANEL 18-DG, VERIFY Closed OR CLOSE MAIN INCOMING FEEDER BREAXER.
- 4. CLOSE the following 120V breaker to energize EMCRGENCY 120V AC DISTRIBUTION PANEL 1B-DG Safe Shutdown loads.
Circuit Number Component Description
. 12 Diesel Generator No. 2 Generator Control Panel (Q ' Instrumentation Circuit Breaker 24 Diesel Generator No. 2 Engine Control Panel Instrumentation Circuit Breaker
- 5. INFORM Unit 2 Shift Foreman that Emergency 120V Distribution Panel 1B-DG is Energized.
k$$q, l BSEP-0/ ASS 0-02 Page 93 of 202 Rev. O !
RESTORING POWER TO 125V Q DISTRIBUTION PANEL 1B The purpose of the folleming steps is to restore power to 125V DC DISTRIBUTION PANEL 1B in the event that an electrical fault causes the fe3 der breakers listed below to trip. 125/250V DC Switchboard 1B
- a. COMPT GL6 125V DC Distribution Panel 1B 125V DC Distribution Panel 1B
- a. Main incoming Feeder Breaker
- 1. TRIP the 125V DC DISTRIBUTION PANEL 1B loads listed below.
Circuit Number Component Description 1 4KV Emergency Bus E2 Test Cabinet Circuit Breaker 3 480V Substation E6 Normal Control Power
. Circuit Breaker g
p.s _ O 5 Remote Shutdown Panel Circuit Breaker _ 6 Diesel Generator Building Emergency Lighting Contactor Supply Breaker _ 7 E3S Logic Cabinet H59 Circuit Breaker 8 Remote Shutdown Pan.il Circuit Breaker 10 BLR #1 ANNUNC (HA4) 12 BLR #2 ANNUNC (HAS) 15 480V Substation E8 Alternate Control Power Circuit Bresker 17 4KV Emergency Bus E2 Normal Control Power Circuit Breaker _ 18 4KY Emergency Bus E4 Alternate Control Power ' Circuit Breaker ( BSEP-0/ASSD-02 Page 94 of 202 Rev. 0
- 1. (Cont'd)
TITcuit Number Component Description 19 Diesel Generator No. 2 Normal Power For Annunciator, Start, And Load Circuit Breaker 20 Diesel Generator No. 4 Alternate Power Supply For Annunciator, Start, And Load Circuit _ Breaker
- 2. At 125/250V DC Switchboard 18 VERIFY Closed OR CLOSE Feeder
- Breaker COMPT GL6125V DISTRIBUTION PANEL 18.-
- 3. At 125V DC Distribution P6nel 18, VERIFY Closed OR~ CLOSE MAIN INCOMING FEEDER BREAKER.
i
- 4. CLOSE the following 125V breakers to energize 125V DC
- Distribution Panel 18 Safe Shutdown loads.
l Ci rcuit Number Component Description I 3 480V Substation E6 Normal Control Power N. Circuit Breaker I 5 Remote Shutdown Panel Circuit Breaker ,
- 8 Remote Shutdown Panel Circuit Breaker l l 15 480V Substation E8 Alternate Control Power ,
Circuit Breaker 17 4KV Emergency Bus E2 Normal Control Power Circuit Breaker i 1 18 4KY Emergency Bus E4 Alternate Control Power 4 Circuit Breaker . _ 19 Diesel Generator No. 2 Normal Power For l Annunciator, Start, And Load Circuit Breaker 1
'20 Diesel Generator No. 4 Alternate Power Supply q For Annunciator, Start, And Load Circuit Breaker S. INFORM Unit 2 shift Forenan that 125V DC Distribution Panel 1B j- . is Energized.
i
- BSEP-0/ASSD-02 Page 95 of 202 Rev. O
l l g SECTION "G" DIESEL GENERATOR OPERATOR ACTIONS
- 1. REPORT to Diesel Generator No. 4 AND ESTABLISH comunications with Unit 2 RSDP using sound powered phone jack labeled REMOTE SHUTDOWN TRAIN 'B' (UNIT #2) SOUNn POWERED PHONE CKT. located on DG #4 Control Panel H57,
- 2. IF Diesel Generator No. 4 is Operating. THEN VERIFY Open Service Water Valve 2-SW-V255 at MCC 000 AND VERIFY Service Water pressure is greater than 25 psig on P1 153 at DG No. 4 Control Panel .
- 3. IF Service Water Valve 2-SW-V255 is Closed OR Service Water Fessure is less than 25 psig, THEN PERFORMThe following:
- a. PERFORM Step 5.b.
- b. DEPRESS "EMERGENCY STOP" push button on DG No. 4 Control Panel.
- c. PERFORM Step 16.b.
- d. DEPRESS "EMERGENCY STOP" push button on DG No. 2 Control Panel.
G}, e. CONTINUE procedure at Step 4 K0,/
~ ~ ~ ~
- 4. Dr2termine the status of Emergoney Bus E4 using the indicators Jisted below AND INFORM Unit 2 Shift Foreman.
Local Generator Control Panel (H57) _~
- a. Emergency Bus E4 energ! zed or de-energized as indicated by voltmeter labeled "VOLTMETER 4160V BUS".
- b. Diesel Generator No. 4 Operating 3., n>t Operating.
- 5. PERFORM Normal / Local switch AND Auxiliary equipment lineup as follows:
- a. At MCC-0GD (1) Compt. 068 - PLACE Normal / Local switch for Supply Fan, 0-SF-DG, in "LOCAL" AND Start /Stop control switch in "STXRT".
(2) Compt. DS9 - PLACE Normal / Local switch for Exhaust Fan, H-EF-0G, in "LOCAL" AND Start /Stop control switch in "STAW. (3) Compt. E18 - PLACE the Normal / Local switch for 2-SW-V255 in "LOCAL". hb BSEP-0/ASSD-02 Page % of 202 Rev. O
- b. At Diesel Generator No. 4 Control Panel (H57)
'O ********************************i*********************************************
CAUTION There are seven (7) keylocked normal / local switches located on Diesel Generator No. 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. (1) PLACE the six keylocked Normal / Local switches in the "LOCAL" position. (2) PLACE the seventh keylocked Normal / Local switch, located above the row of keylocked Normal / Local switches, in "LOCAL" position.
- r. . At 480V Substation E8 (1) Compt. FN2 - PLACE the Normal / Local switch for Sub. E8 480V Main Breaker in the "LOCAL" position AND VERIFY Closed OR CLOSE 'M' Sub. E8 480V Main Breaker from compartment m FN2.
Q3 (2) Compt. AZ6 - TRIP Reactor Building MCC 2XH ^ (3) Compt. A03 - TRIP Reactor Building MCC IXX (4) Compt. A04 - TRIP Reactor Building HCC 2XF (5) Compt. A07 - TRIP Reactor Building MCC 2Xti
, (5) Compt. A09 - TRIP Control Building HCC 2CB (7) Compt. A12 - TRIP Emergency 190V AC l
Distribution Panel 2E8 l 6 IF Diesel Generator No. 4 is not running, _THEN OPEN the circuit Tr~eaker EF?, Diesel Generator No. 4 Jacket Water Cooler Supply Isolation Valve 1-SW-V213, located on HCC DGD. i 7 INFORM Unit 2 Shif t Foreman that Diesel Generator No. 4 lineup is Complete AND Diesel Generator No. 4 is ready to be started.
- 8. IF Diesel Generator No. 4 is running and supplying power to
.Tiiiergency Bus E4 THEN G0 to Step 12.
(!b. BSEP-0/ASSD-02 Page 97 of 202 Rev. O
- 9. THEN START Diesel Generator No.
I WHEN directed 4 by depressing the by Shifi; Foreman, "EMERGENCY S TKRT" push button on the Local fy" Control Panel.
- 10. WHEN Diesel Generator No. 4 has reached rated speed (514 RPM) l IND~is at rated voltage (4160V) THEN l
PLACE synchronizing switch labeled "SYNCHRONIZING a. l GENERATOR" in the "0N" position,
- b. CLOSE Diesel Generator No. 4 Output breaker by placing control switch labeled "GENERATOR CIRCUlT BREAKER" in the "CLOSED" position.
- 11. At NCC DGD Compartment EF4, VERIFY Service Water Valve 2-SW-Y255 is Open, OR., OPEN 2-SW-Y255 using Control Switch j located at MCC DGD compartment E18.
- 12. INFORM Unit 2 Shift Foreman that Diesel Generator No. 4 is running and supplying Emergency Bus E4
- 13. IF circuit breaker EF7 for Diesel Generator No. 4 Jacket Water T6oler Supply Isolation Valve,1-SW-V213, on MCC DGD was opened in Step 6 THEN WHEN Service Water Pressure (PI-153) as indicated on Diesel Generator No. 4 Local Control Panel is greater than ?5 psig, l
- d. THEN CLOSE 480V circuit breaker for Diesel Generator No. 4 ,
kM Jacket Water Cooler Supply Isolation Valve,1 SW-7213, at MCC DGD compartment EF7
- 14. RE-LOCATE phone comunication from Diesel Generator No. 4 to Diesel Generator No. 2. RE-ESTABLISH comunicatien with Unit 2 sound powered phone jack labeled REMOTE i
RSDP SHUTDOWN Operator TRAIN "B" using(UNIT #2) SOUND P0WERED PHONC CKY. located on l Diesel Generator No. 2 Cor. trol Panel (H55). l 15. Determine the status of Emergency Bus E2 us'ing the indicators I listed below AND INFORM Unit 2 Shift Foreman. l Loc.a1 Generator Control Panel (H55)
- a. Emergency Bus E2 energized or de energized *as indicated by voltmeter labeled "VOLTHETER 4160V BUS".
- b. Diesel Generator No. 2 Operating OR, not Operating.
(Y - BSEP-0/ASSD-02 Page 98 of 202 Rev. 0 A _ _ _ _ _ _ _ _ _ _ _ . _ _
- 16. PERFORM Normal / Local switch AND Auxiliary Equipment lineup as g follows:
- a. At MCC-DGB (1) Compt. DZ9 - PLACE Normal / Local switch for vent supply air f an B-SF-DG in "LOCAL" ,
AND Start /Stop control switch in "START". (2) Compt. D99 - PLACE Normal / Local switch for exhaust air fan F-EF-DG in "LOCAL" AND Start /Stop control switch in "STARTV
- b. At Diesel Generator No. 2 Control Panel (H55)
CAUTION There are seven (7) keylocked normal / local switches located on Diesel Generator No. 2 Control Panel. Six 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. (1) PLACE the six keylocked Normal / Local switches in the "LOCAL" position. g h, , (2) PLACE the seventh keylocked Normal / Local switch, located above the row of six keylocked Normal /Lecal switches, in "LOCAL" position.
- c. At 480V Substation E6 (1) Compt. FNO - PLACE the Normal / Local switch for Sub E6 480V Main Breaker in the LOCAL position AND VERIFY closed OR CLOSE Sub E6 480V Main breaker from compartment FNO.
(2) Compt. AV5 - TRIP Reactor Building MCC 1XH (3) Compt. AW1 - TRIP Reactor Building MCC 2XX (4) Cont. AW2 - TRIP Reactor Building MCC 1XF (5) Compt. AW4 - TRIP Off Gas Building MCC 20G (6) Compt. AW5 - TRIP Reactor Building MCC 1XM (7) Compt. AW7 - TRIP Control Building MCC 1C8 (8) Compt. AX3 - TRIP Emergency 120V AC g , Distribution Panel 1E6 supply breaker BSEP-0/ASSD-02 Page 99 of 202 Rev. 0 ,
- 17. INFORM Unit 2 Shift Foreman that Diesel Generator No. 2 lineup
() is Complete AND Diesel Generator No. 2 is ready to be started.
- 18. IF Diesel Generator No. 2 is running and supplying power to Tiiiergency Bus E2 THEN GO to Step 21.
- 19. WHEN directed by Unit 2 Shift Foreman, THEN START Diesel Generator No. 2 by depressing the "EMER'GiCY START" push button on the Local Control Panel.
- 20. WHEN Diesel Generator No. 2 has reached rated speed (514 RPM)
D T is at rated voltage (4160V) THEN
- a. PLACE synchronizing switch labeled "SYNCHRONIZING GENERATOR" in the On position,
- b. CLOSE Diesel Generator No. 2 Output breaker by placing control switch labeled "GENERATOR CIRCULI BREAXER" in the closed position.
- 21. INFORM Unit 2 Shif t Foreman that Diesel Generator No. 2 is Running AND Supplying Emergency Bus E2.
- 22. BLOCK OPEN Diesel Generator Building doors, as indicated on Attachment 1 to Section G, to establish ventilation for Diesel Generator operations. Ma
- 23. WHEN directed by Shif t Foreman THEN PLACE Diesel Generator No. 3 Tn~ Tocal control by completing the steps below,
- a. At HCC-DGC l (1) Compt. N7 - PLACE Normal / Local switch for l Supply Fen, C-SF-DG, ir. "LOCAL" AlO Start /Stop control switch in "SfART".
1 l (2) COMPT. DJ6 - PLACE Nonnal/ Local switch for l Exhaust Fan, G-EF-DG, in "LOCAL" AND l Start /Stop control switch in "STAW.
- b. At Diesel Generator No. 3 Local Control Panel (1) PLACE the six (6) Normal / Local switches located in the "LOCAL" position.
- c. At 480V Substation E7 (1) Compt. FN1 - PLACE the Normal / Local switch for Substation E7 480V main breaker in "LOCAL" AND VERIFY Closed OR CLOSE Sub. E7 480V MailiTreaker from comliartment FN1.
BSEP-0/ASSD-02 Page 100 of 202 Rev. O
- 24. INFORH Unit 2 Shift Foreman that Diesel Generator No. 3 is
@ Operating OR that Diesel Generator No. 3 is NOT Operating AND that DieseTGenerator No. 3 is in LOCAL control.
- 25. WHEN DIRECTED by Unit 2 Shift Foreman, IF Diesel Generator No. 3 is Operating THEN TRIP Diesel Gene'ratorTo. 3 circuit breaker AND STOP Diesel Generator No. 3 by depressing "EMERGENCY STOP" pushbutton.
- 26. WHEN directed by Shift Foreman THEN PLACE Diesel Generator No.1 in local control by completing the steps below,
- a. At HCC DGA (1) Compt. DR7 - PLACE Normal / Local switch for supply f an, A-SF-DG in "LOCAL" AND Start /Stop control switch in "STAR".
(2) Compt. DRS - PLACE Normal / Local switch for service water valve 1-SW-V255 in "10 CAL" position. (3) Compt. DR6 - PLACE the Normal / Local switch for Exhaust Fan E-EF-DG in the "LOCAL" position AND Start /Stop control switch in N "START". (? l 6,,, _,,, b . At Diesel Generator No. 1 Local Control Panel (1) PLACE the six (6) keylocked Normal / Local l switches in the "LOCAL" position.
- c. At 480V Substation ES (1) Coupt FH9 - PLACE the Normal / Local switch for Sub E5 480v Hain Breaker in the "LOCAL" position AND VERIFY Closed OR Ct.0SE Sub ES 480V MainTFeaker f rom compaFtment FH9.
- 27. INFORM Unit 2 Shift Foreman that Diesel Generator No.1 is Operating OR that Diesel Generator No.1 is NOT_ Operating AND that DieseTGenerator No.1 is in Local control.
- 28. WHEN directed by Unit 2 Shift Foreman, IF Diesel Generator No.1 is operating THEN TRIP Diesel GeneratorTo.1 output breaker AND STOP Diesel Generator No.1 by depressing the "EHERGENCY STOP" pushbutton.
9
.3 V. .. -
BSEP-0/ASSD-02 Page 101 of 202 Rev. O
RESTORING POWER TO 480V SUBSTA E8
@)
The purpose of the following steps is to restore power to 480V SUBSTA E8 in the event that an electrical fault causes 4KV breaker on Emergency Bus E4 or 480V Sub E8 Main breaker to trip. !
- 1. TRIP the 480V Substa E8 loads listed below Compartment Number Component Description AZ6 Reactor Building MCC 2XH AZ7 Standby Distribution Panel E12 AZ8 S. Adby Distribution Panel E11 AZ9 Reactor Building MCC 1XB-2 l A02 Reactor Building MCC 2X8 A03 _
Reactor Building MCC 1XK Reactor Building MCC 2XF E gh , A04 A05 Service Water Building MCC 2P'4 l A0/ , _ Reactor Building MCC 2XM i A08 Reactor Building MCC 2XD ! A09 Control Building MCC 2C8 A10 Tie breaker To E7 , _ A01 Diesel Generator Building MCC DGD A12 Emergency 120V AC Distribution Panel 2E8
'Q BSEP-0/ASSD-02 Page 102 of 202 Rev. 9
- 2. At Emergency Bus E4 VERIFY Closed OR-CLOSE COMPT. AX7 UFIT
(@ SUBSTA E8 4XV breaker.
- 3. VERIFY Closed OR CLOSE SUB E8 480V MAIN BREAXER AZ5 from COMPT.
FN2 using control switch.
- 4. CLOSE the following 480V breakers to energize 480V SUBSTA E8 Safe Shutdown loads listed below.
- a. COW T. A02 REACTOR BUILDING HCC 2XS '
- b. COMPT. A01 DIESEL GENERATOR BUILDING MCC DGD
- c. COMPT. A08 REACTOR BUILDING MCC 2XD
- d. COMPT. A05 SERVICE WATER INTAKE STRUCTURE MCC 2PB
- e. C0WT. AZ9 REACTOR BUILDING MCC 1XB-2
- 5. INFORM Unit 2 Shift Foreman that Substation E8 is Energized and -
the breakers for Safe Shutdown loads that are not in the fire area are Closed. , RI 1 (7)! . r r l i
@.y ,
BSEP-0/AS$0-02 Page 103 of 202 Rev. O
RESTORING POWER TO DIESEL GENERATOR BUILDING HCC DGD The purpose of the following steps is to restore power to Diesel Generator Building HCC DGD in the event that an electrical fault causas 480V Feeder breaker to MCC DGD to trip.
- 1. OPEN the following 480V circuit breakers on HCC DGD.
Compartment Number Component Description D49 Emergency 120V AC Distribution Panel 2B-DG Supply Breaker 0 54 Diesel Generator No, 4 Starting Air Compressor 1 Circuit Breaker D55 Diesel Generator No. 4 Fuel Oil Transfer Pump 4A Circuit Breaker DS9 Exhsust Fan H-EF-DG Circuit Breaker D60 Diesel Generator No. 4 Crankcase Vacuum Blower Circuit Breaker % m W D64 Diesel Generator No. 4 Start'ng Air Compressor 2 Circuit Breaker , 067 Diesel Generator No. 4 Fuel Oil Transfer Pump 2B Circuit Breaker - EF4 Service Water Valve 2-SW.V255. Circuit Breaker (F6 Diesel Generator No. 4 Jacket Water Cooler H0 Supply Isolation Valve, 2-SW-V213, Circuit Breaker EF7 Diesel Generator No. 4 Jacket Water Cooler Supply Isolation Valve,1-SW-Y213, Circuit Breaker BD6 Distribution Panel 2-FB-1 Supply Breaker D2A Off Gas Stack Rad Hon Building Distribution Panel Supply Breaker (~ . BSEP-0/ASSD-02 Page 104 of 202 Rev. O
- 1. (Cont'd)
Yh Compartment Number . Component Description D43 Diesel Generator No. 4 Jacket Water Pump Circuit Breakkr 046 SERVICE NO 6 DIESEL GENERATOR NO. 4 COND RECEIVER PU 9 D47 Diesel Generator No. 4 Fuel Oil Booster Pug Circuit Breaker D48 Diesel Generator No. 4 Filter And Prelube Pug Circuit Breaker D50 Diesel Generator No. 4 Jacket Water Heater Pump Circuit Breaker D51 Exhaust Fan D-EF-DG Circuit Breaker yS2 Exhaust Fan M-EF-DG Circuit Breaker 3*] 0 53 Diesel Generator No. 4 Jacket Water Heater ,g Circuit Breaker , { 057 Smok) Removal Fan 20-SFSR-DG Circuit Breaker ,
- D61 Diesel Generator No. 4 Barring Gear Circuit Breaker D62 Diesel Generator No. 4 Crankcase Drain / Fill Pump Circuit Breaker 063 Diesel Generator No. 4 Lube Oil Filter Heater Circuit Breaker 065 Diesel Generator No. 4 Auxiliary Lube Oil Pump Circuit Breaker 066 Diesel Building Sump Pump 2G-1 Circuit Breaker D68 Supply Fan D SF DG Circuit Breaker D69 SERVICE NO 5 CONU RECEIVER PUN.6 A-CRP-DG 1 01sconne'.t .
Switch 9KVA 39 480-208Y/120V Transformer ! j.. BSEP-0/ASSD-02 Page 105 of 202 Rev. 0
- 2. CLOSE 480V feeder breaker COMPT A01 DIESEL GENZRATOR BUILDING g
e MCC DGD located on 480V SUBSTA E8.
- 3. CLOSE the following 480V circuit breakers on MCC DGD to energize the Safe Shutdown loads.
1.~ohartment Num>er Component Description D49 Emergency 120V AC Distribution Panel 28-DG Supply Breaker D54 Diesel Generator No. 4 Starting Air Compressor 1 Circuit Breaker D55 Diesel Generator No. 4 Fuel Oil Transfer Pump 4A Circuit Breaker DS9 Exhaust Fan V EF-DG Circuit Breaker D60 Diesel Generator No. 4 Crankcase Vacuum Blower I
~
Circuit Breaker D64 Diesel Generator No. 4 Starting Air Compressor 2 E Circuit Breaker 06 Diesel Generator No. 4 Fuel Oil Transfer Pump 4B , Circuit Breaker l EF4 Service Water Valve 2-SW-Y255, Circuit 3reater EF6 Diesel Generator No. 4 Jacket Water Cooler M0 Supply Isolation Valve, 2-SW-V213, Circuit Breaker EF7 Diesel Generator No. 4 Jacket Water Cooler Supply Isolation Yalve,1-SW-Y213, Circuit Breaker 4 INF0RM Unit 2 Shift Foreman that MCC DGD is Energized and Safe Shutdown load breakers are Closed. 6 l (5 - ' ! BSEP-0/ASSD-02 Page 104 of 202 Rev. O
- s i RESTORING POWER TO 480V lh SUBSTA E6 l
The purpose of the following steps is to restore power to 480V SUBSTA E6 in the event that an electrical f ault causes 4KV breaker on Emergency Bus E2 or 480V Sub E6 Main breaker to trip, s
- 1. TRIP the 480V Substa E6 loads listed below, ,
l Compartment Number Component Description , AVS Reactor Building MCC 1XH AV6 480V Lighting Distribution Panel E10 AV7 480V Lighting Distribution Panol E9 t AV8 Reactor Building MCC 2XB-2 i AV9 Diesel Generator Building MCC DGB , AWO Reactor Building MCC 1XB g' AW1 Reactor Building MCC 2XK g3 AW2 Reactor Building MCC 1XF AW3 Service Water intake Structure Mr.C 1PB AW4 Off Gas Building MCC 20G AWS Reactor Building MCC IXM j AW7 Control Building MCC 108 _ l AX1 Tie Breaker lo E5 l AW6 Re$ctorBuildingMCC110 l AX3 Emergency 120V AC Distribution Panel l 1E6 Supply Breaker , bk. BSEP-0/ASSD-02 Page 107 of 202 Rev. 0
- 2. At Emergency Bus E2, VERIFY Closed OR~ CLOSE COMPT. AH1 UNIT Qi! SUBSTA 3Y 4KV breaker.
- 3. VERIFY Closed OR CLOSE SUB E6 480V MAIN BREAKER AV4 from COWT.
FNO using control switch.
- 4. CLOSE the following 480V breaker to energize 480V SUBSTA E6 Safe Shutdown loads listed below.
Compartment Number Component Description AV8 REACTOR BUILDING MCC 2XC-2 AV9 DIESEL GENERATOR BUILDING MCC DGB AWO REACTOR BUILDING MCC-1XB AW3 SERVICE WATER INTAKE STRUCTURE MCC 1PB AW6 REACTOR BUILDING MCC 1XD
- 5. INFORM Unit 2 Shift Foreman that Substation E6 is Energized and RE the breakers for Safe Shutdown leads that are not in the fire y area are riosed.
I t
@(, -
l BSEP-0/AS$0-02 Page 108 of 202 Ray. 0 ' l e _
RESTORING POWER TO DIESEL
@ GENERATOR BUILDING MCC DGB The purpose of the following steps is to restore power to Diesel Generator Building MCC DGB in the event that an electrical fault causes 480V Feecler breaker to MCC DGB to trip.
- 1. OPEN the following 480V circuit breakers on MCC DGB.
tomartment Numar Component Description DY6 Diesel Generator No. 2 Crankcase Vacuum Blower Circuit Breaker DZ5 Diesel Generator No. 2 Starting Air Compressor 2 Circuit Breaker DZ8 Diesel Generator No. 2 Fuel Oil Transfer Pump 2B Circuit Breakea D89 Emergency 120V AC Distribution Panel 18-DG Supply Breaker p 0 94 Diesel Generator No. 2 Starting Air Cogressor 1 Circuit Breaker D95 Diesel Generator No. 2 Fuel Oil Transfer Pug 2A Circuit Breaker D99 Exhaust Fan F-!F-DG Circuit Breaker 1 EC3 Diesel Generator No. 2 Jacket Water Cooler Supply Isolation Valve, 2-$W-V2M. Circuit Breaker EC4 Diesel Generator No. 2 Jacket Water Cooler Supply Isolation Valve, 1-SW-V211, Circuit Breaker DY4 Diasel Generator No. 2 Jacket Water Pug Circuit Breaker _ DY5 Diesel Generator No. 2 Jacket Water Heater Pug Circuit Breaker DY7 Diesel Generator No. 2 Barring Gear Circuit Breaker O_. . BSEP-0/ASSD-02 Page 109 of 202 Rev. D
-]
- 1. (Cont'd)
Compartment Component Description Number DY8 Diesel Generator No. 2 Crankcase Drain / Fill Pump Circuit Breaker DY9 Diesel Generator No. 2 Lube Oil Filter Heater Circuit Breaker DZ6 Diesel Generator No. 2 Auxiliary tube Oil Pump Circuit Breaker DZ9 Vent Supply Air Fan B-SF-DG Circuit Breaker D91 Swgr. Room Exhaust Fan B-EF-DG Circuit Breaker 092 Swgr. Room Exhaust Fan J-EF-DG Circuit Breaker D93 Diesel Generator No. 2 Jacket Water Heater Circuit Breaker EC1 Smoke Removal Fan 28-SFSR-DG Circuit Breaker o Disconnect V Switch 9KVA 39 480-208Y/120V Transformer 88. A51 Distribution Panel, 2-FB-2, Supply Breaker DY2 Diesel Generator llo. 2 Fuel Oil Booster Pump Circuit Breaker DY3 Diesel Generator No. 2 Filter And Prelube Pump Circuit Breaker
- 2. CLOSE 480V feeder breaker COMPT AV9 DIESEL GENERATOR BUILDING MCC DGB located on 480V SUBSTA E6.
en
%E ' .
BSEP-0/ASSD-02 Page 110 of 202 Rev. O
- 3. CLOSE the following 480V circuit breakers on MCC DGB to energize g
~, the Safe Shutdown loads. C artment ! Nu r Component Description l i DY6
' Diesel Generator No. 2 Crankcase Vacuum Blower i circuit gresker. .. .... ... . .... .. .. ..
j DZ5 Diesel Generator No. 2 Starting Air Compressor 2 ; Circuit treaker. - - - - - i i DZB ' Diesel Generator No. 2 Fuel Oil Transfer Pug 28 I
- Circuit Breaker -
[ ! 089 Emerfy Supp treaker -ency 120V AC Distribution Panel 18-06 - - - t i DM Diesel Generator No. 2 starting Air cogressor 1 i Circuit Breaker- - - - - - - ! 0 95 Diesel Generator No. 2 Fuel 011 Transfer Pug ! 2A Circuit Breaker - - t
- G D99 Exhaust Fan F-EF-DG Circuit treaker 1
! EC3 Diesel Generator No. 2 Jacket Water Cooler i 1 j Supply Isolation Valve, 2-$W-V211 Circuit ' l Breaker. - - - - - - - { EC4 Diesel Generator No. 2 Jacket Water Cooler f 3 Supply Isolation Valve,1-$W-V211. Circuit ! y Breaker - - - 1 l 4 INFORM Unit 2 shift Foreman that MCC DGB is Energized and Safe l
- Shutdown load breakers are Closed.
1
, SSEP-0/ASSD-02 Page 111 of 202 Rev. O
SECTION G l ', h DIESEL GENERATOR VENTILATION
- I
- 1. OPEN/ BLOCK OPEN doors identified on drawing below. !
l
- 2. BL0dt, OPEN doors using door wedge blocks.
4 < 10 5 10 5 10e 10 7 108 109 110 IN lit l13 11 4 101 10 4 l'
------n h.---- e, -
- laggi n of e . - .-- at" /
t" L y,....-.--l I'Q l
- g I l,(_,l.t 5 l := l,l:8 =
,1 I . IM
- l. l- :l ga
- W n
s l I " "1 1 8,:3. 8] j 1 ) m j , c{ .c
- - _ <r. s s al :e
- s
- i - i. I I I I w ai s ;
10 2 miamu l l . ..... . I ,,,
, ,1 , ,
Epmm 4 mum ). , , , ,
.--------------------------------------------------A I
) <--------. EL.23'-O' i l i 1 ! > l i 1 i i i i i
. ATTACHMENT 1 l l l l Diesel Generator Building Door Position '
j For i Diesel Cell Ventilation !
.,n
,R$' -
l . l BSEP 0/ASSD-02 Page 112 of 202 Rev. 0 l
l
, SECTION "H" i(*).
UNIT 1 SHIFT FOREMAN ACTIONS
- 1. ESTABLISH comunication with other Remoso Shutdown stations l using the phone jack labeled f!E TO UN:T 2 REMOTE SHUTDOWN l PANEL SOUND POWERED PHONE" on the RSDP.
l l NOTE The Unit 1 Shift Foreman will be on the Remote Shutdown Train B (Unit 2) Sound Powered Phone l Ckt. The Unit 1 RSOP operator and Unit 1 Reactor i Building MCC operator will be on the Remote l l Shutdown Train B (Unit 1) Sound Powered Phone Ckt. The Unit 1 Shift Foreman and Unit 1 l RSDP operator will use voice communication to coordinate the Unit 1 Shutdown.
- 2. IF any of the following conditions should occur THEN Rapidly WPRESSURIZE the Reactor Vessel using Appendix 6.
- a. Reactor vessel level as indicated on 1-B21-L1-604BX decreased to 45 inches OR indication of Reactor Vessel level is lost. g l
b NOTES l The loss of Drywell cooling can be confirmed by monitoring points #1, #3 and #4 on recorder l 1-CAC-TR-778 located on the Remote Shutdown Panel. The time the event occurred can be determined from l the chart paper speed. Drywell cooling may be lost due to fire damage. It will be lost in the performance of this procedure,
- b. Loss of Drywell cooling has occurred and Reactor l Vessel cooldown rate of 100 0 F/hr. or greater has not started within'1 hour of the loss of Drywell cooling.
k BSEP-0/ASSD-02 Page 113 of 202 Rev. O L
- c. Failure of any SRV (1-B21-F013E, G, or B) to open
@ using the local control switches on the Remote Shutdown Panel,
- d. The continuous SRV pneumatic supply is or becomes unavailable as confirmed by the following:
NOTE The Div. I and Div. Il N2 Backup Systera isolation valves will fail to the open position when the Diesel Generator Operator de-energizes MCC-1CA (Section G. Step 28) and Emergency 120V AC Distribution Panel 1E6 (Section G, Step 16.c)
- 1. Np Backup System isolation valves are Open (5tep 16.c and Step 28 of Section G have beenperformed).
AND
- 2. N2 Backup System Div. I pressure as indicated on 1-RNA-PI-5266 h less than 70 psig.
AND RB.I
- 3. N2 Backup System Div. Il pressure as
'@, indicated on 1-RNA-PI-5264 is less than 70 psig.
- 3. WHEN:
- a. INFORMED by Unit 2 Shift Foreman that:
(1) Diesel Generators No. 4 AND No. 2 are running AND supplying Emergency Buses E4 AND E2 ARi~
~ (2) INFORMED by Unit 1 RSDP Operator that the switch alignment for Unit 1 Reactor Building MCC is COWLETE
_THEN:
- c. DIRECT Unit 1 RSDP Operator to COORDINATE wit' Reactor Building MCC Operator to PLACE Suppression Pool in recirculation using RHR Loop B.
(1) WHEN directed by Unit 1 RSDP Operator, TRER DIRECT Emergency switchgear Operator T5 TTART RHR Pump 1D. (2) WHEN informed by Emergency Switchgear 53 Operator, THEN INFORM Unit 1 RSDP Operator k.' that RHR Pump 1D is Running. BSEP-0/ASSD-02 Page 114 of 202 Rev. O
i q Lj
- 4. WHEN:
- a. RCIC is operational AND maintaining Reactor Yessel water level greater than +70", AND
- b. Suppression Pool Cooling is in recirculation using RHR Loop B. THEN
- c. DIRECT the RSDP Operator to BEGIN plant depressurization 0
and cooldown at greater than ! 100 F/hr using SRV's and RCIC.
- 5. DIRECT Unit 1 RSDP Operator to DIRECT Reactor Building MCC Operator to CLOSE 1-SW-Y106 AND 1-SW-V118.
- 6. WHEN informed by Unit 1 RSDP Operator that 1-SW-V106 A!O T-3-Y118 are Closed THEN ESTABLISH Service Water flow through RHR Heat Exchanger "B' Tor suppression pool cooling AND shutdown i cooling as follows: '
- a. DIRECT Service Water Building Operator to MONITOR Unit 1 Nuclear Service Water pressure _AND INFORM Unit t 1 Shift Foreman when pressure decreases to 40 psig.
- b. DIRECT RSDP Operator to have Reactor Building MCC t Operator THROTTLE Oprn 1-E11-PDV-F068B.
@ c. WHEN informed by Service Water Building Operator that y I
f Unit 1 Nuclear Service Water pressure has decreased . to 40 psig THEN Imediately DIRECT RSDP Operator 9 ( L Operator to have Reactor Building MCC Operator STOP ! Throttling Open 1-E11-PDV-F068B.
- 7. WHEN informed by RSDP Operator that reactor pressure is less than 125 psig THEN DIRECT RSDP Operator to have Reactor Building -
MCC Operator ST5F Suppression Pool Cooling. t'
- a. THEN DIRECT WHEN Emergency directed by Operator Switchgear Unit 1 RSDP Operator, to STOP R ER7 ump 10. l i
- b. WHEN informed by Emergency Switchgear Operator, THEN i TRT6RM Unit 1 RSDP Operator that RHR Pump 10 is ,
Stopped. ! t
- 8. WHEN informed by RSDP Operator that Suppression Pool Cooling has !
been Stopped THEN DIRECT RSDP Operator to COORDINATE with 4 Operators and 7[KCE RHR Loop "B" in Shutdown Cooling. {
- a. WHEN directed by RSDP Operator THEN DIRECT Emergency I
, Twitchgear Operator to START RIE Tump 10. i I
- b. WHEN informed by Emergency Switchgear Operator, THEN '
@, TsTURM RSDP Operator that RHR Pump 10 is Running. i BSEF-0/AS3D-02 Page 115 of 202 Rev. O
kp 9. IF mheup water is needed to raise reactor water level while in d liiutdown Cooling, THEN PERFORM the following as directed,
- a. WHEN directed by Unit 1 RSDP Operator, THEN DIRECT Emergency Switchgear Operator to STOP RHR PLmp 10.
- b. WHEN informed by Emergency Switchgear Operator, THEN TEMRM Unit 1 RSDP Operator that RHR Pump 10 is Stopped.
- c. WHEN directed by Unit ' RSDP Operator, THEN DIRECT Emergency Switchgear Oprator to START WPump 10.
- d. WHEN informed by Emergency Switchgear Operator THEN TRMRM Unit 1 RSDP Operator that RHR Pump 1D is Running.
.0. IF Rapid Depressurization of Reactor was performed THEN PLACE WR System in Shutdown Cooling WHEN the lineup to stop LPCI Mode is Complete by performing the fM Ewing:
- a. IF service water flow through RHR HX 1B has NOT been TreviouslyestablishedTHEN
- (1) DIRECT Unit 1 RSDP Operator to have Reactor Building MCC Operator PERFORM Step @'G 6 of Section "J" (To verify closed or manually close 1-SW-V106 and 1-SW-V118.) w (2) PERFORM Step 6 above. D T
- b. WHEN service water flow through RHR HX IB is Established THEN DIRECT RSDP Operator to COORDINATE with Operators to PLACE RHR Loop "B" in Shutdown Cooling using applicable steps 07 their designated -
Section.
- 11. WHEN informed by Unit 1 RSDP Operator that RCIC System operation is not longer required and is being shut down, THEN DIRECT S.A.O. to Manually CLOSE HPCI and RCIC Combined Suction From CST Isolation Valve,1-CO-V127, locally at Unit 1 CST.
___ 12. CONTINUE Shutdown Cooling operation as required to achieve AND maintain Reactor pressure at 0 psig until an alternate method of determining Reactor water temperature is provided.
- 13. RETURN plant to General Operating Condition as directed by Plant Management.
h BSEP-0/ASSD-02 Page 116 of 202 Rev. 0 1
gg SECTION "1" UNIT 1 CONTROL ROOM OPERATOR (REMOTE SHUTDOWN PANEL OPERATOR) ACTIONS
- 1. REPORT to Unit 1 RSDP Operator AND ALIGN switches on RSDP listed in table below as follows:
- a. PLACE control switch in position THEN
- b. PL ACE Normal / Local switch to "LOCAL" EQulPMENT CONTROL NORMAL / LOCAL NUMBER DESCRIPTION SWT POS SWT POS 1-E51-CS-3314 RCIC Flow Controller N/A LOCAL 1-SW-V143 Well Water Supply Valve CLOSED LOCAL 1-E51-RS-SS RCIC Turb Trip Logic N/A LOCAL Remote Shutdown Train "B" (Unit 1) Control Rm isolation Sw. N/A LOCAL R I'l 1-821 -F 013E Manual Relief Valve E %FF LOCAL h
1-821-F013G Manual Relief Valve G *0FF LOCAL 1-B21-F013B Manual Relief Valve B *0FF LOCAL 1-SW-V141 Well Water To Vital Header CLOSED LOCAL 1-821 -CS-3345 Reactor Water level N/A LOCAL
- Control switch is spring return to 0FF position.
- 2. ALLOW SRV's to operate at their mechanical setpoint to conserve accumulator air.
NOTE To save time, establishing comunications with other operators on the ASSD sound powered phone system can
'be performed simultaneously with the implementation of other steps in this procedure.
$? BSEP-0/ ASS 0-02 Page 117 of 202 Rev. O
- 3. ESTABLISH sound powered phone comunications as follows:
@,9
- a. PLUG sound powered phone headset into 25' sound powered phone extension cord AND PLUG extension cord into sound powered phone jack on RSDP labeled REMOTE SHUTDOWN TRAIN "B" (UNIT #1) SOUND POWERED PHONE CXT.
- b. HAN sound powered phone headset AND ESTABLISH comunications with Unit 1 Reactor Building MCC Operator.
4 OBSERVE RSDP indication for RCIC system status THEN INFORM Shift Foreman of one of the following conditions.
- a. RCIC is Running
- b. RCIC is NOT Running AND turbine indicates Tripped,
- c. RCIC is NOT Running AND turbine does N0_T, indicate Tripped.
- 5. E RCIC is running THEN PERFORM the following:
- a. ANUST RCIC Flow Controller 1-E51-FIC-3325 setpoint tape as necessary to maintain Reactor Vessel level between 170' and 200" as indicated on 1-B21-LI-604BX at RSDP. g
('.) b. WHEN informed by Reactor Butiding MCC Opertator that the switch lineup for MCC 1XDB is Cog lete THEN (1) INFORM Reactor Building MCC Operator that the RCIC System is Running. (2) DIRECT Reactor Building MCC Operator to TRANSFER 1-E51-F007 AND 1-E51-F062 from normal power supply to ASSD power supply per Step 3 of Section J.
- 6. IF RCIC is NOT running THEN START RCIC turbine by performing the To11owing:
NOTE 1 1-E51-F045 may have closed due to high reactor water level. NOTE 2 1-E51-Y8 may have tripped closed on turbine overspeed. If this has occurred, the RCic Turbine Trip light will NOT be 111uminated and the valve will still ir.dicate open at MCC 1XDB. RCIC Turbine Trip itght will only be illuminated if
. actuated by a RCIC Pug Suction Low Pressure and/or a RCIC Turbine Exhaust Diaphrapu High Pressure trip signal. The valve g., motor must be run fully clesed to reset the actuator to enable v;;v reopening the valve.
BSEP-0/ASSD-02 Page 118 of 202 Rev. O
I (. - 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.
- a. PLACE RCIC Flow Controller 1-E51-FIC-3325 Auto / Manual selector switch in "MAN" AND potentiometer output at minimum,
- b. WHEN informed by Reactor Building MCC Operator that the switch lineup for MCC 1XDB is Complete THEN (1) INFORM Reactor Building MCC Operator that the RCIC System is NOT Running.
(2) DIRECT Reactor Building MCC Operator to PERFORM the following per Step 4 of Section J: (a) CLOSE 1-E51-F045 (b) CLOSE 1-E51-Y8 g n q: (c) OPEN 1-E51-F019 (d) RESET mechanical overspeed trip device locally at Trip and Throttle Valve, 1-E51-Y8.
- c. WHEN infomed by Reactor Building MCC Operator that:
(1) 1-E51-F045 is Closed (2) 1-E51-Y8 is Closed (3) 1-E51-F019 is Open (4) Trip and Throttle Valve, 1-E51-Y8, is Reset THEN DEPRESS RCIC Turbine Reset push button on RSDP.
- d. VERIFY RCIC Turbine Trip light on RSDP is Extinguished.
J BSEP-0/ASSD-02 Page 119 of 202 Rev. O
NOTE b)$ 1-E51-F007 and 1-E51-F062 may close due to spurious operations. The valves are transferred to their ASSD power sup' ply to prevent spurious operations and to ensure that they are open.
- e. d! RECT Reactor Building NC Operator to TRANSFER 1-E51-F007 and 1-E51-F062 from normal power supply to ASSD power supply.
- f. WHEN informed by Reactor Building MCC Operator that M1-F007 AND 1-E51-F062 are Transferred from normal power supplyTo ASSD power supply A2 WHEN power is available to MCC 2XD i
THEN DIRECT Reactor Building MCC Operator to OPEN W1-F007 A_g,1-E51-F062.
- g. WHEN infonned by Reactor Building MCC Operator that THEN OBSERVE 13'['
W1-F062 and 1-E51-F007 reactor water areon level indication Open. 1- MI-604BX at the Remote Shutdown Panel. bh
" h. W'IEN reactor water level is < 200" as indicated on j W1-LI-604BX at RSDP THECDIRECT Reactor Building MCC Operator MCC Operator to OPEN 1-E51-V8 AW then OPEN 1-E51-F045.
- l. WHEN informed by Reactor Building MCC Operator that M 1-V8 and 1-E51-F045 are Open, THEN VERIFY RCIC Flow increases to minimum as directed by RCIC Flow Controller 1-E51-FIC-3325 on RSDP.
J. DIRECT Reactor Butiding MCC Operator to CLOSE 1-E51-F019.
- k. ADJUST RCIC Flow Controller 1-E51-FIC-3325 manual pot
. as necessary to maintain reactor water level between 170" and 200" as indicated on 1-821-LI-604BX at RSDP.
- 1. INFORM Shift Foreman of RCIC System status.
NEP-0/ASSD-02 Page 120 of 202 Rev. O
- 7. WHEN directed by Shift Foreman, THEN COORDINATE with other Q., operators to place the Suppression Pool in recirculating usir.g RHR Loop B as follows:
- a. DIRECT Reactor Building MCC Operator to APEN 1-E11-F0288.
b
'. WHEN informed by Reactor Building MCC Operator that TIT 1-F0288 is Open THEN DIRECT Unit 1 Shift Foreman to have RHR Pump 10 started,
- c. WHEN informed by Unit 1 Shift Foreman that Rm Pump THEN DIRECT Reactor Building MCC TIFTs Operator RunningloTw to S THROTTLE Open 1-E11-F0488 to fill system and limit water hammer.
- d. WHEN informed by keactor Building MCC Operator that T-TT1-F048B is Open, THEN DIRECT Reactor Building MCC Operator to THROTTLE Open 1-E11-F024B.
- e. WHEN RHR System B flow indicator 1-E11-FI-3338 on THEN DIRECT EDT Reactorindicates approximately Building MCC 1000 Operator to STOP 1 gpm. 7RUTILING 1-E 11-F024 B.
- f. DIRECT Reactor Building MCC Operator to CLOSE fg 1-E11-F0078.
6 -
- g. WHEN informed by Reactor Building mci Operator that THEN DIRECT Reactor Building T'ET1-F0078 is closed. TTpen 1-E11-F0248, MCC Operator to THROTTL
- h. WHEN Rm System B flow indicator 1-E11-F1-3338 on E DT indicates 6000-7500 THEN DIRECT Reactor Building MCC Operator to STOPgpm, TIRUTTLING Open 1-E1 F024B.
- 1. DIRECT Reactor Building MCC Operator to establish RHR flow through RR Heat Exchanger 18.
- j. WHEN informed by Reactor Building MCC Operator that the lineup for placing the Suppression Pool in recirculating using RHR Loop B is Complete.1TN INFORM Shift Foreman that tw Suppression Pool .s in recirculation using RHR Loop B.
i l
\
jv BSEP-0/ASSD-02 Page 121 of 202 Rev. O J
s
- 8. WHEN directed by Shift Foreman THEN START reactor g depressurization and cooldown at greater than 1000 F/hr using SRY's and RCIC as follows:
- a. IF any of the SRVs controlled from the RSDP fails to osien when the control switch is placed in the OPEN THEN LEAVE the control switch in the OPEN position.
position AIFThFORM the Shift Foreman. NOTES When cycling SRVs use sequence E, G, 8 to evenly distribute the heat load to the Suppression Pool. To determine cooldown rate, obtain reactor coolant tegerature using Temperature vs Pressure curve on Section "1" Table 1. Then plot tegarature on Section "I" Table 2 for Tegerature vs Time to derive the cooldown rate.
- b. ry to achieve a OPENasmanySRVsasisnecessgF/hr.
cooldown rate greater than 100
- c. PLOT cooldown rate on Section "1" Table 2.
- d. IF reactor water level approaches +70 inches during 7epressurization as indicated on 1-821-L1-604BX at y3 n
, .; RSDP, THEN CLOSE SRV(s) at RSDP as necessary to a maintain reactor water level greater than +70 inches.
. NOTE Do not transfer RCIC suction from the CST to the Suppression Pool if the Supprgssion Pool tegerature is greater than 140V,
- e. 1F Suppression Pool level increases to -24" as Tidicated on 1-CAC-L1-3342 AND Suppression Pool water temperature is less than 14M as indicated on point 7 of 1-CAC-TR-778 at RSDP, THIN DIRECT Reactor Building MCC Operator to perform steps to TRANSFER RCIC suction from CST to Suppression Pool.
- 9. WHEN directed by Shift Foreman THEN DIRECT Reactor Building MCC Ype'Fator to CLOSE 1-SW-Y106 ANDD-Y118.
- 10. WHEN informed by Reactor Building MCC Operator, THEN INFORM ThTTt Foreman that 1-SW-V106 AND 1 SW-Y118 are Closed.
O_ . BSEP-0/ASSD-02 Page 122 of 202 Rev. O
g 11. ESTABLISH service water flow through RHR Heat Exchanger 1B for ud Suppression Pool Cooling and Shutdown Cooling as follows.
- a. THEN DIRECT Reactor WHEN directed Building MCC bytoShift Operator Foreman. FUpen THROTTL 1-E11-PDV-F068B.
- b. WHEN directed by Shift Foreman. THEN DIRECT Reactor ETTding MCC Operator to STOP THT0TTl!NG Open 1-E11-PDV-F0688.
- 12. WHEN Reactor Pressure indicates < 125 psig on 1-C32-PI-3332 at 75DT, THEN INFORM Shift Foreman.
- 13. WHEN directed by Shift Foreman THEN DIRECT Reactor Building MC?
Operator to STOP Suppression PooT Tooling,
- a. WHEN directed by Reactor Building MCC Operator THEN VIKTCT Shift Foreman to have RHR Pump 10 Stopped.
- b. WHEN informed by Shift Foreman, THEN INFORM Reactor ETTding MCC Operator that RHR Pump 1D is Stopped,
- c. WHEN directed by Reactor Building MCC Operator. THEN TRT6RM Shift Foreman that Suppression Pool Cooling is Stopped. %
- 14. WHEN directed by Shift Foreman. THEN C0 ORDINATE with Unit 1 Operators to PLACE RHR Loop "B" in Shutdown Cooling Mode as k follows:
- a. DIRECT. Reactor Building MCC Operator to COMPLETE Steps 10.a (1) through 10.a (14) of Section "J" to PERFORM initial valve lineup.
- b. WHEN informed by Reactor Building MCC Operator that Steps 10.a (1) through 10.a (14) of Section "J" are Completed. THEN DIRECT Unit 1 Shift Foreman to have RHR Pump 10 started for Shutdown Cooling,
- c. WHEN informed by Unit 1 Shift Foreman that RHR Pump TD~Ts Running THEN DIRECT Reactor Building MCC Operator to:
(1) PLACE the control switch in the OPFN position for 1-E11-F048B AND (2) Imediately THROTTLE Open 1-E11-F017B Valve to establish approximately 1000 gpn flow rate. C BSEP-0/ASSD-02 Page 123 of 202 Rev. O
l l l i 1 CAUTION i 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 closed. l d. WHEN approximately 1000 gpm is indicated on RHR i I System B flow indicator 1 E11-FI-3338 at R$DP THEN DIRECT Reactor Building MCC Operator to STOP THR0TTLING Open 1 E11-F0178. l e. t%!NTAIN approximately 1000 gpm flow through the RHR system for 15 minutes to warm up the system piping. l CAUTION
- The maximum RHR total flew rate of 7500 gpm should not be exceeded during the shutdown cooling mode of operation to prevent damage to the RHR heat exchanger.
r,%
****************************************************************************** l i
$$8 f. DIRECT Reactor Building HCC Operator to THROTTLE Open 1-E11-F017B to establish 6000-7500 gpm flow rate.
'l l l tQ
- g. WHEN 6000 to 7500 gpm flow rate is indicated on RHR t Syst(1 B flow indicator 1-E11-F1-3338 at RSDP, THEN~
DIRECT Reactor Building MCC Operator to STOP , THROTTLING Open 1-E11-F017B. '
- h. O! RECT Reactor Building MCC Operator to ESTABLISH RHR l flow through RHR Heat Exchanger 18.
- i. DIRECT Reactor Building MCC Operator to INCREASE OR !
DECREASE 0 cooldown rate, to achieve approximately ~~~ 50 F/hr cooldown rate. NOTE Use temperature vs pressure curve on Table 1 of Section "1" to nonitor reactor cooldown.
- 15. WHEN reactor pressure decreases to 75 psig as indicated on T!fil-PI-3332 THEN increase atreactor water level to 200" as indicated onat RSDP, T!o74BX RSDP. r
, 1-B21-L ' <su ' \l BSE P-0/ ASSD-02 Page 124 of 202 Rev. 0 1
1
- 16. DIRECT Reactor Building HCC Operator to CLOSE 1-E51-F045 to stop RCIC operation AND INFORM Unit 1 Shift Foreman that RCIC System operation is no longer required and RCIC is being shut down.
- 17. MONITOR reactor vessel cooldown using Section "1" Table 1 AND AS$1ST Shift Foreman as directed.
- 18. WHEN Reactor Pressure has decreased to O psig as indicated on M -PI-3322 at RSDP, THEN INFORM Shift Foreman.
- 19. IF makeup water is needed to raise reactor water level while in 3Futdown Cooling OR to DECREASE Suppression Pool water level, THEN PERFORM the To11owing:
- a. DIRECT Unit 1 Shift Foreman to have RHR Pump 10 stopped.
- b. WHEN informed by Unit 1 Shift Foreman that RHR Pump 10 is Stopped. THEN DIRECT Reactor Building HCC i Operator to:
! (1) CLOSE 1-E11-F008 l (2) CLOSE 1-E11-F006D (3) CLOSE 1-E11-F0178 {'. (4) CLOSE 1-E11-F047B (5) CLOSE 1-E11-F048B N.
- c. WHEN informed by Reactor Building MCC Operator that (1) 1-E11-F003 is Closed (2) 1-E11-F006D is Closed ,
(3) 1-E11-F017B is Closed (4) 1-E11-F047B is Closed (5) 1-E11-F048B is Closed THEN LINE UP for LPCI injection from the Suppression T65T as follows: (1) O! RECT Reactor Building HCC Operator to (a) PLACE breaker for 1-E11-F0078 to "0N" position (b) OPEN 1-E11-F007B (c) OPEN 1-E11-F020B (d) OPEN 1-E11-F0040 BSEP-0/ ASS 0-02 Page 125 of 202 Rev. 0
l l )V l r ,. (2) WHEN informed by Reactor Building MCC Operator that ( (a) Breaker for 1-E11-F007B is in l the "0N" position (b) 1-E11-FC07B is Open 1-E11-F0208 is Open ' (c) I (d) 1-El'4-F004D is Open THEN DIRECT Unit 1 shift Foreman to have W Pump 10 started. (3) WHEN informed by Unit 1 Shift Foreman that E ump 10 is Running THEN (a) DIRECT Reactor Building MCC Operator to OPEN 1-E11 F048B AND THROTTLE Open 1-E11-F0178. (b) OBSERVE reactor vessel water level increasing on 1-821-L1-604BX at RSDP. (c) WHEN desired rate of water g Ti7el increase is achieved THEN DIRECT Reactor Building MCC D Operator to STOP THROTTLING \ Open 1-E11-F0178. (d) O! RECT Reactor Building MCC Operator to CLOSE 1-E11-F0078.
- 20. WHEN reactor water level has been raised using LPCI to 200" as -
indicated on 1821-LI-6048X at RSDP, THEN PERFORM the following i to return to Shutdow.1 Cooling Mode, l
- a. DIRECT Unit 1 Shift Foreman to have RHR Pump 10 l Stopped. '
- b. Wl(N informed by Unit 1 Shift Foreman that RHR Pump M s Stopped. THEN DIRECT Reactor Building MCC Operator to (1) CLUSE 1 E11-F0178 (2) CLOSE 1-E11-F0488 (3) CLOSE 1 E11-F0040 (4) CLOSE 1-E11-F0208 h (5) PLACE breaker for 1-E11-F007B to "0FF" position BSEP-0/ASSD-02 Page 126 of 202 Rev. 0
g, c. WE N informed by Reactor Building MCC Operator that (1) 1-E11-F017B is Closed l l (2) 1-E11 F048B is closed (3) 1 E11-F0040 is Closed ! (4) 1 E11-F0208 is Closed i (6) Breaker for 1 E11-F007B is in "0FF" I position. l THEN DIRECT Reactor Building MCC Operator to L (1) OPEN 1-E11-F006D (2) Slowly OPEN 1-E11-F008 [ t
- d. WHEN informed by Reactor Building MCC Operator that (1) 1-E11-F006D is Open ;
(2) 1-E11-F008 is Open l THEN O! RECT Unit 1 Shift Foreman to have RHR Pump 10 y l
$ Started, q
- e. WHEN informed by Unit 1 Shift Foreman that RHR Pump \ f TU Ts Running. THEN DIRECT Reactor Building MCC t Operator to:
l (1) PLACE the control switch in the OPEN position for 1-E11-F0478 A.NO, ! (2) Imediately THROTTLE Open 1-E11-F0178. . i
- f. WHEN 6000 '/500 gpa flow rate is achieved as indicated l DR System B flow indicator 1-E11-FI-3338 at RSDP, ;
THEN DIRECT Reactor Building MCC Operator to STOP : TRRUTTLING Open 1 E11-F0178. l i l l l I i i O BSE P-0/ASSD-02 Page 127 of 202 Rev. O i i
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SECTION "J" q{p UNIT 1 REACTOR BUILDING MCC OPERATOR ACTIONS ,
- 1. REPORT to Reactor Building MCC 1XB AND_ ESTABLISH communications with the RSDP Operator using sound powered phone jack labeled REMOTE SHUTDOWN TRAIN 'B' (UNIT #1) SOUND POWERED PHONE CKT located on MCC 1XB Compartment 03Z. -
- 2. PERFORM lineup of items on the following table as directed by i instructions at the top of the table. [
l.
?
i f k$) i 6 i l e I i I f i 1 h i I l I klbh r BSEP-0 / ASS 0-02 Page 130 of 202 Rev. 0
p To perform lineup of the items listed on this table, do the following steps as Gp directed. For items that have two-position or three-position maintained contact control switches: PLACE the control switch to the position indicated on the table. to ensure the item will line up or remain lined up to the position indicated on the table THEN PLACE the Nomal/ Local switch to "LOCAL". For items that have three-position spring return ~ to "EUT' or *0FF" control switches (indicated by an *): ! PLACE the Normal / Local switch to "LOCAL" THEN ! OPERATE the control switch as required to line up the item to the position indicated on the table. NOTE: Items indicated with an (*) must be verified in position or be placed ; in position using control switches when power is available to the MCC. D. , CONTROL NORMAL / LOCAL / . COPPT/ EQUIPMENT SWT/ ISOLATE SWT CKT DESCRIPTION pa NUSER VLV POS P05 t T5tATIN Mcc-1xos Reactor su11 ding j El 20' South t RFJ Shutdown Cooling Outboard 1-E11-F006
- CLOSED LOCAL !
Suction Isolation Valve , 835 RCIC Barometric condenser 1-E51-C002 START LOCAL l Yacuum Pump i 836 RClc Barometric Condenser 1-E51-C002 START LOCAL Condensate Pump , B37 RCIC Turbine Trip & Throttle 1-E51-V8
- OPEN LOCAL !
Ylv l 836 RCIC Condensate Storage Tank 1-E51-F010
- OPEN LOCAL l
~
Suction Valve l I
- Control switches for these items are spring returned to "NEUT" or '0FF'. i
@~ BSEP-0/ASSD-02 Page 131 of 202 Rev. 0
hp " CONTROL NORMAL / LOCAL / COWT/ EQUIPMENT SWT/ ISOLATE SWT CKT DESCRIPTION NUMBER VLV POS POS R39 RCIC Cooling Water Supply 1-E51-F046
- OPEN LOCAL Valve 840 RCIC Purp Discharge Valve- 1-E51-F012
- CPEN - LOCAL-
] B41 RCIC Injection Valve 1-E51-F013
- OPEN LOCAL B42 RCtc Bypass to Condensate 1-E51-F022
- CLOSED LOCAL Stocage Tank Valve -
l B43 RCic Steam Supply Outboard 1-E51-F008 #* OPEN LOCAL
!solatici Valve
- # If 1-E51-F008 is found closed on initial lineup of table, then throttle
, open valve for approximately 10 seconds. Wait approximately 60 seconds for l RCIC steam line to repressurire then fully open valve.
- 844 RCIC Steam Supply to Turbine 1-E51-F045
- OPEN LOCAL M 84 5 RCIC Suppression Pool Suction 1-E51-F031
- CLOSED LDCAL a
f 6 , Valve - - - - - - - - - B46 RCIC Suppression Pool Suction 1-E51-F029
- CLOSED LOCAL Valve B47 RCIC Minimus Flow Bypass to 1-E51-F019
- CLOSED LOCAL Suppression Pool Valve - - - - -
B48 RWCU Inlet Outboard Throttle 1-G31-F004
- CLOSED LOCAL 1 solation Valve .
B52 Pain Steam Line Outboard 1-B21-F019
- CLOSED LOCAL Drain Isolation Valve
- Control switches for these items are spring returned to "NEUT* or *0FF".
WEN the switch lineup for MCC 1XDB is Complete. THEN INFORN the M T Operator. e_ . BSEP-0/ASSD-02 Page 132 of 202 Rev. O
([J CONTROL NORMAL / LOCAL / COMPT / EQUIPMENT $WT/ !$0 LATE SWT CXT DESCRIPTION NUMBER YLV POS PO$ 1RITT5K McC-1XB Reactor Building E1, 20' South - - - DP5 Recirculation Pug 18 1-832-F0238
- CLOSED LOCAL Suction Valve DP5 Vent Am HX Area 1-5-FCU-RS START LOCAL Cooling Fan - -
DN6 RHR Pump 18 and 10 Supp. Pool 1-E11-F0208 OPEN LOCAL suction Valve DP2 Nuclear Service Water To 1-$W V117
- OPEN LOCAL ,
Vital Header Inboard Isolation Valve - - - - DN9 R m HX B service Water 1-E11-7002B
- OPEN LOCAL Discharge Valve. - - - - - . - - - -
DN2 R R service Water 1-E11-F073
- CLOSED LOCAL N
Outboard Injection Valve - .- -- - - (. DM1 R M Service Water Booster 1-$W-V106
- OPEN LOCAL Pumps B and D Inboard '
! solation Valve -
DM6 Service Water To Rm Service 1-$W-V102
- CL0$ED LOCAL !
Water Header Cross-Tie Valve - DL8 Drywell spray Outboard 1-E11-F0168 CLOSED LOCAL l Isolation Valve ; I DM2 Suppression Pool Cooling 1 E11-F0248
- CLOSED LOCAL 1 solation Valve . ;
i DM4 Sup ression Pool Spray 1 E11-F0278 CLOSED LOCAL iso atton Yalve ' ml R M HK t service Header 1 E11-PDV-
- CLOSED LOCAL i Outlet Valve F0688 l i
DL1 RHR Pug 18' Shutdown Cooling 1-E11 F0065 CLOSED LOCAL t Suction Yalve [
- Control switches for thesa items are spring returned to *NEUT" or "0FF'.
([L , ESEP 0/A$$D-02 Page 133 of 202 Rev. O
CONTROL NORMAL / LOCAL / l
@' COWT/ EQUIPMERf SVT/ ISOLATE /SWT l CKT DESCRIPTION NUMBER VLV POS POS 4
RHR Pump 10 Shutdown Cooling 1-E11-F006D CLOSED LOCAL l Suction Valve - - - - - -
't Turbine Exhaust V6cuum 1-E51-F066
- OPEN LOCAL
. Breaker Vaive - - - .- - - - - - - - - . .. . ... -
DK9 RHR Pump 1B Suppression Pool 1-E11-F004B OPEN LOCAL Suction Vaive - - - - - - - DL3 Ninimum Flo'w Bypass Valve 1-E11-F0078
- OPEN LOCAL DLO RHR Pump 1D Suppression Po01 1-E11-F0040 OPEN L0 CAL Suction Valve - - - - - - - - - - - - -
DK8 RHR HX 1B Outlet Valvt - 1-E11-F0038 OPEN LOCAL-DM7 RfR_ HX 1B Inlet-Valve - - 1-E11-F0478. CLOSED. LOCAL DM8 RfR HX 1B Bypass Valve - 1-E11-F0488 CLOSED 1.0 CAL- g D3Y ! solation Switch 1-D3Y-IS1 1-CAC-SV- N/A ISOLATE for V1v 1-CAC-SV-1218C 1218C - - . -
.}.
03Y Isolation Switch 1-03Y-IS2 1-CAC-SV- N/A ISOLA)E for Viv 1-CAC-SV-1225C . - 1225C- - - - - - - 03Y ! solation Switch 1-03Y-IS3 1-CAC-SV- N/A ISOLATE for Viv 1-CAC-SV-4345 - 4345-LOCATIOR MCC-1XB-2 Reactor Building El 20' South DLo LPCI Outboard Injection Viv 1-E11-F017B OPEN LOCAL DL7 LPCI Inboar
- Injection Viv 1 E11-F0158
- CLOSED LOCAL DMS Suppression Pool Discharg;r 1-E11-F0288 CLOSED LOCAL Isolation Valve - - -
- Control switches for these items are spring returned to "NElff" or "0FF".
G% - BSEP-0/ASSD-02 Page 134 of 202 Rev. O S
-_.n.
w
- 3. IF informed by RSDP Operator that RCIC is Running. THEN when h 3Trected by RSDP Operator TRANSFER 1-E51-F007 AND 1 T5T-F062 from normal power supply to ASSD power supply as follows:
- a. PLACE the circuit breaker control switch in the ON position for RCIC Steam Supply Line Isol. Viv.1 TB1-F007 ASSD Feed at MCC 1XD Compartment DY1.
l (Looking at the front of the panel at the bottom, it is the fourth compartment in from the right side at j the bottom.)
- b. PLACE the circuit breaker control switch in the ON position for RCIC Turb. Vac Breaker Viv.1-E51-r0T2 ASSD Feed at MCC 1XD Compartment DW2.
(Looking at the front of the panel at the bottom, it is located four compartments in from the right side and is the second compartment up from the bottom.) , l
- c. PLACE the circuit breaker control switch in the OFF l position for Steam Supply Inboard Isolation Valve, '
Q 1-E51-F007, at MCC 1XC Compartment DS4.
. (Looking at the front of the panel at the bottom, it is located four compartments in from the left side and is the third compartment up rom the bottom.)
- d. PLACE the circuit breaker control switch in the OFF
, position for Turbine Exhaust Vacuum Breaker Valve, ,
1-E51-F062, at MCC 1XA Compartment DE4.
'Looking at the bottom of the side of the panel that !
is facing South, it is the third compartment in from ' the left side at the bottom.)
- e. VERIFY 1-E51 F007 AND 1-E51-F062 are Open by observing valve open indicating lights illuminated at MCC 1XD AND INFORM RSDP Operator that 1-E51-F007 AND M1-F062 are transferred from normal poweF supply to ASSD power supply.
_ f. COMPLETE the alignment of switches on table per Step 2. l i . l . i i l L
- l l
l . BSEP-0/ASSD-02 Page 135 of 202 Rev. 0 1 _ _ _ _ - - - . _ _ _ . _ _ _
l l
- 4. IF informed by RSDP Operator that RCIC is NOT running THEN l
($ PTRFORM the following: l
- a. WHEN directed by RSDP Operator, THEN
_(1) CLOSE RCIC Turbine Steam Supply Valve,
. 1-E51-F045, at MCC 1XDB Compartment B44.
(2) CLOSE RCIC Turbine Trip And Throttle Valve, 1-E51-V8, at MCC 1XDB Compartment B37. (3) OPEN RCIC Minimum Flow Bypass To Suppression Pool Valve,1-E51-F019, at MCC 1XDB Compartment B47. (4) RESET mechanical overspeed trip device locally at Tiip and Throttle Valve, 1-E51-V8 as follows: (a) Depending on body position, either push or pull against spring pressure the emergency connection rod in the direction of the Turbine Trip and
' Throttle Valve,one (approximately E51-V8,).
inch M. (b) Observe the ' tappet and ball assembly, 9- . which resembles a plunger, drop into place. (c) If the tappet and ball assemble does not drop in place, lightly depress the assen61y. (d) Release the emergency connection rod.
- b. INFORM RSDP Operator that:
__ (1) 1-E51-F045 is Closed, (2) 1-E51-V8 is Closed (3) 1-E51-F019 is Open (4) Mechanical overspeed trip device for Trip and Thrott.le Valve, 2-E51-V8 is Reset. l l b-BSEP-0/ASSD-02 Page 136 of 202 Rev. 0 l
. 1
- c.
WHEN directed by RSDP Operator, THEN TRANSFER TIT 1-F007 AND 1-E51-F062 f rom normal power supply to ASSD power supply as follows: (1) PLACE the circuit breaker control switch in the ON position for RCIC Steam Supply Line
. Iso 1Div.1-E51-F007 ASSD Feed at MCC IXD Compartment DY1.
(Looking at the front of the panel at the bottom, it is the fourth compartment in from the right side at the bottom.) (2) PLACE the circuit breaker control switch in the ON V1v. T position E51-F062for RCIC ASSD FeedTurb. Vac at MCC Breaker 1XD Compartment DW2. (Looking at the front of the panel at the bottom it is located four compartments in ; from the right side and is the second compartment up from the bottom.) (3) PLACE the circuit breaker control switch in the _0FF position for Steam Supply Inboard Isolation Valve,1-E51-F007, at MCC 1XC g Compartment DS4. (Looking at the front of the panel at the bottom, it is located four compartment in from the left side and is the third compartment up from the bottom.) (4) PLACE the circuit breaker control switch in the OFF position for Turbine Exhaust Vacuum Breaker Valve, 1-E51-F062, at MCC 1XA Compartment DE4
. (Looking at the bottom of the side of the panel that is facing South, it is the third compartment in from the left side at the bottom.)
(5) INFORi1 RSDP Operator that 1-E51-F007 AND 1-E51-F062 have been transferred from normal power supply to ASSD power supply. W BSEP-0/ASSD-02 Page 137 of 202 Rev. 0
a d. WHEN directed by RSDP Operator AND when p~. 9r is 6 available to MCC 1XD, THEN OPEN 1-E51-FC - A 1-E51-F062 as fo11ews: (1) To repressurize RCIC steam line PLACE Keylock the Close/Off/Open Switch in the
. OPEN position for 10 seconds THEN PLACE the tTose/off/open Keylock Switch in the OFF '
position for RCIC Steam Supply Lire Isol. Viv.1-E51-F007 ASSO Feed at MCC 1X0 Compartment DY1. (Looking at the front of the panel at t5e bottom, it is the fourth compartment in from the right side at the botton.) (2) After 60 seconds PLACE the Close/0ff/0 pen Keylock Switch in the OPEN position for RCIC Steam Supply LineM. Viv. 1-E51-F007 ASSD Feed at MCC 1XD Compartment DY1 until valve is Full Open. (3) PLACE the Close/Off/0 pen Keylock Switch in the OPEN position for RCIC Turb. Vac Breaker Viv.1-E51-F062 ASSO Feed at MCC E 1XD Compartment DW2 until valve is Open. (Looking at the front of the panel at the bottom it is located four compartments in from the right side and is the second compartment up from the bottom.) (4) INFORM RSDP Operator that 1-E51-F007 AND 1-E51-F002 are Open.
- e. WHEN directed by RSDP Operator THEN (1) OPEN RCIC Turbine Trip And Throttle Valve, 1-E51-V8, at MCC 1XDB Compartment B37.
l (2) OPEN RCIC Turbine Steam Supply Valve. l 1-E51-F045, at MCC 1XDB Compartment 844
- f. INFORM RSDP Operator that 1-E51-V8 AND 1-E51-F045 are Open.
($% *
, BSEP-0/ASSD-02 Page 138 of 202 Rev. 0
V
- g. WHEN directed by RSDP Operator, THEN CLOSE RCIC h Minimum Flow Bypass To Suppression Pool Valve, 1-E51-F019, at MCC 1XDB Compartment B47.
- h. INFORM RSDP Operator that 1-E51-F019 is Closed,
- i. COMPLETE the alignment of switches on table per Step 2.
- j. WHEN aligr. ment of switches on the MCCs is Complete, TITER DIRECT the RSDP Operator to INFORM Unit 1 Shift Foreman.
- 5. WHEN the switch' alignment of table in Step 2 is COMPLETE THEN FERT0RM the following to assist in placing the Suppression Pool in recirculation using RHR Loop B.
- a. WHEN directed by RSDP Operttor THEN OPEN suppression F55T Discharge Isolation Valve,~I T11-F028B, at MCC 1XB-2 Compartment DMS.
- b. INFORM RSDP Operator that 1-E11-F028B is Open,
- c. WHEN directed by RSDP Operator, THEN Slowly THROTTLE Open RHR HX 18 Bypass Valve,1-ETDT0488, at MCC 1XB Compartment DMB. g,
- d. WHEN RHR HX IB Bypass Valve,1-E11-F048B, is fully Open THEN INF0RM RSDP Operator.
- e. WHEN directed by RSDP Operator THEN THROTTLE Open Suppression Pool Cooling Isolation Valve,1-E11-F0248, at MCC 1XB Compartment DK to establish approximately 1000 gpm flow rete.
- f. WHEN_ directed by RSDP Operator, THEN STOP THROTTLING Open Suppression Pool Cooling Isolation Valve, 1-E11-F024B, at MCC 1XB Compartment DR.
- g. WHEN directed by RSDP Operator, THEN CLOSE Minimum Flow Bypass Valve,1-E11-F007B, at MCC 1XB Compartment' DL3.
- h. WHEN 1-E11-F007B is Closed, THEN INFORM RSDP Operator.
- 1. WHEN directed by RSDP Operator, THEN Tm 0TTLE Open Suppression Pool Isolation Valve,1-E11-F0248, at MCC IXB Compartment DK to establish 6000-7500 gpm flow rate.
J. WHEN directed by RSDP Operator, THEN STOP THROTTLING Open Suppression Pool Isolation Valve,1-E11-F024B, at k<, , MCC 1XB Compartment DE . BSEP-0/ASSD-02 Page 139 of 202 Rev. 0
t
- k. WHEN directed by RSDP Operator, THEN COMPLETE the C6 b 7UTowing steps to establish R$Ww through RHR Heat Exchanger 18 AND Cool down the Suppression Pool.
(1) OPEN RHR HX IB Inlet Valve, 1-L11-F0478, at - MCC 1XB Compartment DM7.
~
(2) CLOSE RHR HX 1B Bypass Valve, 1-E11-F048B, at MCC IXB Compartment DM8
- 1. INFORM RSDP Operator that the lineup to place the Suppression Pool in recirculation using RHR Loop B is Coglete.
- 6. WHEN directed by RSDP Operator to CLOSE 1-$W-V106 AND 1-SW-V118 THEY STOP Service Water flow through RBCCW heat exchangers AND M oop of the Vital Service Water header by performing the following:
- a. PLACE the circuit breaker control switch in the 0FF position for Nuclear Header to RBCCW Heat Exchanger Isolation Vly,1-SW-V106, at MCC 1XA Compartment DE3.
- b. PLACE the circuit breaker control switch in the OFF position for Vital Service Water Divisional Tie YaTve, 1-SW-V118, at MCC 1XA Compartment DE1.
M.
@ c. VERIFY Closed OR Man 0 ally CLOSE Nuclear Header to RBCCW Heat ExcTanger Isolation Valve, 1-SW-Y106,
- d. VERIFY Closed GR Manually CLOSE Vital Service Water Divisional Tie Talve,1-SW-V118.
- e. DIRECT RSDP Operator to INFORM Unit 1 Shift Foreman that 1-SW-V106 AND 1-SW-V118 are Closed.
- 7. ESTABLISH service water flow through RHR Heat Exchanger "B" for Suppression Pool Cooling and Shutdown Cooling as follows,
- a. WHEN directed by RSDP Oper& tor THEN THROTTLE Open RHR RET Service Header Outlet Yalve,1-E11-PDY-F0688, at MCC 1XB Compartment DN1.
- b. WHEN directed by RSDP Operator, THEN STOP THROTTLING Open RHR HX B Service Header Outlet Yalve, 1-E11-PDV-F0688, at MCC IXB Compartment DN1.
@)
BSEP-0/ASSD-02 Page 140 of 202 Rev. 0
r
- 8. IF directed by RSDP Operator, THEN TRANSFER RCIC Suction from-
' C~M.. UT to Suppression Pool as follows:
- a. OPEN RCIC Suppression Pool Suction Valve,1-E51-F031, at MCC 1XDB Compartment B45.
- b. OPEN RCIC Supprete n Pool Suction Volve,1-E51-F029, at HCC 1XDB Com5, ". ment B46.
- c. CLOSE RCIC Condensate Storage Tank Suction Valve,
.. 51-F010, at MCC 1XDB Compartment B38.
- 9. WHEN directed by Shift Foremar., THEN STOP Suppression Pool tooling as follows:
- a. OPEN Minimum Flow Bypass Valve,1-E11-F0078, at MCC 1XB Compartment DL3.
- b. CLOSE Suppression Pool Cooling Isolation Yalve, 1-E11-F0248, at MCC IXB Compartment DM2.
- c. DIRECT RSDP Operator to have RHR Pump 10 Stopped.
- d. WHEN infonned by RSDP Operator that RHR Pump ID is Stopped.
1-E11-F00 Tat MCC 1XB Compartment DL3.THEN CLOSE y Min
- e. CLOSE Suppression Pool Discharge Isolation Valve, N 1-E11-F028B, at MCC IXB-2 Compartment DMS. T
- f. CLOSE RHR HX IB Inlet Valve,1-E11-F047B, at MCC 1XB Compartment DM7.
9 DIRECT RSDP Operator to INFORM Unit 1 Shift Foreman that Suppression Pool Cooling is Stopped. -
- 10. PERFORM the following to assist in placing RHR Loop B in shutdown Cooling.
- a. THEN COMPLETE Steps WHEN 10.a(1) throughdirected10.a(14) by RSDP Operator, below o TTe~ctionas "J" follows:
(1) CLOSE RHR Pump 18 and ID Supp. Pool Suction Valve,1-E11-F0208, at MCC IXB Compartment DN6. (2) CLOSE RHR Pump 1B Suppression Pool Suction Valve,1-E11-F004B. at MCC 1XB Compartment
. DK9.
'm W/ (3) CLOSE RHR Pump 10 Suppression Pool Suction Valve,1-E11-F0040, a MCC IXB Compartment DLO. BSEP-0/ASSD-02 Page 141 of 202 Rev. 0
I (4) PLACE the circuit breaker control switches hf-in the UN position AND OPEN RHR Pump 1B Shutdown ~ Cooling Suction Valve 1-E11-F0068, at MCC 1XB Compartment DLI. (5) PLACE the circuit brtaker control switch in the ON position AE OPEN RHR Pump ID ShutTiwn Cooling- 5Iiction Valve 1-E11-F0060, at MCC 1XB Compartment DL2.
- (6! PLACE the circuit breaker control switch in the ON position AND Open Shutdown Cooling Outboird Suction Isolation Valve, 1-E11-F008, at MCC 1XDB Compartment 850.
(7) PLACE the circuit breaker control switch in the ON position A2 using keylock control
~
switcT Slowly THIOTTLE Open RHR Suction Isolation Valve 1-E11-F009, at MCC IXD Compartment DX5 until valve is Full Open. (Looking at the bottom of the front of the panel, it is located three compartments in from the right side and is the third compartment up from the bottom.) N
- $ (8) VERIFY Closed RHR HX 1B Inlet Valve, 1-E11-F0478, at MCC 1XB Compartment DM7.
j g (9) VERIFY Open RHR HX 1B Outlet Valve, l 1-E11-F003B, at MCC 1XB Compartment DK8. (10) VERIFY Closed Minimum Flow Bypass Valve, 1-E11-F007B, at MCC 1XB Compartment DL3. l (11) PLACE the circuit breaker control switch in the OFF position for Minimum Flow Bypass Valve,1-E11-F007B, at MCC 1XB Compartment OL3. (12) CLOSE LPCI Outboard Injection Viv, 1-E11-F0178, at MCC 1XB-2 Compartment DL9. (13) OPEN LPCI Inboard Ir.jection Viv, 1-E11-F0158, at MCC 1XB-2 Compartment DL7. (14) INFORM RSDP Operator that Steps 10.a(1) through 10.a(14) of Section "J" are Completed. h BSEP-0/ASSD-02 Page 142 of 202 Rev. O
g b. WHEN directed by RSDP Operator, THEN: (1) PLACE the control switch in the OPEN position for RHR HX 1B Bypass Valve 1-E11-F048B, at MCC 1XB compartment DN AND (2) Imediately THROTTLE Open LPCI Outboard Injection Valve, 1-E11-F0178, at MCC 1XB-2 Compartment DL9 to establish approximately 1000 gpm flow rate.
- c. WHEN directed by RSDP Operator, THEN STOP THROTTLIN3 Open LPCI Outboard Injection Valve,1-E11-F0178, at MCC IXB-2 Compartment DL9.
- d. WHEN directed by RSDP Operator, THEN THROTTLE Open IRT Outboard Injection Valve,1W-F0178, at MCC IXB-2 Compartment DL9 to establish 6000-7500 gpm flow rate.
- e. WHEN directed by RSDP Operator, THEN STOP THROTTLING Open LPC1 Outboard Injection Valve,1-E11-F0178, at MCC IXB-2 Compartment DL9.
- f. When directed by RSDP Operator, THEN ESTABLISH flow through RHR Heat Exchanger 1B by performing the Q) following.
(1) OPEN RHR HX 1B Inlet Valve,1-E11-F047B, at g MCC IXB Compartment DM7. (2) VERIFY Open RHR HX 1B Outlet Valve, 1-E11-F003B, at MCC 1XB Compartment DK8.
- g. IF directed by RSDP Operator to increase cooldown
- THEN THROTTLE Closed RHR HX 1B Bypass Valve, Tite, 1-E11- T6EIB, at MCC 1XB Compartment DN as direct RSDP Operator.
- h. IF directed by RSDP Operator to decrease cooldown Tite, THEN PERFORM one or more of the following actions as directed by the RSDP Operator.
(1) THROTTLE Open RHR HX IB Bypass Valve, 1-E11-F0488, at MCC 1XB Compartment DMB. (2) THROTTLE Closed RHR HX B Service Header Outlet Valve,1-E11-PDV.r0688, at MCC 1XB Compartment DN1.
~
- 11. WHEN directed by RSDP Operator, THEN CLOSE RCIC Steam Supply to TuWine,1-E11-F045, at MCC 1XDB Compartment 844.
b BSEP-0/ASSD-02 Page 143 of 202 Rev. 0
g.a 'sA
- 12. IF makeup water is needed to raise reactor water level while in 3Iiutdown Cooling, THEN PERFORM the following: ,
- a. WHEN directed by RSDP Operator THEN (1) CLOSE Shutdown Cooling Outboard Suction Isolation Valve,1-E11-F008, at MCC 1XDB Compartment B50.
(2) CLOSE RHR Pump 1D Shutdown Cooling Suction Valve,1-E11-F006D, at MCC 1XB Compartment DL2. (3) CLOSE LPCI Outboard Injection Viv, 1-E11-F017B at MCC 1%B-2 Compartment DL9. < (4) CLOSE RHR HX 1B Inlet Yalve,1-E11-F047B, dt MCC IXB Compartment DM7. (5) CLOSE RHR HX 1B Bypass Valve,1-E11-F048B, at MCC IXB Compartment DMB.
- b. INFORM RSDP Operator that (1) 1-E11-F008 is Closed.
Q2 (2) 1-E11-F006D is Closed. 3 (3) 1-E11-F017B is Closed. (4) 1-E11-F047B is Closed. (5) 1-E11-F048B is Closed,
- c. WHEN directed by RSDP Operator THEN *
(1) PLACE circuit breaker control switch in the ON position for Minimum Flow Bypass Valve, T'E11-F007B, at MCC 1XB Compartment DL3. (2) OPEN Minimum Flow Bypass Valve, 1-E11-F007B, at MCC 1XB Compartment DL3. (3) OPEN RHR Pump 1B and 10 Supp. Pool Suction Valve,1-E11-F0208, at MCC 1XB Compartment DN6. (4) OPEN RHR Pump 1D Suppression Pool Suction Valve,1-E11-F0040, at MCC 1XB Compartment DLO. BSEP-0/ASSD-02 Page 144 of 202 Rev. O
i g d. INFORM RSDP Operator that (1) Breaker for 1-E11-F007B is in the ON position. (2) 1-E11-F007B is Open. (3) 1-E11-F0208 is Open. (4) 1-E11-F004D is Open.
- e. WHEN directed by RSDP Operator THEN:
(1) OPEN RHR HX 1B Bypass Valve,1-E11-F048B, at MCC 1XB Compartment DM. (2) THROTTLE Open LPCI Outboard Injection Viv, 1-E11-F0178, at MCC 1XB-2 Compartment DL9.
- f. WHEN directed by RSDP Operator THEN STOP THROTTLING Open LPCI Outboard Injection Viv,1-E11-F0178, at MCC IXB-2 Compartment DL9.
- g. WHEN directed by RSDP Operator THEN CLOSE Minimum Flow Bypass Valve 1-E11-F0078 at MCC'"III Compartment DL3.
kl 13. To return to Shutdown Cooling Mode from reactor vessel makeup, PERFORM the following: 5
- a. WHEN directed by RSDP Operator THEN (1) CLOSE LPCI Outboard Injection Viv, 1-E11-F017B at MCC IXB-2 Compartment OL9.
(2) CLOSE RHR HX 1B Bypass Valve, 1-E11-F0488, . at MCC 1XB Compartment DM. (3) CLOSE RHR Pump 1D Suppression Pool Suction Valve,1-E11-F004D, at MCC 1XB Compartment OLO. (4) CLOSE RHR Pump 18 and ID Supp. Pool Suction Valve,1-E11-F020B, at MCC 1XB Compartment DN6. (5) PLACE circuit breaker control switch in the OFF position for Minimum Flow Bypass Valve T-f11-F007B at MCC 1XB Compartment DL3. Gk BSEP-0/ASSD-02 Page 145 of 202 Rev. 0
glj b. INFORM RSDP Operator that ( (1) 1-E11-F017B is Closed. (2) 1-E11-F048B is Closed. (3) 1-E11-F004D is Closed, i (4) 1-E11-F0208 is closed. 1 (5) Circuit Breaker control switch for 1-E11-F007B is in OFF position.
- c. WHEN directed by RSDP Operator THEN (1) OPEN RHR Pump 10 Shutdown Cooling Suction i Valve,1-E11-F0060, at MCC 1XB Compartment l DL2.
(2) Slowly OPEN Shutdown Cooling Outboard , Suction Isolation Valve,1-E11-F008, at MCC 1XDB Compartment 850.
]
- d. INFORM RSDP Operator that M (1) 1-E11-F006D is Open.
(2) 1-E11-F008 is Open.
- e. WHEN directed by RSDP Operator THEN:
(1) PLACE the control switch in the OPEN I position for RHR HX 1B Bypass Valve, l 1-E11-F048B, at MCC 1XB Compartment DMB AND 1 (2) Immediately THROTTLE Open LPCI Outboard l Injection Valve,1-E11-F017B, at MCC IXB-2 I Compartment DL9.
- f. WHEN directed by RSDP Operator THEN STOP THROTTLING Open LPCI Outboard Injection Valve, 1-E11-F0178, at MCC 1XB-2 Compartment DL9.
(?) BSEP-0/ASSD-02 Page 146 of 202 Rev. O
RESTORING POWER TO REACTOR BUILDING h MCC IXB The purpose of the following steps is to restore power to Reactor Building MCC IXB in the event that an electrical fault causes the feeder breaker at 480V Substation E6 Compartment AWO to trip.
- 1. IF power is NOT available to Reactor Building MCC 1XB as Tetermined by loss of indicating lights and control for items powered from Reactor Building MCC IXB, THEN DIRECT Diesel Generator Operator to CONFIRM the following:
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Reactor Building MCC IXB at Compartment AWO is Tripped.
- 2. WHEN Diesel Generator Operator CONFIRMS that
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Reactor Building MCC 1XB at Compartment AWO is Tripped, THEN OPEN the following breakers on Reactor Building MCC 1XB.
Comparcment Number Component Description # S-DP8 Reactor Bldg. Off Gas Drain Tank Pump B, 1-G16-1B-1, Circuit Breaker DP7 Vent RHR HX Area Cooling Fan 18-FCU-RB DK1 Recirculation Pump 18 Suction Valve, 1-B32-F023B, Circuit Breaker BN9 Primary Containment Atmosphere Radiation Monitor,1-CAC- AT1260, Circuit Breaker EF5 Reactor Building Personnel Decontamination Room Hot Water Heater Circuit Breaker DP9 TBCCW HXs Service Water Header Inboard Isolation Valve,1-SW-V3, Circuit Breaker h.L ,
. BSEP-0/ASSD-02 Page 147 of 202 Rev. O
- 2. (Cont'd)
Compartment Number Component Description DN3 , RHR Service Water Inboard Injection Valve, 1-E11-F075. Circuit Breaker . DP1 Recirculation Pump 1B Seal Water Injection Valve,1-B32-V30, Circuit Breaker - DN6 RHR Pump 18 and ID Suppression Pool Suction Valve,1-E11-F0208. Circuit Breaker. DP2 Nuclear Service Water To Vital Header Inboard Isolation Valve,1-SW-V117. Circuit Breaker DN2 RHR Service Water Ortcard Injection Valve, 1-E11-F073, Circuit Breaker . . DM1 RHR Service Water Booster Pumps B and D Inboard Isolation Yalve,1-SW-Y105, Circuit Breaker. . .... . ...... ... . .. . . M DH6 Service Water To RlR Service Water Header (3 Cross-tie Valve,1-SW-V102, Circuit Breaker. DL8 Drpell Spray Outboard Isolation Valve, 1-E11-F0168 Circuit Breaker DHO Drpell Spray Inboard Isolation Yalve, 1-E11-F021B, Circuit Breaker DH2 Suppression Pool Cooling Isolation Valve, 1-E11-F0248, Circuit Breaker DM Suppression Pool Spray Isolation Valve, 1-E11-F027B, Circuit Breaker DN1 RHR HX B Service Header Outlet Yalve, 1-E11-PDV-F068B, Circuit Breaker DQO HPCI Turbine Exhaust Vacuum Breaker Valve, 1-E41-F079, Circuit Breaker I (e.E - l BSEP-0/ASSD-02 Page 148 of 202 Rev. O l
- 2. (Cont'd)
Compartment Number Component Description e DL1 . RHR Pump 1B Shutdown Cooling Suction Valve,- 1-E11-F006B, Circuit Breder-DL2 RHR Pump 1D Shutdown Cooling Suction Valve, 1-E11-F006D Circuit- Breaker DL5 RCIC Turbine Exhaust Vacuum Breaker Valve, 1-E51-F066, Circuit Breaker DK9 RHR Pump 1B Suppression Pool Suction Valve, 1-E11-F004B Circuit P.reaker - - DL3 Mininum Flow Bypass Valve,1-E11-F007B, Circuit Breaker = . - - - DLO RHR Pump 1D Suppression Pool Suction Yalve. 1-E11-F004D, Circuit Breaker - DN4 RHR HX 1B Outboard Vent Valve,1-E11-F103B, N Circuit Breaker - - .
- b. DK8
~
RHR HX 1B Outlet Valve,1-E11-F003B, Circuit Breaker. - - - DM7 RHR HX 1B Inlet Valve,1-E11-F047B, Circuit Breaker- - DH8 RHR HX 1B Bypass Valve,1-E11-F048B. Circuit Breaker DL6 RHR HX 1B Drain To Suppression Pool Valve, 1-E11-F011B Circuit Breaker DM3 RHR HX 1B Drain To RCIC Valve,1-E11-F0268, Circuit Breaker - DNS RHR HX 1B Inboard Vent Valve,1-E11-F104B, Circuit Breaker Disconnect Switch 9KVA 39 480-208Y/120V Transformer D3A Battery Charger 1B-1 Alternate Feeder . D3B Battery Charger 18-2 Alternate Feeder { BSEP-0/ASSD-02 Page 149 of 202 Rev. O
p*, 3. PERFORM switch lineup on MCC 1XB per Step 2 of Section J without power available to MCC IXB, THEN CONTINUE restoration with Step 4 below.
- 4. DIRECT Diesel Generator Operator to RECLOSE Reactor Building MCC IXB power supply breaker at 480V Substation E6 Compartment AWO.
- 5. WHEN informed by Diesel Generator Operator that power supply breaker for Reactor Building MCC 1XB is Closed THEN CLOSE the following breakers to energize Safe Shutdown loads on Reactor Building MCC 1XB.
Compa rtment Number Component Description DP7 Vent RHR HX Area Cooling Fan IB-FCV-RB DK1 Recirculation Pump 1B Suction Valve, 1-B32-F023B, Circuit Breaker , DN6 RHR Pump 1B and 10 Suppression Pool Suction Valve,1-E11-F0208. Circuit Breaker l DP2 Nuclear Service Water To Vital Header Inboard g g3 gg Isolation Valve,1-SW-V117, Circuit Breaker DN9 RHR HX B Service Water Discharge Valve, 1-E11-F002B, Circuit Breaker ! DN2 RHR SW Outboard Injection Valve,1-E11-F073, Circuit Breaker DM1 RHR Service Water Booster Pumps B and D Inboard Isolation Valve,1-SW-V105, Circuit Breaker DM6 Service Water To RHR Service Water Header Cross-tie Valve,1-SW-V102, Circuit Breaker DL8 Drywell Spray Outboard Isolation Valve, 1-E11-F016B, Circuit Breaker DM0 Drywell Spray Inboard Isolation valve, 1-E11-F021B, Circuit Breaker DK! Suppression Pool Cooling Isolation Valve, 1-E11-F0248, Circuit Breaker (! BSEP-0/ASSD-02 Page 150 of 202 Rev. O
- 5. (Cont'd)
Compartment Nurner Component Description DU.4 Suppression Pool Spray Isolation Yalve, 1-E11-F027B, Circuit Breaker DN1 RHR HX B Service Header Outlet Yalve, 1-E11-PDV-F068B, Circuit Breaker DL1 RHR Pump 1B Shutdown Cooling Suction Valve, 1-E11-F006B, Circuit Breaker DL2 RHR Pump ID Shutdown Cooling Suction Valve, 1-E11-F006D, Circuit Breaker-DL5 RCIC Turbine Exhaust Vacuum Breaker Valve, 1-E51-F066, Circuit Breaker _ DK9 RRR Pump 18 Suppression Pool Suction Valve, nn 1-E11-F004B, Circuit Breaker . .. .. . nC DL3 Mininum Flow Bypass Valve,1-E11-F007B,
. Circuit Breaker . ... . ... . . .
DLO RHR Pump ID Suppression Pool Suction Valve, 1-E11-F0040, Ci rcuit Breaker .. . DK8 RHR HX 1B Outlet Valve,1-E11-F003B, Circuit Breaker DH7 RHR HX 1B Inlet Valve,1-E11-F0478, Circuit Breaker DH8 RHR HX 1B Bypass Valve, 1-E11-F048B, Circuit Breaker 03A Battery Charger 1B-1 Alternate Feeder 03B Battery Charger 18-2 Alternate Feeder
- 6. COMPLETE switch / valve position lineup for HCC 1XB per Step 2 of Section.J with power available to MCC 1XB.
W BSEP-0/ASSD-02 Page 151 of 202 Rev. O
I l l RESTORING POWER TO REACTOR BUILDING (J MCC 1XD i The purpose of the following steps is to restore power to Reactor Building MCC IXD in the event that an electrical f ault causes the feeder breaker at 480V Substation E6 Compartment AW6 to trip.
- 1. IF power is'NOT available to Reactor Butiding MCC 1XD as Tetermined by loss of indicating lights and control for items powered from MCC 1XD, THEN DIRECT Diesel Gensrator Operator to CONFIRH the following:
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Reactor Building MCC IXD at Compartment AW6 is Tripped.
- 2. WHEN Diesel Generator Operator CONFIRMS that
- a. 480V Substation E6 is Energized AND
- b. Power supply breaker to Reactor Building MCC 1XD at Compartment AW6 is Tripped, THEN_ OPEN the followin.g breakers on Reactor Building MCC 1XD. M Number - Component Description - - -
DW9 Core Spray Pump 18 Minimum Flow Bypass Valve, 1-E21-F0318. Ci reuit Breaker. - DW8 Core Spray Full Flow Test Bypass Valve, 1-E21-F0158, Circuit Breaker DW6 Core Spray Inboard Injection Valve, 1-E21-F0058 Circuit Breaker DX8 Standby Air Compressor 1B Circuit Breaker DX2 Vent Core Spray Pump Area Cooling Fan, 1D-FCU-RB, Circuit Breaker - DW3 Core Spra l Valve,1 yi.21-F001B, Pump 1B Suppression Circuit BreakerPool Suction
. I DW5 Core Spray Outboard Injection Valve, 1-E21-F004B Circuit Breaker j
(
- s. . . ~
l BSEP-0/ASSD-02 Page 152 of 202 Rev. 0
l l I l
- 2. (Cont'd) l Com partment Num>er Component Description 1
DX4 Suppression Pool 2 In. Exhaust Valve, 1-CAC-V22, Circuit Breaker DX9 COMPT 1-DX9 HOTOR 1-KE3 NSS MN STM DRN LIE YLV 1-B21-F016 ASSD FEED - DYO Welding Receptacle Elev. -17' 0" 480V 39 DX7 Reactor Building Equipment Drain Tank Pump 1 A,1-G16-C006A, Circuit Breaker DW2 COMPT.1-DW2 MOTOR 1-RR7 RCIC TURB. VAC BREAKER VLY.1-E51-F062 ASSD FEED - DY1 COMPT.1-DY1 MOTOR 1-KS8 RCIC STEAM SUPPLY LINE ISOL. VLV.1-E51-F007 AS$D FEED p DX5 COMPT.1-DX5 MOTOR 1-kM2 RR SUCTION ISOL. VLV.1-E11-F009 ASSD FEED. - - - DW1 Steam Supply Inboard Isolation Yalve. 1-E41-F002 Circuit Braaker-DXO Feedwater Line B Isolation Valve, 1-B21-F0328 Circuit Breaker - DY2 Miscellaneous 120V AC Distribution Panel 1DXB Supply Breaker-DX6 Welding Receptacle (Elev. 20'-0") 480V 39 DX3 Recirculation Pung 1B Hotor Heater Circuit Breaker Disconnect. Switch 9KVA 39 480-208Y/120V Transformer -
- 3. DIRECT Diesel Generator Operator to RECLOSE Reactor Building MCC 1XD power supply breaker at 480V Substation E6 Compartment AW6.
9 (;b BSEP-0/ASSD-02 Page 153 of 202 Rev. O
- 4. WHEN informed by Diesel Generator Operator that power supply
-(, breaker for Reactor Building MCC 1XD at 480V Substation E6 Compartment AW6 is Closed, THEN CLOSE the following breakers to energize Safe Shutdown loads on Reactor Building MCC 1XD.
Compartment ' Nu h r Component Description. DW2 COMPT.1-DW2 MOTOR 1-RR6 RCIC TURB. VAC BREAXER VLV.1-E51-F062 ASSD FEED DY1 (DMPT.1-DY1 MOTOR 1-XS8 RCIC STEAM SUPPLY LINE ISOL. VLV.1-E51-F007 ASSD FEED DX5 COMPT.1-DX5 MOTOR 1-KM2 RHR SUCTION ISOL. VLV. 1-E11-F009 ASSD FEED T ([$ l@_ ! BSEP-0/ASSD-02 Page 154 of 202 Rev. 0 [
RESTORING POWER TO REACTOR BUILDING g MCC 1XB-2 The purpose of the following steps is to restore power to Reactor Building MCC , 1XB-2 in the event that an electrical fault causes the feeder breaker at 480V 1 Substation E8 Compartment AX9 to trip.
- 1. IF power is'NOT available to Reactor Building MCC 1XB-2 as Tetermined by loss of indicating lights and control for items powered f rom Reactor Building MCC 1XB-2, THEN DIRECT Diesel Generator Operator to CONFIRM the following:
- a. 480V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC IXB-2 at Compartment AZ9 is Tripped.
- 2. WHEN Diesel Generator Operator CONFIRMS that
- a. 480V Substation E8 is Energized AND
- b. Power supply breaker to Reactor Building MCC 1XB-2 at Compartment AZ9 is Tripped, M.
THEN OPEN the following breakers on Reactor Building MCC 1XB-2. h' Compartment Number Component Description - - DK2 Recirculation Pump 1B Discharge Valve, 1-B32-F031B, Circuit Breaker DK3 Recirculation Pump 1B Discharge Bypass Valve, 1-B32-F032B, Circuit Breaker DL7 LPCI Inboard Injection Valve, 1-E11-F0158, Circuit Breaker DL9 LPCI Outboard Injection Valve, 1-E11-F0178, Circuit Breaker DMS Suppression Pool Discharge Isolation Valve,1-E11-F0288 Circuit Breaker (;?.A* BSEP-0/ASSD-02 Page 155 of 202 Rev. 0
- a. - 3. PERFORM switch lineup on HCC 1XB-2 per Step 2 of Section J v without power available to HCC 1XB-2, THEN CONTINUE restoration with Step 4 below.
4 DIRECT Diesel Generator Operator to RECLOSE Reactor Building MCC 1XB-2 power supply breaker at 480V Substation E8 Compartment AZ9.
- 5. WHEN informed by Diesel Generator Operator that power supply breaker for Reactor Building MCC 1XB-2 is Closed THEN CLOSE the following breakers to energize Safe Shutdown loads on Reactor Building HCC 1XB-2.
Compartment Number Component Description DL7 LPCI Inboard injection Valve, 1-E11-F015B, Circuit Breaker-DL9 LPCI Outboard Injection Valve, 1-E11-F017B, Circuit Breaker - - DH5 Suppression Pool Discharge Isolation Valve,1-E11-F0288, Circuit Dreaker - 0 6. COMPLETE switch / valve position lineup for HCC 1XB-2 per Step 2 of Section J with power available to HCC 1XB-2.
- h. '-
BSEP-0/ASSD-02 Page 156 of 202 Rev. O
RESTORING POWER TO REACTOR BUILDING h., HCC 1XDB The purpose of the following steps is to restore power to Reactor Building HCC 1XDB in the event that an electrical fault causes the feeder breaker listed below to trip. 125/250V DC Switchboard 1B
- a. Compt. GL3 Reactor Building MCC 1XDB Supply Breaker
- b. Compt. B30 Incoming Feeder Breaker Reactor Building MCC IXDB
- 1. OPEN the following breakers on Reactor Building HCC IXDB.
Compartment Number Component Description B35 RCIC Barometric Condenser Vacuum Pump Circuit Breaker - B36 RCIC Barometric Condenser Vacuum Tank Condensate Pump Circuit Breaker - - M B37 .RCIC Turbine Trip And Throttle Valve, 1-E51-VB, Circuit Breaker (]i B38 RCIC Condensate Storage Tank Suction Valve,1-E51-F010, Circuit Breaker B39 RCIC Cooling Water Supply Valve, 1-E51-F046, Circuit Breaker B40 RCIC Pump Discharge Valve, 1-E51-F012, Circuit Breaker B41 RCIC Injection Yalve, 1-E51-F013, Circuit Breaker B42 RCIC Bypass To Condensate Storage Tank Valve 1-E51 F022, Circuit Breaker B43 RCIC Steam Supply Outboard Isolation Valve,1-E51-F008, Circuit Breaker B44 RCIC Turbine Steam Supply Valve, 1-E51-F045, Circuit Breaker B45 RCIC Suppression Pool Suction Valve, 1-E51-F031, Circuit Breaker (,J . - Page 157 of 202 Rev. O BSEP-0/ASSD-02
l l
- 1. (Cont'd)
Com partment Num>er Component Description - B46 . RC1c Suppression Pool Suction Valve, 1-F51-F029 . Circuit Breaker - B47 RCIC Minimum Flow Bypass To Suppression Pool Valve,1-E51-F019, Cireuit Breaker- - - B48 RWCU Inlet Outboard Throttle Isolation Valve,1-G31-F004, Circuit Breaker-B49 Reactor Vessel Head Spray Outboard Isolation Valve,1-E11-F023, Circuit Breaker- - - - - - - B50 Shutdown Cooling Outboard Suction Isolation Valve,1-E11-F008. Circuit y} Breaker - - - - B51 RM To Radwaste Outboard Isolation Valve,1-E11-F040. Circuit Breaker - - ($.9 B52 Main Steam Line Outboard Drain Isolation Valve,1-B21-F019. Circuit Breaker - - - - B53 REMOTE SHUTOOWN PANEL IR-RB-4 ALT. MFE SHUTDOWN INSTRUENTS - ('). BSEP-0/ASSD-02 Page 158 of 202 Rev. O
- 2. PERFORH switch lineup on MCC 1XDB per Step 2 of Section J (E"
without power available to HCC 1XDB, THEN CONTINUE restoration with Step 3 below.
- 3. At 125/250V DC Switchboard 1B, VERIFY Closed OR CLOSE Feeder Breaker COMPT GL3 Reactor Building HCC 1XDB. -
- 4. At Reactor Building MCC 1XDB VERIFY Closed OR -
CLOSE Compt. B30 INCOMING FEEDER BREAXER.
- 5. CLOSE the following breakers on Reactor Building MCC 1XDB.
Compartment Number Component Description _ B35 RCIC Barometric condenser Vacuum Pump Circuit Breaker B36 RCIC Barometric Condenser Vacuum Tank Condensa'i'pmp Circuit Breaker - B37 RCIC T"fo!ne T rip And Throttle Valve, 1-E51-V8 Circuit Breaker . . g B38 RCIC Condensate Storage Tank Suction {. Valve.1-E51-F010 Circuit Breaker- .- B39 RCIC Cooling Water Supply Valve, 1-E51-F046, Circuit Breaker B40 RCIC Pump Discharge Valve,1-E51-F012, Circuit Breaker B41 RCIC Injection Valve,1-E51-F013, Circuit Breaker B42 RCIC Bypass To Condensate Storage Tank Valve, 1-E51-F022, Circuit Breaker B43 RCIC Steam Supply 0"tboard Isolation Valve, 1-E51-FG08 Circuit Breaker B44 RCIC Turbine Steam Supply Valve, 1-E51-F045, Circuit Breaker B45 RCIC Suppression Pool *,uction Yalve, 1-E51-F031, Circuit Breaker l Q( . CSEP-0/ASSD-02 Page 159 of 202 Rev. O
E.
- 5. (Cont'd)
Compartment Number Component Description B46 RCIC Suppression Pool Suction. Valve, 1-E51-F029, Circuit Brecker B47 RCIC Minimum Fiow Bypass To Suppressica Pool Valve,1-E51-F019, Circuit Breaker B48 RWCU Inlet Outboard Throttle Isolation Valve,1-G31-F004 Circuit Breaker
*B50 Shutdown Cooling Outboard S.ction Isolation Valve,1-E11-F006, Circuit Breaker 852 Main Steam Line Outboard Drain Isolation Valve,1-B21-F019, Circuit Breaker 8
s B53 REMOTE SHUTDOWN PANEL IR-RB-4 ALT. g SAFE SHUTDOWN INSTRUMENTS
*1f the pre-fire rackout tag has not been previously removed during performance of ASSD-02, then g NOT close this breaker.
- 6. COWLETE switch / valve position lineup for MCC IXD3 por Step 2 of Section J with power available to MCC 1XDB.
I a j k.3-Rey, 0 I BSEP-0/AS50-02 Pa9e 160 of 202 i
APPENDIX 1 UNIT 2 ASSO REMOTE SHUTDOWN EQUIPMENT LIST NOTE: 2 spare keys are included in the number of T112 keys and GE75 keys distributed to persons oelow.
- 1. Unit 2 Shift Foreman '
(1) Sound powered phone headset (1) Twenty-five foot sound powered phone extension cord
- 2. Unit 2 Remote Shutdown Panel Operator Log book Copy ASSD-02, Control Building Copy 2-APP-UA-29 Annunciator Procedure for Panel UA-29
) Keys,SerialNumberT112 Sound powered phone headset Sound powered phone jumrer cord (8")
Twenty-five foot sound powered phone extension cord Dual comunication Jacks (Y-Jacks) 7'.l
- 3. Unit 2 Reactor Building MCC Operator Copy ASSD-02, Control Building Sound powered phone headset h'; Twenty-five foot sound powered phone extension cords
) Keys, Serial Number T112 Flashlight CO Key (125V Distribution Panels) 4 Emergency Switchgear Operator
( Copy ASSD-02, Control Building ( ( Sound powered phone headset Twenty-five foot sound powered phone extension co ds
) Keys Serial Number GE-75 i Set fuse pullers l Flashlight i C0 Key (125% Distribut'sn Panels) ;
r 1 i ! l [ I ' CL . { t BSEP-0/ASSD-02 Page 161 of 202 Rev. 0 : I f
- 5. O sel Generator 0.serator G l Copy ASSD-02 Control Building Il, Sound powered phone headset I
Twenty-five foot sound powered phone extension cords
) Keys, Serial Number T112 (1,
) Keys, Serial Number GE-75 I Set fma pullers' Il Flash.i@t I C0 Key (125V Distribution Panels)
I,, ) Door wedge blocks
- 6. Service Water Buildino Doerator Copy ASSD-02 Control Butiding Set sound-powered phsnes Twenty-five foot sound-powered phone extension cords
) Keys. Serial Number T112 Set fuse pullerr Flashlight
]\10.
(}fli . 1 I i l ) I i t k$i ESEP-0/ASSD-02 Page 162 of 202 Rev. 0 j .
APPENDIX 2 g'.w' UNIT 1 ASSD REMOTE SHUTDOWN EQUIPMENT LIST NOTE: 2 spare keys are included in the number of T112 keys and GE75 keys distributed to persons below.
- 1. Unit 1 Shift Foreman '
(1) Sound powered phone headset (1) Twenty-five foot sound powered phone extension cord.
- 2. Unit 1 Remote Shutdown Panel Operator (1 Log book (1 Copy ASSD-02, Control Building (1 Copy 1-APP-UA-29, Anr.onciator Procedure for Panel UA-29 1 ) Keys, Serial Number T112
- 1) Sound powered phone headset
- 1) Twenty-five foot sound powered phone er, tension cord
- 3. Unit 1 Reactor Building HCC Operator *
(1 Copy ASSD-02, Control Building (1 Sound powered phone headset Twenty-five foot sound powered phone extension cords
) Keys, Serial Number T112
(~:
. Flashlight CO Key (125V Distribution Panels) s O
BSEP-0/ASSD-02 Page 163 of 202 Rev. O
hN E APPENDIX 3 , gj UNIT 1 ACCES$/ EGRESS ROUTES l ( l . i (;E. ' . BSEP-0/AS$0-02 Page 164 of 202 Rev. O
i e - 1 i CONTMOL BUILDING _
- .8 _ , ,
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- - - actuttenese J oneet ace,rnse a en s ,
l FIGURE 1 Control Building 49'-0" Elevation - Access / Egress and Sound Powered Phone Comunications
,p .
v.i BSEP-0/ ASS 0-02 Page 16b of 202 Rev. 0
CONTMOL BUILOING 70.'OltSEL GENERATOM SUILDING, SERVICK WATEM OUILONt0, REACTOM GUILDING ANO tnt EAST YARD., CONTMOLLED ACCESS SMEfftwAr 8000 123/20010C 12 3 30YOC _= __ SWITCHOQAMO 20 lQI 0_0eM010 = y = aseat tL. a# " M,g ' .pygg gg, 40W= f'l gg og ,y 40** 0*
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- - - AcCluiteatn y ruent aca,rMeon A Ca 0 1
FIGURE 2 Control Building 23'-O' Elevation - Access / Egress I M)
.s BSEP.0/ASSO 02 Page 166 of 202 Rev. O
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& A 6 MC SET 2E ORIVE N0 TOR T3. ELEVATOR A ** ~~ 0 UNIT I TUR0lNE SLDO.
4.It KV SWITCNetAR SUS IC A B COND.StTR. PUMP la l h 10 CONO. ESTR. PUMP IC T Il COND.FUMP IE g 4.80KV SWITCHOEAR BUS ID VACUUN l It CONO.ESTR.PtNP IE PUMPS 13 COND. PUMP IA 4* D h I4 COND. 90'4P IC 4.It KV SWITCNSEAR EUS 18 l 15 MC SET IA DRIVE MOTOR BREEZE WAY / '* "**'**'V'"*'** 4m, .>. --*l h _ &.4 i n 4 r LE0ENO ACCESS / EGRESS ~ ~ ~ FIGURE 4 Turbine Building 20'-0" Elevation - Access / Egress b,.,, BSEP-0/ASSD-02 Page 168 o.' 202 Rev. 0
i UNIT I MtACr0M eUtLDING 400Tu i - l # l \ enou carr a suoteen acun p. antrerwr \ !' r0 e anon -
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- - - - uctuiunauss 9 ruona aca,rasia a ca.a e speLdit 29ticW FIGURE 5 Unit 1 Rea'ctor Building 20'-0" ELEVATION - Access / Egress aM .
Sound Powered Phone Connunications m' ESEP-0/ASSD-02 Page 169 of 202 Rev. O
UNor/ ntMTOR OLMLDING y*NO l 1
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DETAll A i ff L. 9 '= 0 ') , g raot , _ l FIGURE 6 Unit 1 Reactor Building (-) 17'-0" ELEVATION - Access / Egress b- '
. BSEP-0/ASSD-02 Page 170 of 202 . Rev 0
i Q UNIT 1 REACTOR BUILDINGg 6 I
% N0 NTH I. Ell-F0602 a
(ELEV. 45'0")~ftI ,,, \ y s f E// F06cA f llg/ (El.EV. 35' 0") e FM
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- - -- ACCiss/tsntss a VALVES I
FIGURE 7 Unit 1 Reactor Building 50'-0" ELEVATION - Access / Egress b, BSEP-U/ASSD-02 Page 171 of 202 Rev. U
G N APPENDIX 4 UNIT 2 ACCESS / EGRESS ROUTES
- {[
9 l r (L' BSEP-0/ASSD-02 Page 172 of 202 Rev. O f
@ l l CONTROL BUILDING norrw M TO WIT N0.2 10 WITN0.4 RfACTOR BLOG - - - CL. 30' O., 0." RE_
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(' and Sound Powered Phone Comunications BSEP-0/AS50-02 Page 173 of 202 Rev. O
CONTMOL BUILDING 70.' CICSEL stNtMATOR OVILDING, SERV 9CC weitM OUILONFC, RieCTOR SUILOING AND tnt te3T TeRO. CONTROLLtB ettERG CMig2 Ewer
= N0hMO 20
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Ci-BSEP-U/ASSD-02 Page 174 of 202 Rev. O
b i CONTROL BUIL DING EL . 23 *-0* r0 04tSCL Ccortne!OR BurLDm6, SERVtt waren earlene, ReaCran surtees ane 1 FMc KA8rrame.
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l I FIGURE 3 I Control Building 23'-0" Elevation - Access / Egress . With Alternate Route to Battery Rooms for Unit 2 l bp[,v BSEP-0/ASSU-02 Pave 175 of 202 Rey, 0 ' t
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4 LeGtND accessitoness - - - FIGURE 4 Turbine Building 20'-0' Elevation - Access / Egress h... w - BSEP-0/ASSD-02 Page 176 of 202 Rev. U
UNIT 1 ethCTOM OUILCING l l
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. and Sound Powered Phone Comunications 2
(. . '_ BSEP-U/AS50-02 Page 177 of 202 Rev. O
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, BSEP-0/A550 02 Page 17S of 202 Rev. O
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~ ~ ~ Access /EcREss n VALVES FIGURE 7 Unit 2 Reactor Building 60'-u' Elevation - Access / Egress e
D" , BSEP-0/AS50-02 Page 179 of 202 Rev. 0
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t I FIGURE 8 I Diesel Generator Building Access / Egress Routes __ and i (' . _ Sound Powered Phone Cornunications ! l BSEP-0/ASSO.02 Page 100 of 202 Rev. 0 l l l l l
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0h 4 l APPENDIX 5 RE$TORING DC POWER
@r-)'
70 125/250V DC $WITCHBOARDS a, . Qp..' t
. ESEP-0/AS$0-02 Page 182 of 202 Rev. O
RESTORING POWER TO 125/250V h DC SWITCHBOARD 1B The purpose of the following steps is to restore power to 125/250V DC Switchboard IB in the event that an electrical fault causes the feeder breakers listed below to trip. 120/250V DC SWITCHBOARD 18
- a. COMPT. GM1 Battery Charger IB-1 DC Output Breaker
- b. COMPT. GM4 Battery Charger 18-2 DC Output Breaker
- c. COMPT. GK! Battery 18-1 Output Breaker
- d. COMPT. GM3 Battery 18-2 Output Breaker REACTOR BUILDING KC IXB
- a. COMPT. 03A Battery Charger 18-1 Alternate feeder
- b. COMPT. 03B Battery Charger 18-2 Alternate Feeder
- 1. OPEN the following 125/250V DC Load breakers on 125/250V DC Switchboard 18.
Rt r-I.
" Compartment Number Component Description M8 Alternate Supply to Unit 2 Lighting Inverter Tracking Rectifier GK6 Control Building 125V DC Distribution Panel 3B Supply Breaker GK7 125Y DC Distribution Panel 3AB Normal Supply Breaker GK8 125V DC Distribution Panel 5A Alternate Supply Breaker GK9 125Y DC Distribution Panel 7B Nonnal Supply Breaker GLO 125V DC Distribution Panel 9A Norsal Supply Breaker
- GL1 125V DC Distribution Panel 13 Alternate Supply Breaker v1 ,.
%: R )
Page 183 of 202 Rev. C BSEP-0/ASSD-02
- 1. (Cont'd) g!; l Compartment Number Component Description i 12 Turbine Building MCC 1TDB Supply Breaker ;
E3 Reactor Building MCC 1XDB Supply treaker i E4 Control Building 125V DC Distributton Panel ! 118 Supply Breaker l 4 15 Power Conversion Unit it (DCC Input to Standby Power Converter 18) Circuit Breaker ( 2 E6 Diesel Generator Building Distribution Panel f Il Supply Breaker , 4 E7 Reactor tutiding Emergency Lighting Contactor Supply treaker - Et Turbine Building Emergency Lighting Contactor Supply RS.h < GL9 COMPT. GL9 LTC. INVERTER U-1 h(~- GM0 WT Building Main Control Panel Alternate L Supply Breaker : I , 879 Emergency tearing 011 Puay Starter E80P ; Circuit Breaker 4
- 2. VERIFY Closed OR CLOSE the Battery and Battery charger Output !
breakers listeThelow, i Compartment Number Component Description [ .: GM1 lattery Charger 18-1 DC Output treaker GM2 Battery 15-1 Output Breaker GM3 Battery 18-2 Output treaker [ lattery Charger 18-2 DC Output Breaker GM4 i i BSEP-0/ASSD-02 Page 184 of 202 Rev. O r i l
- 3. At B.7 w e 9.., ars 1B-1 and 1B-2 perform the following L .aU- OR PLACE FLCAT-EQUALIZt control switches in the r,nif70sition,
~
- b. VERIFY OR PLACE EQUALIZING CHARGER TIMER switches in the "ZE F position.
NOTE Contact Unit 1 Shift Foreman to obtain necessary tool for opening Battery Charger transfer switch cover.
- 4. At Battery Charger 1B-1 and 18-2 Transfer Switches. VERIFY OR ~
PERFORM the following.
- a. OPEN battery charger 1B-1 transfer switch cover.
- b. PLACE Normal / Emergency switch for battery charger 1B-1 to "EMERGENCY".
- c. RECLOSE battery charger 1B-1 transfer switch cover,
- d. OPEN battery charger 18-2 transfer switch cover.
- e. PLACE Normal / Emergency switch for battery charger 1B-2 bJ,'
to "EMERGENCY". g
- f. RECLOSE battery charger 18-2 Transfer switch cover.
- 5. At Reactor Building MCC 1XB perform the following,
- a. VERIFY Closed OR CLOSE COMPT D3A Battery Charger 18-1 Alternate FeedeF.
- b. VERIFY Closed OR, CLOSE COMPT D3B Battery Charger 1B-2 Alternate Feeder.
- 6. CLOSE the following breakers to on 125/250V DC Switchboard IB to I
energize Safe Shutdown loads. 1 ! a. COMPT. GL3 Reactor Juilding MCC 1XDB Supply Breaker 1
- b. COMPT. GL6125V DC Distribution Panel IB Supply Breaker
- 7. INFORM Unit 1 Shif t Foreman that 125/250V DC Switchboard 1B is Energized and load breakers are Closed.
,pd.
e. BSEP-0/ASSD-02 Page 185 of 202 Rev. O
RESTORING POWER TO 125/250V (,f DC SWITCHBOAAD 2B The purpose of the following steps is to restore power to 125/250V DC Switchboard 2B in the event that an' electrical fault causes the feeder breakers listed below to trip. 125/250V DC SWITCHB0ARD
- a. COMPT. GM1 Battery Charger 28-1 DC Output Breaker
- b. COMPT. GM Battery Charger 2B-2 DC Output Breaker
- c. COMPT. GM2 Battery 2B-1 Output Breaker
- d. COMPT. GM3 Battery 2B-2 Output Breaker REACTOR BUILDING MCC 2XD
- a. COMPT. 03A Battery Charger 28-1 Alternate Feeder
- b. COMPT. 03B Battery Charger 2B-2 Alternate Feeder
- 1. OPEN the fellowing 125/250V DC Load breakers on 125/250V DC Switchboard 28.
cf RB Compa rtment Number Component Description GJ8 Normal Supply To Tracking Rectifier Circnit Breaker GK6 125V DC Distribution Panel 4B Supply Breaker GK7 125V DC Distribution Panel 4 AB Normal Supply Breaker GK8 125V DC Distribution Panel 6A Alternate Supply Breaker GK9 125V DC Distribution Panel 88 Normal Supply Breaker GLO 125V DC Distribution Panel 10A Normal Supply Breaker GLI 125V DC Distribution Panel 13 Nornal Supply i Breaker GL2 Turbine Building MCC 2TDB Supply Breaker (mL-I BSEP-0/ ASSD-02 Page 186 of 202 Rev. O i
- 1. (Cont 'd)
Compartment Number Component Description GL3 Reactor Building MCC 2XDB Supply Breaker GL4 125V DC Distribution Panel 12B Supply Breaker GL5 Power Coriversion Unit 2B (DB Input To Standby Power Converter 28) GL6 125V DC Distribution Panel 2B supply Breaker GL7 Radwaste Building Emergency Lighting Contactor Supply Breaker GL8 Turbine Building Emergency Lighting Contactor supply Breaker R B.I GL9 Alternate Supply To Tracking Rectifier Circuit - Breaker GM0 WT Building Main Control Panel Normal Supply Breaker kh GM5 1_25V DC Distribution Panel A0G-2 Supply Breaker B79 Emergency Bearing 011 Pump Starter, EBOP Circuit Breaker
- 2. VERIFY Closed OR CLOSE the Battery And Battery Charger Output breakers listeThelow.
Compartment Number Component Description GM1 Battery Charger 28-1 DC Output Breaker GH2 Battery 28-1 Output Breaker GM3 Battery 28 2 Output Breaker GM4 Battery Charger 28-2 DC Output Breaker D* BSEP-0/AS$0 02 Page 187 of 202 Rev. O
- 3. At Battery Chargers 28-1 And 28 2 perform the following.
- a. VERIFY OR PLACE FLOAT-EQUALIZE control switches in the "FLOAi7osition.
- b. VERIFY OR PLACE EQUALIZING CHARGER TIER switches in the "ZEllP position.
NOTE Contact Unit 2 shift Foreman to obtain necessary tool for opening Battery Charger Transfer Switch cover.
- 4. At Battery Charger 28-1 and 28-2 Transfer Switches. VERIFY OR ~
PERFORM the following.
- a. OPEN battery charger 28-1 transfer switch cover.
- b. PLACE Normal / Emergency switch for battery charger 28-1 to "EMERGENCY".
i
- c. RECLOSE battery charger 28-1 transfer switch cover,
- d. OPEN battery charger 28-2 transfer switch cover. gg [
' /3 e. PLACE Normal / Emergency switch for battery charger 2B-2 6 to "EMERGENCY". j f. RECLOSE battery charger 2B-2 transfer switch cover. !
- 5. At Reactor Building MCC 2XD perfona the following. 7
- a. VERIFY Closed OR CLOSE COMPT. 03A Battery Charger 28-1 Alternate FeedeF.
- b. VERIFY Closed OR CLOSE COMPT. 038 Battery Charger 25-2 !
Alternate Fee 6r.
- 6. CLOSE the following breakers to on 125/250V DC Switchboard 2B to .
energize Safe Shutdown loads. l
- a. COMPT. GL3 Reactor Building MCC 2XDB Supply Breaker,
- b. COMPT. GL6125V DC Distribution Panel 28 Supply i Breaker. j
- 7. INFORM Unit 2 Shift Foreman that 125/250V DC Switchboard 2B is I Energized and load breakers are Closed. L b, '
BSEP-0/ASSD-02 Page 188 of 202 Rev. O
e APPENDIX 6 - A. TITLE ! UNIT 1 REACTOR VESSEL RAPID DEPRESSURIZATION !
- 8. ENTRY CONDITION -
This pro.edure is entered y_H,EN
- 1. Operation of the SRV's is in jeopardy as confirmed by:
- a. N2 Backup System Div. I pressure as indicated on r 1-RNA-PI-5266 is less than 70 psig. '
AW _ b. N2 Backup System Div. !! pressure as indicated on 1-RNA-5264 is less than 70 psig. E !
- c. Loss of Drywell cooling has occurred AND Reactor -
0 Yessel cooldown rate of 100 F/hr. has not started w thin 1 hour of the loss of Drywell cooling. g,f - 3 <
- d. Failure of any SRY (1-821-F0135 E or G) to open using ,
the local control switches on ti:e Remote Shutdown Panel. OR l
- 2. Reactor vessel level as indicated on 1821-LI-6048X has !
decreased to 45 inches OR indication of Reactc.* Vessel level is lost. ( l L l l l r > hs.. t [ Page 189 of 202 Rev. 0 BSEP-0/ASSD-02 ( i
t 1
-] .
+
p
.. C. : OPERATOR ACTION
{y ' ' 1. INFORM Unit 2 Shift Foremen that Unit 1. is required to PERFORM a V Rapid Depressurization of Unit 1 Reactor Yessel.
- 2. IF the switch alignment for the Remote Shutdown Panel is not '
E mplete. THEN DIRER,T the RSDP operator to COMPLETE Step 1 of ; Section "1". i
- 3. IF RCIC is NOT running ~THEN
~ DIRECT the RSDP Operator to PLACE T61C in service. ;
- 4. IF NORMAL / LOCAL switch lineup for Unit 1 Reactor Building KCs Ts not complete, THEN DIRECT RSDP Operator to have the Reactor Building MCC Operator CO WLETE Step 2 of Section "J". :
- 5. WHEN
- a. Diesel Generators No. 2 AND No. 4 are running ~AND
, supplying Emergency Buses T2 AND E4 AW
- b. NORMAL / LOCAL switch lineup for Unit 1 Reactor Building !
MCCs is Complete. , j THEN PERFORM Step 6 OR Step '/ to Rapidly DEPRESSURIZE and gg, l t TE3 TORE water level W the reactor vessel. ' fl : t i ! t i !
- r I
r i 1 l I
@k l
BSEP-0/ASSD-02 Page 190 of 202 Rev. O l .
- 6. IF RHR System is in Suppression Pool Cooling, THEN TRANSFER RHR g Tfstem to LPCI Mode AND DEPRESSURIZE as follows:
- a. DIREC1 RSDP Operator to have Unit 1 Reactor Building MCC Operator:
(1) OPEN Minimum Flow Bypass Valve, 1-E11-F007B, at MCC lB Compartment DL3. (2) OPEN RHR HX IB Bypass Valve,1-E11-F048B, at MCC IXB Compartment DMB. (3) CLOSE RHR HX 1B Inlet Valve,1-E11-F0478, at MCC IXB Compartment DK7. (4) CLOSE Suppression Pool Discharge Isolation Valve, 1-E11-F028B, at MCC 1XB-2 Compartment D>6. NOTE RHR Pump 10 still remains in operation.
- o. DIRECT Emergency Bus Operator to START RHR Pump 18 at Emergency Bus E4 Compartment ALO.
RS. I Q9 ******************************u .*****************,*************************** CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running AND available for injection.
- c. DIRECT RSDP Operator to OPEN all SRVs at the Remote Shutdown Panel.
- d. DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to OPEN LPCI Inboard Injection Valve, 2-E11-F015B, at F.C 2XB-2 Compartment DL7 WHEN reactor pressure has durcised to 425 psig AND prior to decreasing to 3ys ptig as indicated on 1-C32-PI-3332 on RSDP.
BSEP-0/ASSD-02 Page 191 of 202 Rev. O
- e. WHEN reactor water level has been restored between g 200" and 208" as indicated on 1-B21-LI-604BX at RSDP THEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 1B at Emergency Bus E4 Compartment ALO.
(2) DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator as necessary to THROTTLE LPCI Outboard Injection Valve, 1-E11-F0178, to maintain reactor water level between 200" and 208" as indicated on 1-B21-LI-604BX at RSDP.
- f. WHEN LPCI Mode of RHR System is no longer needed THEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 1D at Emergency Bus E2 Compartment AHS.
_ (2) DIRECT RSDP Operator to INSTRUCT Reactor-Building MCC Operator to PERFORM the following. RS. (a) CLOSE LPCI Inboard Injection
.a '~
Valve, 1-E11-F0158, at MCC
^
1XB-2 Compartment DL7. (b) OPEN LPCI Outboard Injection Valve,1-E11-F0178, at MCC 1XB-2 Compartment DL9. (c) CLOSE Minimum Flow Bypass Valve, 1-E11-F0078, at MCC 1XB Compartment DL3.
- g. REFER to Step 10 in ~ tion "H" to place RHR System in Shutdown Cooling C '
Rapid Depressurization, t l l l l ! l.' l l l BSEP-0/ASSD-02 Page 192 of 202 Rev. O i i
- i
- 7. IF RHR System is NOT in Suppression Pool Cooling, THEN PLACE RHR lystem in LPCI Mode AN[i DEPRESSURIZE as follows,
- a. DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to OPEN Minimum Flow Bypass Valve, 1-E11-F007B, at MCC IXB Compartment DL3.
- b. WHEN informed by Reactor Building MCC Operator that TTF1-F007B is open, THEN (1) Direct Emergency Bus Operator to START RHR Pump 1D at Emergincy Bus E2 Compartment AH5.
(2) Direct Emergency Bus Operator to START RHR Pump 1B at Emergency Bus E4 Compartment ALO.
- c. WHEN informed that RHR Pumps 1B AND ID are running, TIIN DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to Throttle OPEN RHR HX IB Bypass Valve, 1-E11-F048B, (to minimize water hamer) at MCC 1XB Compartment DMB.
*********************************ce******************************************* gg, CAUTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are runt.ing AND available for injection.
1
- d. DIRECT RSDP Operator to OPEN all SRVs at Remote ,
Shutdown Panel.
- e. WHEN reactor pressure has decrea a to 425 psig AND prior to decreasing to 395 psig as indicated on 1-C32-PI-3332 on RSDP, THEN DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to OPEN LPCI Inboard injection Valve,1-E11-F015B, at MCC 1XB-2 Compartment DL7.
hk.... BSEP-0/ASSD-02 Page 193 of 202 Rev. O l- _
- f. WHEN reactor water level has been restored between p Y57 and 208" as indicated on 1-B21-LI-604BX at RSDP THEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 1B at Emergency Bus E4 Compartment ALO.
(2) DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to THROTTLE LPCI Outboard injection Valve,1-E11-F0178, to maintain reactor water level between 200" and 208" as indicated on 1-B21-LI-604BX at RSDP.
- g. WHEN LPCI Mode of RHR system is no longer needed THEN
_ (1) DIRECT Emergency Bus Operator to STOP RHR Pump 1D at Emergency Bus E2 Compartment AH5. (2) DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to PERFORM the foilowing, gg
- (a) CLOSE LPCI Inboard Injection o Valve, 1-E11-F015B, at MCC 1XB-2 D, Compartment DL7.
(b) OPEN LPCI Outboard Injection Valve,1-E11-F017B, at MCC 1XB-2 Compartment OL9. (c) CLOSE Minimum Flow Bypass Valve, 1-E11-F0078, at MCC IXB Compartment DL3. I
- h. REFER to Step 10 in Section "H" to PLACE RHR System in Shutdown Cooling after Rapid Depressurization.
(i)i , BSEP-0/ASSD-02 Page 194 of 202 Rev. O
= - -
7;
- 8. EXIT Appendix 6 and return to Section H. Step 11.
_ gg . G RB.l l i l I i i 1 (I) , I-i BSEP-0/ASSD-02 , Page 195 of 202 Rev. t f i ..
ApPEHDIX 7 h A. TITLE UNIT 2 REACTOR VESSEL RAPID DEPRESSURIZATION B. , ENTRY CONDITION This procedure is entered WHEN
- 1. Operation of the SRV's is in jeopardy as confirmed by:
- a. N2 Backup System Div. I pressure as indicated on 2-RNA-PI-5266 is less than 70 psig Ato
- b. N2 Backup System Div. 11 pressure as indicated on 2-RNA-5264 is less than 70 psig.
E
- c. Loss of Drywell cooling has occurred AND Reactor Vessel cooldown rate of 1000 F/hr. has not started within 1 hour of the loss of Drywell cooling, g Rs.1
- d. Failure of any SRV (2-B21-F0138, E or G) to open using the local control switches on the Remote Shutdown Panel.
E
- 2. Reactor vessel level as indicated on 2-821-L1-604BX ha; decreased to 45 inches OR indication of Reactor Vessel level is lost.
C. OPERATOR ACTION
- 1. IF the switch alignment for the Remote Shutdown Panel is not complete, THEN DIRECT the RSDP operator to COMPLETE Step 1 of Section "C".
- 2. .lF RCIC is NOT runr,ing THEN DIRECT the RSDP Operator to PLACE EIC in service.
- 3. IF NORMAL / LOCAL switch lineup for Unit 2 Reactor Building MCCs Ts not complete COMPLETE Step 2 oTTiction "D".THEN DIRECT Reactor Building MCC Opera b
BSEP-0/ASSD-02 Page 196 of 202 Rev. O
- 4. IF Service Water Building lineup is not complete THEN DIRECT
@ Tirvice Water Building Operator to COMPLETE Steps 2 through 8 of Section "E".
- 5. IF Diesel Generator No. 4 is not running AND supplying power to IT THEN
- a. DIRECT Diesel Generator Operator to complete Steps 4 through 7 of Section "G" At0
- b. DIRECT Emergency Switchgear E4 Operator to complete Steps 2 through 7 of Section "F".
- c. WHEN (1) Diesel Generator Operator reports that Diesel Generator No. 4 is ready to be started, AND (2) Emergency Switchgear Operator reports that Emergency Bus E4 is ready to be energized, AND__
(3) Service Water Building Operator reports that the Service Water lineup is complete, THEN RS. . (4) DIRECT Diesel Generator Operator to START AND LOAD Diesel Generator No. 4.
- d. WHEN INFORMED that Diesel Generator No. 4 is tied to Emergency But E4 THEN Ininediately DIRECT the Emergency Switchgear Operator to START Nuclear Service Water Pump 28.
- 6. IF Diesel Generator No. 2 is not running AND supplying power to TE THEN
- a. DIRECT Diesel Generator Operator to complete Steps 14 through 17 of Section "G" Ato
- b. DIRECT Emergency Switchgear Operator to complete steps 10 through 16 of Section "F".
BSEP-0/ASSD-02 Page 197 of 202 Rev. O
i c. WHEN (1) Diesel Generator Operator reports that Diesel Generator No. 2 is ready to be started, AND (2) Emergency Switchgear Operator reports that Emergency Bus E2 is ready to be energized, THEN (3) DIRECT Diesel Generator Operator to START AND LOAD Diesel Generator No. 2.
- d. WHEN INFORMED that Diesel Generator No. 2 is tied to Emergency Bus E2 THEN imediately DIRECT the Emergency Switchgear Operator to START Nuclear Service Water 1B.
- e. INFORM Unit 1 Shift Foreman of the following:
(1) Diesel Generators No. 4 AND No. 2 are running AND supplying Emergency Buses E4 AND E2 (2) Unit 1 Nuclear Service Water is available,
- f. DIRECT Diesel Generator Operator to ESTABLISH Diesel 88. /
-1 Generator Cell ventilation by Completing Step 22 in v Section G.
- 7. WHEN
- a. Diesel Generator No. 2 AND No. 4 are running AND supplying Emergency BusTE AND E4 Ato
- b. NORMAL / LOCAL switch lineup for Unit 2 Reactor Building MCCs is complete.
THEN PERFORM Step 8 g Step 9 to Rapidly DEPRESSURIZE and RETURN water level to the reactor vessel.
- 8. IF RHR System is in Suppression Pool Cooling, THEN TRANSFER RHR Tystem to LPCI Mode AND DEPRESSURIZE as follows.
- a. DIRECT Reactor Building MCC Operator to PERFORM the following:
(1) OPEN Minimum Flow Bypass Valve, 2-E11-F0078, at MCC 1XB Compartment DL3. h BSEP-0/ASSD-02 Page 198 of 202 Rev. O
O (2) OPEN RHR HX 2B Bypass Valve, 2-E11-F048B,
@ at MCC 2XB Compartment DMB.
(3) CLOSE RHR HX 2B Inlet Valve, 2-E11-F047B, at MCC 2XB Compartment DM7. (4) CLOSE Suppression Pool Discharge Isolation Valve, 2-E11-F028B, at MCC 2XB-2 Compartment DM5. NOTE RHR Pump 2B still remains in operation,
- b. DIRECT Emergency Switchgear Operator to START RHR Pump 2D at Emergency Bus E2 Compartment AG9.
********************************************************c******,**************
CAVTION DO NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient to maintain reactor vessel level are running AND available for injection.
************************************************************w*****************
bi* c. DIRECT RSDP Operator to OPEN all SRVs at the Remote Shutdown Panel.
- d. DIRECT RSDP Operator to INSTRUCT Reactor Building MCC Operator to OPEN LPCI Inboard Injection Valve, 2-E11-F015B, at MCC 2XB-2 Compartment DL7 WHEN reactor pressure has decreased to 425 psig AND prior to decreasing to 395 psig as indicated on 2-C32-PI-3332 on RSDP,
- e. WHEN reactor watar level has been restored between 200" and 208" as indicated on 2-B21-LI-604BX at RSDP JHEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 2D at Emergency Bus E2 Compartment AG9.
(2) DIRECT Reactor Building MCC Operatcr to THROTTLE LPCI Outboard Injection Valve, 2-E11-F017B, to maintain reactor water level between 200" and 208" as indicated on 2-B21-L1-604BX at RSDP. i 00 BSEP-0/ASSD-02 Page 199 of 202 Rev. O
- f. WHEN LPCI Mode of RHR System is no longer needed THEN (1) DIRECT Emergency bus Operator to STOP RHR Pump 2B at Emergency Bus E4 Compartment AK3.
(2) DIRECT Reactor Building MCC Operator to PERFORM the following. (a) CLOSE LPCI Inboard injection Valve, 2-E11-F015B, at MCC 2XB-2 Compartment DL7. (b) OPEN LPCI Outboard injection Valve, 2-E11-F017B, at MCC 2XB-2 Compartment DL9. (c) CLOSE Minimum Flow Bypass Valve, 2-E11-F007B. at MCC 2XB Compartment DL3.
- g. REFER to Step 33 in Section "A" to place RHR System in Shutdown Cooling af ter Rapid Depressurization.
- 9. IF RHR System is NOT in Suppression Pool Cooling, THEN TRANSFER g to LPCI Mode to RT5 TORE r9 actor water level as follows.
e a. DIRECT Reactor Building MCC Operator to OPEN Minimum Flow Bypast Valve, 2-E11-F007B, at MCC 2XB Compartment DL3.
- b. WHEN intormed by Reactor Building MCC Operator that 2-ET1-F007B is open, THEN (1) Direct Emergency Bus Operator to START RHR Pump 2D at Emergency Bus E2 Compartment i AG9.
(2) Direct Emergency Bus Operator to START RHR Pamp 2B at Emergency Bus E4 Compartment AK3.
- c. WHEN informed that RHR Pumps 2B AND 20 are running, TREN DIRECT Reactor Building MCC Operator to OPEN RHR l
EX TB Bypass Valve, 2-E11-F0488, at MCC 2XB Compartment DMB. , i I
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BSEP-0/ASSD-02 Page 200 of 202 Rev. O i . . - . _ _ _ - - - _ _ - _ _ .__
$? CAUTION 00 NOT DEPRESSURIZE below 120 psig UNLESS motor-driven pumps sufficient co maintain reactor vessel level are running AND available for injection.
- d. DIRECT RSDP Operator to OPEN all SRVs at Remote Shutdown Panel,
- e. WHEN reactor pressure has decreased to 425 psig AND prior to decreasing to 395 psig as indicated on 2-C32-PI-3332 on RSDP, THEN DIRECT Reactor Building MCC Operator to OPEN LPtTTnboard Injection Valve, 2-E11-F015B, at MCC 2XB-2 Compartment DL7.
- f. WHEN reactor water level has been restored between T67 and 208" as indicated on 2-B21-LI-604AX at RSDP THEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 2D at Emergency Bus E2 Compartment AG9. R B. I DIRECT Reactor Building MCC Operator as Q
G (2) necessary to THROTTLE LPCI Outboard injection Valve, 2-E11-F017B, to maintain reactor water level between 200" and 208" as indicated on 2-B21-L1-604BX at RSDP.
- g. WHEN LPCI Mode of RHR system is no longer needed THEN (1) DIRECT Emergency Bus Operator to STOP RHR Pump 2B at Emergency Bus E4 Compartment AX3.
(2) DIRECf Reactor Building MCC Operator to PERFORM the following. (a) CLOSE LPCI Inboard injection Valve, 2-E11-F015B, at MCC 2XB-2 Compartment DL7. (b) OPEN LPCI Outboard injection Valve, 2-E11-F017B, at MCC 2XB-2 Compartment DL9. (c) CLOSE Minimum Flow Bypass Valve, 2-E11-F0078, at MCC 2XB Compartment DL3. BSEP-0/ASSD-02 Page 201 of 202 Rev. O
u. i
- h. REFER to Step 33 in Section "A" to PLACE RHR System in I h Shutdown Cooling after Rapid Depressurization.
- 10. DIRECT Diesel Generator Operator to PLACE Diesel Generator No. 3 AND Diesel Generator No.1 in local control by Completing Steps T3 through 28 in Section G.
- 11. DIRECT Emergency Switchgear Operator to place Emergency Bus E3 AND Emergency Bus El in local control by Completing Steps 23 through 30 in Section F.
- 12. EXIT Appendix 7 and return to Section A, Step 34.
R8.1 O BSEP-0/ASSD-02 Page 202 of 202 Rev. O}}