ML20077L190
| ML20077L190 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/20/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17214A362 | List: |
| References | |
| PROC-830620-01, NUDOCS 8308080566 | |
| Download: ML20077L190 (48) | |
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EMERGENC
Y. PROCEDURE
- p. .
. 2-0030141 ~ REV.~6 --
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FLORIDA POWER & LIGHT COMPANY ;.
ST. LUCIE UNIT 2 W. ,
EMERGENCY OPERATING PROCEDURE 2-0030141 REVISION 6 l
l l
l CONTROL R00H INACCESSIBILITY (CRI) l l
l TOTAL NO. OF PAGES 41 l -
f FOR INFORMATION ONLY 5
This document is not contro!!ed. Before use, verify information with a controlled document .
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f FLORIDA POWER & LIGHT COMPANY
_ ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 CONTROL ROOM INACCESSIBILITY 1
1.0 Scope. 1 This procedure provides instructions for placing the plant in a safe condition when operations cannot safely be conducted from the Control Room.
/R6
2.0 Symptoms
Conditions exist such that the Control Room becomes uninhabitable and must be evacuated.
3.0 Automatic Actions: /R6 None 4.0 Immediate Operator Action:
ACTION NOTES 4.1 Manually trip the reactor and 4.1 Push buttons on RTGB-201 Turbine prior to leaving the and 204.
, Control Room, if possible.
1 4.2 Announce evacuation of the Control Room over the P.A. system.
4.3 Implement the Emergency Plan, as necessary, in accordance with EPIP 3100021E, " Duties l and Responsibilities of the Emergency Coordinator". /R6
- 4.4 Obtain the Remote Shutdown Room 4.4 Key Number 2 Keybox Master Key from the Control Room Key Locker.
4.5 Evacuate all personnel from the i
l Control Room.
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FOR 15F0EiA7?DN 00L7' TMs document is not controlled. Before use, verify information with a controlled document, u
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ST. LUCIE UNIT 2 !
'{'
EMERGENCY FROCEDURE 2-0030141, REVISION 6
, , , , CONTROL ROOM INACCESSIBILITY -
- 5.0 Subsequent Actions
5.1 Man and take control of stations as follows: CHE
. R
- 1. Reactor. Control Operator "A" - Remote Shutdown Panel A! Establish communications on the Sound Power
- - - Phone System (Circuit No.1).
B. Monitor available plant parameters on the Remote Shutdown Panel and the column, 30' east of the Remote Shutdown Panel Room. /R6 C. Start motor or steam-driven AFW Pumps and feed the Steam Generators as required.
CAUTION Slowly open AFW valves to Steam Generators to prevent decreasing pressurizer level due to excessive cooldown.
/R6 D. Control Pressurizer pressure and level by manual control of Pressurizer heaters, auxiliary spray valves, and letdown valves.
NOTE: Only the "P" Letdown level and pressure valves are controllable from outside the Control Room.
Control Pressurizer level with letdown level controller (LCV-2201P) and letdown pressure controller (LCV-2110P) located on column, 30' east of Remote Shutdown Panel Room. /R6 NOTE: 20% output on LCV-2201P (Letdown Level Controller) is approximately 40 GPM letdown flow. /R6 l 2. Nuclear Plant Supervisor - Electrical Equipment Room, Reactor Auxiliary Building - 43' Elev.
A. Open or check open Reactor Trip Breakers TCB-1 through 8.
B. Place isolation switches in the ISOLATE position l
on the following switchgear in the order listed:
(See Appendix A) 4160V Swgr. 2A3 480V Load Center 2A3*
480V Load Center 2A2
, 480V Load Center 2A5 r - , 480V MCC 2A5 480V MCC 2A6 Transfer Panel 2A 480V MCC 2AB
- Open Bkr 2-40305 (Proportional Heater Bank 1) l
Pcga 4 of 41 ST. LUCIE UNIT 2 'N EMERGENCY PROCEDURE 2-0030141, REVISION 6 CONTROL ROOM INACCESSIBILITY fi a I
- l
'I 5.0 Subsequent Actions:
j' (continued) ____ . _ _ _ _ _..
/
5.1 (continued) -
- ~ ~ ~ ~2.__ Nuclear Plant Supervisor: (continued)
{
B. (continued) - CHECK ~ ~ - ~~
4160V Swgr. 2B3
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480V Load Center 233**
480V Load Center 2B2 480V Load Center 285 480V MCC 2B5 480V MCC 2B6 Transfer Panel 2B Transfer Panel 2AB Communications Isolation Panel
- Open Bkr 2-40602 (Proportional Heater Bank 2) 4 C. Assist Reactor Control Operator "A" in monitoring unit parameters from the Remote Shutdown Panel.
- 3. Reactor Control Operator "B" - Turbine Operating Level A. Locally trip or verify the Turbine has tripped. /R6 B. Verify rurbine Stop Valves and Control Valves are shut. If no t, initiate Turbine trip from Turbine front standard.
C. At the AIW Pump area, place the isolate switches for MV-08-19B, MV-08-188, MV-08-18A, and MV-08-19A in ISOLATE.
D. Proceed to Turbine Building Switchgear Room and establish communications on the Sound Powered Phone circuit (Circuit No.1).
E. Place isolation switches in the ISOLATE position for bus feeder breakers as follows (See Appendix A):
4160V Swgr. 2A2 4160V Swgr. 2B2 6900V Swgr. 2A1 6900V Swgr. 2B1 F. Stop 2A and 2B Main Feedwater Pumps , 2A and 2B Heater Drain Pumps, and one Condensate Pump by opening their respective breakers.
CAUTION Ensure that one Condensate Pump remains in service.
/R6 r
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ST. LUCIE UNIT 2 [." A EMERGENCY PROCEDURE 2-0030141, REVISION 6 #
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CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued)
., 5.1 (continued) CHEC j
- 4. . . Nuclear Operator - Reactor Aux 411ary Building ~ ~~
A. Place isolate switches in ISOLATE / LOCAL position
_ _ , _ _ on the following switchgear (see Appendix A):
4160V Swgr. 2AB
~ ~ ~ ~
480V Load Center 2AB B. Proceed to the Diesel Generator Building and place isolation switches on ZA and 2B Diesel Control Panels in ISOLATE position (see Appendix A)
C. Open or check open isolation valves for Letdown pressure and level control valves (V-2110P and V-2201P). Isolate V-2110Q and V-2201Q.
D. Proceed to the Charging Pump area and establish
, communications on the Sound Powered Phone circuit " " " ~ ~
( Circuit No. 1) .
5.2 Maintain Pressurizer level at approximately 33:
indicated level.
NOTE: 20% output on LCV-2201P (Letdown Level Controller) is approximately 40 GPM letdown flow. /R6 5.3 Maintain Pressurizer pressure at approximately 2100 psia by use of auxiliary sprays.
NOTE: If pressurizar auxiliary spray actuates with spray line temperature >200 F, record as per AP 0010134 /R6 5.4 Maintain RCS temperature at or below 5320 F (2A cold leg temperature) by use of atmospheric steam dump and/or selective starting / stopping of Reactor Coolant Pumps.
NOTE: If RCS temperature is decreasing, consider decreasing AFW flow. /R6 NOTE: If RCS temperature is increasing, stop RCPs as required by opening the RCP breakers in the Turbine Building Switchgear Room.
I 5.5 When conditions have stabilized after a plant trip, maintain l li or slowly increase S/G levels by operation of the AFW Pumps and discharge valves to the S/G's. /R6 l-
, CAUTION If decreasing RCS temperature and/or Pressurizer level occurs, consider decreasing AFW flow to the S/Gs l 5.6 Isolate S/G blowdown by manually closing isolation valves at the Closed Blowdown Heat Exchangers.
5.7 When Turbine speed decreases to "0" RPM, verify that the Turning Gear Oil Pump and the turning gear are in operation.
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ST. LUCIE UNIT 2 p
, EMERGENCY PROCEDURE 2-0030141, REVISION 6 g 8
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CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued)
CHECK L
5,8-.._ Period [callycheckthehabitabilityoftheControlRoon b add when conditions permit, reoccupy the Control Room. _. _ _ , _
Return isolai: ion switches to NORMAL 'for switches and controls that are operational and maintain the Unit at Hot Standby until a complete evaluation has been made.
3;9 ~If Control Room accessibility is not possible, place the unit in a Cold Shutdown condition as follows:
- 1. Commence boration to Ccid Shutdown conditions by manual valve lineup. Borate to 1900 ppa as shown below.
C say out boron sampling as required during cooldown. ,
NOTE: Ihis concentration will ensure >5% Shutdown Margin at 2010F at any time in core life, assuming the most reactive CEA stuck full out. Use both the local boron flow
. meters vs. time and BAM Tank level change to determine how many gallons of boron have been added. Do not interpolate values shown, always round critical boron concentration DOWN to next lower value on table.
NOTE: If plant curves are available, they may be used to determine shutdown boron concentrat. ion requirements instead of this Table.
~ Boron Concentration Number of Gallons BAM Tank Prior to Control of Boron needed level change i
Room Inaccessibility to reach 1900 ppa (1 BAM Tank) l l 50 PPM l 7223 Callons l 75% l l 100 PPM l 7039 Gallons l 73% l l 200 PPM l 6668 Callons l 70% l l 300 PPM l 6295 Gallons l 66% l l 400 PPM l 5919 Gallons l 62% l l 500 PPM l 5442 Callons l 57% l l 600 PPM l 5162 Gallons l 54% l l 700 PPM l 4779 Gallons l 50% l l 800 PPM l 4395 Callons l 46% l l 900 PPM l 4008 Gallons l 42% l l 1000 PPM l 3618 Gallons l 38% l l 1100 PPM l 3226 Gallons l 34% l l 1200 PPM l 2832 Gallons l 30% l l 1300 PPM l 2435 Gallons l 25% l l 1400 PPM l 2036 Gallons l 21% l l 1500 PPM l 1634 Gallons l 17% l
- 2. Ensure S/G 1evels are constant or slowly increasing to maintain 65% level by use of the AW Pumps. /R6
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- ST. LUCIE UNIT 2 1 *
. _ EMERGENCY PROCEDURE 2-0030141 REVISION 6 lw LI-CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) - - - - - . - - - -
, 5.9 -(continued) CHECK l l~
- 3. -Stop at least one RCP prior to reaching 500*F by tripping its breaker at the 2A1 or 2B1 switchgear. Additional RCPs may be stopped as desired to control cooldown rate.
After pump coastdown, stop the lift pumps by opening the associated breakers in the electrical switchgear roca.
Re-close lift pump breakers after one minute elapses.
- 4. Place all Pressurizer heater switches at the Remote Shutdown Panel to 0FF. Heaters may be energized to control RCS pressure as needed.
- 5. The highest RCS cold leg temperature (highest one with RCP running) shall be plotted every 30 minutes. The copy of the graph (Figure 1) shall be kept with this procedure.
The RCS temperature and pressure shall be determined to be within the limits of Figure 3.4-3 at least once per 30 minutes during cooldown.
NOTE: Cooldown of the RCS shall be limited to <75"F in -
any one hour period with RCS temperature >97*F.
- 6. The Pressurizer water phase temperature shall be plotted every 30 minutes using the Saturated Temperature vs.
Pressure curve of this procedure (Figure 2). If i possible, maximize letdown and minimize charging when
, using auxiliary spray to minimize thermal stress on spray nozzle.
NOTE: Cooldown of the Pressurizer shall be limited to <190*F in any one hour period. _
- 7. When the quantity of boron calculated in Step 5.9.1 has
- been added, cooldown may proceed. Verify by chemistry sample (if possible) that desired boron concentration has been obtained. Commence taking data on cooldown curve. Have the "B" Reactor Control Operator break Condenser vacuum by manually opening vacuum breaker MOVs.
CAUTION MSIS will occur at about 475*F, and sealing i
steam will be lost. Condenser vacuum must be broken prior to 475 F to prevent seal damage.
/R6
- 8. Have I & C personnel install temporary VCT level monitoring equipment. While locally monitoring and controlling VCT level, slowly open the atmospheric stesa dumps and establish the desired cooldown rate NOTE: A makeup blend ratio to the VCT of about 9:1 is sufficient to maintain 1900 PPM boron in the RCS.
NOTE: A temperature differential of approximately 100*F between the RCS and Pressurizer should be maintained during cooldown. Cooldown of the Pressurizer must be accomplished by use of auxiliary spray and heater control.
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ST. LUCIE UNIT 2 5 l *
. _. EMERGENCY PROCEDURE 2-0030141 REVISION 6 -
i CONTROL ROOM INACCESSIBILITY e i jj' 5.0 Subsequent Actions: (continued) _ _ _ _
5.9 (continued) CHEC 9.-When the SIAS amber permissive lights come on (1825 psia), ' 1>
block SIAS by turning the key operated switch on the Remote Shutdown Panel for both A and B channels.
i 10. At 1750 psia, isolate and bypass the following transmitters:
~
A. Charging header flow: close valve marked "HIGH SIDE", open valve marked " BYPASS",
and close valve marked " LOW SIDE".
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B. Charging header pressure: close its isolation valve. ,
I
- 11. Commence venting all four SITS from remote valve stations in the Electrical Penetration Room. (Valves 3733, 3734,
- 3735, 3736, 3737, 3738, 3739, and 3740).
NOTE: Do not vent more than one SIT to <235 psig.
- 12. Maintain at leay two RCPs operating. If possible, two RCPs in the same u.op should be left running.
- 13. Periodically adjust the steam dump controllers and auxiliary spray control to maintain the desired cooldown 1 and de-pressurization rate. Verify that the S/G's are j are being maintained at approximately 65% level.
- 14. With RCS pressure <1700 psia, but prior to commencing
, SDC operations, rack out 2A and 2B Containment Spray l Pump breakers (2-20203 and 2-20407).
! 15. When RCS temperature is <5000F and RCS pressure is
- <1500 psia, perform the following
A. Close 2-V-07145 and 2-V-07130 (Containment Spray Pump disch valves).
B. Close the following Containment Spray header manual isolation valves:
2-V-07161 (A bdr FCV upstream isol) 2-V-07164 (B hdr FCV upstress isol)
MV-07-3 (A hde FCV downstress isol) l MV-07-4 (B hdr FCV downstream isol)
CAUTION Prior to lowering RCS pressure below 390 psia, two RCPs in the same loop must be operating.
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ST. LUCIE UNIT 2 If ' -
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EMERGENCY PROCEDURE 2-0030141, REVISION 6 CONTROL ROOM INACCESSIBILITY __
'! 5.0 Subsequent Actions: (continued) '
j' 5.9 (conttaued) CHECK [
- 17. SIoptheoperatingRCPsbytrippingthebreakerson2A1 2
and 2B1 switchgear. After pump coastdown, stop the oil lif t pumps by opening the breaker for each pump for one
! minute, then re-closing the breakar.
NOTE: Since RCS forced circulation has been terminated, it is necessary to proceed quickly to Shutdown Cooling .
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- 18. Lower RCS pressure to <275 psia, rack in the breakers and then close the SIT discharge valves by placing
- j the local control switch in the CLOSE position.
i MV-3614: Bkr. 2-41219 MV-3624: Bkr. 2-41311 4
MV-3634: Bkr. 2-42117 MV-3644: Bkr. 2-42048
- 19. Rack out the SIT discharge valve breakers.
CAUTION With SDC in service, an increase in RCS pressure >350 psia will result in rapid RCS inventory loss due to lifting of ,
relief valves in Hot Leg suction lines l (Total capacity 4,600 gpa).
- 21. Ensure RCS pressure <275 psia, then open the following valves from their local controllers:
A. Hot Leg Suction Valves: V-3651, V-3652, Y-3665, V-3480, V-3481, V-3664. /R6
)
NOTE: V-3664 and V-3665 local controllers are in l Pipe Penetration Rooa; all others are in.
! , the Cable Spreading Room.
NOTE: V-3545 (Hot Leg Suction Cross-Tie) is normally closed. It may be used to provide flow during off-normal conditions and aust be open if both trains of SDC are in service.
B. Open CCW from SDC Heat Exchangers: HCV-14-3A and HCV-14-38 by isolating instrument air to the HCVs and bleeding off air pressure.
C. SDC Heat Exchanger Discharge Valves:
j MV-3436 and MV-3457.
D. LPSI Header Isolation Valves: MV-3615, MV-3625, MV-3635 and MV-3645.
/R6 '
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ST. LUCIE UNIT 2 R EMERGENCY PROCEDURE 2-0030141, REVISION 6 '~
~ Ll
, CONTROL ROOM INACCESSIBILITY <
5.0 Subsequent Actions: (continued) 4 5.9 (continued) CHECK
~
j 22.~ C1bse the following valvest ,
A. LWT recirculation stop valves: V-3459, V-3463, and V-1597.
B. Miniflow header stop valves: V-3659, V-3660. V-3495 and V-3496.
C. LPSI suction from RWT: V-3432 and V-3444.
i
- 23. Have the Nuclear Operator establish communications on the Sound Power Phone System (Circuit No.1) in the 2A LPSI Pump Room.
- 24. Establish SDC as follows:
A. Insert keys for MV-3306 and MV-3657 (controllers located in A LPSI Roon) and place switches to MODULATE position.
! B. Using key switches at local controllers, open MV-3517 and MV-3658.
l C. Give MV-3306 a three second open signal, then allow switch to return to NORMAL.
D. Start the 2A LPSI Pump, then open MV-3306 to obtain 3000 gpa flow as indicated on FI-3306 at the Remote Shutdown Panel.
E. While observing SDC outlet temperature and flow on the Remote Shutdown Panel, alternately open MV-3657 and close MV-3306 to achieve desired cooldown rate and maintain 3000 gps.
- 25. At 2000F RCS temperature, remove the trip and close fuses on the remaining HPSI Pump. Open the breaker for one Charging Pump so that no more than two Charging Pumps are operable.
- 26. Stabilize RCS temperature at approximately 100 F and RCS pressure at approximately 250 psia. Control pressure by use of Pressurizer heaters and auxiliary spray. Do not take the Pressurizer solid until Control Room access has l been re-established.
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, ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISICN 6 -
f [' , ,
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, CONTROL ROOM INACCESSIBTE.~if , /
' 6.0 Purpose and Discussion: '
e a__,___.,
j i This procedure provides instructions for placing the plant in a safe i c6ndition.xhen operations cannot safely be conducted from the Control Room. The reactor and turbine are maqually tripped prior to leaving the -
Control Room, if possible, or locally from the Reactor Trip Switchgear and the Turbine front standard. A heat sink is provided by automatic steam dump to the Condenser and/or to atmosphere. 14 vel is maintained in the Steam Generators by manual control of auxiliary feedwater valves with flow furnished by the AFW Pumps. Pressurizer level and pressure are maintained by manual control of Pressurizer heaters, auxiliary spray valves, and letdown valves, and are monitored at the Hanote Shutdown Panel.
Isolation switches located in the Reactor Auxiliary Building Electrical Equipment Room, Turbine Building Switchgear Room, Diesel Generator Rooms, and Reactor Auxiliary Building are manually selected to the ISOLATE
- position to prevent inadvertant operation of vital equipment due to possible electrical malfunction in the unattended Control Room. .
A copy of this procedure will be posted at each manned operating station required for plant shutdown from outside the Control Room. A listing of isolation switches will be posted on each of the following panels, MCCs, and distribution buses.
- 1. Load Centers 2A, 2B, 2AB
- 2. Transfer Panels 2A, 2B, 2AB
- 3. MCC 2AS, 2A6. 2B5, 2B6
- 4. 41607 Buses 2A3, 2B3, 2AB
! 5. 4160V Buses 2A2, 2B2
- 6. 6900V Buses 2A1, 281
- 7. Diesel Generator 2A and 2B Control Panels l
The Nuclear Plant Supervisor will utilize additional personnel as available to assist in required subsequent actions.
/R6 4
1 1
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' CRI ST. LUCIE UNIT 2 .
.. EMERGENCY PROCEDURE 2-0030141, REVI3 ION 6 $ l
, CONTROL ROOM INACCESSIBILITY
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i 7.0 References
- 7.1 Emergency Operating Procedure 1-0030141 7.2 St. Lucie Unit 2 Technical Specitica,tions
8.0 Records
8.1 A completed, initialed copy of this procedure shall be retained in the plant file.
9.0 Approval Reviewed by Facility Review Group October 26 1982 Approved by J. H. Barrow (for) Plant Manager October 26 1982 Revision 6 Reviewed by FRG r,c e /(; 19.T.I Approved by // //f// // h Plant Manager d - /[o- 19 9.3 EP 2-0030141 Revision 6 Total No. of Pages 41
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, EMERGENCY PROCEDURE 2-0030141, REVISION 6 -
_ CONTROL ROOM INACCESSIBILITY l j
i l APPENDIX "A" __ __. __ . , _
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f ISOLATION SWITCHES f.
g
=
480V Load Center 2A3 - Pressurizer Heater Bus, Auxiliary Building Electrical Equipment Roon .
- 1. Pressurizer Backup Heater Bank B-1
- 2. Pressurizer Backup Heater Bank B-2
- 3. Pressurizer Backup Heater Bank B-1 e
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. Pega 14 of 41 CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 -ya -%-
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CONTROL ROOM INACCESSIBILITY
.m I* l y
APPENDIX "A"
- (continued) _
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ISOLATION SWITCHES 4
.. . - . - - - . . - - - - N 480V Load Center 2B3 - Pressurizar Heater Bus, Auxiliary Building Electrical Equipment Room
- 1. Pressurizar Backup Heater Bank B-4
- 2. Pressurizer Backup Heater Bank B-5
- 3. Pressurizer Backup Hester Bank B-6
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ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 ,
g
, CONTROL ROOM INACCESSIBILITT '
l p APPENDIX "A"
- (continued)
^~'
ISOLATION SWITCHES 480V Load Center 2A2 - Auxiliary Building Electrical Equipsact_ Room --- ~
- 1. Station Service Transf 2A2 Main Breaker
- 2. Bus Tie to 480V L.C. 2AB
- 3. Containment Fan Cooler 2-HVS-1A
- 4. Charging Pump 2A
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, Pega 16 of 41 CRI ST. LUCIE UNIT 2 EMERGENCY PkOCEDURE 2-0030141, REVISION 6 -
l CONTROL ROOM INACCESSIBILITY I -L APPENDII "A" j (continued) /
ISOLATION SWITCHES .
480V Ioad Center 2A5 - Auxiliary Building Electrical Equipment Room ,_
- 1. Containment Fan Cooler 2-HYS-1B i
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EMERGENCY PROCEDURE 2-0030141 REVISION 6 '
h CONTROL ROOM INACCESSIBILITY '
, 3_- -
APPENDIX "A"
, (continued)
_ ISOLATION SWITCHES l 4160V SWGR 2A3 - Auxiliary Building Electrical Equipment. Room ___ _. . --
- 1. HP Safety Injection Pump No. 2A -
- 2. LP Safety Injection Pump No. 2A
- 3. Containment Spray Pump No. 2A
- 4. Pressurizer Heater Transf No. 2A3
- 5. CEDM Cooling Fan 2H'E-21A V
- 6. Component Cooling Water Pump No. 2A
- 7. Intake Cooling Water Pump No. 2A
- 8. Feeder to 4.16KV Bus No. 2AB
- 9. Feeder from 4.16KV Bus No. 2A2
- 10. Feed to 480V SS Transformer 2A2/2A5
- 11. Emergency Diesel Generator No. 2A
- 12. Auxiliary Feedwater Pump No. 2A
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i
, P g318 cf 41
~-' CRI g l ST. LUCIE UNIT 2 r j .
EMERGENCY PROCEDURE 2-0030141, REVISION 6 I fl _ .
CONTROL ROOM INACCESSIBILITY k l -! l; APPENDIX "A" (concinued) ,
ISOLATION SWITCHES ; 2_
, 480V MCC 2A5 - Auxiliary Building Electrical Equipment Ro_om . _ _
- 1. Makeup Bypass to Charging Pumps V-2514 (Emergency Borate) 6
- 2. Aux. F.W. Pump 2A Discharge Valve to S/G 2A (MV-09-9 and I-SE-09-2)
- 3. S/G #2B to AFWP-2C Turbin MV-08-12
- 4. Comp Cool Wtr to Cont Cool Unit 2A Valve MV-14-9
- 5. Comp Cool Wer from Coat Cool Unit 2A MV-14-10
- 6. Comp Cool Wtr Cont Cool Unit 23 MV-14-11 i
- 7. Comp Cool Wtr from Cont Cool Unit 2B Valve MV-14-12
- NOTE: Switch 1, 6, and 7 must be in ISOLATE to have remote coctrol of 2A charging pump.
- } ' '
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- P gs 19 of 41
~~
CRI r
ST. LUCIE UNIT 2 i ,
EMERGENC
Y. PROCEDURE
2-0030141, REVISION 6 .... -
_ CONTROL ROOM INACCESSIBILITY -
)
I APPENDIX "A" (continued) (
' ~
ISOLATION SWITCHES 480V MCC 2A6 - Auxiliary Building Electrical Equipment Room._
- 1. Boric Acid Makeup Pump 2A
- 2. Boric Acid Makeup Pump 2B
- 3. Control Room Air Cond Unit 2HVA/ACC 3A
- 4. Shield Bldg. Vent Exhaust Fan 2HVE-6A
- 5. Control Room Emerg. Filtration Fan 2HVE-13A
- 6. Containment Spray Isolation Valve MV-07-161
- 7. 2A LPSI Pump Suction Valve V-3444 l
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'! P:g2 20 cf 41
' CRI
.I ST. LUCIE UNIT 2
- ~
EMERGENCY PROCEDURE 2-0030141, REVISION 6 _ . _ ,
.. CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued)
J
~
ISOLATION SWITCHES /
q f
480V Load Center 2B2 - Auxiliary Building Electrical Equipment Room
- 1. Station Service Transf. 2B-2 Main Breaker
- 2. Bus Tie to 480V L.C. 2AB
- 3. Containment Fan Cooler 2HVS-1C
- 4. Charging Pump 2B I
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P*g2 21 of 41
- CRI ST. LUCIE UNIT 2
, EMERGENCY PROCEDURE 2-0030141 REVISION 6 CONTROL ROOM INACCESSIBILITY
[9, APPENDIX "A" i
(continued)
ISOLATION SWITCHES *
. . ~ . - - - -
480V Load"Cin'i:er 2BS - Auxiliary Building Electrical Equipment Room ..
- 1. Containment Fan Cooler 2-HVS-1D s
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Pega 22 of 41
" CRI ST. LUCIE UNIT 2 4 l
- EMERGENCY PROCEDURE 2-0030141, REVISION 6 _ __ ,
.t-CONTROL ROOM INACCESSIBILITY ,l -_ -.a
'! APPENDIX "A" I
(continued) .'"
ISOLATION SWITCHES
_ 4160V SWGR 283 - Auxiliary Building Electrical Equipment. Room _.__ __._ __ _
- 1. Emergency Diesel Generator No. 2B
- 2. Feed to 480V SS Transformer 2B2/2B5
- 3. Pressurizer Heater Transf No. 283
- 4. Component Cooling Water Pump No. 2B
- 5. RP Safety Injection Pump No. 2B
- 6. LP Safety Injection Pump No. 2B *
- 7. Containment Spray Pump No. 2B
- 9. Feeder to 4160V Bus No. 2AB
- 10. Intake Cooling Water Pump No. 2B
- 11. Incoming Feeder from 4.16KV Bus 2B2
- 12. Auxiliary Feedwater Pump No. 2B
(
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P:go 23 of 41 CRI ST. LUCIE UNIT 2
.} .
EMERGENCY PROCEDURE 2-0030141 REVISION 6 - - %}. g
- , CONTROL ROOM INACCESSIBILITY __
ll' APPENDIX "A" t
I (continued)
.. ISOLATION SWITCHES
_l_ .
480V MCC 2B6 - Auxiliary Building Electrical Equipment Room _
- l. 2HVE-138 - Control Room Booster Fan
- 2. Control Room Air Cond 2HVA-38
- 3. Containment Spray Isolation Valve (MV-07-164) l 4. Shield Bld Vent Exh Fan 2HVE-6B
- 5. 2B LPSI Pump Suction Valve (V-3432) e
I Prga 24 of 41 J ~ CRI
] .
ST. LUCIE UNIT 2 si -
EMERGENCY PROCEDURE 2-0030141, REVISION 6 g
CONTROL ROOM INACCESSIBILITY ,
i
- APPENDIX "A" (continued)
/
- /
~~' /
ISOLATION SWITCHES j -
4 480V MCC 2B5 - Auxiliary Building Electrical Equipment Room __. . _
- 3. Boric Acid Gravity Feed Valve (V-2508)
', 4. Boric Acid Gravity Feed Valve (V-2509)
- 7. 28 AFW Pump Discharge to 2B Steam Generator (MV-09-10 and I-SE-09-3)
(Back of MCC 285) 8, 2A Steam Generator to 2C AFW Pump Turbine (MV-08-13)
(Back of MCC 2BS)
- NOTE: Switch 3 and 5 must be in ISOLATE to have remote control of 2B charging pump.
l 1.-
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P:gs 27'of 41
^ CRT I .
ST. LUCIE UNIT 2
'! EMERGENCY PROCEDURE 2-0030141, REVISION 6 --
1 d * !
3 CONTROL ROOM INACCESSIBILITY ,
d
.: APPENDIX "A" 3
(continued) .
~-
! ISOLATION SWITCHES -
L I
480V HCC 2AB - Auxiliary Building Electrical Equipment Room.._ _ _
- 1. Component Cooling Water Suction Valve Edr. A (MV-14-3)
- 2. Component Cooling Water Suction Valve Edr. B (MV.14-4)
- 3. Component Cooling Water Discharge Valve Hdr. A (MV-14-1)
- 4. Component Cooling Water Discharge Valve Hdr. B (MV-14-2)
- 5. Control Roon Air Cond Unit 2-HVA/ACC 3C-
- NOTE: Switch 4 and 5 aust be in ISOLATE to have remote control of 2C charging pump.
l.
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j' P:gs 26 cf 41
,e CRI
( , ST. LUCIE UNIT 2 - g i EMERGENCY PROCEDURE 2-0030141, REVISION 6 1
'i .
CONTROL ROOM INACCESSIBILITY
~ ~ ~
h-
'I APPENDIX "A" '
! (continued)
ISOLATION SWITCHES /
Transfer Panel 2AB - Auxiliary Building Electrical Equipment Room' - ~ ~ ~ ~ ~ ~ .
(2AB Battery Room) 4, 1. 2C Aux Feed Pump Stop Valve MV-08-3 9
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Pcg3 27 bf 41 CRI *
{ ST. LUCIE UNIT 2 1-
- EMERGENCY PROCEDURE 2-0030141, REVISION 6 1
- CONTROL ROOM INACCESSIBILITY ..
APPENDIX "A" (continued)
~!
ISOLATION SWITCHES -
i; . .. ~ . ,
l, Transfer Panel 2A - Auxiliary Bttiding Electrical Equipment-Room-- ---
l' l
- 1. 2A Steam Gen Atas Steam Dump PIC-08-1A1 1
- 2. 2A Steam Gen Atas Steam Dump PIC-08-1A1
- 3. SS-1-157 - Letdown Cont Isol Valve (V-2516)
- 4. SS-1-189 - Aux Spray Valve (I-SE-02-3)
( 5. SS-194 - Charging Line Isol Valve (V-2523)
- 6. 2A Diesel Gen Watt / Volt Meter
- 7. SS-1-176 - Charging to Loop 2A2 (I-SE-02-02)
- 8. 2C AW Pap Diseg to 2B Steam Gen (MV-09-12 and I-SE-09-5)
- 9. 2B Steam Generator Atas Steam Dump PIC-08-3Al e
99 4
_.m___
j P:gs 24 cf 41 CRf I '
~~
ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 -
R -g CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued) l ISOLATION SWITCHES _,_
Transfer Panel 28 - Auxiliary Building Electrical Equipment _ Room _ _ _
- 1. 2B Steam Gen Atas Steam Dump PIC-08-1B1
<l.
- 2. 2B Steam Gen Atas Steam Dump PIC-08-1B1
- 3. SS-2-157 - Letdown Stop Valve (V-2515)
- 4. SS-2-189 - Aux Spray Valve (I-SE-02-04)
- 5. SS-1-194 - Letdown Coat Isol Valve (V-2522)
- 6. 2B Diesel Gen Watt / Volt meter
- 7. SS-2-176 - Charging to Loop 2B1 (I-SE-02-01)
- 8. 2C AN Pump Disch to 2A Steam Gen (MV-09-11 and I-SE-09-4)
- 9. 2A Steam Gen Atas Steam Dump PIC-08-381 l
k h
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-- - - - . ~ . .
e P gs 29 of 41
~~ CRI ST. LUCIE UNIT 2
, EMERGENCY PROCEDURE 2-0030141 REVISION 6 - --
4
_ , _ CONTROL ROOM INACCESSIBILITY _
I APPENDIX "A"
- (continued) ,, ,
ISOLNfl0N SWITCHES __
l Communications Isolation Panel - Auxiliary Building Communicatioca..Hom_. -
t 1. Fire 4aara/ Site Evacuation - (Control Console, Isolation Switch) i 1
i 4
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P g3 30 of 41 i
CRI ST. LUCIE UNIT 2 '
- EMERGENCY PROCEDURE 2-0030141, REVISION 6 .- -
1 ~
J .
~
CONTROL ROOM INACCESSIBILITY -
m I
i APPENDII "A" (continued)
ISOLATION SWITCHES t
3 y
- - ~ - . ,
L 4160 SWGR 2A2 - Turbine Building Switchgear Room
- 1. Feeder to 480V SWGR No. 2A1
- 2. Feeder to 4.16KV Bus'No. 2A3
- 3. Incoming Feeder from 4.16KY SWGR 2A4 9
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Pcgo 31 of 41 i
. CRI I - ----
, , _ . ST. LUCIE UNIT 2
} EMERGENCY PROCEDURE 2-0030141, REVISION 6 ~. .-
j'~ .
CONTROL ROOM INACCESSIBILITY f i
! APPENDIX "A" (continued)
, ISOLATION SWITCHES i - ,
_I i -:
,' 4160V SWGR 2B2 - Turbine Building Switchgear Room _ _ _ _ .____.._
- 1. Feeder to 480V SWGR No. 2B1
, 2. Feeder to 4.16KV Bus No. 2B3
6
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' CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 CONTROL ROOM INACCESSIBILITY h },
_J_' ,
9' '
APPENDII "A" j (continued)
.1 ISOLATION SWITCHES l 8
,i a'
6900V SWGR 2A1 - Turbine Building Switchgear Room _ _ _ _ _ _ __. . ._ . _ .
- 1. Incoming Feeder from S/U Transf No. 2A
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. ST. LUCIE UNIT 2 i r, 4
"^
EMERGENCY PROCEDURE 2-0030141, REVISION 6 - -- !
-l l !
. CONTROL ROOM INACCESSIBILITY I--l-l APPENDIX "A" 4 //
(continued) ,f' {
L 1
j , . _ _ _ . ISOLATION SWITCHES 8 i
I ~
] 6900V SWGR 2B1 - Turbine Building Switchgear Room - - - - - - - - - - - - - -
i i 1. Incoming Feeder from S/U Transf No. 2B
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Peg 2 34 cf 41 ST. LUCIE UNIT 2 .
. . EMERGENCY PROCEDURE 2-0030141, REVISION 6 - . _
- CONTROL ROOM INACCESSIBILITY 3 APPENDIX "A" ,
(continued) (,
i
__ ISOLATION SWITCHES '
_1 AFW PUMP AREA
- 1. MV-08-198 (Atmospheric Dump Valve)
- 2. MV-08-18B (Atmospheric Dump Valve)
- 3. MV-08-18A (Atmospheric Dump Valve)
- 4. MV-08-19A (Atmospheric Dump Valve) l
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CRI' ST. LUCIE UNIT 2
^~
- EMERGENCY PROCEDURE 2-0030141, REVISION 6 .
4-
~~'
CONTROL ROOM INACCESSIBILITY -
N; APPENDII "A" /
(continued) /
_ . , _ , ISOLATION SWITCHES 4160V SWGR 2AB - Auxiliary Building Ground Floor - - - - - - - - - -
- 1. Component Cooling Water Pump No. 2C
- 2. Intake Cooling Water Pump No. 2C
- 3. Incoming Feeder from 4.16KV Bus 2A3
- 4. Incoming Feeder from 4.16KV Bus 2B3 s
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- P:g2 36 cf 41
' _ ,. CRI
' ST. LUCIE UNIT 2 _ . o :
EMERGENCY PROCEDURE 2-0030141, REVISION 6 - -'
CONTROL ROOM INACCESSIBILITY I] df APPENDIX "A" ,
- (continued)
-s ISOLATION SWITCHES "
~ ~~
480V Ioad Center 2AB - Auxiliary Building Ground Flocr 1 ---- --
- 1. Bus Tie to 480V L.C. 2A2 (Left End of Panel)
- 2. 2C Charging Pump
- 3. Bus Tie to 480V L.C. 2B2 -
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l P ga 37 ,of 41 CRI
' ST. LUCIE UNIT 2 a v- ..,
EMERGENCY PROCEDURE 2-0030141, REVISION 6 l ']
. l
- 1 CONTROL ROOM INACCESSIBILITY l APPENDIX "A" j (continued) .7
~
ISOLATION SW TCHES -
~
2A Diesel Generator Control Panel - - - ---- -- -- - -
- 1. Voltage Control
- 2. Frequency Control
- 3. Start Circuit e
J
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i Page;38 of 41 l
'L :
ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 6 -: -A
\
- i --
CONTROL ROOM INACCESSIBILITY ---
t ,
APPENDIX "A" /
(continued)
I
-~.
ISOLATION SWITCHES 2B Diesel Generator Control Panel - - - - - - - - - -
- 1. Voltage Control
- 2. Frequency Control
- 3. Start Circuit h
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ST. LUCIE UNIT 2- '
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EMERGENCY PRCCEDURE NO. 2-0030141, REVISION 6 __ _
. - - CONTROL ROOM INACCESSIBILITY . -
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- TO 10 YEARS OF OPERATICN
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! UNIT II DCCUZEIT RIVISION DISTRIBUTION SEZIT - !
0FF NORMAL & OfERGDiCY OPE
R. PROCEDURE
DCCUlGNT TITLI $0 $Xf_SYll$ $7 V/ 7"Y '~' f ? % <
DCCa INT FILI NUM3IR 2-03/dd.3/ Il DCCUZENT RIVISIOtt NUMBER [
DCCUMINT DISTRIBUTID ON -
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DATE DCCCMINT,SINT TO: g A
COPY ' T R A N S M I I" A L COPY
- NO-- -- -- DOCUMINT ECLDER TRANSMITT."C I RITURNID NO. DOCUMENT EOLDER RETURNED I MAS M ,
UNCONTROLLED COPIES -
l' D. A. Sager 2
3 NRC - Region II 4
- Atta: EPPS 3 ranch Chief 5 N. G. Roos H. Paduano - GO 6 T.SC A. W. Bailey 7
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G. J. Boissy R. R. Jennings H. M. Mercer R. J. Frechette M ident NRC
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< Attu: Chief, Nuclear Res te s C. Burns - CE i
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_ FLORIDA POWER & LIGHT COMPANY - - -- 5 S 0_
ST. LUCIE UNIT 2 -- -
~~ ~~ -- *' I-0FF-NORMAL OPERATING PROCEDURE NO. 2-0310031' ' '~~I~,
REVISION 1 - - -
. - - . - _ _6 . . _
_ i 7 l
~ ~
1.0 TITLE:--,,.m_._ - -
.CCW . EKESSIVE ACTIVITY ,
2.0 REVIEW AND APPROVAL:
Reviewed by Facility Review Group December 28 1982 Approved by J. H. Barrow ( for) Plant Manager December 28 1982 Revision 1 Reviewed by FRG eb) u.1 T 19d Approved by h b A_ m / Manager fft , 41 fl9 d t/
t) 3.0 PURPOSE AND DISCUSSION:
3.1 This procedure provides instruction in the event of high activity in the Component Cooling Water (CCW) System.
3.2 Leakage from the Reactor Coolant System to the CCW System could '
occur at:
- 1. Letdown Heat Exchanger
- 2. Sample Heat Exchangers
- 3. Shutdown Cooling Heat Exchangers
- 4. Reactor Coolant Pump Seal Coolers
- 5. HPSI Pump Seal Coolers
4.0 SYMPTOMS
4.1 Increase in CCW activity observed on radiation detectors PLP-101 and PLP-102 or annunciated in Control Room at se t point. /R1 4.2 Unexpected rise in CCW Surge Tank level.
FOR INFORMATION OilLY Thisinformation Lverify document h not controlled. Before use with a controlled d .
ocument.
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f Pag 3 2 of 5 I
ST. LUCIE UNIT 2
- 5 0FF-NORMAL OPERATING PROCEDURE NO. 2-0310031, REVISION 1
).}
' ' ' , CCW - EXCESSIVE ACTIVITY
5.0 INSTRUCTIONS
- l]cq l
r 5.1 Immediate Automatic Action:
- 1. 'CCW' Surge Tank Vent valve (2-RCV-14-1) will divert from I ,
_____ atmosphere to the Chemical Drain Tank when activity in system _
~
reaches preset alarm.
- 2. Annunciation and alarm due to high radiation in CCW System should occur.
~~~~~ ~ ~ ~ ~~ 3. A highdh.T of 2030F across the RCP seal cooler will close individual valves on the discharge side.
~ .. -- --
2A1: 2-HCV-14-11-Al
' - ~
2A2: 2-HCV-14-ll-A2 2B1: 2-HCV-14-11-B1 2B2: 2-HCV-14-11-B2 5.2 Immediate Operator Action:
- 1. Check CCW return temperatures and flow rates from the following components for possible indication of leakage source:
Letdown Heat Exchanger (FIS-14-6)
RCP Low Flow or High A T alarms SDC Beat Exchangers Sample Heat Exchangers
- 2. Notify Chemistry Department of condition.
5.3 Subsequent Action:
- 1. Af ter source of activity has been determined, if possible, isolate the leaking equipment as follows:
A. Hot Leg Loop 2A Sample Heat Exchanger: (2A) l Close A07-5203 (Reactor Coolant Sample) (RTGB-206)
Close V-5162 (Hot Leg Sample Cooler Outlet)
Close V-14426 (CCW Inlet to Hot Leg Sample Hx)
Close V-14428 (CCW Outlet from Hot Leg Sample Ex)
B. Pressurizer Surge Line Sample Heat Exchanger: (2B)
Close A0V-5204 (Pzr Surge Line Sample) (RTGB-206)
Close V-5163 (Pzr Surge Line Sample Cooler Outlet)
Close V-14424 (CCW Inlet to Pzr Surge Line Sample Rx)
Close V-14429 (CCW Outlet from Pzr Surge Line Sample Rx) ,
. . .~. _ . - - .-
j Paga 3 cf 5 i
ST. LUCIE UNIT 2 -
-0FF-NORMAL OPERATING PROCEDURE NO. 2-0310031, REVISION 1
[r +^ ~
~ ---
- ' CCW - EXCESSIVE ACTIVITY
( ") I m- s I 5.0 INSTRUCTIONS : (Cont.) _
5.3 (Co nt.)
- 1. (Cont.) _
C. Pressurizer Steam Space Sample Heat Exchanger: (2C)
Close A0V-5205 (Pzr Steam Space Sample) (RTGB-206)
Close V-5157 (Pzr Steam Space Sample Cooler Outlet)
Close V-14422 (CCW Inlet to Pzr Steam Space Sample Hz)
Close V-14430 (CCW Outlet from Pzr Steam Space Sample Hx)
D. Shutdown Cooling Sample Heat Exchanger: (2D)
Close V-5165 (2B Mini Flow to Sample Hz)
Close V-5127 (2A LPSI Pump Disch)
Close V-5130 (2A Mini Flow Sample to Rx)
Close V-5161 (SDC Suction Line Sample to Rx)
Close V-5128 (SDC Sample Rx Outlet)
Close V-14420 (CCW Inlet to SDC Sample Rx)
Close V-14431 (CCW Outlet from SDC Sample' Hx)
E. Letdown Heat Exchanger:
CAUTION: PRESSURIZER LEVEL WILL HAVE TO BE CONTROLLED BY MANUALLY STARTING AND STOPPING CHARGING PUMPS.
Close LCV-2110P (Letdown Control Valve)
Close LCV-2110Q (Letdown Control Valve)
Close A0V-2515 (Letdown Isol)
Close A0V-2516 (Letdown Isol)
Close V-2347 (Inlet Isol PCV-2201Q)
Close V-2348 (Inlet Isol PCV-2201P)
Close V-14241 (CCW to Letdown Rx)
Close V-14254 (CCW Regulator Bypass)
Close V-14248 (CCW to Regulator Stop)
.- . . . ~ - -
g,~ g - - - .. . . + . . . ,
l, Peg 3 4 cf 5 ST. LUCIE UNIT 2 0FpdiORMAL OPERATING PROCEDURE NO. 2-0310031, REVISION 1 t-CCW - EXCESSIVE ACTIVITY e. 8,
._J r
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
[
- 1. (Cont.)
F. 2A Shutdown Cooling Heat Exchanger:
Close V-7145 (2A CS Pump Disch)
Close V-7162 (2A SDC Hx Outlet to Spray Hdr) /R1 Close V-3517 (LPSI Pump to 2A SDC Ex) ,
Close HCV-3456 (2A SDC Hx to Low Press Rdr)
Check closed V-3460 (CS Pump Recire to RWT)
Check closed V-7158 (CS Pump Test to RWT)
Close V-14348 (CCW to 2A SDC Ex)
, close V-14365 (CCW from 2A SDC Hx)
] G. 2B Shutdown Cooling Heat Exchanger:
Close V-7130 (2B CS Pump Disch)
Close HCV-3457 (2B SDC Hx to Low Press Hdr)
Check closed V-3511 (CS Pump Recire. to RWT)
Check closed V-7157 (CS Pump Test to RWT)
Close V-14357 (CCW to 2B SDC Hx)
Close V-14487 (CCW from 2B SDC Ex)
NOTE: Both SDC Heat Exchangers shall be operable before
, increasing RCS temperature to ""> 323 0F or RCS pressure 2,1750 psia.
- 2. If the source of leakage cannot be determined or isolated, evaluate both the magnitude of the leakage and activity. Refer to Off-Normal 0F 2-0120031, " Excessive RCS Leakage".
, . . _ _ . _ _ .. . . _ _ . - _ _ _ . . . _ _ _ _ . . _ _ _ _ _ _ . - . _ _ - - -- . -.. a--.- _- . -- - -
Pcg3 5 of 5 ST. LUCIE UNIT 2
~~
~
, .. OFF-NORMAL OPERATING PROCEDURE NO. 2-0310031, REVISION 1 -
CCW - EXCESSIVE ACTIVITY
6.0 REFERENCES
6.1 Ebasco ~P&ID 2998-G-083 6.2 C. M ID E13172-310-130 6.3 C.E. P&ID E13172-310-150 -
6.4 Ebasco P&ID 2998-G-088 7.0 RECORDS REQUIRED:
7.1 Normal log entries '
O l
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