ML20079P092
| ML20079P092 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/13/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17214A671 | List: |
| References | |
| PROC-831213-01, NUDOCS 8401310080 | |
| Download: ML20079P092 (46) | |
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Page 1 of 41 l l EMERGENCY PROCEDURE 2-0030141 REY. 7 i CRI j l 1 l FLORIM POWER & LIGHT COMPANY ST. LUCIE UNIT 2 EMERGENCY OPERATING PROCEDURE 2-0030141 REVISION 7 CONTROL 10(D( INACCESSIBILITY (CRI) l . TOTAL NO. 6F PAGES 41 " ,ss ,,sss#fM*sd.. ,
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. EMERGENCY PROCEDUR5 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 1.0 _ Scope: -
i This procedure provides instructions for placing the plant in a safe condition when operations cannot safely be conducted from the Control Room.
2.0 Symptoms
Conditions exist such that the Control Room becomes uninhabitable and must be evacuated. 3.0 Automatic Actions: None 4.0 Imandiate Operator Action: ACTION NOTES 4.1 Manually trip the reactor and 4.1 Push buttons on RTGB-201 Turbine prior to leaving the ard 204, Control Room, if possible. 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 and Responsibilities of the - Emergency Coordinator". . 4.4 05tain the Remote Shutdown Room 4.4 Key Number 2 Keybox Master Key from the Control Room Ke7 Locker. 4.5 Evacuate all personnel from the Control Room. i 1 l
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, . ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions:
5.1 Man and taka control of otations as follows: CHECK
- 1. Reactor Control Operator "A" - Reacte Shutdown Panel !
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A. Establish cosmiunications on the Sound. Power l Phonn 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. C. Start motor or steaa-driven AFW Pumps 1 and feed the Steam Generators as required. l t CAUTION Slowly oper. AFW valves to Steam Generators to
, prevent decreasing pressurizer level due to excessive cooldown.
I D. Control Pressurizar pressure and level by manual control of Pressurizer heaters, auxiliary spray valves, and letdown valves. _ NOTE: Only the "P" Imedown level and pressure valves are controllable from outside the Control Room. Control Pressurizer level with letdown level controller (LCV-2201P) and letdown pressure controller (I4V-2110P) located on column,
; 30' east of Remote Shutdown Panel Room.
NOTE: 20% output on IrV-2201P (Letdown I4 vel Controller) is approximately 40 GPM letdown flow.
- 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 iselation switches in the ISOLATE position on the following switchgear in the order listed: . (See Appendix A) t:
.l 4160V Swgr. 2A3 l 480V Ioad Center 2A3*
480V Ioad Center 2A2
'i 480V Ioad Center 2A5 480V MCC 2A5 l }' 480V MCC 2A6 Transfer Panel 2A E 480V MCC 2AB 480V MCC 2A9 (Place Switch in Slow) /R7
- Open Bkr 2-40305 (Proportional Heater Bank 1) *
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, ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) 5.1 (continued)
- 2. Nuclear Plant Supervisor: (continued) l B. (continued) CHECK 4160V Swgr. 2B3 .
480V Ioad Center 2B3** 480V Load Center 2B2 480V Load Center 2B5
, 480V MCC 2B5 480V MCC 236 480V MCC 2B9 (Place switch in slow) /17 Transfer Panel 2B Transfer Panel 2AB Communications Isolation Panel
** Open Bkr 2-40602 (Proportional Heater Bank 2)
C. Assist Reactor Control Operator "A" in monitoring unit parameters from the Remote Shutdown Panel.
- 3. Reactor Control Operator "B"'+ Turbine Operating I4 vel A. Iocally trip or verify the Turbine has tripped.
B. Verify Turbine Stop Valves and Control Valves are shut. If not, initiate Turbine trip from Turbine front standard. C. At the APW Pump area, place the isolate switches for MV-08-19B, MV-08-18B, 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 l opening their respective breakers. l CAUTION - Ensure that one Condensate Pump remains in service. e
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, . ST. LUCIE UNIT 2 i EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) 5.1 (continued) CHECK _
- 4. Nuclear Operator - Reactor Auxiliary Building -
A. Placa isolate switches in ISCLATE/ LOCAL position on the following switchgear (see Appendix A): 4160V Swgr. 2AB 480V Ioad Center 2AB B. Proceed to the Diesel Generator Building and place isolation switches on 2A sad 2B Diesel Control Panels in ISOLATE position (see Appendix A) C. Open or check open isolation valves for Letdown prissure and level control valves (V-2110P and V-2201P). Isolata V-2110Q and V-2201Q. D. Proceed to the Charging Pump area and establish comm nicatious 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 (Intdown Level Controller) is approximately 40 GPM letdown flow. 5.3 Maintafn Pressurizer pressure at approximately 2100 ps.a by use of auxiliary sprays. NOTE: If pressurizer auxiliary spray actuates with spray line temperature >200 0F, record as per AP 0010134 5.4 Maintain RCS temperature at or below 532*F (2A cold leg temperature) by use of atmospheric steam dump and/or t. elective I starting / stopping of Reactor Coolant Pumps. NOTE: If RCS temperature is decreasing, consider ~ decreasing AFW flow. NOTE: If RCS temperature is increasing, stop RCPs as required by opening the RCP breakers in the , Turbine Building Switchgear Room. ] 5.5 When conditions have stabilized after a plant trip, maintain I or slowly increase S/G 1evels by operation of the AFW Pumps and discharge valves to the S/G's. CAUTION If decreasing RCS tagerature and/or Pressurizer level occurs. consider decreasing AFW flow to the S/Cs t I. l' 5.6 Isolate S/G blowdown by manually closing isolation i valves at the Closed Blowdown Heat Exchangers.
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5.7 When Turbine speed decrosses to "0" REM, verify that the . ! Turning Gear Oil Pump and the turning gear are in operation. --
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Page 6 of 41 CRI l- ' ' . ST. LUCIZ UNIT 2 , l ENERGEFCY PROCEDURE 2-0030141 REVISION 7 l CONTROL ROOM INACCESSIBILITY l 5.0 Subsequent Actions: (continued) l CHECK 5.8 Periodically check the habitability of the Control Room and when conditions permit, reoccupy the Control Room.
- Return isolation switches to NORMAL for switches and controls that are operational and maintain tha Unit at Hot Standby until a complete evaluation has been ande.
5.9 If Control Room accessibility is not possible, place the unit in a Cold Shutdown condition as follows:
- 1. Commence boration to Cold Shutdown conditions by annual valve lineup. Borate to 1900 ppa as shown below.
Carry out borou sampling as required during cooldown. j NOTE: This concentration will ensure >5% Shutdoan Margin at 201'F 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 detaraine shutdown boron concentration requirements instead of this Table. i Boron Concentration Number of Gallons BAM Tank l Prior t,o Control of Boron needed level change i Room Inaccessibility to reach 1900 ppa (1 BAM Tank) l 50 PPM i 7223 Ge11ons l 75% l l_ 100 PPM l 7039 Callons l 73% l l 200 PPM l 6668 Gallons l 70% l l 300 PPM l 6295 Gallons l 66% l l 400 PPM i 5919 Gallons l 62% l , l 500 PPM i 5442 Gallons l 57% l l 600 PPM i 5162 Gallons i 54% l l 700 PPM i 4779 Gallons l 50% l l 800 PPM l 4395 Gs11ons l 46% l l 900 PPM l 4008 Gallons l 42% i / !' l 1000 PPM l 3618 Gallons l 38% l / 1100 PPM l 3226 Gallons ' 34% l l l 1200 PPM i 2832 Gallons ! 30% l l 1300 PPM l 2435 Callons l 25% l g l l 1400 PPM l 2036 Gallons l 21% l l l- 1500 PPM l 1634 Gallons l 17% l L 2. Ensure S/G 1evels are conatent or slowly increasing to - maintain 65% level by use of the AFW Pumps. ? i
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Page 7 cf 41 CRI
. ST. LUCIE UNIT 2 EHERGENCY TROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) h . 5.9 (continued) CHECK
- 3. Stop at least one RCP price to reaching 5000 F by tripping its breaker at the 2A1 or 251 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 switchgtar room.
- Re-close lift pump breakers af ter oca 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 7 97*F.
- 6. The Pressuriser water phase temperature shall be plotted every 30 minutes using the Saturated Temperature vs.
Pressure curve of this procedure (Figure 2). If possible, maximize letdown and minicize charging when using auxiliary spray to minlai:e thermal stress on spray nozzle. NOTE: Cooldown of the Pressurizer shall be limited 0 to fl90 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. Conumence 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 4750 F, and sealing steam will be lost. Condenser vacuum rust be broken prior to 475 0F to prevent seal damage.
- 8. Have I & C personnel install temporary VCT level monitoring equipment. While locally monitoring and
- controlling VCT level, slowly open the atmospheric steam dugs and establish the desired cooldown rate NOTE
- A makeup blend ratio to the VCT of about 9:1 is ,
i sufficient to maintain 1900 PPM boron in the RCS. 6 NOTE: A temperature differential of approximately 1000 F betw.en 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 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL RCOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) 5.9 (continued) CHEK ~
- 9. When the SIAS amber permissive lights come on (11136 psia),
block SIAS by turning the key operated switch on the Remote Shutdown Panel for both A and B channels.
- 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". B. Charging header pressure; close its isolation valve.
- 11. Commence venting all four SITS from remote valve stations in the Electrical Penetration Room. (Valves 3733, 3734, 3735, 37?6, 3737, 3738, 3739, and 3740).
NOTE: Do not vent more than one SIT to <235 psig.
- 12. Maintain at least two RCPs operating. If possible, two RCPs in the same loop should be left running.
- 13. Periodically adjust the steam dump controllers and auxiliary spray control to inmintain the desired cooldown and de-pressurization rate. Verify that the S/G's are are being maintained at approximately 65% level.
- 14. With RCS prese 2re <1700 psia, but prior to comencing SDC operations, rack out 2A and 2B Containaant Spray Pump breakers (2-20203 and 2-20407).
- 15. When RCS tesperature is <500 F and RCS pressure is
<1500 psia, perform the following:
A. Close 2-7-07145 and 2-V-07130 (Containment Spray Pump disch valves). B. Close the following Containment Opray header - manual isolation valves: , 2-V-07161 (A bdr FCV upstream isol) 2-V-07164 (3 bdr FCV upstream isol) MV-07-3 (A hdr FCV downstream isol) MV-07-4 (B hdr FCV downstream isol) CAUTION l Prior to lowering R'CS pressure below 390 psia, I. two RCPs in the sam loop must be operating.
- 16. Iower RCS temperature to 3250F and RCS pressure to ;; ,
320 psia. 1
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. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: .(continued) i 1
5.9 (continued) CHECK I
- 17. Stop the operating RCPs by tripping the breakers on 2A1 and 2B1 switchgear. After pump coastdown, stop the oil lift pumps by opening the breaker for each- pump for one minute, then re-closing the breaker.
NOTE: Since RCS forced circulation has been terminated, it is necessary to proceed quickly to Shutdown Cooling.
- 18. Iower RCS pressure to <275 pria, rack in the breakerc and then close the SIT discharge valves by placing tha local control switch in the CLOSE position.
MV-3614: Bkr. 2-41219 MV-3624: Bkr. 2-41311 MV-3634: Bkr. 2-42117 MV-3644: Bkr. 2-42048
- 19. Rack out the SIT discharge valve breakers.
- 20. Rack out one HPSI Pump prior to 250 F. 0 Ensure the other HPSI Pump remains operable.
t CAun0N 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 (Total capacity 4,600 gps).
- 21. Ensure RCS preesure <275 psia, then open the following valves from their local controllers: -
A. Hot Leg Suction Valves: V-3651. V-3652, - V-3665, V-3480, V-3481, V-3664.
!XyfE: V-3664 and V-3665 local controllers are in Pipe Penetration Room; all others are in l' the Cable Spreading Room.
1 NOTE: V-3545 (Hot Iag Suction Cross-Tie) is normally closed. It may be used to provide flow during
. off-normal conditions and must be open if both trains of SDC are in service.
(' B. Open CCW from SDC Heat Exchangers: HCV-14-3A and HCV-14-3B by isolating instrument air to the HCVs and bleeding off air pressure. C. SDC Heat Exchanger Discharge Valves: MV-3456 and MV-3457. D. LPSI Header Isolation Valves: MV-3615, . MV-3625. MV-3635 and MV-3645. .
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. ST. LUCIE UNIT 2 EMi1RGENCY PROCEDURE 24)030141 REVISION 7 CONTROL ROOM INACCESSIBILITY 5.0 Subsequent Actions: (continued) 5.9 (continued) CHECK l
- 22. Close the followf.ng valves:
A. RWT rec.irculation stop valves: V-3459 V-3463, and V-3597. ' B. Miniflow baader stop valves: V-3659 V-3660 V-3495 and V-3496. C. LPSI suction from RWT: V-3432 and V-3444.
- 23. Have the Nuclear Operator establis'n consraications on s the Sound Power Phona Systea (Circuit No.1) in the 2A LPSI Pump Room.
- 24. Eetablish SDC as follows:
A. Insert keys for MV-3306 and MV-3657 (controllers located in A LPSI Room) and place switches to MODULATE position. B. Using key switches at local contre 11ers, open hT-3517 and MV-3658. C. Give MV-3306 a three second open . signal, then allow switch to return to NORMAL. D. - Start the 2A LPSI Pump, then oper. MV-3306 to obtain 3000 gpa flow as indicated on FI-3306 at the Remote Shutdown Pans 1. , 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 gpa.
- 25. At 200 0F 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 s are operable.
, 26. . Stabilize 'RCS tagerature at approximately 100 F0 and RCS pressure at approximasely 250 psia. Control pressure by s
use of Pressurizer heatars and auxiliary spray. Do not take the Pressurizer solid until Control Rapa access has been re-established.
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. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY 6.0 Purpose and Discussion:
This procedure provides instructions for placing the plant in a safe condition when operations cannot safely be conducted from the Control Room. The reactor and turbine are manually 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. Level 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 v,1ves, and are sonitored at the Ramote Shutdown Panel. Isolation switchas 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 poaltion 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. Ioad Centers 2A, 2B, 2AB
- 2. Transfer Panels 2A, 2B, 2AB
- 3. MCC 2A5, 2A6, 235, 256, 2A9, 2B9
- 4. 4160V Buses 2A3, 2B3, 2AB
- 5. 4160V Buses 2A2, 2B2 -
- 6. 6900Y Buses 2A1, 231
- 7. Diesel Generator 2A and 23 Control Panels
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The Nuclear Plant Supervisor will utilize additional personnel as available to assist in required subsequent actions. i c e e
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. ST. LUCIE UNIT 2 ENERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITT i
7.0 Raferences
7.1 Emergency Operating Procedure 1-0030141 7.2 St. Lucie Unit 2 Technical Specifications
.. ..a 8.0 Records : -
8.1 A coupleted, initialed copy of this procedure shall be retained in the plant file.
9.0 Approval
Reviewed by Facility Revier Group October 26 1981 Approved by J. H. Barrow (for) Plant Manager October 26 19E Revision 7 Reviewed by FRG /#/.21993 ' Approved by b [ h ant Manager / 2 - / 1 19 V EP 2-0030141 Revision 7 Total No. of Pages 41 I I b 9 d$ h O
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Page.13 of 41 CRI ST. LUCIE UNIT 2 DERGENCY PROCEDURE 2-0030141 R5 VISION 7 CON'a10L ROON INACCESSIBILITY f 8 APPENDIX "A" ISOLATION SWITCHES , , 480V Imad Center 2A3 - Pressurizer Bester Bus, Auxilia,ry Building Electrical Equipment Room
- 1. Pressurizer Backup Beater Bank B-1
- 2. Pressurizer Backup Hester Bank B-2
- 3. Pradaurizar Backup Heater Bank B-3 G
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- 1. Pressurizer Backup Hester Bank B-4
- 2. Pressuriser Backup Heater Bank B-5
- 3. Pressurizar Backup Bester Bank B-6 e
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POge 15 of 41 CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTRCL ROOM INACCESSIBILITY APPENDIX "A" (continued) ISOLATION SWITCHES 480V Ioad Center 2A2 - Auxiliary Building Electrical Equipment Room
- 1. Station Service Transt 2A2 Main Breaker
- 2. Bus Tie to 4807 L.C. 2AB
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- 3. Charging Pump 2A e
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Page 16 cf 41 CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVIEION 7 CONTROL ROOM INACCf.FSIBILITY f APPENDIX "A" - (continued) ISOLATION SWITCHES 4160V SWGR 2A3 - faxiliary Building Electrical Equipas,nt Room
- 1. HP Safety Injection Pump No. 2A
- 2. LP Safety Injection Pump No. 2A
- 3. Containment Spray Pamp No. 2A
- 4. Pressurizer Eeater Transf No. 2A3
- 5. CEIM Cooling Fan 2HVE-21A
- 6. Component Cooling Water Pump No. IA
- 7. Intake Cooling Water Pump No. 2A
- 8. Feeder to 4.16KY Bus No. 2AB
- 9. Feeder from 4.16%V 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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j Page 17 cf 41 CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROCH INACCESSIBILITY APPENDIX "A" - (continued) . ISOLATION SWITCHES 480V MCC 2A5 - Auxiliary Building Electrical Equipment, Room
- 1. Makeup Bypass to Charging Pumps V-2514 (Emergency Borate)
- 2. Aux. P.W. Pump 2A Dischstge Valve to S/G 2A (MV-09-9 and I-SE-09-2)
- 3. S/G #25 to AFWP-2C Turbin MV-08-12
- 4. Comp Cool Wtr to Cont Cool Unit 2A Valve MV-14-9
- 5. Coup Cool Wtr from Cont Coci Unit 2A MV-14-10
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- 6. Comp Cool Wtr Cont Coci Unit 25 MV-14-11
- 7. Comp Cool Wtr from Cent Cool Unit 2B Valve MV-14-12
- NOTE: Switch 1, 6. and 7 mitt be in ISOLATE to have remote control of 2A charging pump.
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. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 ,
CONTROL ROOM INACCESSIBILITY { , APPENDIX "A" (continued) - 1 ISOLATION SWI*CHES _ ,, j l 480V MCC 2A6 - Auxiliary Building Electrical Equipment Room
- 1. Boric Acid Makeup Pump 2A
- 2. Boric Acid Makaup Pump 2B
- 3. Control Room Air Cond Unit 2HVA/ACC 3A
- 4 Shield Bldg. Vent Exhaust Fan 2HVE-6A
- 5. Control Room Emerg. Piltration Fan 2HVE-13A
- 6. Containment Spray Isolation valve MV-07-161
- 7. 2A LPSI Pump Suetics Valve V-3444
.I I e t 4 i !i i s t e o i e " f
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j Page 19 of 41 CRI ST. LUCIE UNIT 2 - EMERGENCY PRCCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued) ISOLATION SWITCHES _ 480V MCC 2A9 - Reactor Auxiliary Building ,
- 1. Containment Cooling Fan 2HYS-1A
- 2. Containment Cooling Fan 2HVS-1B
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. . - ._ .. . - . . ..,.. . ~ . .
Pzge 20 cf 41 l' ~ CRI
. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued) -
ISOLATION SWITCHES _, 480V bad Center tB2 - Auxiliary Building Electrical Equipment Room
- 1. Station Service Transf. 2B-2 Main 3reaker
- 2. Bus Tie to 480V L.C. 2AB
/R7
- 3. Charging Pump 2B 4
5 9 e i o
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1 J l l P ge 21 cf 41 l CRI j
, , . ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES 4160V SWGR 2B3 - Auxiliary Building Electrical Equipment Room
- 1. Emergency Df esel Generator No. 2B
- 2. Feed to 480V SS Transformer 2B2/2B5
- 3. Pressurizer Heater Transf No. 253
- 4. Component Cooling Water Pump No. 23
- 5. HP Safety Injection Pump No. 2B
- 6. LP Safety Injection Pump No. 2B
- 7. Containment Spray Pump No. 2B
- 8. CED( Cooling Pan 2HVE-21B S Feedar te 41607 bus No. 2AB
- 10. Intake Cooling Water Pqar. ib. 2B
, 11. Incoming Feeder from 4.1617 Bee 232
- 12. tamilir.r/ Feedwater Pamp No. 2B 4 y l:
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Paga 22 ef 41 CRI
. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 -
S CONTROL ROOM INACCESSIBILITY g APPENDIX "A" - (continued) ISOLATION SWITCHES u 480V MCC 236 - Auxiliary Building Electrical Equipment. Room
- 1. 2HVE-13B - Control Room Booster Fan
- 2. Control Room Air Cond 2HVA-3B
- 3. Contain:nect Sprey Isolation Valve (MV-07-164)
- 4. Shield Aid Vent Exh Fan 2HVE-6B
- 5. 2B LPSI Pump Suction Valve (V-3432) i, l
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P ge 23 cf 41 , CRI
. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 CONTROL ROON INACCESSIBILITY j APPENDIX "A" -
, (continued) ISOLATION SWITCHES 480V MCC 235 - Auxiliary Building Electrical Equipment, Room ,
- 1. CCW to Containment Fan Cooler 2HVS-1C (MV-14-13)
- 2. CCW from Containannt Fan Cooler 2HYS-1D (MV-14-14)
- 3. Boric A..id Gravity Feed Valve (V-2508)
- 4. Boric Acid Gravity Feed Valve (V-2509)
- 5. CCW to Containment Fan Cooler 2HVS-1D (MV-14-15)
- 6. CCW from Containment Fan Cooler 2HVS-ID (MV-14-16)
- 7. 2B AFW Pump Discharge to 2B Steam Generator (MV-09-10 and I-SE-09-3)
(Back of MCC 285)
- 6. 2A Steam Generator to 2C APW Pump Turbine (MV-08-13)
(Back of MCC 235)
- NOTE: Switch 3 and 5 must be in ISOLATE to have remote control of 2B chargiag pump.
e f e d 9 l e
" & l
. . . . . . ~ - . . . .,. - . . .. ..- -.. . . ~ . . . . . - . 1 :_ .: _. . ~ . .
Page 24 of 41 CRI ST. LUCIE UNIT 2 EMERGENCY PEOCEDURE 2-0030141 EEVISION 7 CONTROI ROON INACCESSIBILITY i APPENDIX "A" (continued) _ i ISOLATION SWITCHES - r 480V MCC 2B Reactor Auxiliary Building '
)
- 1. Containment Cooling Fan 2HYS-1C
- 2. Containment Cooling Fan 2HYS-1D 1
o
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- - . - . - - . . ...... : - . - ...~ . -- . . . ; .
Page 25 ef 41
' CRI
, . St. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" -
(continued) ISOLATION SWITCHES 1 480V MCC 2AB - Auxiliary Building Electrical Equipment. Room
- 1. Component Cooling Water Suction Valve Hdr. A (MV-14-3)
- 2. Component Cooling Water Suction Ysive Hdr. B (MV-14-4)
- 3. Component Cooling Water Discharge Valve Bdr. A (MV-14-1)
- 4. Component Cooling Water Discharge Valve Hdr. B (MV-14-2)
- 5. Control Roos Air Cond Unit 2-HVA/ACC 3C i 1
- NOTE: Switch 4 and 5 aust be in ISOLATE to have remote control of 2C charging pump.
i G s 8 e 9 e s O _ _ _ _ _ . o
. I
~ .- - . ..
I P ge 26 of 41 l CRI l
. ST. LUCIE UNIT 2 EMERCENCY PROCEDURE 2-0030141 REVISION 7 C0YrROL ROOM INACCESSIBILITY APPENDIX "A" (continued) .
ISOLATION SWITCHES _, g Transfer Panel 2AB - Auxiliary Building Electrical Equipment Room (2AB Battery Room)
- 1. 2C Aux Feed Pump Stop valve MV-08-3
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Page 27 ef 41 CRI
. ST. LUCIE UNIT 2 EMEFCENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROON INACCESSIBILITY APPENDIX "A" -
(continued) , ISOLATION SWITCHES Transfer Panel 2A - Auxiliary Building Electrical Equipment Roon l l 1. 2A Steam Cen Atas Steam Dump PIC-08-1A1 1
- 2. 2A Steam Con Atas Steam Dump PIC-08-1A1
- 3. SS-1-157 - Letdown cont Isol Valve (V-2516)
I
- 4. SS-1-189 - Aux Spray Valve (I-SE-02-3)
- 5. SS-194 - Charging Line Isol Valve (V-2523)
- 6. 2A Diesel Con Watt / Volt Meter
- 7. SS-1-176 - Charging to Icop 2A2 (I-SE-02-02)
- 8. 2C AFW Fmp Diseg to 2B Stsan Cen (MV-09-12 and I-SE-09-5)
- 9. 2E Steas Cenerator Arr s. Jteam Dap PIC-08-Mi s.
G e
'6
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.. . ..- -. ....... A .-- ----.. -. . .- - - . . . - . -u-P2ge 28 cf 41 ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 COtrTROL ROOM INACCESSIBILITY APPENDIX "A" '
f (continued) ISOLATION SWITCHES _ _ Transfer Panel 2B - Auxiliary Building Electrical Equipment Room
- 1. 2B Steam can Atas Steam Dump PIC-08-1B1
- 2. 2B Steam can Atas Steam Dump PIC-08-1B1
- 3. SS-2-157 - 14tdown Stop Valve (V-2515)
- 4. SS-2-189 - Aux Spray Valve (I-SE-02-04)
- 5. SS-1-194 - 14tdown Cont 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 AFW Pump Dicch to 2A Steam Can (HV-J9-11 sad I-SE-09-4) 9.. 2A Steau Can Atas Steam Dump PIC-08-3B1 o
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l l 1 Page 29 cf 41 l CRI ST. LUCIE UNIT 2 ENERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY . APPENDIX "A" ' (continued) ISOIATION SWITCHES Comm nications Isolation Panel - Auxiliary Building Co.==naf cations Room
- 1. Fire Alare/ Site Evacuation - (Control Console, Isolation Switch)
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Page 30 cf 41 CRI
,' . ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 CUltTR6C K008'iNACCEssinitYtt APPENDIX "A" (continued) .
j ISOLATION SWITCHES _ 4160 SWGR 2A2 - Turbine Building Switchgear Room - 4 .
- 1. Feeder to 480V SWGR No. 2A1 I
- l 2. Feeder to 4.16KV Ius No. 2A3
- 3. Incoming Feeder from 4.16KV SWGR 2A4 l
4 1 9 l 1 4 l' i i J! 4 i e
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- . - _ . . . . - . . . . - . - . . :- ..-..x.. --
Page 31 Cf 41 CRI
. ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" .
(continued)
.I.S. 01ATION. SWITCHES
. m 4160V SWGR 2B2 - Turbine Building Switchgear Roon
- 1. Feeder to 480V SWGR No. 2B1
- 2. Feeder to 4.16KV Bus No. 2B3
- 3. Incoming Feeder from 4.16KV SWGR 2B4 l
l l 4> l' f - 3 4 h s s e e
. _ _ _ . - . _ .. -.- -. . . . . . . - - . - - - - . . -'~ L
. . . . . -. _ . - . - . .- ---r.
Pcge 32 cf 41 CRI
, , , ST. LUCIE UNIT 2 EMERGENCf PROCEDURE 2-0030141 REVISION 7
, CONTROL RefM INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES 69007 SWGR 2A1 - Turbine Building Switchgear Room -
- 1. Incoming Feeder from S/U Tranaf No. 2A l '
a 8 1 l l , H I E l. I i l e& f
Page 33 cf 41 CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY l APPENDIX "A" (continued) , ISOLATION SWITCHES 6900V SWGR 251 - Turbine Building Switchgear Room -
- 1. Incoming Feeder from S/U Transf No. 2B
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. \
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, Page ,J4 of 41
' ' GI
- ST. Lt1CIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 .C CONTROL ROOM INACCESSIBILITY ,
APPENDIX "A" N ' (continued) ISOLATION SWITCHES
. . - . . a.
a APW PUMP AREA -
- 1. MV-08-198 (Atmospheric Dump Valve)
! 2. MV-08-185 (Atmospheric Dump Valve) J
- 3. MV-08-18A (Atmospheric Dump Valve)
I
- 4. MV-08-19A (Atmospheric Dump Valve) a P
t e 4 4
- 3 f
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4
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- . . . . .es
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. . ......... . . - -- . . - - . ~. a.a .s- - - - - - -. - - ~- ~~ 't Page 35 cf 41 CRI ST. LUCIE tmIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 )
CONTROL ROOK INACCESSIBILITY i l APPENDIX "A" (continued) > . i ISOLATION SWITCHES ,ya . s wd 4160V SUCR 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 4.16KY Bus 253 I:
4 t i 6 9 4 i e a~ g
.. ._.. _ .l__ . . . . _ . _ _ . ~
Page 36 cf 41 CRI ST. LUCIE UNIT 2 l EHERGENCY PROCEDURE 2-0030141, REVISION 7 l CONTROL ROOM INACCESSIBILITY APPENDII "A" (continued) ISOLATION SWITCHES 480V Ioad Center 2AB - Auxiliary Building Cround Floor,
- 1. Bus Tie to 480V L.C. 2A2 (I4ft End of Panel)
- 2. 2C Charging Puny
- 3. Bus Tie to 480V L.C. 2B2 I
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Page 37 of 41 CRI
, , , ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141 REVISION 7 CONTROL ROOM INACCESSIBILITY APPENDIX "A" -
(continued) ISOLATION SWITCHES . 2A Diesel Generator Control Panel .
- 1. Voltage Control 1
- 2. Frequency Control
- 3. Start Circuit t
l 1 9 b i 1 l e
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' ~
CRI ST. LUCIE UNIT 2 EMERGENCY PROCEDURE 2-0030141, REVISION 7 CONTROL ROOM INACCESSIBILITY l APPENDIX "A" . (continued) ISOLATION SWITCHES 23 Diesel Generator Control Panel . .
- 1. Voltage Control
- 2. Frequency Control
- 3. Start Circuit e
h
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- i 3
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UNCONTROLLED COPIES 1 D. A. Sager 2 3 NRC-Region II 4 Attn: EPPS Branch Chdof 5 N. G. Roos H. Paduano.- GO 6 TSC A. W. Bailey 40g 8 9 10 Control Room II r ..I". c 4/*/eM 11 G. Regal f Ugelow, A. - Backfit g12 ECI
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14 TM.A!j - ls,J4iAc4:,R,,,. 15 Training J. Spodick , T. Vogan - GO G. J. Boissy-R. P.. Jennings IbedWP91ersee R. J. Frechette Re ident NRC C - IElPHQ' - Attn: Chief, Nucles r Respon
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L2 PROCESSED ST: DATE I .
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Page 1 cf 3 - , l FLORIDA POWER & LIGHT COMPANY s ST. LUCIE UNIT 2 ) 0FF-NORMAL OPERATING PROCEDURE NUMBER 2-1560030 1 REVISION 1
1.0 TITLE
'"'"^^' "Arra srsTEu - oy, yo ,
FOR If! FORMATION ONLY This documentis not contro!!ed. Before use, d nt. verify information with a centrolledaocume
2.0 APPROVAL
)
Reviewed by Facility Review Group November 10. 1981 Approved by C. M. Wethy ~ Plant Manager November 16, 1981 Revision 1 ' Reviewed by F R G 7"M 19 P I Approved by' bl[ M o n M t Manager /1 - //) 19M
3.0 FURPOSE
vs The purpose of this procedure is to provide instructions to be followed when a failure or malfunction in the Primary Water System occurs.
4.0 SYMPTOMS
4.1 High Primary Water Tank level 4.2 Low erinary Wcter Tank level 4.3 Iow Primary Water Pump discharge pressure 4.4 Alaras 4.4.1 Disch Header lo Pressure (Annunciator F-15) 4.4.2 Primary Water Tar.k Hi - Io level (Annunciator F-23) . l-l t-l{ l. o "O
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Page 2 cf 3 . ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NUMBER 2-1560030, REVISION 1 PRIMARY WATER SYSTEM - 0FF NORMAL t
5.0 INSTRUCTIONS
5.1 Immediate Automatic Actions t 5.1.1 The standby pump will start on a low primary water pump discharge pressure of 100 peig. 5.2 Immediate Operator Actions 5.2.1 On low discharge header pressure, verify that the standby pump has started and the system pressure has returned to normal. 5.3 Subsequent Operator Actions 5.3.1 If the standby pump did not start, start manually and investigate the failure of the auto start feature. 5.3.2 Investigate the cause of the low pressure condition and correct. 5.3.3 On a Primary Water Tank icvel problem, take appropriate action to return the tank to normal, as follows: 5.3.3.1 High Level
- a. Discontinue water transfer operations if in progress.
- b. Discontinue filling from WTP.
- c. Ensure fill and bypass valves are closed.
5.3.3.2 Low I4 vel
- a. Commence filling operations from WTP if not in
, progress. t
- b. If the low level condition is the result of a sudden .
changa in tank level, investigate the ;:rimary water system for signs of leaks and isolate affected components. i 5.3.4 Low Header Pressure Condition
- a. When normal system pressure is restored, return the l
! second Primary Water Pump to standby lineup.
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Fage 3 of 3 - ST. LUCIE UNIT 2
** OFF-NORMAL OPERATING FROCEDURE NUMBER 2-1560030, REVISION 1 FRIMARY WATER SYSTEM - 0FF NORMAL ;
6.0 REFERENCES
6.1 FSAR, Chapter II, Tables 9.2-8 and 9.2-9 7.0 RECORDS REQUIRED: 7.1 Normal log entries , e e e m g _ _-}}