ML20069F928
| ML20069F928 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/03/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17213B160 | List: |
| References | |
| PROC-830303, NUDOCS 8303240133 | |
| Download: ML20069F928 (86) | |
Text
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. t FLORIDA POWER & LIGHT COMPANY JPage 1 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE 2-0030141 REVISION 1 .
1.0 TITLE
CONTROL ROOM INACCESSIBILITY
. -d
2.0 APPROVAL
Reviewed by Facility Review Group Oct. 26 198_2 Approved by J. H. Barrow (for) Plant Manager Oct. 26 1982 Rev. 1 Reviewed by FRG 47- 3 / 198Z Approved by 8JtJ)M Plant Manager 2.-/ rr-- 19D 3.0 PURPOSE & DISCUSSION:
3.1 This procedure provides *nstructions for placing the plant in a safe condition when operations cannot safely be conducted from the Control Room.
3.2 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.
3.3 A heat sink is provided by automatic steam dump to the Condenser and/or to atmosphere.
3.4 Level is maintained in the Steam Generators by manual control of auxiliary feedwater valves with flow furnished by the Auxiliary Feedwater Pumps.
3.5 Pressurizer level and pressure are maintained by manual control of l Pressurizer heaters, auxiliary spray valves, and letdown valves, and are monitored at the Remote Shutdown Panel.
3.6 Isolation switches located in the Reactor Auxiliary Building i
i Electrical Equipment Room, Turbine Building Switchgear Room, Diesel l Generator Rooms, and Reactor Auxiliary Building are manually I selected to the ISOLATE position to prevent inadvertant operation of vital equipment due to possible electrical malfunction in the unattended Control Room.
3.7 A copy of this procedure will be posted at each manned operating station required for plant shutdown from outside the Control Room.
s .
i FOR INFORMATION Di1LY This document is not cont o%d. Bene use, verify information with a c:ntreiled datument.
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Page.2 of 40 ST. LUCIE UNIT No. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY 3.0 PURPOSE & DISCUSSION: (continued) 3.8 A listing of isolation switches will be posted on each of the following ' panels, MCCs, and di'tribution s buses. .
- 1. Load Centers 2A, 2B, 2AB
- 2. Isolation Switch Panels 2A, 2B, 2AB
- 3. MCC 2AS, 2A6, 2B5, 2B6
- 4. 4160V Buses 2A3, 2B3, 2AB
- 5. 4160V Buses 2A2, 2B2
- 6. 6900V Buses 2A1, 2B1
- 7. Diesel Generator 2A and 2B Control Panels
- 8. Auxiliary Feedwater Pump Area R1 3.9 The Nuclear Plant Supervisor will utilize additional personnel as ~
available to assist in required subsequent actions.
4.0 SYMPTOMS
4.1 Conditions exist such that the Control Room becomes uninhabitable and must be evacuated.
5.0 INSTRUCTIONS
5.1 Immediate Actions:
5.1.1 Manually trip the reactor and Turbine prior to leaving the Control Roon, if possible.
5.1.2 Announce evacuation of the Control Room over the P.A. system.
5.1.3 Implement the Emergency Plan, as necessary, in accordance with EPIP 3100021E, " Duties of the Emergency Coordinator".
5.1.4 Obtain the Remote Shutdown Room Keybox Master Key from the Control Room Key Locker: Key Number (LATER).
5.1.5 Evacuate all personnel from the Control Room.
5.2 Subsequent Actions:
5.2.1 Man and take control of stations as follows:
1 Reactor Control Operator "A" - Remote Shutdown Panel.
s A. Establish communications on the Sound Power Phone
( System.
B. Monitor available plant parameters on the Remote Shutdown Panel.
~
i C. Start motor or steam-driven Auxiliary Feedwater Pumps I and feed the Steam Generators as required.
. Page 3 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY
5.0 INSTRUCTIONS
(continued) 3.2 (continued) 5.2.1 (continued)
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 the Remote Shutdown Panel.
- 2. Nuclear Plant Supervisor - Electrical Equipment Room, Reactor Auxiliary Building - 43' Elev. ,
A. Open or check open Reacter Trip Breakers TCB-1 through 8.
B. Place isolation switches in the ISOLATE position on the following switchgear in the order listed: (See Appendix A).
480V Load Center 2A3 480V Load Center 2B3 480V Ioad Center 2A2 4160V SWGR 2A3 480V MCC 2A5 480V MCC 2A6 4801' Load Center 2B2 4160V SWGR 2B3 480V MCC 2B6 480V MCC 235 I
480V MCC 2AB Isolation Panel 2AB Isolation Panel 2A l
Isolation Panel 2B Communications Isolation Panel l C. Assist Reactor Control Operator "A" in monitoring unit parameters from the Remote Shutdown Panel.
D. Open or check opent 480V Load Center 2A3 P-1 HTR Peed 2-40305 l 480V Load Center 2B3 P-2 HTR Feed 2-40603 R1
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. / 'Page 4'of 40 )
, ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY 5.0 INSTRUCTIONS _: (continued) 5.2 (continued) .
5.2.1 (continued)
- 3. Reactor Control Operator "B" - Turbine Operating Level.
A. Locally trip or verify tripped Unit No. 2 Turbine.
B. Verify Turbine Stop Valves and Control Valves are shut; if not, initiate Turbine trip from Turbine front standard.
C. At the AFW Pump area, place the isolate switches for ~
MV-08-19B, MV-08-18B, MV-08-18A, and MV-08-19A in ISOLATE.
R1 D. Proceed to Turbine Building Switchgear Room and establish communications on the Sound Powered Phone circuit.
R1 E. Place isolation switches in the ISOLATE position for bus feeder breakers as follows (see Appendix A):
R1 4160V SWGR 2A2 4160V SWGR 2B2 6900V SWGR 2Al 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. R1 CAUTION: Ensure that one Condensate Pump remains in service.
- 4. Nuclear Operator - Reactor Auxiliary 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 4:e Diesel Generator Building and place isolation switches on 2A and 2B Diesel Control Panels in ISOLATE position (see Appendix A).
a
- - - / Page 5 of 40 ST. LUCIE UNIT NO. 2
'- EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY ,d
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5.0 INSTRUCTIONS
(continued) [,
5.2 (continued) ,
5.2.1 (continued)
- 4. (continued)
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 communicationa on the Sound Powered Phone circuit.
5.2.2 Maintain Pressurizer level at approximately 33% indicated-level. ,
5.2.3 Maintain Pressuriser pressure at approximately 2100 psia.
5.2.4 Maintain Reactor Coolant System temperature at or below 532*P (2A cold leg tempe'rature) by use of atmosphere steam dump and/or selective shutdown of R.setor Coolant Pumps.
i.
NOTE: Stop Reactor Coolant Pumps as required by opening the Reactor Coolant Pump breakers in the Turbine Building Switchgear Room.
5.2.5 Maintain Steam Generator levels at the approximately 65%
indicated level by operation of the Auxiliary Peedwater Pumps and discharge valves to the Steen Generators.
5.2.6 Isolate Steam Generator blowdown by manually closing isolation valves at the Closed Blowdown Heat Exchangers.
l 5.2.7 When Turbine speed decreases to "O" RPM, verify that the Turning Gear Oil Pump and the turning gear are in operation.
i
( 5.2.8 Periodically check the habitability of the Control Room and i when conditions permit, reoccupy the Control Room. Return l isolation switches to NORMAL for switches and controls that are operational and maintain the Unit at Hot Standby until a i- complete evaluation has been made.
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. Page 6 of 40
. ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY
5.0 INSTRUCTIONS
(continued) 5.2 (continued) - .
5.2.9 If Cantrol-Room accessibility is not possible, place the unit in a Gold Shutdown condition as follows:
- 1. Coomence boration to Cold Shutdown conditions by manual valve lineup. Borate to 1900 ppa as shown below.
NOTE: This concentration will ensure >5% Shutdown Margin at 20l*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 borr a 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 uay be used to determine shutdown boron concentration trouirements instead of this Table.
l Boron Conc. INumber of Gallons IBAM Tank l l Prior to Control of Boron needed llevel change l l Room Inaccessibility to reach 1900 ppe l(1 BAM Tank) l l 50 PPM l 7223 Gal l 75% l
- l 100 PPM l 7039 Gal l 73% l I l 200 PPM l 6668 Gal l 70% l l 300 PPM l 6295 Gal I 66% l l 400 PPM i 5919 Gal i 62% l l 500 PPM i 5442 Gal l 57% l l 600 PPM i 5162 Gal l 54% l l 700 PPM l 4779 Gal i 50% l l 800 PPM i 4395 Gal l 46% l l 900 PPM l 4008 Gal l 42% l l1000 PPM l 3618 Gal i b1 l l l1100 PPM I 3226 Gal l 34% l l1200 PPM i 2832 Gal l 30% l l1300 PPM i 2435 Gal l 25% l l1400 PPM l 2036 Cal l 21% l l1500 PPM l 1634 Gal i 17% l
Page 7 of 40
, ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOK INACCESSIBILITY
5.0 INSTRUCTIONS
(continued) -
5.2 (centinued) -
5.2.9 (continued)
- 2. Ensure Steam Generator level is being maintained at approximately 65% by the Auxiliary Feedwater Pumps.
- 3. Stop at least one Reactor Coolant Pump 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. Af ter pump coastdown, stop the lift pumps by opening the associated breakers in the electrical switchgear room. 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 3.4-2b at least once per 30 minutes during cooldown.
NOTE: Cooldown of the RCS shall be limited to ;[ 750 F in
, any one hour period.
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- 6. The Pressurizer water phase temperature shall be plotted i avery 30 minutes using the Saturated Temperature v, Pressure curve of this procedure (Figure 2). If l possible, maximize letdown and minimize charging when
! using auxiliary spray to minimize thermal stress on spray nozzle.
NOTE: Cooldown of the. Pressurizer shall be linited to j( 190*F in any one hour period.
- 7. When the quanity of boron calculated in Step 5.2.9.1 has been added, cooldown may proceed. Verify by chemistry I sample (if possible) that desired boron concentration has been obtained. Commence taking data on cooldown curve.
l 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 steam will be lost. Condenser vacuum must be broken pr'ior to 475'F to prevent seal damaga.
Page 8 of 40.
ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY
5.0 INSTRUCTIONS
(continued) 5.2 (continued) 5.2.9 (continued)
- 8. Have I & C personnel install temporary VCT level monitoring equipment. While locally monitoring and controlling VCT level, slowly open the atmospheric steam dumps and establish the desired cooldown rate. R1 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 1000 P between the RCS and Pressurizer should be -
maintained during cooldown. Cooldown of the Pressurizar must be accomplished by use of auxiliary spary and heater control. .
- 9. At 1750 psia, isolate and bypass the following transmitters:
- 1) Charging header flow: close vaJve marked "HIGH SIDE", open valve marked " BYPASS", and close valve marked " LOW SIDE".
- 2) Charging header pressure: close its isolation valve.
I 10. When the SIAS amber permissive lights come on (1808
( psia), block SIAS by turning the key operated switch on the Remote Shutdown Panel for both A and B channels. El
- 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). R1 l 12. Maintain at least two Reactor Coolant Pumps operating.
If possible, two RCPS in the same loop should be lef t l
running.
- 13. Periodically adjust the steam dump controllers and
' auxiliary spray control to maintain the desired cooldown and de-pressurization rate. Verify that the Steam ,
Generators are being maintained at approximately 65%
level.
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- 14. With RCS pressure < 1700 psia, but prior to commencing l
SDC operations, rack out 2A and 2B Containment Spray Pump l breakers (2-20203 and 2-20407) .
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Page 9 w! 40
- ST. LUCIE UNIT No. 2 EMEMENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 "'*%
CONTROL ROOM INACCESSIBILITY 1 i ?
. 5.0 INSTRUCTIONS: (cont.)
5.2 (continued) .
5.2.9 (continued)
1500 psia, preform the following:
A. Close 2-V-07145 and 2-V-07152 (Containment spray pump disch valves)
B. Close the following containment spray header manual isolation valves.
2-V-07161 (A hdr FCV upstream isol) -
2-V-07164 (B hdr FCV upstream isol) - '
2-V-07162 (A har FCV downstream isol) 2-V-07165 (B hdr FCV downstream isol) i 16. When RCS pressure is < 275 psia, rack in the breakers j for and then close the SIT discharge valves by placing
! the 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
- 17. Rack out the SIT discharge valve breakiers.
CAUTION: Prior to lowering RCS pressure below (LATER)
- psia, two RCPs in the same loop must be operating.
. 19. Rack out one HPSI Pump prior to 280*F. Ensure the other EPSI pump remains operable. R1 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- (Total capacity 4,600 spa).
NOTE: Miniaua pressure for RCP operation is (LATER), so it
. is necessary to proceed quickly to Shutdown Cooling.
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.Page 10 of 40-ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOH INACCESSIBILITY
5.0 INSTRUCTIONS
(cont.)
5.2 (continued) L 5.2.9 (continued)
- 20. Stop the operating RCPs prior to lowering pressure to (LATER) by tripping the breakers on 2Al and 2B1 switchgear. After pump coastdown, stop the oil lift pumps by opening the breaker for each pump for 1 minute, then re-closing the breaker.
- 21. Reduce RCS pressure to < 275 psia, then open the following valves from their local controllers: R1 A. Hot Leg Suction V'lves:
a V-3651, V-3652, V-3665, -
V-3480, V-3481, V-3664.
NOTE: V-3664 and V-3665 local controllers are in Pipe Penetration Room, all'others are in the Cable Spreading Room.
NOTE: V-3545 (Hot Leg Suction Cross-Tie) le normally closed. It may be used to provide flow during off-normal conditions.
B. Open CCW from SDC Heat Exchangers: HCV-14-3A and HCV-14-3B by isolating instrument air to the HVC's and bleeding off air pressure. R1 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.
- 22. Close the following valves:
A. RWT recirculation stop valves: V-3459, V-3463, and V-3597.
B. Miniflow header stop valves: V-3659, V-3660, V-3459 and V-3496.
- 23. Have the Nuclear Operator establish communications on the Sound Power Phone System in the 2A LPSI Pump Room.
.. o Paga'll of 40 .
ST. LUCIE UNIT NO. 2 .
EMERGENCY OPERATING' PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY f...
5.0 INSTRUCTIONS
(cont.)
/jf 5.2 (continued) 5.2.9 (continued)
- 24. Establish 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 controllers, open MV-3517 and MV-3658. R1
^
C. Give MV-3306 a 3 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 gym.
- 25. At 200*F RCS temperature, remove the trip and close fuses on the remaining HPSI rump. 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 no t take the Pressurizer solid antil Control Room access has been re-established.
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. Page 12 of 40- -
. ST. LUCIE UNIT NO. 2 .
EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 1 CONTROL ROOM INACCESSIBILITY l
APPENDIX "A" (continued)
ISOLATION SWITCHES 480V Load Center 2A3 - Pressurizer Heater Bus, Auxiliary Building Electrical Equipment Room
- 1. Heater Bank B-1
- 2. Heater Bank B-2
- 3. Hea::er Bank B-3 R1 l
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. . Page 13 of 40
. -ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROCH INACCESSIBILITY APPENDIX "A" (continued) -
ISOLATION SWITCHES 480V Load Center 2B3 - Pressurizer Heater Bus, Auxiliary Building Electrical Equipment Room 1.- Heater Bank B-4
- 2. Heater Bank B-5
- 3. Heater Bank B-6 R1
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Page 14 of 40
, ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING IROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY J
APPENDIX "A" (continued) '
ISOLATION SWITCHES 480V Load Center 2A2 - Auxiliary Building Electrical Equipment Room 1.- SS Transformer 2A2
- 2. Bus Tie to 480V L.C. 2AB
- 3. Containment Fan Cooler 2-HVS-1A
- 4. 2A Charging Pump ,
R1
- Page'15 of 40
. . ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141 REVISION 1 CONTROL ROON INACCESSI31LITY lP APPENDII 'A" (continued)
/
ISOLATION SWITCHES j-r -
b m ,._,
480 V Load Center 2A5 - Auxiliary Building Electrical Equipment Room
- 1. Containment Pan Cooler 2-HVS-1B R1 O
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. P2gs 16 of 40 .
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ST. LUCIE UNIT NO. 2 EhERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued) /'/
ISOLATION SWITCHES '
4160V SWGR 2A3 - Auxiliary Building Electrical Equipment-Room
- 1. 2A HPSI Pump
- 2. 2A LPSI Pump
- 3. 2A Containment Spray Pump _
- 4. Pressurizer Heater Transformer 2A3
- 5. 2A Component Cooling Water Pump
- 6. - 2A Intake Cooling Water Pump
- 8. Feed to 4160V Bus 2AB
- 9. Feed from 4160V Bus 2A2
- 10. Feed to 480V SS Transformer 2A2
- 11. Feed from 2A Emergency Diesel Generator
- 12. 2A Auxiliary Feedwater Pump -
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Page 17 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NLMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY ,
1
~- ~ APPENDIX "A" (continued)
ISOLATION SWITCHES 480V MCC 2A5 - Auxiliary Building Electrical Equipment Room
- 1. Makeup Bypass to Charging Pumps (V-2514) R1 2.- 2A AFW Eump Discharge to 2A Steam Generator (MV-09-9)
- 3. 2B Steam Generator to 2C AFW Pump Turbine (MV-08-12)
- NOTE: Switch 1, 6 and 7 must be in ISOLATE to have remote control of 2A charging pump. R1 i
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Page 18-of 40
, ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY- l APPENDIX "A" (continued)
ISOLATION' SWITCHES f
480V MCC 2A6 - Auxiliary Building Electrical Equipment Room
- 1. 2A Boric Acid Makeup Pump
- 2. 2B Boric Acid Makeup Pump
- 3. 2HVA-3A - Control Room Outdoor Air Conditioner 4, 2HVE-6A - Shield Building Exhaust Fan .
- 5. 2HVE-13A - Control Room Booster Fan
- 6. Containment Spray Isolation Valve (MV-07-161)
- 7. 2A LPSI Pump Suction Valve (V-3432) r
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. ST. LUCIE UNIT NO. 2 -
EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY
. s APPENDIX "A" (continued)
ISOLATION SWITCHES 480V Load Center 2B2 - Auxiliary Building Electrical Equipment Room
- 1. SS Transformer 2B2 ,
- 2. Bus Tie to 480V L.C. 2AB
. 3. Containment Pan Cooler 2HVS-1C
- 4. 2B Charging Pump I
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- .Page 20 of.40-ST. LUCIE UNIT NO. 2 -
EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL' ROOM INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES 480V LOAD CENTER 2B5 - Auxiliary Building Electrical Equipment Room
- 1. Containment Fan Cooler 2-HVS-1D.
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. - Page 21 of 40 ST. LUCIE UNIT NO. 2 -
EMERGENCY OPERATING PROCEDURE NDnBER.2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY' APPENDIX "A" (continued)
ISOLATION SWITCHES 4160V SWGR 2B3 - Auxiliary Building Electrical Equipment Room
- 1. Feed from 2B Emergency Diesel Generator
- 2. Feed to 480V SS Transformer 2B2
- 3. Pressurizer Heater Transformer 2B3
- 4. CEni Cooling Fan 2HVE-21B
- 5. 2B Component Cooling Water Pump
- 6. 2B HPSI Pump
- 7. 2B LPSI Pump
- 8. 2B Containment Spray Pump
- 9. Feed to 4160V Bus 2AB
- 10. Feed from 4160V Bus 2B2
- 11. 2B Intake Cooling Water Pump
- 12. 2B Auxiliary Feedwater Pump l
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. ST. LUCIE UNIT NO.'2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOK INACCESSIBILITY ie r
. APPENDIX "A" (continued)
ISOLATION SWITCHES
. 2.
480ir MCC 2B6 - Auxiliary Building Electrical Equipment Room
- 1. 2HVE-6B.- Shield' Building Exhaust Fan
- 2. 2HVA-3B - Control Room Air Conditioner
- 3. 2HVE-13B - Control Room Booster Fan
- 4. Containment Spray Isolation Valve (MV-07-164)
- 5. 2B LPSI Pump Suction Valve (V-3444) e 6
e
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Page 23 of 40
< ST. LUCIE UNIT.NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141,- REVISION 1
-CONTROL ROG( INACCESSIBILITY ,
. APPENDIX "A" (continued)
ISOIATION 4 WITCHES 480V MCC 2B5 - Auxiliary Building Electrical Equipment Room
- 1.. Boric Acid Gravity Feed Valve (V-2508) El
- 2. Boric Acid Gravity Feed Valve (V-2509)
- 3. 2B AFW Pump Discharge to 2B Steam Generator (MV-09-10).
- 4. 2A Steam Generator to 2C AFW Pump Turbine (MV-08-13)
- NOTE: Switch 1 and 7 must be in ISOLATE to have remote control of 23 charging pump. 'R1 i
l l
l i
d"%
. . Page 24 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY l
APPENDIX "A" (cont'inued)
ISOIATION SWITCHES 480V MCC 2AB - Auxiliary Building Electrical Equipment Room
- ' 1. 2HVA-3C- Control Room Air Conditioner, Indoor Unic R1
- 2. CCW Discharge Valve -.A Edr. (MV-14-1)
- 3. CCW Discharge Valve - B Bdr. (MV-14-2) Rl'
- 4. CCW Discharge Valve - A Hdr. (MV-14-3)
- 5. CCW Discharge Valve - B Bdr. (MV-14-4)
- NOTE: Switch 1 and 3 must be in ISOLATE to have remote control of 2C charging pump. R1 o
i .
e l
1 l ._
. . . Page 25.of 40
. ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES Isolation Panel 2AB - Auxiliary Building Electrical Equipment Room
- 1. 2C Auxiliary Feed Pump Stop Valve (MV-08-3)
O e
S
.,n-- , --.,-,ln.-, -
. o Page 26 of.40 ST. LUCIE UNIT NO. 2
' EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY ,
APPENDIX "A" (continued) .
ISOLATION SWITCHES Isolation Panel 2A - Auxiliary Building Electrical Equipment Room
< 1. SS-1-189 - Auxildary Spray Valve (I-SE-02-3)
- 7. . SS-1-157 - Letdown Containment Isolation-Valve (V-2516)
- 3. SS-1-176 - Charging to Loop 2A2 (I-SE-02-02)
- 4. SS-194 - Charging Line Isolation Valve (V-2523)
- 5. 2A Steam Generator Atmospheric Steen Dump PIC-08-1A1 (2 switches)
- 6. 2B Steam Generator Atmospheric Steam Dump PIC-08-3Al
- 7. 2A Diesel Generator Watt / Volt Meter
- 8. 2C AW Pump Discharge to 2B Steam Generator (MV-09-12) e i
o
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Page 27 of 40
~
ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROCK INACCESSIBILITY
! n w<
APPENDIX "A" (continued)
/
If0LATION SWITCHES f L_
Isolation Panel 2B - Auxiliary Building Electrical Equipment Room
- 1. SS-2-189 - Auxiliary Spray Valve (I-SE-02-04)
- 2. SS-2-157 - Letdown Stop Valve (V-2515)'
- 3. SS-2-176 - Charging to Loop 2B1 (I-SE-02-01)
- 4. SS-1-194 - Letdown Containment Isolation Valve (V-2522)
- 5. 2B Steam Generator Atmospheric Steam Dump PIC-08-131 (2 switches)
- 6. 2B Steam Generator Atmospheric Steam Dump PIC-08-3B1
- 7. 2B Diesel Generator Watt / Volt meter
- 8. 2C AW Pump Discharge to 2A Steam Generator (MV-09-11) e l
l l
l
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_ w Peg 2 28 of.40
-ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 _
CONTRCL ROOM INACCESSIBILITY I APPENDIX "A" (continued) ,f ISOLATION SWITCHES u
Communications Isolation Panel - Auxiliary Building Communications Room
- 1. Fire Alarm / Site Evacuation - Control Console, Isolation Switch
- 2. Control Room PA Isolation Switch
- 3. Code Call Isolation Switch l
4
.a w w * -
9-- c --' *
. Pega 29 of.40
,ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY A l
w APPENDIX "A" (continued)
ISOIATION SWITCHES. f 4160V SVGR 2A2 - Turbine Building Switchgear Room
- 1. Feed to 480V SS Transformer 2Al ,
- 2. Feed to 4160V Bus 2A3
- 3. Feed from 2A4 SWGR
~
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. . . . . . . P gs 30 of 40 .
ST. LUCIE UNIT NO. 2
. EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROON INACCESSIBILITY APPENDIX "A" (continued) -
ISOLATION SWITCHES 4160V SWCR 2B2 - Turbine Building Switchgear Room
- 1. Feed to SS Transformer 2B1
- 2. Feed to 4160V Bus 2B3
- 3. Feed from 2B4 4160V Bus
.W 4
.e
Pagd 31 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL R00t( INACCESSIBILITY J
APPENDIX "A" (continued) ,+
/ i 8
ISOLATION SWITCHES : ;
. -t 6900V SWGR 2Al - Turbine Building Switchgear Room )
- 1. Feed _from Startup Transformer 2A i
1 w---- 'e -w w -emp---m-
I Page 32 of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUM3ER 2-0030141, REVISION 1 CONTROL ROON INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES -
6900V SWGR 2B1 - Turbine Building Switchgear Room
- 1. Feed from Startup Transformer 2B 9
l l
l p .
Prgs 33 of 40 ST.'LUCIE UNIT NO. 2-EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOK INACCESSIBILITY l
APPENDIX "A" (continued)
,ISOIATION 94 ITCHES f L
APW FUMP AREA
- 1. MV-08-19B (Atmospheric Dump Valve)
- 2. MV-08-18B (Atmospheric Dump Valve)
- 3. MV-08-18A (Atmosph.eric Dump Valve)
- 4. MV-08-19A (Atmospheric Dump Valve)
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- .* Page 34'of 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued) ,,
ISOLATION SWITCHES f a
4160V SWGR 2AB - Auxiliary Building Ground Floor
- 1. 2C Component Cooling Water Pump " Local" switch position
- 2. 2C Intake Cooling Water Pump " Local" switch position
- 3. Feed from 4160V Bus 2A3
- 4. Feed from 4160V Bus 2B3 G
i l
l l
? . .
l Paga 35'cf 40 ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY lJ APPENDIX "A" (continued)
ISOLATION SWITCHES o
480V Load Center 2AB - Auxiliary Building Ground Floor
- 1. Bus Tie to 480V L.C. 2A2
- 2. 2C Charging Pump
- 3. Bus Tie to 480V L.C. 2B2 O
J '
- - . Page 36 of'40 '
s ST. LUCIE. UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY APPENDIX "A" (continued)
ISOLATION SWITCHES k
.2A Diesel Generator Control Panel'
- 1. Voltage Control'
- 2. Frequency Contrcl
- 3. Start circuit 4
l l
l I
~
Page 37 of 40
. ST. LUCIE UNIT NO. 2 EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITY ,
- a. ,1 APPENDIX "A" (continued) /
r ISOLATION SWITCHES
{
28 Diesel Generator Control Panel
- 1. Voltage Control
- 2. Frequency Control
- 3. Start Circuit e
i I
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" . EMERGENCY OPERATING PROCEDURE NUMBER 2-0030141,. REVISION 1 CONTROL ROOM INACCESSIBILITY O
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Page 39 of 40 ST. LUCIE UNIT 'O. 2 N
- EMERGENCY OPERATING PROCEDURE" NUMBER 2-0030141, REVISION 1 CONTROL ROOM INACCESSIBILITT Lf J
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EMERGENCY CPERATING PROCEDURE NUMBER 2-0030I41, REVISIdN'1 .
CONTROL ROOM INACCESSIBILITY 'N '
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Acts: EPPS 3 ranch : hief '
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ST. LUCIE UNIT NO. 2 0FF NORMAL OPERATING PROCEDURE NO. '-019n0w
/ x?
f , j' REVISION O Uq 2
- 1. TITLE: PRESSURIZER PRESSURE & LEVEL - OFF - NOR'fAL OPERATION
- 2. PREPARED Big C. Marple 2-8 19- 83
- 3. SUBCOMMITTEE REVIEW BY: c. M. tJnnd For FP&L 2.-T 193
- 4. REVIEWED BY FRG ON: 7-/ 19 4 ?
- 5. APPROVED BY: d /[ d n u_ e - b ant Manager c-/ 19f? -
- 6. REVISION REVIEWED BY FRG ON: 15i-
- 7. APPROVED BY: Plant Manager 19 ;
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- FLORIDA POWER & LIGHT COMPANY ,. Page 1 of 5 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE 2-0120035 REVISION 0 f. O '
lA $ il
.? 4 5 1.0 TITLE: / .
./
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PRESSURIZER PRESSURE AND LEVEL-OFF-NORMAL OPERATION g rt. . ,
! II
. 2.0 APPROVAL:
- Reviewed by Facility, Review Group
- - 19 6 Approved by /7 '/- O a A.M /' ,t- _. Plant Manager -
19_T Rev. Reviewed by FRG 19 _
Approved by Plant Manager - 19 _
4
3.0 PURPOSE
This procedure provides instructions for operator action in the event of-malfunction of Pressurizar pressure and level control systems, or
, pressure transient caused by inadvertant operation of the suxiliary spray- .
valves. ,
i
4.0 SYMPTOMS
4.1 Pressurizer High-Low Pressure alarm, Channel X or Y.
i 4.2 Pressurizer High-Low Level alarm, Channels I or Y.
l 4.3 Pressurizer Low-Low I4 vel alarm, Channels X or Y.
4.4 Pressurizer Proportional Heaters Low Level trip.
l 4.5 Pressurizer Back-up Heaters Low I4 vel Trip Control Switch Isolated.
4.6 Safety or Relief Valve (s) open alarm.
{ .'
5.0- INSTRUCTIONS:
5.1 Immediate Automatic Actions:
5.1.1 Abnormal Pressurizer Pressure Condition.
1 Pressurizer safety valves open at 2500 psia.
l, l
- 2. High pretsure reactor trip and power operated reliefs I open at 2375 psia.
~
i l
- 3. High pressure alarm actuates at 2340 psia.
i
- 4. Proportional heaters cycle from minimum output at 25 psi above setpoint, to maximum output at 25 psi below setpoint..
l l
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Pagy 2 of 5 ST. LUCIE UNIT 2 0FF-NORMAL OPERATIN PROCEDURE 2-0120035, REVISION O f, h PRESSURIZER PRESSUIL AND LEVEL-OFF-NORMAL OPERATION Q.g
.J.
5.0 INSTRUCTIONS
(continued) .
" . ; ,[
4 5.1 (cont.) f
. 5.1.1 (cont.) .
- 5. Spray valves cycle from full closed at 25 psi above -
setpoint, to full open 25 psi below setpoint.
'6. Backup heaters energize at < 2200 psia and de-energize .
at > 2200 psia.
- 7. Iow pressure alarm actuates at 2100 psia.
- 8. TM/LP reactor trip initiates at 1887 psia minimum pressure. ,
. 9. SIAS initiates at 1708 psia.
5.1.2 Abnormal Pressurizer Level Condition.
- 1. All Pressuriser heaters deenergize at 26.9% indicated level, and respective Pressurizar Heater Transformer Feeder Breaker opens.
- 2. Iow level alarm actuates and signal to start the back-up Charging Pump is received at -5% below RRS setpoint.
NOTE: Only one back-up Charging Pump is in the level control system.
- 3. The back-up Charging Pump receives a signal to start at
-3% below RRS setpoint, decreasing.
- 4. The back-up Charging Pump receives a signal to stop at
-1% below RRS 'setpoint, increasing, and minimum letdown (29 gpa).
- 5. All back-up heaters energize and a back-up stop signal to the back-up Charging Pump is received at + 4.0% above RRS setpoint.
- 6. Maximum letdown is 138 gpa at 9% above RRS setpoint.
- 7. High level alarm actuates at 10%'above RRS setpoint.
i
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. Pegs 3 of 5 ST. LUCIE UNIT 2 gy OFF-NORMAL OPERATING PROCEDURE 2-0120035, REVISION 0 r, z,S PRESSURIZER PRESSURE AND LEVEL-OFF-NORMAL OPERATION '[ J' 't
' ' )'
~
T
5.0 INSTRUCTIONS
(continued) //
/
5.2 Immediate Operator Actions: ,,,,,
t 1 5.2.1 Abnormal Pressurizer Pressure. L" ~~ J
- 1. Ensure Pressurizer spray, and Proportional and Backup heaters are operating properly in automatic. If not, shift spray valve controller to MANUAL, and energize or deenergize beaters, whichever is applicable.
- 2. Ensure power operated relief vakves are elesed. If open, isolate by closing 7-1476 and/or V-1477 (power operated relief isolation valves). Refer to OP #2-0120036, " Pressurizer Relief / Safety Valve-Off-Normal Operation". ,
- 3. Ensure SE-02-03 and SE-02-04 (Auxiliary spray valves) are closed. If open, attempt to close using key switch. If still open, stop all Charging Pumps and isolate letdown. Refer to OP #2-0210030, " Charging and Letdown Off-Normal Operation".
- 4. Ensura pressure anomaly is not caused by a large rate of '
change of T,y .
CAUTION: During. blackout conditions with the Diesel Genertors supplying power, the control bistables for the Back-up heaters are not energized, and must be bypassed.
Therefore, in a blackout, the breakers on the l
Electric Panel must be reset and the key I switch selected to PRESSURE OVERRIDE to regain heater control. Note, however, this will only energize B1 and B4 banks of Back-up heaters.
5.2.2 Abnormal Pressurizer Level.
l 2. Ensure the backup Charging Pump starts and letdown flow ,
is decreasing, or the backup Charging Pump stops and .
letdown flow is increasing, whichever is applicable.
- 3. Ensure level anomaly is not caused by a large rate of change in T,y,,
Ppg 3 4 of S
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ST. LUCIE UNIT 2 _
0FF-NORMAL OPERATING PROCEDURE 2-0120035, REVISION O ]
PRESSURIZER PRESSURE AND LEVEL-OFF-NORMAL OPERATION 's- * *
.I
5.0 INSTRUCTIONS
(continued) / f
- a.== y 5.3 Subsequent Actions. (_ _
l 5.3.1 Check that Pressurizer Safety Valves are not leaking or have -
actuated by observing downstresa header temperature indication and Quench Tank indications.
5.3.2 Ensure A0V-2515, A0V-2516, and A0V-2522 (Letdown Isol) are open.
5.3.3 Ensure SE-02-01 and SE-02-02 (Charging Isol) are open. -
5.3.4 Ensure LCV-2110P and LCV-2110Q (Pressurizer Level Control) are operating properly.
, 5.3.5 Ensure PCV-2201P and PCV-2201Q (Letdown Pressure Control) are operating properly.
5.3.6 Manually start the third Charging Pump, if conditions require.
5.3.7 Ensure Letdown Valve Limiter Bypass switch and Pressurizer Level Bypass control switches are in the NORMAL positions.
5.3.8 Compare letdown flow, charging flow, charging pump header pressure, and VCT level for indications of leaks or lifting relief valves in the CVCS system. Refer to OP #2-0120035,
" Charging and Letdown-Off-Normal Operation".
5.3.9 Ensure that Power Operated Relief Valve (V-1474 and 1475) hand switches are in the proper mode for existing plant conditions.
! NOTE: (1) Switch in NORMAL RANGE:
l RCS Temperature > 320*F RCS Pressure > 490 psia (2) Switch in LTOP:
RCS Temperature < 320*F l
RCS Pressure < 460' psia.
5.3.10 If Pressurizar level decrease cannot be immediately explained, refer to OP #2-0120035, " Excessive Reactor Coolant System Leakage".
I
i Prgs 5 of 5.
ST. LUCIE UNIT 2
- .2% _ a.
OFF-NORMAL OPERATING PROCEDURE 2-0120035.' REVISION 0 .
. ?,
PRESSURIZER PRESSURE AND LEVEL-OFF-NORMAL OPERATION ! [
5.0 INSTRUCTIONS
(continued)
/ d.r . 3 5.3 (cont.) F ,
'A' Pressurizer Heater 4 5.3.11 With < 27% level on Channel I, the Transformer . feeder breaker trips and the 'B' side 480v breakers trip. With < 27% level on Channel Y, the 'B' Pressurizar Tranformer feeder breaker trips and the 'A' side 480v breakers trip. The key operated override switch placed in the LEVEL OVERRIDE position will reset the 480v breakers.
NOTE: (1) With Channel 'X' selected, and if Channel 'X' fails low, all heaters trip. The operator must then select Channel Y and LEVEL OVERRIDE to get.
power to the 'B' side heaters. (i.e. , P1, B4, B5, ,
and B6).
(2) With Channel 'X' selected, and if Channel 'Y' fails low, all heaters trip. The operator must then select LEVEL OVERRIDE to get power to the
'A' side heaters. (i.e., P1, B1, B2, B3).
i
6.0 REFERENCES
6.1 St. Lucie Unit 2 FSAR.
6.2 C-E Setpoint Guidelines.
6.3 F.P.L. Training Lesson outline #91. <
1 7.0 RECORDS REQUIRED:
j 7.1 Normal log entries.
7.2 Applicable chart recorders.
7.3 If pressure transient was caused by inadvertant auxiliary spray l valve actuation, document transient per AP f 2-0010134, " Component Cyclic and Transient Limits Records".
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UNIT II QCCZENT RIVISICE DISTR 30TTON S='*T -
0FT NORMAL & EMERGENCY OPER. FRCCZXRE CC32 C 2~ :2OUT bc Llm.*e $ft%99 $m&a: ^ lute,*n Mu MAmt T&\
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NC. CCC3 INT ECI.::IR RE"'URNID NC. DCCUMI!C ECI.DIR FITJRNID MASTER UNCONTROLI.ZD COPIES 1 D. A. Sager 2
3 NRC - Region II Ac:n: EPPS 3 ranch Chief -
4 H. Paduano - GO 5 N. G. Roos '
A. W. 3a11ey 6 T.SC G. Anglehar: - CE 7
8 9
10 Qw / etoaA II
' G. Regal 11 Ugelou, Al -3ackf1:
12 13 Training - Larry 3ak er 14 15 Tra4' 5s J. Spodick T. Vogan - GO G. J. Soissy R. R. Jennings H. M. Mercer A. Pell R. J. Frechette ident NRC
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gluu - A cy Acts: Chief, Nuclear Rescense
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Branch C. Burns v PRCCISSID ST: DA2
t 0 l ,
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE 2-0120038 REVISION O
- 1. TITLE: Out of Limit Steam Generator Chemistry Parameters
- 2. PREPARED BY: R. Kress February 24 1983
- 3. SUBCOMMITTEE REVIEW BY: for FP&L J-G 19N
- 4. REVIEWED BY FRG ON: *S 19 T,3 V
- 5. APPROVED BY: N/////Mffdt= Plant Manager 3 19F3 LT
- 6. REVISION REVIEWED BY FRG ON: 19
- 7. APPROVED BY: Plant Manager 19 i
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FLORIDA P0k'ER & LIGHT COMPANY !
ST. LUCIE UNIT 2 0FT-NORMAL OPERATING PROCEDURE 2-0120038 REVISION O i 4
1.0 TITLE
- i Out of Limit Steam Generator Chemistry Parameters i l
2.0 REVIEW AND APPROVAL: !
Reviewed by Facility Review Group 53'- :3- 19dI?5 l.
Approved by [M/]/,rfi . Plant Manager 3' 19 D l 4Gl $
Revision Reviewed by FRG 19 i
Approved by Plant Manager- 19 J 3.0 PURPOSE AND DISCUSSION: ~l :
3.1 This procedure provides Steam Generator specifications and !
appropriate actions to be taken in the event that they are exceeded. ;
3.2 Adherence to these limits and actions will provide raasonable '
assurance that the Steam Generators will be protected from excessive i corrosion during operation. l
4.0 SYMPTOMS
4.1 Increase in specific or cation conductivity in the Steam Generator (s).
2A Steam Generator - specific conductivity.
2B Steam Generator - cation conductivity.
4.2 Alarm or increase in cation conductivity of the condensate header or hotwells, 4.3 Increase or decrease of pH in the Feedwater System or Steam Generators.
4.4 Increase in dissolved oxygen reading.
4.5 Abnormal _ results from grab samples.
4.6 Increase in sodium levol of condensate on recorder in Unit 1 Cold Lab.
l l
l
. o .
a Pag 3 2 cf 6 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE 2-0120038, REVISION O OUT OF LIMIT STEAM GENERATOR CHEMISTRY PARAMETERS
5.0 INSTRUCTIONS
5.1 Immediate Automatic Action.
5.1.1 High cation conductlyity alara on condensate or hotwells.
5.2 Immediate Operator Action.
5.2.1 Stop any evolution in progress if suspected of being the problem.
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- ST. LUCIE UNIT 2 OFF-NORMAL OPERATING PROCEDURE 2-0120038, REVISION O I OUT OF LIMIT STEAM GENERATOR CHEMISTRY PARAMETERS I I
lt
/
5.0 INSTRUCTIONS
[
r 5.3 Subsequent Operator Action.
5.3.1 If a conductivity alarm is present, determine from multipoint recorder whether it is the condensate header or a particular hotwell. If it is determined to be a Condenser leak, refer to Off-Normal GP #2-0610030, " Condenser Tube Leak."
5.3.2 Inform the Chemistry Department of the location, the magnitude, and whether the indication is increasing, stabilized, or decreasing. .
5.3.3 Inform the Chemistry Department of any plant evolutions in progress or recent evolutions which could have caused the change in that particular chemistry parameter.
~'
5.3.4 Chemistry Department will verify the indication with grab samples and cross checks of instruments involved.
5.3.5 Inform Chemistry Department of any changes in indications.
5.3.6 If indication is determined to be valid, take the following actions based on concentrations determined by Chemistry Department personnel:
- 1. Concentrations and Action Levels.
A. System t Steam Generator (Power Operation).
Chemistry Parameters Action Level Parameter Normal Value 1 2 3 pH 8.5-9.2 <8.5
>9.2 Cation Coaductivity ;[.8 > .8 >2 >7 unho/cm Sodium, ppb j[20 >20 >100 >500 Chloride, ppb j[20 >20 >100 Silica, ppb j[300 >300 O
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P*g2 4 of 6 ST. LUCIE UNIT 2
- OFF-NORMAL OPERATING PROCEDURE 2-0120038, REVISION d OUT OF LIMIT STEAM GENERATOR CHEMISTRY PARAMETERS
5.0 INSTRUCTIONS
(continued)
- JI 5.3 (continued) 5.3,6 (continued) . .
- 1. (continued)
B. System t Condensate Chemistry Parameters Action Level Parameter Normal Value 1 2 3 pH 8.8-9.2 <8.8
>9.2 Dissolved 0 , ppb f,10 >10 >30 2
Cation Conductivity, f,0.2 >0.2
, unho/an Sodium, ppb f,3 >3
- 2. Action Level Definitions.
A. Action Level 1 Objective: To promptly identify and correct the cause of an out-of-normal value without power reduction.
Actions:
- 1. Return parameter to within normal value range within one week following confirmation of excursion.
- 2. If parameter is not within normal value range within one week following confirmation of excursion, proceed to Action Level 2 for those parameters having Action Level 2 values.
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Pega 5 of 6 i.
ST. LUCIE UNIT 2 '
0FF-NORMAL OPERATING PROCEDURE 2-0120038, REVISION O s OUT OF LIMIT STEAM GENERATOR CHEMISTRY PARAMETERS
5.0 INSTRUCTIONS
(cont'inued) I' 5.3 (continued)
'5.3.6 (continued) 2.- (continued)
B. Action Level 2 Objective: To minimize corrosion by operating at reduced power while corrective actions are taken. Power reduction should be to a level which will reduce available Steam Generator superheat and heat flux while providi'ng sufficient system flow to maintain.
automatic operation while the source of the impurity is corrected. This reduced power level is typically 30% of full power or less. _
Actions:
- 1. Reduce power to appropriate level (typically 30% or less) within four hours of initiation of Action Level 2.
- 2. Return parameter to within normal value range within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> or go to Action Level 3 for those parameters having Action Level 3 values.
C. Action Level 3 Objective: To correct a condition which may result in rapid
, Steam Generator corrosion during continued operation. Plant shutdown will avoid ingress and eliminate further. concentration of harmful impurities.
- Action
- 1. Shut down within four hours and clean up by feed and bleed or drain and refill as appropriate until normal values are reached.
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. ST. LUCIE UNIT 2
~OFF-NORMAL OPERATING PROCEDURE 2-0120038, REVISION ~0 OUT OF LIMIT STIAM GEN 22ATOR CHEMISTRY PARAMETERS i I am m[( .-
6.0 REFERENCES
6.1 Chemistry CP C-50 and C-51.
6.2 EPRI Secondary Chemistry Guidelines.
6.3. FPL Nuclear ' Chemistry Specification Manual.
7.0 RECORDS REOUIRED:
7.1 Normal log entries t
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 i
, EMERGENCY OPERATING PROCEDURE No. 2-0360040 g REVISION O
- 1. TITLE: Operational Regttirements for Emergency Cooling Water Canal
- 2. PREPARED BY: be d MA N/f / 1/d196/
- 3. SUBCOMMITTEE REVIEW BY: Is [e OA4NW/N PP&L PR 2./23 19 F3
- 4. REVIEWED BY FACILITY REVIEW GROUP ON: 2- /2 7 19 f-)
- 5. APPROVED BY:
y' 6D L4(U ant Manager Y-b 19 .[ 2
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P:g3 1 of 3 FLORIDA POWER & LIGHT COMPANY f ST. LUCIE UNIT 2 U' EMERGENCY OPERATING PROCEDURE NO. 2-0360040 REVISION O gj/ j 1
1.0 TITLE
l Operational Requirements for the Emergency Cooling Water Canal 2.0 REVIEW AND APPROVAL:
Reviewed by Facility Review Group 2/l .f~ 19fd Approved by 17. h b (CA M [ d Plant Manager 7 'b 19 fl V
Revision Reviewed by FRG 19 Approved by Plant Manager 19 _
3.0 PURPOSE
The Emergency Cooling Water System consists of a canal connecting Big Mud Creek to the intake in front of the circulating water intake structure.
This secondary source will be used only in the event that the primary source from the Atlantic Ocean becomes inoperable. For normal operation I
the barrier wall across the Ultimate Heat Sink (UMS) separates the intake canal from Big Mud Creek.
An operable UHS ensures that sufficient cooling capacity is available to either (1) provide normal cooldown of the facility, or (2) to mitigate the effects of accident conditions within acceptable limits.
4.0 SYMPTOMS
4.1 Intake structure low water. level (Annunciators LA-1 and LB-1) 4.2 Intake local level indication less than -9 ft. ,
4.3 Intake water temperature high (TR-21-2) b O
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Ptg3 2 cf.3 ST. LUCIE UNIT 2-EMEL:;ENCY OPERATING PROCEDURE NO. 2-0360040 REVISION O OPERATIONAL REQUIREMENTS FOR EMERGENCY COOLING WATER CANAL
5.0 INSTRUCTIONS
5.1 The Operations Supervisor shall determine the need to operate the #
/ '
UHS. [
E i 5.2 The Operations Supervisor shall notify the Duty Call Supervisor. "~~'~'**<
5.3 The turbine generator and associated equipment will be shut down per OP 2-0030125.
5.4 The Circulating Water System shall be shut down per OP 2-0620020.
5.5 Implement the Emergency Plan as necessary in accordance with EPIP 3100021E, " Duties of the Emergency Coordinator."
5.6 The reactor shall be shut down and placed in mode 3.
NOTE: The reactor shall be in mode 3 within one hour of (1) reaching an intake water level of less than -10.5 ft., or (2) an average intake temperature of greater than or equal to 960F.
5.7 Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after placing the reactor in mode 3, the flow barrier wall valves I-SE-37-1 and I-SE-37-2 shall be opened providing cooling water from Big Mud Creek. Notify Unit 1 Control Room to open and verify by alarm (E-44).
NOTE: In the event barrier valves fail to open on signal, a temporary air jumper hose is available at barrier valve's air supply and steps 5.7.1.1 through 5.7.1.4 may be performed to manually open barrier valves.
5.7.1 Operation Procedure 5.7.1.1 Allow normal movement in open direction before attaching hose so upper piston void can intake air preventing a vacuum from forming.
5.7.1.2 Attach hose to upper piston connection.
5.7.1.3 Unlock and open supply air valve (BA 3 key).
5.7.1.4 Regulate 1-2 psig intervals until valve opens (normally <5 psig opens valve).
5.8 Continue reactor cooldown per OP 2-0030127.
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I Prg3 3 of 3 ST. LUCIE UNIT 2 EMERGENCY OPERATING PROCEDURE NO. 2-0360040, REVISION O OPERATIONAL REQUIREMENTS FOR EMERGENCY COOLING WATER CANAL ,
6.0 REFERENCES
6.1 St. Lucie Unit 2 TSAR, Section 9.2.5 af'
/
6.2 Unit 2 Technical Specification Section 3.7.5.1 d -
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6.3 Circulating Water Sistem Normal Operation, OP 2-0620020 6.4 Turbine Shutdown, OP 2-0030125 ,
6.5 Reactor Cooldown from Mode 3, OP 2-0030127 7.0 RECORDS REQUIRED:
7.1 Normal log entries e
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UNIT II CCCUZEIT REVISICN* DIS'"RI3UTICN, SmT -
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1 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO.'2 0FF NORMAL OPERATING PROCEDURE NO. ' nAAnn'n REVISION O w,1 u
- 1. TITLE: SDC/LPSI - OFF NORMAL OPERATION
- 2. PREPARED BY: H. Johnson /K. Thomas 4 Jan. 19 S 3.. SUBCOMMITTEE REVIEW BY: dk[ For FP&L j-/7 19p
- 4. REVIEWED BY FRG ON: Eb / 7 19F 2
- 5. APPROVED BY:
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- 6. REVISION REVIEWED BY FRG ON: 19 _
- 7. APPROVED BY: ,
Plant Manager 19 _
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FLORIDA POWER & LIGHT COMPANY Pago 1 cf,12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-0440030 REVISION O
1.0 TITLE
SDC/LPSI - 0FF NORMAL OPERATION
2.0 APPROVAL
Reviewed Review Group MI'/ 7 19 b Approvedbyby Facility,I O/// M f q/ @ nt Manager E> / /7 193 Revision No. Reviewed by FRG 19 _
Approved by Plant Manager 19 _
3.0 PURPOSE AND DISCUSSION:
3.1 Purpose
This procedure provides instructions to be followed in the event of a component malfunction which could degrade the.sbility to provide shutdown cooling or safety injection flow.
3.2 Discussion
- 1. No single active component failure will prevent the system from performing its design functions. However, manual action may be required to maintain maximum system effectiveness.
- 2. Operation with a partial system means only that the cooldown process will take a longer period of time.
- 3. The "A" and "B" trains of the SDC system are two separate and distinct systems. The only cross-connect between the two trains is MV-3545. This valve connects the section of piping between MV-3481 and MV-3480 on the 2A Hot Leg suction line to that section of piping between MV-3651 and MV-3652 on the 2B Hot Leg suction line.
4.0 SYMPTCHS
4.1 The following are indications of SDC/LPSI System leakage.
- 1. Safeguards Room Sump High Level alarms.
- 2. Local visual leakage indications.
FOR INFOR?,1AT!DM ONLY]
This document is not c:ntroNed. 32:ce Lverify .
I use information with a controlled document.
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.P ga 2.cf 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION O '
SDC/LPSI 0FP NORMAL OPERATION 4.0 SYMPTOMS : (continued) 4.2 The following are indications of a loss of shutdown cooling capacity:
- 1. LPSI Pump trip.
- 2. SDC low flow as indicated by:
"A" Train "B" Train FI-3312 FI-3332 FI-3322 FI-3342 FIC-3306 FIC-3301
- 3. Increasing temperature on SDC Heat Exchanger outless as _,
indicated on:
"A" Train "B" Train TI-3303X TI-3303Z TI-3303W TI-3303Y TIR-3351 TIR-3352
- 4. LPSI Pump low discharge pressure as indicated on PI-3507 (2A LPSI Pump) or PI-3304 (2B LPSI Pump).
- 5. SDC High Pressure alarm A and/or B Trains.
5.0 INSTRUCTIONS
5.1 Immediate Automatic Actions:
5.1.1 SDC loop suction valves close on high pressure of 500 psig.
.Page 3 of 12. .
ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION 0 SDC/LPSI 0FF NORMAL OPERATION 1
5.0 INSTRUCTIOlS:l (continued) 5.2 If System leakage is indicated:
5.2.1 Immediate Operator Action: None ,
5.2.2 Subsequent Oparator Action.
- 1. Isolate affected portion of system.
- 2. Re-establish flow to core using remaining portion of system.
- 3. If leak cannot be isolated proceed to Step 5.3.
O
,Prgs 4 of,12 ST.2LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION 0 SDC/LPSI 0FF NORMAL OPERATION I
5.0 INSTRUCTIONS
(continued) 5.3 If a loss of SDC capacity has occurred:
5.3.1' Immediate Operator Ac' tion: None
~
5.3.2 Subsequent Operator Action.
- 1. Check LPSI Pumps operating and restart if necessary.
- 3. ' Check Intake Cooling Water flow t'o.be normal and if necessary increase ICW flow through the Heat Exchangers..
~^
- 4. Check ICW strainer for high d P.
- 5. ' Verify proper valve lineup as follows:
"A" SDC TRAIN VALVE NO. DESCRIPTION POSITION MV-3517 2A LPSI Pump disch to 2A SDC HX Open FCV-3306 2A SDC HX Bypass Flow Control Throttled MV-3456 SDC from 2A SDC HX Open HCV-3657 SDC from 2A SDC HX Flow Control Throttled
. MV-3615 LPSI Bdr disch to Loop 2A2 Open MV-3625 LPSI Hdr disch to Loop 2Al Open MV-3480 SDC Suction from Loop 2A Open MV-3481 SDC Suction from Loop 2A Open MV-3664 SDC Suction from Loop 2A Open "B" SDC TRAIN MV-3658 2B LPSI Pump Disch to 2B SDC HI Open FCV-3301 2B SDC HI Bypass Flow Control Throttled MV-3457 SDC from 2B SDC HX Open HCV-3512 SDC from 2B SDC HK Flow Control Throttled MV-3635 LPSI Hdr disch to Loop 2B1 Open MV-3645 LPSI Edr disch to Loop 2B2 Open MV-3652 SDC Suction from Loop 2B Open MV-3651 SDC Suction from Loop 2B open MV-3665 SDC Suction from Loop 2B Open
- .. . _. - . _ . - _ . . _ .- - - . = _ - .
Pega 5 cf 12
-ST. LUCLE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION 0 SDC/LPSI 0FF NORMAL OPERATION
5.0 INSTRUCTIONS
(continued) 5.3 (Cont.)
5.3.2. (Cont.)' *
- 6. If MV-3480 or MV-3481 ("A" SDC loop suction) or MV-3651 or MV-3652 ("B" SDC loop suction) have tripped closed due to high pressure, perform the following:
A. Stop both LPSI Pumps.
-B. Reduce RCS pressure to < 275 psig.
C. For loop "A" perform the following:
~'
1.) Open MV-3480 and MV-3481.
2.) Close HCV-3657 (2A SDC HX Flow Control).
3.) Throttle FCV-3306 (2A SDC HX Bypass Flow Control) to 5% open.
4.) Start 2A LPSI Pump. Slowly reopen FCV-33G6 to its original position and return to auto Control.
5.) Slowly open HCV-3657 to obtain desired heat exchanger flow.
- D. For loop "B" perform the following:
1.) Open MV-3651 and MV-3652. _
2.) Close HCV-3512 (2B SDC HX Bypass Flow Control).
3.) Throttle FCV-3301 (2B SDC HX Bypass Flow Control) to 5% open.
t 4.) Start 2B LPSI Pump. Slowly reopen FCV-3301 to its original position and return to auto Control.
5.) Slowly open HCV-3512 to obtain desired heat exchanger flow.
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Peg 2 6 cf 12 ST. LUCIE UNIT 2 i 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION O SDC/LPSI 0FF NORMAL OPERATION
)
5.0 INSTRUCTIONS
(continued) J 5.4 If a plant cooldown is in progress and shutdown cooling capability cannot be restored, perform the following:
5.4.1 Immediate Operator Action: None 5.4.2 Subsequent Operator Action. ,
- 1. Isolate the Shutdown Cooling System by closing the following valves:
MV-3481.(SDC suction from loop 2A)
MV-3480 (SDC suction from loop 2A)
MV-3651 (SDC suction from loop 2B) _ _ .
MV-3652 (SDC suction from loop 2B)
MV-3615 (LPSI hdr disch to loop 2A2)
MV-3625 (LPSI hdr disch to loop 2A1)
MV-3635 (LPSI hdr disch to loop 2B1)
MV-3645 (LPSI hdr disch to loop 2B2)
- 2. If the RCS is solid, rely on natural circulation flow, and do not start Reactor Coolant Pumps.
- 3. If a Pressurizer bubble is still established, increase .
RCS pressure to 400 psig and start at least one Reactor
-Coolant Pump in the "B" loop.
- 4. Establish feedwater flow to each Steam Generator using the Auxiliary Feedwater Pumps.
- 5. Re-establish cooldown using the Atmospheric Steam Dumps and proceed to Cold Shutdown.
l
. Page 7 of,12 ST. LUCIE UNIT 2 J
0FF-NORMAL OPERATING EROCEDURE NO. 2-0440030, REVISION 0 SDC/LPSI 0FF ' NORMAL OPERATION
5.0 INSTRUCTIONS
(continued) 5.5 If refueling operations are in progress and shutdown cooling capability cannot be restored, perform the followfug: ,
5.5.1 Immediate Operator Action: None 5.5.2 Subsequent Operator Action.
- 1. Stop refueling operations and restore Containment integrity.
- 2. Verify the Fuel Pool Cooling System is in operation per OP #2-0350020.
- 3. Line up to recirculate the refueling cavity with the Fuel -
Pool Purification Pump as follows: ,
A. Verify that the purification pump is stopped.
B. Position the following valves:
VALVE NO. DESCRIPTION POSITION V-4201 Fuel Pool skimmer suction Closed V-4220 Purification pump low suction Open-V-4222 Purification pump suction Open V-4226 Purification pump disch Open V-4228 Purification filter inlet Closed V-4229 Purification filter bypass Open V-4236 Fuel Pool IX inlet Closed -
V-4251 Fuel Pool IX bypass Open V-4252 Purification loop to fuel pool Closed V-7206 Purification loop to refueling cavity (outside Containment) Open V-7189 Purification loop to refueling cavity (inside Containment) Open C. Start the Purification Pump and verify flow from the Spent Fuel Pool to the refueling cavity. Return flow will be via the fuel transfer tube.
D. Continue this mode of operation until the Shutdown Cooling System can be returned to service.
I l
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Page 8 of 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION O SDC/LPSI 0FF NORMAL' OPERATION
5.0 INSTRUCTIONS
(continued) 5.6 Loss of Power to FCV-3306, FCV-3301, EvC-3657, HCV-3512, FIC-3306, or FIC-3301. ,
5.6.1 immediate Operator Action: ~None 5.6.2 Subsequent Operator Action.
- 1. .If FCV-3306 or FCV-3301 fail open, throttle the valve manually to maintain 3000 GPM flow to the RCS.
- 2. If HCV-3657 'or.HCV-3512 fail closed, throttle the valve manually to maintain RCS temperature as required on TR-3351.. .
- 3. If FIC-3306 fails resulting in loss. of flow indication and full opening of Fr.V-3306, or FIC-3301 fails which results in loss of flow indication and FCV-3301 failing full open, A. Throttle FCV-3306 or FCV-3301 manually.
B. Observe individual header flow instruments to maintain 1 3000 GPM.
2Al : FI-3322 2B2 : FI-3342 2A2 : FI-3312 2B1 : FI-3332
__ __ . - _ _ ___- _.w, . - , . _ - - . _ _ _ . _ ..w,_
Page 9 'of 12.
ST. LUCIE UNIT 2' 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION 0 SDC/LPSI OFF NORMAL OPERATION
5.0 INSTRUCTIONS
(continued) 5.7 If Shutdown Cooling capability is lost and the RCS level has dropped below the hot leg suction and/or the RCS has heated up excessively,
' reestablish shutdown c'ooling as follows:
5.7.1 Immediate Operator Action: None ,
5.7.2 Subsequent Operator Action.
- 1. Open MV-3536 or MV-3539 (associated warmup valve for LPSI pump to be started).
- 3. Throttle HCV-3615, HCV-3625, HCV-3635, and HCV-3645 (LPSI hdr valves).
- 4. Start the LPSI Pump. If the pump cavitates severely, open the suction valve further or stop the pump as necessary.
NOTE: Several start attempts (with several minutes between starts) may be required.
NOTE: During Step 5 below, reactor vessel level should be monitored closely.
- 5. When the pump is running satisfactorily, slowly close the LPSI suction valve and ensure suction from the RCS hot leg is adequate. Slowly close tre warmup valve and open .
the LPSI header valves as desired-v, , ,- - , - - , , , . w, -
Pa'ge 10 of 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-0440030, REVISION 0 SDC/LPSI 0FF NORMAL OPERATION
5.0 INSTRUCTIONS
(continued) 5.8 Loss of Power to A or B electrical trains.
5.8.1 Immed'iate Operator Action: None l 5.8.2 Subsequent Operator Action.
NOTE: MV-3545 (Hot leg suction cross-conn) is powered from 480V MCC 2AB. It is therefore essential for the operation of MV-3545 that the proper electrical lineup be ensured from the remaining operable electrical train. (See Figure 1). ;
- 1. Loss of power to "A" electrical train will cause loss
~'
of operability oi MV-3652, MV-3481, and MV-3664. SDC flow s_uction to che 2B LPSI Pump will then have to be ,
aligned through dV-3480, MV-3545, MV-3651, and MV-3665.
- 2. If MV-3545 is inoperable, ensure power is available by verifying the following breaker alignment in the given order:
BREAKER 480V SWITCHCEAR POSITION 2-40702 2AB Open 2-40220 2A2 Open '
2-40706 2AB Closed 2-40703 2AB Closed 2-40504 2B2 Closed 2-42404 2AB MCC Closed
- 3. Loss of Power to "B" electrical train will cause loss of operability of MV-3480, MV-3651, and MV-3665. SDC flow suction to the 2A LPSI Pump will then have to be aligned through MV-3652, MV-3545, MV-3481, and MV-3664.
l
- Page 11 of 12 pw==%g ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0440030, REVISION 0 ,
SJC/LPSIOFFNORMALOPERATION
5.0 INSTRUCTIONS
(continued) 5.8 (Cont.)
'5.8.2 (Cont.)
- 4. If MV-3545 is inoperable, ensure power is available by verifying the following breaker alignment in the given order:
BREAKER 480V SWITCHGEAR POSITION 2-40706 2AB Open 2-40504 2B2 Open 2-40702 2AB Closed _.
2-40703 2AB ,
Closed 2-40220 2A2 Closed 2-40404 2AB MCC Closed l
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1110031 '
REVISION O 1.- TITLE: Off-Normal Operation of the Condenser Air Ejector Monitor
- 2. PREPARED BY: B. W. Kelsey February 22 1983
- 3. SUBCOMMITTEE REVIEW BY: R. J. Frechette for FP&L PR February 22 1983
- 4. REVIEWED BY FRG ON: February 25 1983
- 5. APPROVED'BY: h (LvM ji Plant- Manager 1- 19 b __ .
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- 6. REVISION REVIEWED BY FRG ON: 19
- 7. APPROVED BY: Plant Manager 19 g,.,,.-----,-.,,,;,-,,,,, .
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Pcg2 1 of 3-FLORIDA POWER & LIGHT COMPANY l ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1110031 j h }4 3 REVISION 0 - *'M" .,8
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1.0 TITLE
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Off-Normal Operation of the Condenser Air Ejector Monitor 2.0 REVIEW AND APPROVAL:
Reviewed by Facility Review Group 2 M S 19 63 Approved by Ci [h k (LAffy hPlantManager 's '- 19 .7 3 V "
Revision Reviewed by FRG 19 Approved by~ Plant Manager 19 3.0 PURPOSE AND DISCUSSION:
3.1 Purpose This procedure provides instruction in the off-normal operation of the Condenser Air Ejector Process Monitor.
3.2 Discussion The Condenser Air Ejector Monitor measures non-condensable fission product gases in the condenser air ejector discharge to detect any primary-to-secondary leakage.
4.0 SYMPTOMS
4.1 Annunciation and alarm on the 3 system operator teminals and at the local skid (RS-26-11) 4.2 Respective channel ALERT, HIGH, or FAIL alarms (Channel EAG-403) 4.3 Increasing activity as noted on the channel graphic display histograms i
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. . Paga 2 of 3 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1110031, REVISION 0 OFF-NORMAL OPERATION OF THE CONDENSER AIR EJECTOR MONITOR
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- 5.0 INSTRUCTIONS: (4) 5.1 Immediate Automatic Action l j.' ,
5.1.1 None 5.2 Immediate Operator Action d l 5.2.1 Acknowledge system alarms and notify the Chemistry l Department. l 5.3 Subsequent Operator Action 5.3.1 For a valid high activity alarm: l 5.3.1.1 The condenser air ejector exhaust shall be manually shifted so that it is routed to the Plant Vent. __ .
, 5.3.1.2 Ensure that backup samples are taken.
1 5.3.1.3 Determination should be made for the source of the activity entering the secondary system and appropriate actions taken to isolate the source.
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5.3.1.4 Using available data, determination should also be i made as.to the relationship of the steam generator activity to the Tech. Spec. limit of 0.1 uc/gm dose equivalent iodine and of the primary-to-secondary ,
leak rate limit of 1 gpm.
5.3.2 Inoperable Monitor i 5.3.2.1 A backlighted blue or magenta light on the channel 1 indicates either a loss of power to the monitor ,
channel or a component failure in the detector or I the ratemeter. Ensure notification of responsible- !
personnel. l l
5.3.2.2 With the number of channels OPERABLE less than i required by the Minimum Channels OPERABLE I requirement, effluent releases.via this pathway may l- continue for up to 30 days provided grab samples are ta' ken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for Isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless air ejector is lined up to Plant Vent and i Plant Vent Monitor is operational, then releases may j
, continue indefinitely. l 1
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ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO.' 2-1110031, REVISION 0 0FF-NORMAL OPERATION OF THE CONDENSER AIR EJECTOR MONITOR
6.0 REFERENCES
-w 6.1. FSAR Chapters 11 and 12- - ", i j b .6 1 4
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6.2.' General Atomic Technical Manuals
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6.2.1 #E-115-1009, Airborne Radiation Monitors / /
6.3 PSL Technical Specifications 6.4 Chemistry Procedure 2-C-62B 7.0 RECORDS REQUIRED:
7.1 Normal log entries t
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12 13 .Tra.uting - Larry Baker 14 15 Tra4"*~g J. Spodick T. Vogan - GO G. J. Boissy R. R. Jennings l H. M. Mercer .
A. Fell R. J. Frechette R==4daac NRC NRC - II: HQ Actu: Chief, Nuclmar Respons anch C. Burns - CZ 8 .
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FLORIDA POWER & LIGHT COMPANY <
ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1110037 I 3 3
REVISION 0 ; '
- 1. TITLE: Off-Normal Operation of the Steam Generator Blowdown Process Monitors A and B
- 2. PREPARED BY: B. W. Kelsey March 22 1983
- 3. SUBCOMMITTEE REVIEW BY: R. J. Frechette for FP&L PR March 22 1983
- 4. REVIEWED BY FRG ON: February 25 1983 _,
- 5. APPROVED BY:
h ant Manager "3 " 1.- 1983 V i
- 6. REVISION REVIEWED BY FRG ON: 19
- 7. APPROVED BY: Plant Manager 19
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 *ec 3 f 't ~
OFF-NORMAL OPERATING PROCEDURE NO. 2-1110037 / J' '
REVISION O c )~ i
1.0 TITLE
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Off-Normal Operation of the Steam Generator Blowdown Process Monitors A and B i
2.0 REVIEW AND APPROVAL:
Reviewed by Facility Review Group Fd m ua25 3 19 Approved by G [M%LA'\/ M ant Manager . / '1 -
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Revision Reviewed by FRG 19 Approved by Plant Manager 19 3.0 PURPOSE AND DISCUSSION:
3.1 Purpose This procedure provides instruction in the off-normal operation of the Steam Generator Blowdown Process Monitors. It does not provide instructions for corrective action for the Steam Generators.
3.2 Discussion The Steam Generator Blowdown Process Radiation Monitors are designed to provide an indication of the radioactivity in the blowdown affluent to the Discharge Canal or the S.G.B.T.F. If the radioactivity in the blowdown of a steam generator reaches the altra setpoint, the process monitor will alarm and send a shut signal to valves in the bicadown piping to terminate the release of the alarming steam generator. The shut signal will also close automatic valves in the Steam Generator-Sampling Lines, thereby isolating the process monitor from the steam generator. The process monitor will then record only the STAGNANT sample left in the isolated piping, so I just because the ratemeter is stable it does not mean that the activity buildup in the steam generator is stable. The alarm on the Steam Generator Blowdown Process Monitor may have either been preceeded or followed by an alarm on the Air Ejector Radiation Process Monitor. The Air Ejector Process Monitor will be the only indication of a possible buildup of radioactivity in an alarming S/G whose Process Monitor has been isolated by a "HIGH" alarm. A S/G ,
' Process Radiation Monitor alarm is indicative of a Primary to Secondary Leak in the S/G. This is the only source that would cause a valid alarm. .
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ST. LUCIE UNIT i .
OFF-NORMAL OPERATING PROCEDURE NO. 2-1110037, REVISION 0 4 fw, j OFF-NORMAL OPERATION OF THE STEAM GENERATOR BLOWDOWN PROCESS MONITORS A AND B gj ,j
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4.0 SYMPTOMS
'[ ,p j 4.1 Annunciation and alam on the three system operator terminals and at "y ?
h each local skid (RS-26-5.and 26-6).
- 4.2 Respective channel ALERT, HIGH, or FAIL alarms channel PLP-121 -
(S/G 2A) or channel PLP-122 (S/G 2B).
4.3 Increasing activity as noted on the channel graphic display hiseograms.
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ST. LUCIE UNIT 2 m s OFF-NORMAL OPERATING PROCEDURE NO. 2-1110037, REVISION 0 ./ '
OFF-NORMAL OPERATION OF THE STEAM GENERATOR BLOWDOWN PROCESS MONITORS A AND 3 ! t'
~ 5.0 INSTRUCTIONS:
5.1 Immediate Automatic Action ..
5 .1.1~ Steam generator blowdown.and sample valves FCV-23-3 and 23 #5 --- ~ =I shut if-the 2A steam generator is affected. . Valves FCV-23 and 23-9 shut if the 2B steam generator is affected.
5.2 .Immediate Operator Action 5.2.1 Acknowledge system alarms and notify the Chemistry Department.
5.3 Subsequent Operator Action 5.3.1 For a valid high activity alarm:
5.3.1.1 Verify that valves FCV-23-3 #nd 23-7 for S/G 2A or valves FCV-23-5 and 23-9 for S/G 2B have shut to secure the blowdown.
5.3.1.2 Check the condenser air ejector monitor to determine the possible extent of leakage into the secondary system.
5.3.1.3 Ensure samples are taken and analyzed to determine the activity levels.
5.3.1.4 If both S/G process monitors are alarming "HIGH",
consider the possibility of abnormally.high background radiation in the vicinity of the detectors.
5.3.1.5 Using available data obtained, determination should be made as to the relationship of the steam generator activity to the Tech Spec limit of 0.1 uc/gm dose equivalent iodine and of the primary-to-secondary leak race limit of 1 gpm.
5.3.1.6 Do not reinitiate blowdown to the discharge canal or to the S.G.B.T.F. without direction from the Chemistry Department. Either of these actions could result in an uncontrolled release.
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ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1110037, REVISION 0 OFF-NORMAL OPERATION OF THE STEAM GENERATOR BLOWDOWN PROCESS MONITORS A AND B ,
5.0 INSTRUCTIONS
(continued)
"""# r-)i ia AY ai 5.3 (continued) ^
.I 5.3.2 -Inoperable Monitor &= g 3
5.3.2.1 A backlighted blue or magenta light on the applicable channel indicates either a loss of power to the monitor channel or a component failure in the detector or.the ratemeter. Ensure notification of responsible personnel.
5.3.2.2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta o alimitofdetectionofatlesst2x10~fgamma)and _ _ .
microcuries/ gram:
- a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT-I-131. +
6.0 REFERENCES
6.1 FSAR Chapters 11 and 12 6.2 General Atomic Technical Manuals 6.2.1 E-115-1008 Liquid Process Radiation Monitors 6.3 PSL Technical Specifications 6.4 Chemistry Procedure 2-C-62C i 7.0 RECORDS REQUIRED:
'7.1 Normal log entries 4
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