ML030730736
| ML030730736 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/18/2002 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0094 AOP-10, Rev 0 | |
| Download: ML030730736 (18) | |
Text
POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 1 of 18 A. PURPOSE
- 1. To provide the operators with the instructions required to maintain Hot Shutdown in the event conditions in the Control Room require evacuation as deemed necessary by the Control Room staff.
The following assumptions apply to this procedure:
a Offsite power is available.
- All controls are operational and no failures are expected to occur to the control board which precludes the safe operation of equipment from outside the Control Room.
- No other accident condition exist requiring use of the Emergency Operating Procedures or any other Abnormal Operating Procedure.
- Both Units are it power. Mode 1.
B. SYMPTOMS OR ENTRY CONDITIONS
- 1. The following are entry conditions for this proceduie:
- a. Toxic gas in the Control Room. requiring evacuation.
- b. Confirmed bomb threat in or adjacent to the Control Room requiring evacuation.
- c. Other life threatening conditions. as determined by the DSS or his designee. that cause the Control Room to be uninhabitable.
C. REFERENCES
- 1. General Design Criteria #19
- 2.
Technical Specifications for Point Beach Nuclear Plant
- 3.
FSAR for Point Beach Nuclear Plant
- 4.
DBD-O1. Auxiliary Feedwater
- 5.
DBD-04. Chemical And Volume Control System tnt c a-Lo9
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POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 2 of 18 sTEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTES
" Steps in this procedure may be performed out of order as deemed necessary by the DSS or his designee.
" Entry into EOP-0.
REACTOR TRIP OR SAFETY INJECTION.
is not required.
Initiate Manual Reactor Trip For Both Units
"* Unit 1 Reactor
- TRIPPED
"* Unit 2 Reactor.- TRIPPED 2
Ensure Both Units Turbine - TRIPPED*
"* Unit 1 Turbine TRIPPED
"* Unit 2 Turbine TRIPPED 3
Shut Main Steam Isolation Valves
"* IMS-2018
"* lMS-2017
"* 2MS-2018
"* 2MS-2017 4
Adjust Atmospheric Steam Dump Controllers To 1005 PSIG"
"* 1HC-468
"* 1HC-478
"* 2HC-468
"* 2HC-478" 5
Align Charging Pump Suctions To RWST:.
- 2CV-112B
POINT BEACH NUCLEAR PLANT AOP-10 POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 3 of 18 SI ACTION/EXPECTED RESPONSE 6
Start Turbine-Driven AFW Pumps
- 2P-29 7
Place Motor-Driven AFW Discharge Valves In - MANUAL PULLOUT AND CLOSE
"* AF-4021 for S/G 1B AF-4022 for S/G 2A RESPONSE NOT OBTAINED 8
Stop Main Feedwater Pumps And Place Control Switches In -
AUTO S
0 S
S IP-28A 1P-28B 2P-28A 2P-28B 9
Stop Heater Drain Tank Pumps S
S U
0 S
1P-27A 1P-27B 1P-27C 2P-27A 2P-27B 2P-27C 10 Ensure Only One Condensate Pump Running Per Unit o P-25A OR o P-25B 11 Evacuate Control Room And Obtain Copies Of This Procedure From The Work Control Center 12 Notify CAS Of Control Room Evacuation CAUTION Placing Main Feed Pump control switches in pull-out will defeat auto start of the Motor Driven AFW pumps.
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POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 4 of 18 IsTE II ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I
13 Dispatch Four Licensed Operators To Perform Local Actions:
- a. Attachment A. Unit 1 AFW PUMP OPERATOR
- b. Attachment B. Unit 2 AFW PUMP OPERATOR
- c. Attachment C. UNIT I CHARGING PUMP OPERATOR
- d. Attachment D. UNIT 2 CHARGINQ PUMP OPERATOR 14 Dispatch Operators To Perform Local Actions:
- a. Attachment E. TURBINE HALL OPERATOR
- b. Attachment F.
PAB OPERATOR 15 Direct STA To Report To TSC And Implement Emergency Plan
- 16 Locally Monitor Operating Equipment Until Control Room Can Be Re-Entered
- 17 Check Control Room - HABITABLE WHEN Control Room can be re-entered.
THEN go to EOP-O, REACTOR TRIP OR SAFETY INJECTION.
-END-t
POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 5 of 18 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (Page 1 of 2)
Unit 1 AFW PUMP OPERATOR CAUTION To prevent AFW pump damage, monitor and maintain minimum AFW discharge flow greater than 75 gpm or stop the affected AFW Pump as necessary to control S/G levels.
Al Check Turbine-Driven AFW Pump Direct PAB Operator to locally align RUNNING steam supply to turbine-driven AFW pump:
"1P-29 "o Locally open B S/G steam supply valve.
a 1MS-2019 "o Locally open A S/G steam supply valve.
l IMS-2020 A2 Manually Control A S/G Level:
- a. Engage clutch and throttle IAF-4001 to maintain S/G level
-BETWEEN 300 INCHES AND 330 INCHES
- ILI-460-AA on 1RK-38 e ILI-460-BA on IRK-38 A3 Manually Control B S/G Level:
- a. Engage clutch and throttle IAF-4000 to maintain S/G level
-BETWEEN 300 INCHES AND 330 INCHES
- ILI-470-AA on IRK-38
- 1LI-470-BA on 1RK-38
POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY STEp ACTION/EXPECTED RESPONSE I
RESPONSE NOT OBTAINED ATTACHMENT A (Page 2 of 2)
Unit I AFW PUMP OPERATOR A4 Maintain S/G Levels Between 300 Inches And 330 Inches Using Turbine-Driven AFW Pump
.1 7
"I IF level can NOT be maintained using turbine-driven AFW pump.
THEN maintain SIG "1A" level using motor-driven AFW pump as follows:
- a. At N-01. place P-38A in
- LOCAL.
- b. At N-01. depress start pushbutton.
- c. Open AF-4023.
- d. Throttle IAF-31 to maintain "lA" SIG level -
BETWEEN 300 INCHES AND 330 INCHES ILI-460AA 1LI-460BA
- e. Inform DOS that "IB" S/G Atmospheric Steam Dump should be isolated.
lMS-2015 A5 Inform DOS That SIG Levels Are BETWEEN 300 INCHES AND 330 INCHES "END-AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 6 of 18 I
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POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 7 of 18 L~ziI ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINEDI ATTACHMENT B (Page 1 of 2)
Unit 2 AFW PUMP OPERATOR CAUTION To prevent AFW pump damage, monitor and maintain minimum AFW discharge flow 0
greater than 75 gpm or stop the affected AFW Pump as necessary to control S/G levels.
B1 Check Turbine-Driven AFW Pump -
Direct PAB Operator to locally align RUNNING steam supply to turbine-driven AFW pump:
2P-29 "o Locally open B S/G steam supply valve.
a 2MS-2019 "o Locally open A S/G steam supply valve.
- 2MS-2020 B2 Manually Control A S/G Level:
- a. Engage clutch and throttle 2AF-4001 to maintain S/G level
-BETWEEN 300 INCHES AND 330 INCHES e 2LI-460-AA on 2RK-38 o 2LI-460-BA on 2RK-38 B3 Manually Control B S/G Level:
- a. Engage clutch and throttle 2AF-4000 to maintain S/G level
-BETWEEN 300 INCHES AND 330 INCHES
- 2LI-470-AA on 2RK-38
- 2L1-470-BA on 2RK-38
POINT BEACH NUCLEAR PLANT AOP-10 POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 8 of 18 I
I ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED ATTACHMENT B (Page 2 of 2)
Unit 2 AFW PUMP OPERATOR B4 Maintain SIG Levels Between 300 Inches And 330 Inches Using Turbine-Driven AFW Pump IF level can NOT be maintained using turbine-driven AFW pump. THEN maintain SIG "2B" level using motor-driven AFW pump as follows:
- a. At N-01. place P-38B in - LOCAL.
- b. At N-OI. depress start pushbutton.
- c.
Open AF-4020.
- d. Throttle AF-45 to maintain "2B" SIG level -
BETWEEN 300 INCHES AND 330 INCHES
- e. Inform DOS that "2A" S/G Atmospheric Steam Dump should be isolated.
-END-
_EP I
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POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY AOP -10
[TEPj ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (Page I of 2)
UNIT I CHARGING PUMP OPERATOR C1 Ensure Charging Pump Suction ALIGNED TO RWST:
- RWST to charging pump suction M0V OPEN I
- a. Open RWST to charging pump suction.
1 lCV-358
"m 1CV-112C
- ICV-112C C2 Check PZR Pressure - BETWEEN Locally operate back-up heaters to 2200 PSIG AND 2250 PSIG maintain PZR pressure - BETWEEN 2200 PSIG AND 2250 PSIG
- PI-449B o Bank C o Bank D CAUTION Placing pressurizer heaters in local defeats heater low level cutout.
I AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 9 of 18 I
POINT BEACH NUCLEAR PLANT ABNORM+/-AL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY LSTE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (Page 2 of 2)
UNIT 1 CHARGING PUMP OPERATOR C3 Check If Letdown Should Be Established:
- a.
Check PZR level -
GREATER THAN 16% AND RISING
- LI-433C
- b. Establish letdown:
- 2) Locally open letdown isolations as necessary
- a.
WHEN PZR level greater than 16%.
THEN do Step C3.b.
- b. Perform the following:
a) Operate charging pumps as necessary to maintain PZR level -
BETWEEN 20% AND 45%
01-15.
CHARGING PUMP LOCAL CONTROL STATION OPERATION b) Go to Step C5.
"o ICV-200A "o 1CV-200B "o 1CV-200C NOTES
- PZR level may require time to stabilize after letdown restoration.
- Charging pumps should remain running in auto/remote if possible.
C4 Check PZR Level - BETWEEN 20% AND Operate charging pumps as necessary, 25%
to maintain PZR level-BETWEEN 20% AND 45%.
01 15.
CHARGING PUMP LOCAL CONTROL STATION OPERATION C5 Inform DOS Of The Following:
"* PZR level PZR pressure
"-END-I AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 10 of 18
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POINT BEACH NUCLEAR PLANT AOP-1O ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 11 of 18 I ACTION/EXPECTED RESPONSE IL RESPONSE NOT OBTAINED ATTACHMENT D (Page 1 of 2)
UNIT 2 CHARGING PUMP OPERATOR D1 Ensure Charging Pump Suction ALIGNED TO RWST:
RWST to charging pump suction MOV OPEN
- a.
Open RWST to charging pump suction.
- 2CV-112C D2 Check PZR Pressure - BETWEEN 2200 PSIG AND 2250 PSIG DTLO Locally operate back-up heaters to maintain PZR pressure - BETWEEN 2200 PSIG AND 2250 PSIG o Bank C o Bank D L-J
-A I
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POINT BEACH'NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY ONSE NOT OBTAINED D4 Check PZR Level -
BETWEEN Operate charging pumps as necessary 20% AND 25%
to maintain PZR level-BETWEEN 20% AND 45%.
- LI-433C
- 01 15.
CHARGING PUMP LOCAL CONTROL STATION OPERATION D5 Inform DOS Of The Following:
PZR level
- PZR pressure
-END-AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 12 of 18 I
TE ACTION/EXPECTED RESPONSE PIESP ATTACHMENT D (Page 2 of 2)
UNIT 2 CHARGING PUMP OPERATOR D3 Check If Letdown Should Be Established:
- a. Check PZR level -
GREATER THAN
- a. WHEN PI 16% AND RISING THEN d
- LI-433C
- b. Establish letdown:
- b. Perfor:
- 1) Inside 2B52-427J. locally open a) Opel letdown line isolation neci levi
- 2RC-427 O
- 2) Locally open letdown C
isolations as necessary b) Go o 2CV-200A o 2CV-200B o 2CV-200C ZR level greater than 16%.
o Step D3.b.
n the following:
rate charging pumps as essary to maintain Pzr el -
BETWEEN 20% AND 45%
[-15..CHARGING PUMP LOCAL ONTROL.STATION OPERATION to Step D5.
AOP-10 POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM4 INACCESSIBILITY L!LEJ ACTION/EXPECTED RESPONSERE ATTACHMENT E (Page 1 of 3)
TURBINE HALL OPERATOR NOTE All or some of the actions performed in this attachment may have been performed in the control room prior to evacuation.
El Check Both Reactors Tripped Prior To Evacuating Control Room
- Unit 1 Reactor - TRIPPED
- Unit 2 Reactor -
TRIPPED I lP-28A 1 lP-27A Steam.Generator Feed Pump Heater Drain Tank Pump
- lP-27C Heater Drain Tank Pump Perform the following:
- a. Open reactor trip breakers for BOTH UNITS.
- Unit I reactor trip breakers OPEN
- Unit 2 reactor trip breakers OPEN
- b. Open reactor trip bypass breakers for BOTH UNITS.
"* Unit 1 reactor trip bypass breakers - OPEN
"* Unit 2 reactor trip bypass breakers - OPEN Perform the following:
- a. At Unit 1 Front Standard. rotate trip lever to trip position.
- b. At Unit 2 Front Standard. rotate trip lever to trip position.
Locally open breakers as necessary per Attachment H. LOCAL.BREAKER OPERATIONI
"* 1A52"05 "4 1A52"OB
¶A-).flO E2 Check Both Turbines Tripped Prior Ti Evacuating Control Room
- Unit I Turbine - TRIPPED
- Unit 2 Turbine - TRIPPED E3 Inform DOS Both Reactors And Both Turbines Are Tripped E4 At IA01.
Check The Following Pumps Stopped Prior To Evacuating The Control Room:
AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 13 of 18 PONSE NOT OBTAINED
POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY tSTEP ACTION/EXPECTED RESPONSE PRESPONSE NOT OBTAINED ATTACHMENT E (Page 2 of 3)
TURBINE HALL OPERATOR E5 At 1A02.
Check The Following Pumps Stopped Prior To Evacuating The Control Room:
"* IP-28B Steam Generator Feed Pump "l P-27B Heater Drain Tank Pump E6 At 2A01.
Check The Following Pumps Stopped Prior To Evacuating The Control Room:
"* 2P-28A
"* 2P-27A
"* 2P-27C Steam Generator Feed Pump Heater Drain Tank Pump Heater Drain.Tank Pump E7 At 2A02.
Check The Following Pumps Stopped Prior To Evacuating The Control Room:
9 2P-28B Steam Generator Feed Pump
- 2P-27B Heater Drain Tank Pump ES At IA01 or IA02.
Check One Unit 1 Condensate Pump Breaker - OPEN Locally open breakers as necessary per Attachment H. LOCAL BREAKER OPERATION.
"* IA52-13
"* 1A52-10 Locally open breakers as necessary per Attachment H. LOCAL BREAKER OPERATION.
"* 2A52-23
"* 2A52-20
"* 2A52-19 Locally open breakers as necessary per Attachment H. LOCAL BREAKER OPERATION.
"* 2A52-30
"* 2A52-33 Locally open breaker per Attachment H. LOCAL BREAKER OPERATION.
o 1A52-07 for 1P-25A OR o 1A52-11 for 1P-25B E9 At 2A01 or 2A02.
Check One Unit 2 Condensate Pump Breaker - OPEN Locally open breaker per Attachment H. LOCAL BREAKER OPERATION.
o 2A52"21 for 2P-25A OR o 2A52-32 for 2P-25B E10 Inform DOS Of The Following:
- Main Feedwater ppmps -
STOPPED
- Heater Drain Tank pumps -
STOPPED
- One Condensate pump -
RUNNING AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 14 of 18 I
POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 15 of 18 SIACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (Page 3 of 3)
TURBINE HALL OPERATOR Eli Check CST Level -
GREATER THAN 15 FT Direct Water Treatment Operator to commence filling CST.
"* LI-4025 for T-24A
"* LI-4031 for T-24B
-END-
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POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY AOP -10 AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 16 of 18 RESPONSE NOT OBTAINED ACTION/EXPECTED RESPONSE ATTACHMENT F (Page 1 of 1)
PAB OPERATOR F1 Check Unit 1 MSIVs Were Shut Prior To Control Room Evacuation
"* IMS-2018 for SIG 1A
"* IMS-2017 for S/G 1B F2 Check Unit 2 MSIVs Were Shut Prior To Control Room Evacuation
- 2MS-2018 for S/G 2A
- a. At IRK-33.
depress both pushbuttons.
- IMS PB-2018A. train A
- IMS PB-2018B. train B
- b. At IRK-34.
depress both pushbu~tons.
- iMS PB-2017A. train A
- a. At 2RK-33. depress both pushbuttons.
- 2MS PB-2018A. train A
- 2MS PB-2018B. train B
- b. At 2RK-34. depress both pushbuttons.
- 2MS PB-2017A. train A
- Open Bkr. IB52-328F for AF-4023
- Open Bkr. 2B52-328C for AF-4022
- DE-ENERGIZED Unit 2 Discharge
-END-I I
POINT BEACH NUCLEAR PLANT AOP-10 ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 17 of 18
- LSTEP, ACTION/EXPECTED RESPONSE ATTACHMENT G (Page 1 of 1)
DOS CHECKLIST G1 Check the following Unit 1 actions completed:
Unit 1 ACTION PERFORMED Reactor tripped Motor-Driven AFW pump discharge valves breakers open PZR level -
20% to 45%
PZR pressure - 2200 PSIG to 2250 PSIG Turbine tripped Both Main Feedwater Pumps stopped All Heater Drain Pumps stopped One Condensate Pump running All S/G levels between 300 inches and 330 inches G2 Check the following Unit 2 actiong completed:
Unit 2 ACTION PERFORMED Reactor tripped Motor-Driven AFW pump discharge valves breakers open PZR level - 20% to.45%
PZR pressure - 2200 PSIG to 2250 PSIG Turbine tripped Both Main Feedwater Pumps stopped All Heater Drain Pumps stopped One Condensate Pump runnin, All S/G levels between 300 inches and 330 inches.
-END-
- COMPLETED
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RESPONSE NOT OBTAINED
POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT ABNOPRMAL OPERATING PROCEDURE CONTROL ROOM INACCESSIBILITY AOP-10 SAFETY RELATED Revision 0 2/18/2002 Page 18 of 18 SEP~jI ACTION/EXPECTED RESPONSE I
RESPON ATTACHMENT H (Page 1 of 1)
LOCAL BREAKER OPERATION Hi Local Opening Of A 4160 Vac Breaker:
- a. Open breaker cubicle door.
- b. Check mechanical indicator indicates closed.
- c.
Open breaker by performing one of the following:
o Depress trip/open push plate.
OR "o Depress trip/open button.
OR "o Lift red tab on open coil.
- d. Check mechanical indicator indicates open.
- e. Close breaker cubicle door.
H2 Local Opening 0f A 480 Vac Breaker:
- a. Check mechanical indicator indicates closed.
- b. Depress square trip push button.
- c. Check mechanical indicator indicates open.
-END-3E NOT OBTAINED I
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