ML030730736

From kanterella
Jump to navigation Jump to search
Pages 1-18 of Abnormal Operating Procedure AOP-1 0, Control Room Inaccessibility
ML030730736
Person / Time
Site: Point Beach  NextEra Energy icon.png
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)
v • d • e


Text

POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORMAL OPERATING PROCEDURE 2/18/2002 Revision 0 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 f /

tntc a- Lo9 ý /_c

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:.

a. Open RWST to charging pump suction MOV's

- 2CV-112B

b. Shut VCT outlet to charging pump suction MOV's 9 1CV-112C e 2CV-112C

POINT BEACH NUCLEAR PLANT AOP-10 AOP-10 POINT BEACH NUCLEAR PLANT SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 3 of 18 CONTROL ROOM INACCESSIBILITY RESPONSE NOT OBTAINEDSI ACTION/EXPECTED RESPONSE I 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

. CAUTION Placing Main Feed Pump control switches in pull-out will defeat auto start of the Motor Driven AFW pumps.

8 Stop Main Feedwater Pumps And Place Control Switches In - AUTO S IP-28A 0 1P-28B S 2P-28A S 2P-28B 9 Stop Heater Drain Tank Pumps 1P-27A S 1P-27B S 1P-27C U 2P-27A 0 2P-27B S 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

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. *
  • 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 "oLocally open A S/G steam supply valve.

IMS-2020 l

  • 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 *
  • 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 *
  • POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 6 of 18 CONTROL ROOM INACCESSIBILITY STEp ACTION/EXPECTED RESPONSE I II RESPONSE NOT OBTAINED I ATTACHMENT A (Page 2 of 2)

Unit I AFW PUMP OPERATOR IF level can NOT be maintained using A4 Maintain S/G Levels Between turbine-driven AFW pump. THEN 300 Inches And 330 Inches Using maintain SIG "1A" level using Turbine-Driven AFW Pump motor-driven AFW pump as follows:

a. At N-01. place P-38A in - LOCAL.
b. At N-01. depress start pushbutton.

.1 c. Open AF-4023.

d. Throttle IAF-31 to maintain "lA" 7 SIG level - BETWEEN 300 INCHES AND 330 INCHES

- ILI-460AA "I - 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-

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 II 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 "oLocally open B S/G steam supply valve.

a 2MS-2019 "o Locally open A S/G steam supply valve.

  • B2 Manually Control A S/G Level: *
  • a. Engage clutch and throttle *
  • -BETWEEN 300 INCHES AND *
  • 330 INCHES *
  • B3 Manually Control B S/G Level: *
  • a. Engage clutch and throttle *
  • -BETWEEN 300 INCHES AND *
  • 330 INCHES *
  • POINT BEACH NUCLEAR PLANT AOP-10 POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 8 of 18 CONTROL ROOM INACCESSIBILITY I I

_EP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I I

ATTACHMENT B (Page 2 of 2)

Unit 2 AFW PUMP OPERATOR IF level can NOT be maintained using B4 Maintain SIG Levels Between turbine-driven AFW pump. THEN 300 Inches And 330 Inches Using maintain SIG "2B" level using Turbine-Driven AFW Pump 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.
  • 2MS-2016 B5 Inform DOS That SIG Levels Are BETWEEN 300 INCHES AND 330 INCHES

-END-

AOP -10 POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 9 of 18 CONTROL ROOM INACCESSIBILITY RESPONSE NOT OBTAINED

[TEPj ACTION/EXPECTED RESPONSE I

ATTACHMENT C (Page I of 2)

UNIT I CHARGING PUMP OPERATOR Align charging pump suction to RWST:

C1 Ensure Charging Pump Suction ALIGNED TO RWST: a. Open RWST to charging pump suction.

  • RWST to charging pump suction M0V

- OPEN lCV-358 1

1CV-112B I b. Shut VCT to charging pump suction MOV.

  • ICV-112C CAUTION Placing pressurizer heaters in local defeats heater low level cutout.
  • C2 Check PZR Pressure - BETWEEN Locally operate back-up heaters to
  • maintain PZR pressure - BETWEEN *

. 2200 PSIG AND 2250 PSIG

  • PI-449B I

, o Bank C

, o Bank D

  • POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORM+/-AL OPERATING PROCEDURE Revision 0 2/18/2002 Page 10 of 18 CONTROL ROOM INACCESSIBILITY RESPONSE NOT OBTAINED LSTE ACTION/EXPECTED RESPONSE I

ATTACHMENT C (Page 2 of 2)

UNIT 1 CHARGING PUMP OPERATOR C3 Check If Letdown Should Be Established:

a. WHEN PZR level greater than 16%.
a. Check PZR level - GREATER THAN THEN do Step C3.b.

16% AND RISING

- LI-433C

b. Perform the following:
b. Establish letdown:

a) Operate charging pumps as

1) Inside 1B52-426M. locally open necessary to maintain PZR letdown line isolation level - BETWEEN 20% AND 45%

1IRC-427 01-15. CHARGING PUMP LOCAL CONTROL STATION OPERATION

2) Locally open letdown isolations as necessary 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%.

-I I*" n'

-aT

    • *- 01 15. CHARGING PUMP LOCAL CONTROL

, STATION OPERATION C5 Inform DOS Of The Following:

"* PZR level

"*PZR pressure

"-END-

POINT BEACH NUCLEAR PLANT AOP-1O ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 11 of 18 L-J I ACTION/EXPECTED RESPONSE IL RESPONSE NOT OBTAINED I ATTACHMENT D (Page 1 of 2)

UNIT 2 CHARGING PUMP OPERATOR D1 Ensure Charging Pump Suction Align charging pump suction to RWST:

ALIGNED TO RWST:

a. Open RWST to charging pump

"*RWST to charging pump suction MOV suction.

- OPEN

b. Shut VCT to charging pump suction

"*VCT outlet to charging pump MOV.

a suction MOV - SHUT

  • D2 Check PZR Pressure - BETWEEN Locally operate back-up heaters to *
  • 2200 PSIG AND 2250 PSIG maintain PZR pressure - BETWEEN *

-A

, DTLO

,- o Bank C

, o Bank D

AOP-10 POINT BEACH'NUCLEAR PLANT SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 12 of 18 CONTROL ROOM INACCESSIBILITY TE ACTION/EXPECTED RESPONSE PIESP ONSE NOT OBTAINED I 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 PIZR level greater than 16%.

16% AND RISING THEN d o Step D3.b.

- LI-433C

b. Establish letdown: , b. Perfor:n the following:

pumps as

1) Inside 2B52-427J. locally open a) Opel rate charging essary to maintain Pzr letdown line isolation neci AND 45%

leviel - BETWEEN 20%

  • 2RC-427 [-15..CHARGING PUMP LOCAL O
2) Locally open letdown CONTROL.STATION OPERATION isolations as necessary b) Go to Step D5.

o 2CV-200A o 2CV-200B o 2CV-200C

  • 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-

POINT BEACH NUCLEAR PLANT AOP-10 AOP-10 RELATED SAFETY Revision 0 2/18/2002 ABNORMAL OPERATING PROCEDURE Page 13 of 18 CONTROL ROOM4 INACCESSIBILITY PONSE NOT OBTAINED L!LEJ ACTION/EXPECTED RESPONSERE ATTACHMENT E (Page 1 of 3)

TURBINE HALL OPERATOR NOTE attachment may have been performed All or some of the actions performed in this in the control room prior to evacuation.

Perform the following:

El Check Both Reactors Tripped Prior To Evacuating Control Room a. Open reactor trip breakers for BOTH UNITS.

  • Unit 1 Reactor - TRIPPED
  • Unit 2 Reactor - TRIPPED
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:

E2 Check Both Turbines Tripped Prior Ti Evacuating Control Room a. At Unit 1 Front Standard. rotate

  • Unit I Turbine - TRIPPED trip lever to trip position.
  • Unit 2 Turbine - TRIPPED b. At Unit 2 Front Standard. rotate trip lever to trip position.

E3 Inform DOS Both Reactors And Both Turbines Are Tripped Locally open breakers as necessary E4 At IA01. Check The Following Pumps per Attachment H. LOCAL.BREAKER Stopped Prior To Evacuating The OPERATIONI Control Room:

"*1A52"05 IlP-28A Steam.Generator Feed Pump "41A52"OB 1lP-27A Heater Drain Tank Pump ¶A-).flO

  • lP-27C Heater Drain Tank Pump
  • POINT BEACH NUCLEAR PLANT AOP-10 SAFETY RELATED ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 14 of 18 CONTROL ROOM INACCESSIBILITY PRESPONSE NOT OBTAINED tSTEP ACTION/EXPECTED RESPONSE ATTACHMENT E I (Page 2 of 3)

TURBINE HALL OPERATOR Locally open breakers as necessary E5 At 1A02. Check The Following Pumps per Attachment H. LOCAL BREAKER Stopped Prior To Evacuating The OPERATION.

Control Room:

"*IA52-13

"*IP-28B Steam Generator Feed Pump "*1A52-10 "l P-27B Heater Drain Tank Pump Locally open breakers as necessary E6 At 2A01. Check The Following Pumps per Attachment H. LOCAL BREAKER Stopped Prior To Evacuating The OPERATION.

Control Room:

"*2A52-23

"*2P-28A Steam Generator Feed Pump "*2A52-20

"*2P-27A Heater Drain Tank Pump "*2A52-19

"*2P-27C Heater Drain.Tank Pump Locally open breakers as necessary E7 At 2A02. Check The Following Pumps per Attachment H. LOCAL BREAKER Stopped Prior To Evacuating The OPERATION.

Control Room:

"*2A52-30 9 2P-28B Steam Generator Feed Pump "*2A52-33

- 2P-27B Heater Drain Tank Pump Locally open breaker per Attachment ES At IA01 or IA02. Check One Unit 1 H. LOCAL BREAKER OPERATION.

Condensate Pump Breaker - OPEN o 1A52-07 for 1P-25A OR o 1A52-11 for 1P-25B Locally open breaker per Attachment E9 At 2A01 or 2A02. Check One Unit 2 H. LOCAL BREAKER OPERATION.

Condensate Pump Breaker - OPEN o 2A52"21 for 2P-25A OR o 2A52-32 for 2P-25B E10 Inform DOS Of The Following:

  • Heater Drain Tank pumps - STOPPED
  • One Condensate pump - RUNNING

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-

, -I

POINT BEACH NUCLEAR PLANT AOP -10 AOP-10 RELATED SAFETY ABNORMAL OPERATING PROCEDURE Revision 0 2/18/2002 Page 16 of 18 CONTROL ROOM INACCESSIBILITY RESPONSE NOT OBTAINED I ACTION/EXPECTED RESPONSE I

ATTACHMENT F (Page 1 of 1)

PAB OPERATOR Shut Unit 1 MSIVs as follows:

F1 Check Unit 1 MSIVs Were Shut Prior To Control Room Evacuation a. At IRK-33. depress both pushbuttons.

"* IMS-2018 for SIG 1A

"* IMS-2017 for S/G 1B

  • IMS PB-2018A. train A
  • IMS PB-2018B. train B
b. At IRK-34. depress both pushbu~tons.
  • iMS PB-2017A. train A
  • IMS. PB-2017B. train B Shut Unit 2 MSIVs as follows:

F2 Check Unit 2 MSIVs Were Shut Prior To Control Room Evacuation 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
  • 2MS PB-2017B. train B F3 De-Energize Unit 1 Motor-Driven AFW Pump Discharge MOV's
  • Open Bkr. IB52-328F for AF-4023
  • Open Bkr. IB52-428C for AF-4021 F4 De-Energize Unit 2 Motor-Driven AFW Pump Discharge MOV's
  • Open Bkr. 2B52-428F for AF-4020 F5 Inform DOS Unit 1 And Unit 2 Discharge Motor-Driven AFW Pump MOV's - DE-ENERGIZED

-END-

AOP-10 POINT BEACH NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 17 of 18 LSTEP, ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT G (Page 1 of 1)

DOS CHECKLIST G1 Check the following Unit 1 actions completed:

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 C. ) 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:

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-

  • POINT BEACH NUCLEAR PLANT POINT BEACH NUCLEAR PLANT AOP-10 ABNOPRMAL OPERATING PROCEDURE SAFETY RELATED Revision 0 2/18/2002 CONTROL ROOM INACCESSIBILITY Page 18 of 18 J

SEP~jI ACTION/EXPECTED RESPONSE I RESPON 3E NOT OBTAINED I 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 "oDepress trip/open button.

OR "oLift 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-

Retrieved from "https://kanterella.com/w/index.php?title=ML030730736&oldid=2696402"