ML051300341

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1 to Emergency Operating Procedure AP-CR.1, Control Room Inaccessibility
ML051300341
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/26/2005
From: Marlow T
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AP-CR.1, Rev 21
Download: ML051300341 (18)
v • d • e


Text

1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC April 26, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, Thomas A. Marlow TAM/jdw xc:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

AP Index AP-CR. 1, Rev 21 aCC) "

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c:

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NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Tue 4/26/2005 9:19:19 am Page 1 of 2 INPUT PARAMETERS: TYPE:

PRAP STATUS VALUE(S):

EF. QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW.1 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP-CW.1 AP-ELEC.1 AP-ELEC2 AP-ELEC.3 AP-ELEC.13/15 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC.2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 LEAKAGE INTO THE COMPONENT COOUNG LOOP LOSS OF CCW DURING POVWER OPERATION LOSS OF CCW - PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW"VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)

LOSS OF BUS 13/15 LOSS OF SAFEGUARDS BUS 14/16 LOSS OF SAFEGUARDS BUS 17/18 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAUINSERTION RCCIRPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTM'rTY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WIlhOUT RX TRIP REQUIRED 017 06/30/2004 0612612002 019 06/30/2004 06/26/2002 016 06/30/2004 06/26/2002 021 04/26/2005 06/26/2002 014 06/30/2004 06/03/2002 005 04/1012005 02/27/2004 012 09/17/2004 04/1612003 028 01121/2005 06/26/2002 011 06/10/2004 06/26/2002 013 01/21/2005 06/2612002 001 06/30/2004 09/24/2003 009 01/21/2005 06/26/2002 008 01/21/2005 06/26/2002 016 06/30/2004 06/26/2002 018 06/2612002 04/16/2003 015 06/30/2004 06/26/2002 009 06/30/2004 04/16/2003 012 04/10/2005 21/20/51/2 006 02/25/2003 02/25/2003 017 06/30/2004 04/24/2003 017 06/30/2004 04/16/2003 012 06/30/2004 04/16/2003 011 06/30/2004 04/01/2002 017 03/18/2005 04/30/2003 019 04/30/2003 04/30/2003 015 04/05/2005 04/30/2003 004 04/10/2005 06/26/2002 021 09/17/2004 04121/2003 007 01/21/2005 1/120/50/3 06126/2007 06/26/2007 EF EF 06/26/2007 EF 06/6/2007 EF 06/03/2007 EF 02/27/2009 EF 04/16/2008 EF 06/26/2007 EF 06/26/2007 EF 06/2612007 EF 09/24/2008 EF 06/26/2007 EF 06/26/2007 EF 06/2612007 EF 04/16/2008 EF 06/26/2007 EF 04/16/2008 EF 01/22/2007 EF 02/2512008 EF 04/24/2008 EF 04/16/2008 EF 04/16/2008 EF 01/22/2007 EF 04/30/2008 EF 04/30/2008 04/30/2008 06/26/2007 04/21/2008 10131/2006 EF EF EF EF EF 014 04/10/2005 06/26/2002 06/26/2007

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NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Tue 4/26/2005 9:19:19 am Page 2 of 2 INPUT PARAMETERS: TYPE.

PRAP STATUS VALUE(S):

EF, QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 021 04t10/2005 06/26/2002 06/26/2007 EF AP-TURB.3 TURBINE VIBRATION 012 06/30/2004 06126/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 018 04110/2005 04/30/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 008 04/10/2005 06/26/2002 06/26/2007 EF PRAP TOTAL 34 GRAND TOTAL 34

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 1 of 14 GINNA STATION CONTROLLED COPY NUMBER 0Z3 IN EFFECTIVBLEAGE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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TITLE:

REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 2 of 14 A.

PURPOSE -

This procedure provides the guidance necessary to place and maintain the plant in a Hot Shutdown Condition in the event that a control room evacuation is necessary.

B.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. ER-SC.2, RESPONSE TO INTRUSION BY ADVERSARY, if the Shift Manager determines to evacuate the Control Room.
b.

ER-FIRE.0, CR RESPONSE TO FIRE ALARMS AND REPORTS, if the fire is in the Control Complex and affects Control Room Habitability or continued safe plant operation.

2. SYMPTOMS -

The symptoms of CONTROL ROOM INACCESSIBILITY are:

a.

Fire in the Control Complex, or

b.

Smoke in the Control Complex, or

c. Noxious Fumes in the Control Room.

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 3 of 14 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 0

Verify Reactor Trip:

o At least one train of reactor trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.

IF reactor trip breakers NOT open.

THEN perform the following:

a. Open Bus 13 and Bus 15 normal feed breakers.
b. Verify rod drive MG sets tripped.
c. Close Bus 13 and Bus 15 normal feed breakers.
d. Reset lighting breakers.

IF the Rx can NOT be tripped from the Control Room, THEN dispatch personnel to locally open the reactor trip breakers.

eVerify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine can NOT be tripped, THEN close both MSIVs.

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 4 of 14 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I NOTE:

Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

3 Evaluate Control Complex IF fire is NOT controllable, THEN Conditions:

perform the following:

o Verify no fire in progress

a. Place BOTH ARVs in AUTO. set at 1005 psig.
b. Manually close both MSIVs.
c. Trip both RCPs AND place in PULL-STOP.
d. Place both PRZR PORV switches to CLOSE.
  • PCV-430

. PCV-431C

e. Stop all charging pumps AND place in PULL-STOP.
f. Operating shift personnel proceed to Appendix R locker immediately outside the Control Room.
g. Go to ER-FIRE.1. ALTERNATIVE SHUTDOWN FOR CONTROL COMPLEX FIRE.

DO NOT continue in this procedure.

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY

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.PAGE 5 of 14 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED NOTE:

PPCS terminals may be used for monitoring and trending plant parameters.

4 Establish Local Operating Stations (Refer to ATT-7.0, -

ATTACHMENT CR EVAC) 5 Locally Verify Emergency AC.

Busses 14 And 18 -

ENERGIZED (STA in A D/G room at ELCP)

Consider restoration of emergency AC power using ER-FIRE.l. ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE.

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 6 of 14

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Locally Establish AFW Flow To S/Gs (HCO):

a. Transfer MDAFW pump LOCAL control to
b. Start MDAFW pumps -

RUNNING ANY PUMPS

b. Locally perform the following:
1) Open TDAFW pump steam supply valves at the steam header.

. MOV-3504A

. MOV-3505A

2) Insert pins in valve operators for TDAEW flow control valves to allow operation of valves.

. AOV-4297

. AOV-4298

3) Throttle TDAFW flow to each S/G to maintain approximately 350 inches wide range level.
4) Go to Step 7.
c. Verify MDAFW pump flow - LESS THAN 230 GPM PER RUNNING PUMP
c. Locally throttle MDAFW flow control valves to maintain flow less than 230 gpm per running pump.

. MOV-4007

. MOV-4008

d. Throttle MDAFP flow to each S/G to maintain approximately 350 inches wide range level.

. MDAFP A. MOV-4007

. MDAFP B. MOV-4008

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AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 7 of 14 ACTION/EXECTED RESPONSE ROT OBTAINED 7 Energize IPELIP (Switch At Bottom Of IBELIP)

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 8 of 14 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I

  • 8 Monitor RCS Temperature (IBELIP)
a. RCS Temperature - STABLE
  • a. IF RCS temperature THEN go to Step 9.

increasing.

IF RCS temperature decreasing, THEN perform the following:

1) Locally throttle that required to level stable.

AFW flow to maintain S/G

. TDAFW Pump AOV-4297

  • TDAFW Pump AOV-4298 A. MOV-4007 B. MOV-4008 to S/G A.

to S/G B.

2) IF cooldown continues. THEN close MSIVs as follows:

(locked valve key required) o S/G A

. Close IA to MSIV. V-5408A

  • Open vent valves. V-5471 AND V-5473 o S/G B

. Close IA to MSIV.

. Open vent valves.

AND V-5474 V-5409B V-5472

3) IF MDAEW pump available to feed S/Gs. THEN manually isolate steam supply to TDAFW pump.

. V-3504

. V-3505

b. Go to Step 10.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Monitor RCS Temperature (IBELIP)

a. RCS temperature -

INCREASING

a. To to Step 10.
b. Locally throttle S/G ARVs to stabilize RCS temperature.
c. IF ARVs NOT adequate, THEN perform the following:
1) Check open MSIVs or open MSIV bypass valves as necessary.

. S/G A, V-3615

. S/G B. V-3614

2) Open priming ejector steam supply root valve. V-3578
3) Throttle open selected priming ejector steam supply to 200 psig (PI-2019)
  • Priming ejector A. V-3581

. Priming ejector B. V-3580 10 Locally Establish Charging Flow Control (CO):

a. Transfer charging pump control to LOCAL
b. Verify at least one charging pump - RUNNING
c. Check PRZR level - GREATER THAN 13%

(charging pump room and AEW pump area, west wall)

b. Locally start one charging pump.
c. Locally increase charging pump speed to restore.PRZR level to greater than 13%.

IF necessary.

THEN locally start a second charging pump.

d. Locally control charging pump speed'and letdown orifices to restore PRZR level to 35%

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY 4

PAGE 10 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Locally Monitor PRZR Pressure PRESSURE STABLE (AFW pump area, west wall)

IF pressure increasing. THEN ensure RCS temperature and PRZR level stable.

IF pressure decreasing. THEN perform the following:

a. Transfer PRZR heater backup group to local control (MDAFW pump area).
b. Verify PRZR level greater than 13%.
c. Energize PRZR heater backup group.

12 Check SW Pumps -

AT LEAST ONE RUNNING IN EACH LOOP (CRF, Locally in the Screenhouse)

Locally close SW Pump breakers to establish one SW pump running in each loop.

o Loop A

. Bus 18 Position 29C. SW Pump A

  • Bus 17 Position 27C, SW Pump B o Loop B

. Bus 18 Position 29D. SW Pump C

  • Bus 17 Position 27D, SW Pump D

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Transfer CNMT Recirc Fan Control To LOCAL And Check -

AT LEAST TWO FANS RUNNING (At local operating stations by TDAFW pump)

  • 14 Monitor S/G Levels (AFW pump area, west wall):

o Levels - APPROXIMATELY 350 INCHES o

Levels - STABLE Establish two fans running.

Locally throttle AEW flows to maintain S/G level approximately 350 inches wide range level.

. MDAFW pump A, MOV-4007

. MDAEW pump B. MOV-4008

. TDAEW pump to S/G A, AOV-4297

  • TDAEW pump to S/G B. AOV-4298

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TITLE:I REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY

.PAGE 12 of 14 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED F 15 Establish CSD Xenon Free Boron Concentration:

a. Determine amount of boron required (Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)
b. Locally open emergency borate
b. Perform the following:

valve, MOV-350 (Primary AO)

1) Locally open manual charging pump suction from RWST, V-358 (charging pump room between A and B pumps).
2) Go to Step 15e.
c. Transfer boric acid pump control to LOCAL (Primary AO)
d. Start one boric acid pump (Primary AO)
e. Check if required amount of
e. Continue with Step 16.

WHEN boric acid added required amount of boric acid added, THEN do Step 15f.

f. Stop boration as follows:
1) Stop all boric acid pumps
2) Locally close emergency borate valve, MOV-350

e EOP:

TITLE:

REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 13 of 14 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 16 Evaluate Control Room Conditions -

CONTROL ROOM HABITABLE Return to Step 5.

17 Evaluate MCB Annunciator Status (Refer to AR Procedures)

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AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 14 of 14 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED NOTE: When the control room is manned by NRC licensed personnel, then equipment control may be transferred back to the control room in an orderly manner.

Consult plant staff for additional guidance.

18 Establish Normal Control Room Operation:

a. Restore normal control room operation of equipment
  • PRZR heaters

. Charging pumps

. CNMT recirc fans

  • TDAFW pump steam supplies
  • TDAFW pump flow control valves
  • Letdown orifice valves
  • MOV-350
  • BAST pumps
  • Other equipment that was locally operated
b. Verify 431K in AUTO
c. Verify PRZR spray valves in AUTO
b. Place 431K in AUTO, if desired.
c. Place PRZR spray valves in AUTO.

if desired.

d. Ensure PRZR heaters restored:

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

e. Verify one charging pump in AUTO
f. Consult Plant Staff to determine if cooldown is necessary
g. At least one RCP - RUNNING
e. Place one charging pump in AUTO.

if desired.

f. IF cooldown NOT required. THEN go to 0-3. HOT SHUTDOWN WITH XENON PRESENT.
g. Perform the following:
1) Ensure 2 control rod shroud fans running.
2) Go to ES-0.2, NATURAL CIRCULATION COOLDOWN. Step 1.
h. Go to 0-2.2. PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN

-END-

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REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 1 of 1 AP-CR.1 APPENDIX LIST TITLE

1) ATTACHMENT CR EVAC (ATT-7.0)
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