ML051300341

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Revision 21 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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NPSP0200 Ginna Nuclear Power Plant Tue 4/26/2005 9:19:19 am E66429 PROCEDURE INDE) 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 LEAKAGE INTO THE COMPONENT COOUNG LOOP 017 06/30/2004 0612612002 06126/2007 EF AP-CCW.2 LOSS OF CCW DURING POVWER OPERATION 019 06/30/2004 06/26/2002 06/26/2007 EF AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 016 06/30/2004 06/26/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 021 04/26/2005 06/26/2002 06/6/2007 EF AP-CVCS.1 CVCS LEAK 014 06/30/2004 06/03/2002 06/03/2007 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 005 04/1012005 02/27/2004 02/27/2009 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 012 09/17/2004 04/1612003 04/16/2008 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 028 01121/2005 06/26/2002 06/26/2007 EF AP-ELEC2 SAFEGUARD BUSSES LOW"VOLTAGE OR SYSTEM LOW FREQUENCY 011 06/10/2004 06/26/2002 06/26/2007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 013 01/21/2005 06/2612002 06/2612007 EF AP-ELEC.13/15 LOSS OF BUS 13/15 001 06/30/2004 09/24/2003 09/24/2008 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 009 01/21/2005 06/26/2002 06/26/2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 008 01/21/2005 06/26/2002 06/26/2007 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 016 06/30/2004 06/26/2002 06/2612007 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/2612002 04/16/2003 04/16/2008 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 015 06/30/2004 06/26/2002 06/26/2007 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAUINSERTION 009 06/30/2004 04/16/2003 04/16/2008 EF AP-RCC.2 RCCIRPI MALFUNCTION 012 04/10/2005 21/20/51/2 01/22/2007 EF AP-RCC.3 DROPPED ROD RECOVERY 006 02/25/2003 02/25/2003 02/2512008 EF AP-RCP.1 RCP SEAL MALFUNCTION 017 06/30/2004 04/24/2003 04/24/2008 EF AP-RCS.1 REACTOR COOLANT LEAK 017 06/30/2004 04/16/2003 04/16/2008 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 012 06/30/2004 04/16/2003 04/16/2008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTM'rTY 011 06/30/2004 04/01/2002 01/22/2007 EF AP-RCS.4 SHUTDOWN LOCA 017 03/18/2005 04/30/2003 04/30/2008 EF AP-RHR.1 LOSS OF RHR 019 04/30/2003 04/30/2003 04/30/2008 EF AP-RHR2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS 015 04/05/2005 04/30/2003 04/30/2008 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 004 04/10/2005 06/26/2002 06/26/2007 EF AP-SW.1 SERVICE WATER LEAK 021 09/17/2004 04121/2003 04/21/2008 EF AP-SW.2 LOSS OF SERVICE WATER 007 01/21/2005 1/120/50/3 10131/2006 EF AP-TURB.1 TURBINE TRIP WIlhOUT RX TRIP REQUIRED 014 04/10/2005 06/26/2002 06/26/2007

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NPSP0200 Ginna Nuclear Power Plant Tue 4/26/2005 9:19:19 am E66429 PROCEDURE INDE) Page 2 of 2 INPUT PARAMETERS: TYPE. PRAP STATUS VALUE(S): EF, QU 5YEARS 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

EOP: TITLE: 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:

EOP: 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.

EOP: TITLE:

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

o At least one train of reactor Manually trip reactor.

IF reactor trip breakers NOT open.

trip breakers - OPEN THEN perform the following:

o Neutron flux - DECREASING a. Open Bus 13 and Bus 15 normal feed breakers.

o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM 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 - Manually trip turbine. IF turbine CLOSED can NOT be tripped, THEN close both MSIVs.

EOP: TITLE: REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 4 of 14 ACTION/EXPECTED RESPONSE STP 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.

fEOP: TIRE: REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY

[ .PAGE 5 of 14 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP 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 . Consider restoration of emergency Busses 14 And 18 - ENERGIZED AC power using ER-FIRE.l. ALTERNATE (STA in A D/G room at ELCP) SHUTDOWN FOR CONTROL COMPLEX FIRE.

EOP: TITLE: 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 control to LOCAL
b. Start MDAFW pumps - ANY PUMPS b. Locally perform the following:

RUNNING

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 c. Locally throttle MDAFW flow THAN 230 GPM PER RUNNING PUMP 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

EOP: TITLE:

AP-CR.1 CONTROL ROOM INACCESSIBILITY

.. PAGE 7 of 14 ACTION/EXECTED RESPONSE ROT OBTAINED 7 Energize IPELIP (Switch At Bottom Of IBELIP)

EOP: TITLE:

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

  • 8 Monitor RCS Temperature (IBELIP)
a. RCS Temperature - STABLE *a. IF RCS temperature increasing.

THEN go to Step 9.

IF RCS temperature decreasing, THEN perform the following:

1) Locally throttle AFW flow to that required to maintain S/G level stable.

. TDAFW Pump to S/G A.

AOV-4297

AOV-4298

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. V-5409B

. Open vent valves. V-5472 AND V-5474

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 b. Locally start one charging pump.

pump - RUNNING

c. Check PRZR level - GREATER c. Locally increase charging pump THAN 13% (charging pump room speed to restore .PRZR level to and AEW pump area, west wall) 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%

EOP: TIRE:

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 IF pressure increasing. THEN ensure

- PRESSURE STABLE (AFW pump RCS temperature and PRZR level area, west wall) 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 Locally close SW Pump breakers to RUNNING IN EACH LOOP (CRF, establish one SW pump running in Locally in the Screenhouse) 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

EOP: TIRE:

REV: 21 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Transfer CNMT Recirc Fan Establish two fans running.

Control To LOCAL And Check -

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

  • 14 Monitor S/G Levels (AFW pump Locally throttle AEW flows to area, west wall): maintain S/G level approximately 350 inches wide range level.

o Levels - APPROXIMATELY 350 INCHES

. MDAFW pump A, MOV-4007 o Levels - STABLE . MDAEW pump B. MOV-4008

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

  • TDAEW pump to S/G B. AOV-4298

. EOP: TITLE:

I REV: 21

. AP-CR.1 CONTROL ROOM INACCESSIBILITY

. .PAGE 12 of 14 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED F SP 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 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I SP 16 Evaluate Control Room Return to Step 5.

Conditions - CONTROL ROOM HABITABLE 17 Evaluate MCB Annunciator Status (Refer to AR Procedures)

EOP: TITLE:

AP-CR.1 CONTROL ROOM INACCESSIBILITY

. PAGE 14 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP 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 b. Place 431K in AUTO, if desired.
c. Verify PRZR spray valves in AUTO 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 e. Place one charging pump in AUTO.

if desired.

f. Consult Plant Staff to determine f. IF cooldown NOT required. THEN if cooldown is necessary go to 0-3. HOT SHUTDOWN WITH XENON PRESENT.
g. At least one RCP - RUNNING 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-

I I .

EOP: TITLE:

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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