ML053120308

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R. E. Ginna, Emergency Operating Procedures
ML053120308
Person / Time
Site: Ginna Constellation icon.png
Issue date: 10/28/2005
From: Holm D
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML053120308 (19)
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Text

1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC October 28, 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.

Truly you' Dave A. Holm DAH/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 23

(.

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NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDED Fri 10/28/2005 8:33:20 am Page 1 of 2 INPUT PARAMETERS: TYPE.

PRAP STATUSVALUE(S):

EFQU 5 YEARS ONLY:

P R AP A B NOR MA L PR OCE D UR E.

PROCEDURE NUMBER 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-ELEC.2 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-RCC2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR.2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 PROCEDURE TITLE LEAKAGE INTO THE COMPONENT COOUNG LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW - PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OFA CIRC WATER PUMP LOSS OF 12A ANDIOR 12B BUSSES SAFEGUARD BUSSES LOWVOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW350 F)

LOSS OF BUS 13115 LOSS OF SAFEGUARDS BUS 14116 LOSS OF SAFEGUARDS BUS 17/18 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD VITHDRAWALI1NSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTI\\ITY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED IIWENTORY CONDmONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WITHOUT RX TRIP REQUIRED EFFECT LAST REV DATE REVIEW 017 06130/2004 06/26/2002 020 04128/2005 06126/2002 017 0412812005 06/26/2002 023 10128/2005 06/26/2002 014 0613012004 06/03/2002 005 04110/2005 02/27/2004 012 09/17/2004 04/16/2003 028 0112112005 06/26/2002 011 06/10/2004 0612612002 013 01/21/2005 06126/2002 001 06130/2004 09/24/2003 009 0112112005 06286/2002 008 01/21/2005 06/26/2002 016 06/3012004 06/26/2002 018 06/26/2002 04/1612003 015 06/30/2004 06/26/2002 009 06/30/2004 04/1612003 012 04/10/2005 2/120/51/2 007 04/28/2005 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 04130/2003 019 04/30/2003 04/3012003 015 04/0512005 04/30/2003 004 04/10/2005 06126/2002 021 09/17/2004 04/21/2003 007 01121/2005 1t/20I50/3 015 06/10/2005 06/2612002 NEXT REVIEW 06126/2007 06/2612007 0612612007 06/26/2007 06/03/2007 02/27/2009 04/16/2008 06126/2007 06126/2007 06/2612007 09/24/2008 06/26/2007 06/2612007 06/26/2007 04/16/2008 06126/2007 04/16/2008 01/22/2007 02/25/2008 04/24/2008 04/16/2008

.04/16/2008 01/22/2007 04/30/2008 04/30/2008 04/30/2008 06/26/2007 04121/2008 10/31/2006 06/26/2007 ST EF EF EF 6:

EF EF EF EF EF EF EF EF EF EF EF EF EF-EF EF EF EF EF EF EF EF EF EF EF EF EF EF

(C C.

C.

I NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDEX Fri 10/28/2005 8:33:20 am Page 2 of 2 INPUT PARAMETERS: TYPE:

PRAP STATUS VALUE(S):

EF, QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE -R1 X-

4.

4 f

n.

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 021 04/10/2005 06/26/2002 06/26/2007 EF AP-TURB.3 TURBINEVIBRATION 014 07/0112005 06126/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 018 04/10/2005 04/3012003 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: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 1 of 15 GINNA STATION CONTROLLED COPY NUMBER _A3 RESPONSIBI AGER

/0- -_

?63 as&

EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 2 of 15 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: 2 3 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 3 of 15 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDI 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: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGEA4 of 15 S

AX.

.S R

O O NOTE:

o. Conditions should'be evaluate'd for site contingency reporting (Refer to EPIP-l.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).,.

o Should an unsafe'condition-exist'in the-Turbine Building, the alternate egress path is'through Door 52 in the Control Room rear.

The'Relay Room can then be exited either to the Turbine Building middle level or to the outside.

j Evaluate Control Complex Conditions:

o Verify no fire in progress IF fire is NOT controllable. THEN perform the following:

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. Place the following in PULL STOP:l l)-TURB DRVN AFW PUMP STM SUPPLY VLV. MOV-3504A.

2) TURB DRVN AFW PUMP STM SUPPLY VLV; MOV-3505A.
3) TURB DRVN AEW PUMP DC OIL PUMP switch.

I I

k.

4) TURB DRVN AFW PUMP AC OIL

'PUMP switch.

g. Operating shift personnel proceed to Appendix R locker immediately outside the Control Room.
h. Go to ER-FIRE.l. ALTERNATIVE SHUTDOWN -FOR CONTROL COMPLEX FIRE. DO NOT continue in this procedure.

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23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 5 of 15 r4[F4 ACTION/EXPECTED RESPONSE RESPONSE'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.1, ALTERNATE SHUTDOWN FOR CONTROL COMPLEX FIRE.

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 6 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Locally Establish AFW Flow To S/Gs (HCO):

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

RUNNING control to 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 TDAFW 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 MDAEW 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.

. MDAEP A, MOV-4007

. MDAFP B. MOV-4008

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 7 of 15 7 Energiie IPELIP (Switch At Bottom Of IBELIP)

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 8 of 15 SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINED

  • 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.

B.

to MOV-4007 MOV-4008 S/G A.

to S/G B.

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

(locked valve key required) o S/G A

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

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

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

. V-3504

. V-3505

b. Go to Step 10.

FO!

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llEOI AP-CR. 1 lTITLE:

CONTROL ROOM INACCESSIBILITY REV: 23 PAGE 9 of 15 I

I K-)

9 Monitor RCS Temperature

. (IBELIP)

a. RCS temperature - INCREASING
b. Locally throttle SIG 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-§581

  • Priming ejector'B, V-3580 10 Locally Establish Charging Flow Control (CO):
a. Transfer charging pump control to LOCAL
a. To to Step 10.

V>

b. Verify at least one charging pump - RUNNING
c. Check PRZR level - GREATER THAN 13%

(charging pump room and AFW 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, ITHEN locally start a second charging pump.

K-i

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

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 10 of 15 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 establish one SW each loop.

Pump breakers to pump running in 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: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 11 of 15 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.

  • MDAEW pump A. MOV-4007
  • TDAFW pump to S/G A, AOV-4297

. TDAFW pump to S/G B. AOV-4298

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REV: 2 3 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 12 of 15 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 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 valve, MOV-350 (Primary AO)
b. Perform the following:
1) Locally open manual charging pump auction 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 boric acid added
e. Continue with Step 16.

WHEN 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

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REV: 23 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 13 of 15 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 16 Evaluate Contrbl Room Conditions -

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

Return to Step 5.

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REV: 2 3 AP-CR.1 CONTROL ROOM INACCESSIBILITY 1

.PAGE 14 of 15 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 0

S S

S 0

0 0

S 0

0 S

PRZR heaters Charging pumps SW pumps CNMT recirc fans ARVs 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

e. Place one charging pump in AUTO, if desired.
f. IF cooldown NOT required, THEN go to 0-3. HOT SHUTDOWN WITH XENON PRESENT.

This Step continued on the next page.

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REV: 2 3 AP-CR.1 CONTROL ROOM INACCESSIBILITY

.PAGE 15 of 15 ScACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 18 continued from previous page)

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-

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REV: 2 3 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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