ML053610182

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Revisions to Emergency Operating Procedures
ML053610182
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/12/2005
From: Holm D
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML053610182 (233)
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Text

1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy

_I R.E. Ginna Nuclear Power Plant, LLC December 12, 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.

--Verytrly DavAly Holrs Dave A. IHolm 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):

ATT Index E Index ATT-8.4, Rev 6 ATT-26.0, Rev 1 A'00"2 E-0, Rev 38

C ( ( kv

'U-,

NPSP0200 Ginna Nuclear Power Plant Mon 12/12/2005 2:31:44 pm E66429 PROCEDURE INDE) Paae I of 2 INPUT PARAMETERS: TYPE: PRATT STATUSVALUE(S): EF, QU 5 YEARS ONLY:

PRATTr EOP ATTACRHMENT PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE AITLEPODATE C M003 1 REVIEW ST ATT-1.0

.... ATTACHMENT AT POWER CCW ALIGNMENT 003 02V12/2003 0211V2003 02V12/2008 EF ATT-1.1 ATTACHMENT NORMAL CCW FLOW 000 05t18/2000 03t252005 03/25/2010 EF ATT-2.1 ATTACHMENT MIN SW 005 02V01t2001 02103/2003 02103/2008 EF ATT-2.2 ATTACHMENT SW ISOLATION 008 03/0512002 03t27/2003 03127/2008 EF ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03(06t2002 04(08(2004 04/06/2009 EF ATT-2.4 ATTACHMENT NO SW PUMPS 002 05130/2003 10/31/2001 10/31/2006 EF ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/2612002 06/26/2002 06/26/2007 EF ATT-3.0 ATTACHMENT CVCVI 008 12101/2004 02V17/2004 02V17/2009 EF ATT-3.1 ATTACHMENT CNMT CLOSURE 005 02117/2004 02117/2004 02V17/2009 EF ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 07126/1994 03/27/2003 03/2712008 EF ATT-5.0 ATTACHMENT COND TO SIG 006 10/10/2003 04/0612004 04/06/2009 EF ATT-5.1 ATTACHMENT SAFW 008 05/30/2002 04/06/2004 04/06/2009 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 004 10/07/2004 8//20/51/2 01/28/2009 EF ATT-6.0 ATTACHMENT COND VACUUM 003 12118/1996 02103/2003 02V03/2008 EF ATT-7.0 ATTACHMENT CR EVAC 006 03106/2002 02103/2003 02/03/2008 EF ATT-8.0 ATTACHMENT DC LOADS 007 02104/2004 02104/2004 02104/2009 EF ATT-8.1 ATTACHMENT D/G STOP 005 03/06/2002 02103/2003 02/03/2008 EF ATT-8.2 ATTACHMENT GEN DEGAS 008 06/2012002 05/28/2004 05/28/2009 EF ATT-8.3 ATTACHMENT NONVITAL 004 03/06/2002 02103/2003 02/03/2008 EF ATT-8.4 ATTACHMENT SWV 006 12V12/2005 02103/2003 02103/2008 EF ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 001 08/26/2003 05/0212002 05/02/2007 EF ATT-9.0 ATTACHMENT LETDOWN 009 01/07/2004 03/06/2002 03/06/2007 EF ATT-9.1 ATTACHMENT EXCESS L/D 006 07/28/2004 10/3112001 10/31/2006 EF ATT-10.0 ATTACHMENT FAULTED S/G 006 03/06/2002 03/27/2003 03/27/2008 EF ATT-11.0 ATTACHMENT IA CONCERNS 004 09/01/2004 03/27/2003 03/27/2008 EF ATT-11.1 ATTACHMENT IA SUPPLY 003 03/06/2002 03/27/2003 03/27/2008 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/2002 03/10/2003 03/10/2008 EF ATT-12.0 ATTACHMENT N2 PORVS 005 02112/2003 02/12/2003 0211212008 EF ATT-13.0 ATTACHMENT NC 003 0211212003 021212003 02V12/2008 EF ATT-14.0 ATTACHMENT NORMAL RHR COOUNG 003 03/06/2002 04/06/2004 04/06/2009 EF

c C7 C -.0 NPSP0200 Ginna Nuclear Power Plant Mon 12/12/2005 2:31:44 pm E66429 PROCEDURE INDE) Page 2 of 2 INPUT PARAMETERS: TYPE: PRATT STATUSVALUE(S): EF,QU 5 YEARS ONLY:

_EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TLE REV DATE REVIEW REVIEW ST

-ATTACHMENT RHR COOL 008 04/10/2005 01/08/2002 01/08/2007 ATT-14.2 ATTACHMENT RHR ISOL 003 02V1212003 02V1212003 02/122008 EF ATT-14.3 ATTACHMENT RHR NPSH 003 03/0612002 01/28/2004 01/28/2009 EF ATT-14.5 ATTACHMENT RHR SYSTEM 003 03/2012003 02/03/2003 02/03/2008 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/28/2004 01/28/2009 EF ATT-14.7 ATTACHMENT ADJUST RHR FLOW 001 02117/2005 02/17/2004 02/17/2009 EF ATT-15.0 ATTACHMENT RCP START 010 01/11/2005 01111/2005 01/11/2010 EF ATT-1 5.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 02/03/2003 02/03/2008 EF ATT-15.2 ATTACHMENT SEAL COOUNG 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-16.0 ATTACHMENT RUPTURED SG 013 01/11/2005 01/11/2005 01/11/2010 EF ATT-16.1 ATTACHMENT SGTL 003 09/01/2004 06/27/2005 06/27/2010 EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 004 04/10/2005 06/27/2005 06/27/2010 EF ATT-17.0 ATTACHMENT SD-1 020 04/10/2005 01/21/2005 01/21/2010 EF ATT-17.1 ATTACHMENT SD-2 007 09/01/2004 01/30/2001 01/30/2006 EF ATT-18.0 ATTACHMENT SFP- RWST 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-20.0 ATTACHMENT VENT TIME 004 09/01/2004 02V03/2003 02/03/2008 EF ATT-21.0 ATTACHMENT RCS ISOLATION 002 03/06/2002 02/03/2003 02/03/2008 EF ATT-22.0 ATTACHMENT RESTORING FEED FLOW 004 11/17/2004 01/22/2002 01/22/2007 EF ATT-23.0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/1999 01/28/2004 01/28/2009 EF ATT-24.0 ATTACHMENT TRANSFER BATTERY TO TSC 002 09/28/2005 09/28/2005 09/28/2010 EF ATT-26.0 ATTACHMENT RETURN TO NORMAL OPERATIONS 001 12/12/2005 10/31/2001 10/31/2006 EF PRATT TOTAL 51 GRAND TOTAL: 51

C C NPSP0200 Ginna Nuclear Power Plant Mon 12/12/2005 2:31:58 pm E66429 PROCEDURE INDE) Page 1 of I INPUT PARAMETERS: TYPE: PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REIEW_ ST E-0 REACTOR TRiP OR SAFETY INJECTION 038 1211212005 03/2412003 03/24/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 032 0810312005 03/24/2003 03/2412008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 012 11/17/2004 03/24/2003 03/24/2008 EF E-3 STEAM GENERATOR TUBE RUPTURE 038 11/17/2004 03/24/2003 03/24/2008 EF PRE TOTAL: 4 GRAND TOTAL: 4

Responsible Manager IV 4),r;r -Date _________

NOTE: This attachment is used for information only. It lists the loads lost with SI only and with SI and either loss of offsite power or associated D/G output breaker closed. SI must be reset before attempting to restore any of these loads. I NOTE: The capacity of the power source should be considered before restoring any loads.

LOADS LOST ON AN SI SIGNAL ONLY

  • Charging pumps
  • Standby Aux Feed Pumps
  • Pressurizer heaters
  • G Aux Bldg Exhaust Fan
  • Motor fire pump
  • Main feed water pumps
  • Spent fuel pool pump B
  • CREATS heating and cooling systems
  • Bus ties 17-18, 15-16, 16-14, 13-14
  • MCC-G
  • Intake heaters LOADS LOST ON AN SI SIGNAL WITH EITHER OF THE FOLLOWING:

o LOSS OF OFFSITE POWER OR o ASSOCIATED D/G OUTPUT BKR CLOSED

  • All of the above
  • Reactor compartment cooling fans
  • Penetration cooling fans
  • Reactor makeup water pump
  • Spent fuel pool pump A
  • RWST purification pump
  • Aux Building exhaust fan C
  • MCC C Breaker 1H (spare breaker used for STBY SFP pump)

EOP: TITLE: REV: I ATT-26.0 ATTACHMENT RETURN TO NORMAL OPERATIONS PAGE 1 of 1 Responsible Manager Date / 2oAd66 This-attachment provides actions to be considered when returning to normal plant procedures following an event requiring entry to EOPs.

CAUTION BEFORE PERFORMING ANY ITEM IN THIS ATTACHMENT, CAREFUL CONSIDERATION MUST BE GIVEN REGARDING THE INITIATING EVENT, CURRENT PLANT CONDITIONS, AND DESIRED PLANT OPERATING MODE. CONSULT PLANT STAFF AS NECESSARY.

  • Restore offsite power to all AC busses (refer to ER-ELEC.1)
  • Place DGs in auto standby (refer to ATT-8.1)
  • Restore power to MCCs (reset UV load shed if necessary)
  • Maintain desired SG level using AFW pumps
  • Open SW isolation valves
  • Restore Instrument/Service Air Systems (refer to T-2 series)
  • Restore normal charging and letdown (refer to S-3.2E)
  • Address existing YELLOW path FRs
  • Refer to 0-6.13 for normal MCB component alignment. Manually align components as necessary.
  • Restore CNMT penetrations affected by CI
1. Place valve switch in closed position
2. Reset xy relays
3. Place/verify valve in desired position
  • Restart CNMT and Plant Vent radiation monitor pumps
  • Stop any operating redundant equipment that is no longer required (CCW Pump, SW Pumps, CRFCs, etc.)
  • Restore motor and diesel fire pumps
  • Restore SFP cooling (refer to S-9 series)
  • Realign CREATS per T-35I, FUNCTIONAL ALIGNMENT OF THE CONTROL ROOM AIR HANDLING UNIT.
  • Review MCB annunciator panels - alarm status valid for plant conditions
  • Restore Generator Seal Oil system (refer to T-34 series)
  • Restore SG blowdown and sample system (refer to T-14 series)
  • Restore CNMT recirculation fans to control CNMT temperature/pressure within ITS limits
  • Verify SDM (refer to 0-3 series)
  • Restore PRT to normal conditions (refer to AR-F-1, AR-F-9, AR-F-17)
  • "match flags" on MCB
  • Restore Aux Bldg ventilation (refer to T-35A)
  • Borate 650 gallons for each rod not fully inserted
  • Perform T-8A for any non-operating CW pump

p EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 29 GINNA STATION CONTROLLED COPY NUMBER __3 I'I RESPONSIB0 MANAGER

/EC- /VEI -DA EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 2 of 29 A. PURPOSE - This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.

B. ENTRY CONDITIONS/SYMPTOMS

1. The following are symptoms that require a reactor trip, if one has not occurred:

o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-i, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

2. The following are symptoms of a reactor trip:

o Any First Out reactor trip annunciator lit.

o A rapid decrease in core neutron level as indicated by nuclear instrumentation.

o MRPI indicates all control and shutdown rods on bottom.

o Reactor trip breakers indicate open.

3. The following are symptoms that require a reactor trip and safety injection, if one has not occurred:

o Any plant parameter reaches the Safety Injection setpoint and logic listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

4. The following are symptoms of a reactor trip and safety injection:

o Any SI annunciator lit.

o Safeguards sequencing started.

EOP: TILE: REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 29 S P ACTION/EXPECTED RESPONSE llRESPONSE 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 reactor will NOT trip OR IF power range NIS indicates greater than 5%. THEN go to FR-S.1, RESPONSE TO REACTOR RESTART/ATWS, Step 1 0 Verify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine trip can NOT be verified, THEN close both MSIVs.

0D Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS: -

Attempt to start any failed emergency DIG to restore power to all AC emergency busses.

  • Bus 14 and Bus 18 IF Bus 14 AND Bus 16 are
  • Bus 16 and Bus 17 deenergized, THEN go to ECA-O.O.

LOSS OF ALL AC POWER, Step 1.

%V

EOP: TITLE:

REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 29 STEP ACTION/EXPECTED RESPONSE = RESPONSE NOT OBTAINED 0 Check if SI is Actuated:

a. Any SI Annunciator - LIT a. IF any of the following conditions are met. THEN manually actuate SI and CI:

o PRZR pressure less than 1750 psig

-OR-o Steamline pressure less than 514 psig

-OR-o CNMT pressure greater than 4 psig

-OR-o SI sequencing started

-OR-o Operator determines SI required IF SI is NOT required. THEN go to ES-O.1, REACTOR TRIP RESPONSE, Step 1.

b. SI sequencing - BOTH TRAINS b. Manually actuate SI and CI.

STARTED.

Wi

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 29 NOTE: o FOLDOUT page should be open and monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

5 Verify SI and RHR Pumps Running:

a. All SI pumps - RUNNING a. Perform the following:
1) Ensure SI pump suction supply open from RWST.
2) Manually start pumps.
b. Both RHR pumps - RUNNING b. Manually start pumps.

6 Verify CNMT RECIRC Fans Running:

a. All fans - RUNNING a. Manually start fans.
b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED with relay rack key to locally open dampers by pushing in trip relay plungers.
  • AUX RELAY RACK RA-2 for fan A
  • AUX RELAY RACK RA-3 for fan C

EOP: TIRE: REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 29 S P ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • 7 Verify CNMT Spray Not Verify CNNT spray initiated.

Required:

IF CNMT spray NOT initiated, THEN o Annunciator A-27, CNNT SPRAY - perform the following:

EXTINGUISHED

a. Depress manual CNMT spray o CNMT pressure - LESS THAN 28 PSIG pushbuttons (2 of 2).
b. Ensure CNMT spray pumps running.

IF no CNMT spray pump available, THEN go to Step 8.

c. Ensure CNMT spray pump discharge valves open for operating pump(s).

o CNMT spray pump A:

  • MOV-860A
  • MOV-860B o CNMT spray pump B:
  • MOV-860C
  • MOV-860D
d. Verify NaOH flow (FI-930)

IF NaOH flow NOT indicated. THEN place switches for NaOH tank outlet valves to OPEN.

  • AOV-836A
  • AOV-836B

EOP: TITLE:

REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 29 8 Check If Main Steamlines Should Be Isolated:

a. Any MSIV - OPEN a. Go to Step 9.
b. Check CNMT pressure - LESS THAN b. Ensure BOTH MSIVs closed and go 18 PSIG to Step 9.
c. Check if ANY main steamlines c. Go to Step 9.

should be isolated:

o Low Tavg (5451F) AND high steam flow (O.4x106 lb/hr) from either SIG

-OR-o High-High steam flow (3.6x106 lb/hr) from either SIG

d. Verify MSIV closed on the d. Manually close valves.

affected SIG(s) 9 Verify MFW Isolation:

a. MFW pumps - TRIPPED a. Perform the following:.
1) Manually close MEW pump discharge valves and trip MFW pumps.
2) Continue with Step 9c. WHEN both MEPs are tripped, THEN perform Step 9b.
b. Depress MANUAL pushbuttons for A and B S/G MEW regulating valve and bypass valve controllers AND adjust to 0%/ demand.
c. SIG blowdown and sample valves - c. Place SIG blowdown and sample CLOSED valve isolation switch to CLOSE.

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 29 ACTION/EXPECTED RESPONSE STEP H RESPONSE NOT OBTAINED 10 Verify Both MDAFW Pumps Manually start both MDAFW pumps.

Running IF less than 2 MDAFW pumps are running, THEN manually open TDAEW pump steam supply valves.

  • MOV-3505A
  • MOV-3504A 11 Verify At Least Two SW Pumps Perform the following:

- RUNNING

a. Ensure one SW pump running on each energized screenhouse AC emergency bus:
  • Bus 17
  • Bus 18
b. IF offsite power NOT available, THEN ensure SW isolation.
c. IF NO SW pumps running, THEN perform the following:
1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

EOP: TITLE:

REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 29 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
b. Verify CI and CVI valve status b. Manually close affected CI and lights - BRIGHT CVI valve(s).

IF valve(s) can NOT be closed from the MCB. THEN dispatch AO to locally close affected valve(s)

IF valve(s) can NOT be locally closed, THEN close alternate isolation valve(s). (Refer to ATT-3.0, ATTACHMENT CI/CVI).

c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

  • FCV-4561 a FCV-4562
d. Letdown orifice valves - CLOSED d. Place affected valve switch to CLOSE. IF valves can NOT be
  • AOV-200A verified closed by MCB
  • AOV-200B indication, THEN close alternate
  • AOV-202 isolations. (Refer to ATT-3.0, ATTACHMENT CI/CVI)

EOP: TITlE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION

. PAGE 10 of 29 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.

13 Check CCW System Status:

a. Verify CCW pump - AT LEAST ONE a. IF offsite power available, THEN RUNNING manually start one CCW pump.
b. Place switch for excess letdown AOV-310 to CLOSE
c. Place switch for CCW from excess letdown, AOV-745 to CLOSE 14 Verify SI And RHR Pump Flow:
a. SI flow indicators - CHECK FOR a. IF RCS pressure less than FLOW 1400 psig. THEN manually start pumps and align valves. IF NOT, THEN go to Step 15.
b. RHR flow indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig, THEN manually start pumps and align valves. IF NOT.

THEN go to Step 15.

15 Verify AFW Valve Alignment: Manually align valves as necessary.

a. AEW flow - INDICATED TO BOTH S/G(s)
b. AEW flow from each MDAFW pump -

LESS THAN 230 GPM

EOP: TITLE:

REV: 38l E-0 REACTOR TRIP OR SAFETY INJECTION 2 PAGE 11 of 291

/ECTED RESPONSM RESPONSE NOT OBTAINED

  • 16 Monitor Heat Sink:
a. Check S/G narrow range level - a. Perform the following:

GREATER THAN 7% [25% adverse CNMT] in any S/G 1) Verify total AFW flow -

GREATER THAN 200 GPM IF total AFW is less than 200 gpm, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow. IF AEW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

2) Go to Step 17.
b. Check S/G narrow range level - b. Secure AFW flow to any S/G with BOTH S/G LESS THAN 50% level above 50%.
c. Control feed flow to maintain S/G narrow range level between 7% [25% adverse CNMT] and 50%.

EOP: TITLE: RV E-OTREACTOR TRIP OR SAFETY INJECTION PAGE 12 of 29 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED 17 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

  • MOV-852A
  • MOV-85>2B
b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
c. Verify SI pump A - RUNNING c. Perform the following:
1) Ensure SI pumps B and C running. IF either pump NOT.

running, THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line A:

o MOV-871A open o MOV-871B closed

3) Go to Step 18.
d. Verify SI pump B - RUNNING d. Perform the following:
1) Ensure SI pumps A and C running. IF either pump NOT, running, THEN go to Step 17e.
2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 18.
e. Verify SI pump C discharge e. Manually open valves as valves - OPEN necessary.
  • MOV-871A
  • MOV-871B

SP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDC CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFESITE POWER) 18 Check CCW Flow to RCP Thermal IF CCW to a RCP is lost, THEN Barriers: perform the following:

o Annunciator A-7. RCP 1A CCW a. Stop affected RCPs.

RETURN HI TEMP OR LO FLOW -

EXTINGUISHED b. Reset SI.

o Annunciator A-15, RCP 1B CCW c. Verify adequate power available RETURN HI TEMP OR LO FLOW - to run one charging pump (75 kw).

EXTINGUISHED

d. Start one charging pump at minimum speed for seal injection.
e. Adjust HCV-142 to establish either of the following:

o Labyrinth seal D/P to each RCP greater than 15 inches of water.

-OR-o RCP seal injection flow to each RCP greater than 6 gpm.

f. IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.

EOP: TITLE: REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION l PAGE 14 of 29 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps - RUNNING a. Go to Step 20.
b. PULL STOP TDAFW pump steam supply valves
  • MOV-3504A
  • MOV-3505A
  • 20 Monitor RCS Tavg - STABLE AT IF temperature less than 547° F and OR TRENDING TO 5470F decreasing. THEN perform the following:
a. Stop dumping steam.
b. Ensure reheater steam supply valves are closed.
c. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 7% [25%

adverse CNNT] in at least one S/G.

d. WHEN SIG level greater than 7%

[25% adverse CNMT] in one SIG.

THEN limit feed flow to that required to maintain level in at least one S/G.

e. IF cooldown continues. THEN close both MSIVs.

IF temperature greater than 547° F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 547°F.

EOP: TITLE: REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 29 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 21 Check PRZR PORVs And Spray Valves:

a. PORVs - CLOSED a. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any valve can NOT be closed, THEN manually close its block valve.

  • NOV-516 for PCV-430
  • MOV-515 for PCV-431C IF block valve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Step 1.

b. Auxiliary spray valve (AOV-296) b. Manually close auxiliary spray

- CLOSED valve. IF valve can NOT be closed, THEN perform the following:

1) Decrease charging pump flow to minimum.
2) Ensure charging valve to loop B cold leg open (AOV-294).
c. Check PRZR pressure - LESS THAN c. Continue with Step 22. WHEN 2260 PSIG pressure less than 2260 psig, THEN do Step 21d.
d. Normal PRZR spray valves - CLOSED d. Place controllers in MANUAL at 0% demand. IF valves can NOT be
  • PCV-431A closed, THEN stop associated
  • PCV-431B RCP(s).

EOP: TITLE:

E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 29 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED SP 22 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING a. Go to Step 23.
b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 23.
c. RCS pressure minus maximum S/G c. Go to Step 23.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs 23 VERIFY CREATS ACTUATION:
a. At least one damper in each a. Depress both CREATS actuation flowpath - CLOSED a.pushbuttons I
  • Normal Supply Air
  • CONTROL ROOM MANUAL ISOLATION Al
  • Normal Return Air
  • CONTROL ROOM MANUAL ISOLATION Bl
  • Lavatory Exhaust Air
b. CREATS fans - BOTH RUNNING I b. Start both CREATS fans I 24 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized. THEN go o Pressure in both S/Gs - STABLE to E-2. FAULTED STEAM GENERATOR OR INCREASING ISOLATION. Step 1.

o Pressure in both S/Gs - GREATER THAN 110 PSIG

EOP: TITLE: REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 17 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If S/G Tubes Are Intact: Go to E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.

o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL 26 Check If RCS Is Intact: Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

a. CNMT area radiation monitors -

NORMAL

  • R-2
  • R-7
  • R-29
  • R-30
b. CNMT pressure - LESS THAN 0.5 PSIG
c. CNMT sump B level - LESS THAN 8 INCHES
d. CNMT sump A level o Level - STABLE o Annunciator C-19, CONTAINMENT SUMP A HI LEVEL - EXTINGUISHED

ACTION/EXPECTED RESPONSERESPONSE NOT OBTAINED 27 Check If SI Should Be Terminated:

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 28.

o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 0 0F Step 28.

USING FIG-1.O, FIGURE MIN SUBCOOLING

c. Secondary heat sink: c. IF neither condition met, THEN do NOT stop SI pumps. Go to o Total feed flow to S/Gs - Step 28.

GREATER THAN 200 GPM

-OR-o Narrow range level in at least one S/G - GREATER THAN 7%

d. PRZR level - GREATER THAN 10% d. Do NOT stop SI pumps. Perform the following:
1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
2) Go to Step 28.
e. Go to ES-1.1, SI TERMINATION, Step 1.

EOP: TIRE: REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION-PAGE 19 of 29 P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o The Critical Safety Function Red Path Summary is available in APPENDIX 1.

28 Initiate Monitoring of Critical Safety Function Status Trees

  • 29 Monitor S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% than 200 gpm until narrow range level greater than 7% in at least one SIG.
b. Control feed flow to maintain b. IF narrow range level in any S/G 1#4 narrow range level between 17% continues to increase in an and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

30 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels - NORMAL RUPTURE, Step 1.

o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 31 Reset SI 32 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

EOP: TITLE: REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION

. PAGE 21 of 29 STEPION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 33 Verify Adequate SW Flow:

a. At least three SW pumps - RUNNING a. Manually start SW pumps as power supply permits (257 kw each).

IF less than three pumps running, THEN ensure SW isolation.

IF NO SW pumps running, THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

IF only one SW pump running.

THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0, ATTACHMENT SD-1)

EOP: TITLE:

REV: 38l E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 29 ACTION/EXPECTED RESPONSE R 34 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
2) Verify adequate emergency D/G capacity to run air compressor(s) (75 kw each).

IF NOT, THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped.

(Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS

3) WHEN bus 15 is restored. THEN reset control room lighting.
b. Check SW Pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)
2) Go to step 34d.

This Step continued on the next page.

EOP: TITLE:

REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 29 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP (Step 34 continued from previous page)

c. Verify SW isolation valves to c. Perform the following:

-turbine building - OPEN

1) Manually align valves.
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664 2) Dispatch AO to locally reset compressors as necessary.
d. Verify adequate air d. Manually start electric air compressor(s) - RUNNING compressor(s) as power supply permits (75 kw each).

IF electric air compressor can NOT be started. THEN start diesel air compressor. (Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

e. Check IA supply: e. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 35. WHEN IA restored, THEN do Steps 34f and g.

f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN

EOP: TITLE: REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 24 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check Auxiliary Building Evaluate cause of abnormal Radiation - NORMAL conditions.

  • Plant vent iodine (R-10B) IF the cause is a loss of RCS
  • Plant vent particulate (R-13) inventory outside CNMT. THEN go to
  • Plant vent gas (R-14) ECA-1.2, LOCA OUTSIDE CONTAINMENT.

Step 1.

  • CCW liquid monitor (R-17)
  • LTD line monitor (R-9)
  • CHG pump room (R-4) 36 Check PRT Conditions Evaluate the following flowpaths for cause of abnormal conditions:

o PRT level (LI-442) - LESS THAN 84%

  • RCP seal return relief
  • PRZR PORVs o PRT temperature (TI-439) - LESS
  • PRZR safeties THAN 120 0F
  • Letdown line relief o PRT pressure (PI-440A) - LESS IF excess letdown previously in THAN 3 PSIG service. THEN close AOV-310, excess letdown isolation valve from loop A cold.

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION

. PAGE 25 of 29 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

  • 37 Monitor If RHR Pumps Should Be Stopped:
a. Check RCS pressure:
1) Pressure - GREATER THAN 1) Go to E-1, LOSS OF REACTOR OR 250 PSIG SECONDARY COOLANT, Step 1.
2) Pressure - STABLE OR 2) Go to Step 38.

INCREASING

b. Stop both RHR pumps and place in AUTO 38 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker -

CLOSED IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.0, ATTACHMENT CNMT RECIRC CLOSED FANS).

EOP: TITLE:REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 29 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 39 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offecale high.

THEN dispatch AO to close seal injection needle valve(s) to affected RCP:

. V-300A for RCP A

  • V-300B for RCP B
2) Ensure HCV-142 open, demand at 0%.
b. Charging pump suction aligned to b. Manually align valves.

RWST:

IF LCV-112B can NOT be opened.

o LCV-112B - OPEN THEN dispatch AO to locally open V-358, manual charging pump o LCV-112C - CLOSED suction from RWST (charging pump room).

IF LCV-112C can NOT be closed, THEN perform the following:

1) Direct AO to locally open V-358, manual charging pump suction from RWST (Charging Pump Room).
2) Verify charging pump A NOT running and place in PULL STOP.
3) WHEN V-358 open. THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

l EOP: TITLE:

REV: 38 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 27 of 29 STEP ACTION/EXPECTED RESPONSE RSPONSE NOT OBTAINEDl 40 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

ACTION/EXPECTED RESPONSE SP [RESPONSE NOT OBTAINED 41 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Perform the following:

energized by offeite power:

1) Verify non-safeguards bus tie o Emergency D/G output breakers breakers closed:

- OPEN

  • Bus 13 to Bus 14 tie o AC emergency bus voltage -
  • Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
2) Place the following pumps in o AC emergency bus normal feed PULL STOP:

breakers - CLOSED

  • EH pumps
  • Turning gear oil pump
  • HP seal oil backup pump
3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:
  • A from Bus 13
  • B from Bus 15
  • E from Bus 15
  • F from Bus 15
5) Start HP seal oil backup pump.
6) Ensure D/G load within limits.
7) Refer to ATT-8.4, ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
8) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1, ATTACHMENT D/G STOP)

EOP: TITLE:REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION l .PAGE 29 of 29 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STE 42 Return to Step 20

-END-

E-0 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)
3) ATTACHMENT CI/CVI (ATT-3.0)
4) ATTACHMENT SD-1 (ATT-17.0)
5) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
6) ATTACHMENT D/G STOP (ATT-8.1)
7) ATTACHMENT SI/UV (ATT-8.4)
8) ATTACHMENT NO SW PUMPS (ATT-2.4)
9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
11) FOLDOUT

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%
b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 7%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 38 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
a. SI pumps - AT LEAST TWO RUNNING
b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG

[400 psig adverse CNMT]

2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).

1503 Lake Road Ontario, NewYork 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC December 15, 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.

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):

ATT Index E-0, Rev 39 FR-C.2, Rev 21 E Index E-1, Rev 33 FR-S.1, Rev 18 ECA Index ECA-0.0, Rev 30 FR-Z.1, Rev 10 ES Index ECA-0.2, Rev 17 FR Index ES-1.3, Rev 39 ATT-3.0, Rev 9 FR-C. 1, Rev 23

C ( f NPSP0200 Ginna Nuclear Power Plant Thu 12/15/2005 8:16:25 am -

E66429 rpf'R11n liI=F IMMF Pane 1 nf 9 INPUT PARAMETERS: TYPE: PRATT STATUS VALUE(S): EF QU 5 YEARS ONLY:

PRATT EOP ATTACHMENTS~

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TrrLE! REV DATE REVIEW REVIEW ST ATT-1.0 ATTACHMENT AT POWER CCWALIGNMENT 003 0211212003 0211212003: 0211212008 EF ATT-1.1 ATTACHMENT NORMAL CCW FLOW 000 0511812000 03/25/2005 03/25/2010 EF A1T-2.1 ATTACHMENT MIN SW 005 0210112001 02/03/2003 02/0312008 EF A1T-2.2 ATTACHMENT SW ISOLATION 008 0310612002 0312712003 03/27r2008 EF ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03/08(2002 04/62004 04/06/2009 EF ATT-2.4 ATTACHMENT NO SW PUMPS 002 05/3012003 1013112001 1013112008 EF ATT-2.5 ATTACHMENT SPUT SW HEADERS 000 062002 06826/2002 08w26/2007 EF ATT-3.0 ATTACHMENT CVCVI 009 121512005 0211712004 02/17/2009 EF ATT-3.1 ATrACHMENr CNMT CLOSURE 005 02117/2004 0211712004 0211712009 EF ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 0712611994 0312712003 03/27(2008 EF ATT-5.0 ATTACHMENT COND TO S/G 008 1011012003 04/06/2004 04/06/2009 EF ATT-5.1 ATTACHMENT SAFW 008 0613012002 04/2004 04060/2009 EF ATT-5.2 ATTACHMENT FIRE WATER COOUNG TO TDAFW PUMP 004 1010712004 8112015112 01/28/2009 EF ATT-8.0 ATTACHMENT COND VACUUM 003 12118/1996 02/0312003 0210312008 EF ATT-7.0 ATTACHMENT CR EVAC 006 03m082002 0210312003 02103/2008 EF ATT-8.0 ATTACHMENT DC LOADS 007 02/04/2004 02104/2004 02104/2009 EF ATr-8.1 ATTACHMENT DIG STOP 005 03/0612002 0210312003 0210312008 EF ATT-8.2 ATTACHMENT GEN DEGAS 008 0682012002 0512812004 05128/2009 EF Arr-8.3 ATTACHMENT NONVMTAL 004 03/0312002 02103/2003 02103/2008 EF ATT-8.4 ATTACHMENT SIAN 008 12112/2005 0210312003 02/03/2008 EF ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 001 08126/2003 05102/2002 05/0212007 EF ATT-9.0 ATTACHMENT LETDOaN 009 01107/2004 0312002 03106/2007 EF ATT-9.1 ATrACHMENT EXCESS LID 008 07128/2004 1013112001 10131/2006 EF ATT-10.0 ATTACHMENT FAULTED S/G oo0 03106(2002 03/2712003 03/2712008 EF ATr-11.0 ATTACHMENT IACONCERNS 004 09/0112004 0312712003 03127/2008 EF A--11.1 ATTACHMENT LASUPPLY 003 03I06n2002 03/27/2003 0312712008 EF ATT-11.2 ATTACHMENT DIESEL AR COMPRESSOR 004 11/1812002 0311012003 03/10/2008 5F ATT-12.0 ATTACHMENT N2 PORVS 005 02112/2003 02112/2003 0211212008 E:

ATT-13.0 ATTACHMENT NC 003 02112/2003 02112/2003 02112/2008 EF A1T-14.0 ATTACHMENT NORMAL RHR COOUNG 003 03/06/2002 04/0682004 04/08/2009 EF

( (

NPSP0200 Ginna Nuclear Power Plant Thu 12115/2005 8:16:25 am E66429 PROCEDURE INDEX Page 2 of 2 INPUT PARAMETERS: TYPE: PRATT STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PRT O TAHET PROCEDURE EFFECT LAST NEXT REV DATE REVIEW REVIEW ST NUMBER PROCEDURE TITLE ATT-14.1 ATTACHMENT RHR COOL 008 04/10/2005 01/08/2002 01/08/2007 EF ATT-14.2 ATTACHMENT RHR ISOL 003 02/12/2003 02/12/2003 02/12/2008 EF ATT-14.3 ATTACHMENT RHR NPSH 003 03/06/2002 01/28/2004 01/28/2009 EF ATT-14.5 ATTACHMENT RHR SYSTEM 003 03/20/2003 02/03/2003 02/03/2008 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/28/2004 01/28/2009 EF ATT-14.7 ATTACHMENT ADJUST RHR FLOW 001 02/1712005 02/17/2004 02/17/2009 EF ATT-15.0 ATTACHMENT RCP START 010 01/11/2005 01/11/2005 01/11/2010 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 02/03/2003 02/03/2008 EF ATT-15.2 ATTACHMENT SEAL COOLING 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-16.0 ATTACHMENT RUPTURED SIG 013 01/11/2005 01/11/2005 01/11/2010 EF ATT-16.1 ATTACHMENT SGTL 003 09/01/2004 06/27/2005 06/27/2010 EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 004 04/10/2005 06/27/2005 06/27/2010 EF ATT-17.0 ATTACHMENT SD-1 020 04/10/2005 01/21/2005 01/21/2010 EF ATT-17.1 ATTACHMENT SD-2 007 09/01/2004 01/30/2001 01/30/2006 EF ATT-18.0 ATTACHMENT SFP - RWST 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-20.0 ATTACHMENT VENT TIME 004 09/01/2004 02/03/2003 02/03/2008 EF ATTACHMENT RCS ISOLATION 002 03106/2002 02/03/2003 02/03/2008 .EF ATT-21.0 ATT-22.0 ATTACHMENT RESTORING FEED FLOW 004 11/17/2004 01/22/2002 01/22/2007 EF ATT-23.0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/1999 01/28/2004 01/28/2009 EF ATT-24.0 ATTACHMENT TRANSFER BATTERY TO TSC 002 09/28/2005 09/28/2005 09/28/2010 EF ATT-26.0 ATTACHMENT RETURN TO NORMAL OPERATIONS 001 12/12/2005 10/31/2001 10/31/2006 EF PRATT TOTAL: 51 GRAND TOTAL: 51

c c c NPSP0200 Ginna Nuclear Power Plant Thu 1211512005 8:16:40 am Dee. Z .4 FA6A9Q IE nrlf%^rnl INSwJcu NM= Mlrme:

S: PA: 1IOWNER r J Ur l INPUT PARAMETERS: TYPE PRE STATUS VALUE(S) EF, CKJ 8YEARS ONLY:

PRE EMERGWE EN~CY PR~OCEDUGRE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST REACTOR TRIP OR SAFETY INJECTION 039 12/15/2005 0312412003 03/24/2008 EF E-0 LOSS OF REACTOR OR SECONDARY COOLANT 033 12/15/2005 03124/2003 03/2412008 EF E-1 FAULTED STEAM GENERATOR ISOLATION 012 11/17/2004 03/24/2003 03/24/2008 EF E-2 STEAM GENERATOR TUBE RUPTURE 038 11117/2004 03/24/2003 03/24/2008 EF E-3 PRE TOTAL 4 GRAND TOTAL 4

C C C NPSP0200 Ginna Nuclear Power Plant Thu 12/1$1200S 8:16:53 am FrAAA r .,

MU~tUU IP / -age I OT -1 INPUT PARAMETERS: TYPE PRECA STATUS VALUE(S)'. EF, QU 5 YEARS ONLY:

PRECA EME NCY NTI PROCEDURE 'EFFECT LAST NEXT PROCEDURE TITLE REV DATE REVIEW REVIEW ST NUMBER LOSS OF ALL AC POWER 030 12115/2005 03124J2003 03/24/2008 EF ECA-0.0 LOSS OF ALL AC POWER RECOVERY WITHOT SI REQUIRED 024 11117/2004 03R24/2003 03/2412008 EF ECA-0.1 LOSS OF ALL AC POWER RECOVERYWNTH SI REQUIRED 017 12/15t2005 03/24/2003 03/24/2008 EF ECA-0.2 LOSS OF EMERGENCYCOOLANT RECIRCULATION 023 11117/2004 03/24/2003 .0312412008 EF ECA-1.1 LOCA OUTSIDE CONTANMENT 008 05130/2003 03/2412003 03/24/2008 EF ECA-1.2 RESPONSE T SUMP B BLOCKAGE 000 08/0312005 08103/2005 08/03/2010 EF ECA-1.3 UNCONTIROLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 028 11117/2004 03/24/2003 0312412008 EF ECA-2.1 SG WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED 027 11/17/2004 03124/2003 03/2412008 EF ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED 028 11/17/2004 03/24/2003 03/24/2008 ' EF ECA-3.2 SGTR WIHOUlT PRESSURIZER PRESSURE CONTROL 031 11/17/2004 03/24/2003 03/24/2008 EF ECA-3.3 PRECA TOTAL 10 GRAND TOTAL 10

c C C NPSP0200 Ginna Nuclear Power Plant Thu 12115/2005 8:17:07 am E66429 PROCEDURE INDE) Paae 1 of 1 INPUT PARAMETERS: TYPE PRES STATUS VALUE(S): EF, QU 5 YEARS ONLY:

PRES EMERGENCY SUB-PROCEDURE" PROCEDURE EFFECT LAST NEXT NUMBER PROCEOURE lIlE REV DATE EVIEW REVIEW ST 010 05/01/1998 0312412003 03/2412008 EF ES-0.0 REDIAGNOSIS REACTOR TRIP RESPONSE 023 11/17/2004 03/2412003 03/2412008 EF ES-0.1 NATURAL CIRCULATION COOLDOtN 013 05130i2003 03/24/2003 03/24/2008 EF ES-0.2 NATURAL CIRCUATION COOLDOW WITHSTEAM VOID INVESSEL 010 1111712004 03124/2003 03124Q2008 EF ES-0.3 SI TERMINATION 027 11117/2004 03/2412003 03124/2008 EF ES-1.1 POST LOCA COOLDON AND DEPRESSURIZATION 027 11/17/2004 03124/2003 -03/2412008 EF ES-1.2 TRANSFER TO COLD LEG RECIRCULATION 039 12115/2005 u 0312412003 0312412008 EF ES-1.3 POST-SGTR COOLDO\MN USING BACKFILL 016 11/1712004 0312412003 03124/2008 EF ES-3.1 POST-SGTR COOLDOWN USING BLOWDO 017 11/1712004 03/24/2003 03/2412008 EF ES-3.2 POST-SGTR COOLDaWN USING STEAM DUMP 017 11/17/2004 03/2412003 03/24/2008 EF ES-3.3 PRES TOTAL 10 GRAND TOTAL: 10

C C: c NPSP0200 Ginna Nuclear Power Plant Thu 12/15/2005 8:17:34 am E66429 PROCEDURE INDE) Page 1 of 1 INPUT PARAMETERS: TYPE: PRFR STATUSVALUE(S): EF QU 5 YEARS ONLY:

P'RFR ~FUNCTIO~NALRE~STORA~TION GUIDELINE PR~OC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FR-C.1 RESPONSE TO INADEQUATE CORE COOUNG 023 12/15/2005 03/24/2003 03/24/2008 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 021 12115/2005 0312412003 0312412008 EF FR-C.3 RESPONSE TO SATURATED CORE COOUNG 010 0810312005 03124/2003 03/24/2008 EF:

FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 033 08/03/2005 03124f2003 03i242W08 EF FR-H.2 RESPONSE TO STEAM GENERATOR 0VERPRESSURE 008 10f10/2003 03/24f2003 03/2412008 EF FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 008 11/17/2004 03124Q2003 03124i2008 EF FR-HA RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 005 05/3012003 03124/2003 03124/2008 EF FR-H.5 RESPONSE TO STEAM GENERATOR LON LEVEL 010 11/17/2004 03124Q2603 03/24/2008 EF FR-1I RESPONSE TO HIGH PRESSURIZER LEVEL 017 01/0712004 03/24/2003 03Q24/2008 EF FR42 RESPONSE TO LOW PRESSURIER LVEL 012 11/17/2004 03/24/2003 03124/2008 EF FR-1.3 RESPONSE TO VOIDS INREACTOR VESSEL 020 11/17/2004. 03124/2003 03/2412008 EF FR-P.1 RESPONSE TO IMMINENT PRESSURZED THERMAL SHOCK CONDl1ION 029 11117/2004 03/2412003 03/24/2008 EF FR-P2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDmON 009 11/17/2004 03/24/2003 03/24/2008 EF FR-S.1 RESPONSE TO REACTOR RESTART/A1WS 018 12/15/2005 03124/2003 03124/2008 EF FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN 009 05/30/2003 03/24/2003 03/24/2008 EF FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE 010 12115/2005 03/24/2003 03/2412008 EF FR-Z.2 RESPONSE TO CONTAINMENT FLOODING 005 05/30/2003 03/24/2003 03/2412008 EF FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 005 05f30/2003 03f2412003 03/2412008 EF PRFR TOTAL 18 GRAND TOTAL: 18

EOP:

ATT-3.0 TITLE:

l ATTACHMENT CI/CVI REV: 9

~PAGE 1 of 4l I

4.-

Responsible ManELger Date _ _ _ _ _ _

NOTE: Locked vaLlve key may be r~quired for local operations.

1. For each of the following AUTO ISOL VALVES that will not close, take the action directed in the ALTERNATE ISOLATION column.

AUTO ISOL VALVE ALTERNATE ISOL AOV-200A(L/D) Close the following valves: (MCB)

  • AOV-371
  • HCV-133 AOV-200B (L/D) Close the following valves: (MCB)
  • AOV-371
  • HCV-133 AOV-202(L/D) Close the following valves: (MCB)
  • AOV-371
  • HCV-133 AOV-5392(IA) Close the following valves: (IB BASEMENT CLEAN SIDE)
  • V-5397
  • V-5410 AOV-371(L/D) Close the following valves: (NRHX ROOM)
  • V-204A
  • V-820 MOV-313(RCP Seal) Close the following valves: (SWRF ROOM

[reach rods])

  • V-315A
  • V-315C AOV-9227(Fire Sys) (Normally closed, and does NOT receive CI signal)
  • Close V-9225 (IB BASEMENT CLEAN SIDE)

AOV-508(RMW) Close the following valves: (MCB)

  • AOV-548
  • AOV-550A
  • AOV-550B

EOP: TITLE:

REV: 9 ATT-3.0 ATTACHMENT CI/CVI PAGE 2 of 4 AUTO ISOL VALVE ALTERNATE ISOL AOV-5738(S/G B/D) Close V-5701 (IB BASEMENT CLEAN SIDE)

AOV-5737(S/G B/D) Close V-5702 (IB BASEMENT CLEAN SIDE)

AOV-5735(S/G Samr z) Close V-5733 (SAMPLE HOOD)

AOV-5736(S/G Samr )) Close V-5734 (SAMPLE HOOD)

SOV-921(H2 Mon) Close V-928A (INSIDE A H2 MON PNL, AFW PUMP AREA, key #38 required)

SOV-922(H2 Mon) Close V-928B (INSIDE A H2 MON PNL, AFW PUMP AREA, key #38 required)

SOV-923(H2 Mon) Close V-929A (INSIDE B H2 MON PNL, AFW PUMP AREA, key #38 required)

SOV-924(H2 Mon) Close V-929B (INSIDE B H2 MON PNL, AFW PUMP AREA, key #38 required)

AOV-539(PRT gas) Close V-546 (BY SFP HX A)

AOV-1789(RCDT to gas anal)

Close V-1655 (BY SFP HX A)

AOV-1786(RCDT/VH) Close AOV-1787 (MCB)

AOV-1787(RCDT/VH) Close AOV-1786 (MCB)

AOV-1721(RCDT Pumps) Close the following valves:

  • AOV-1003A (WASTE PANEL)
  • AOV-1003B (WASTE PANEL)
  • V-1722 (AB SUB-BASEMENT, NORMALLY LOCKED CLOSED)

AOV-1003A(RCDT Pump A) Close AOV-1721 (WASTE PANEL)

AOV-1003B(RCDT Pump B) Close AOV-1721 (WASTE PANEL)

AOV-1597(CNMT rad) Close V-1596 (IB BASEMENT CLEAN SIDE)

AOV-1598(CNMT rad) Close AOV-1599 (MCB)

AOV-1599(CNMT rad) Close AOV-1598 (MCB)

EOP: TITLE: REV: 9 ATT-3.0 ATTACHMENT CI/CVI PAGE 3 of 4 AUTO ISOL VALVE ALTERNATE ISOL MOV-813 (CCW) Locally close MOV-813 (AB Int Level). IF MOV-813 can not be closed, THEN perform the following:

1) Direct AO with locked valve key to unlock and close breaker for MOV-817 (MCC D POS 10C)
2) Stop both RCPs
3) Manually close MOV-817 (MCB). IF MOV-817 will not close, THEN direct AO to locally close MOV-817 (AB INT LEVEL).

MOV-814(CCW) Close V-815A (AB INT LEVEL)

AOV-1723(CNMT sump) Perform the following:

1) Place BOTH CNMT Sump Pumps in PULL-STOP (MCB REAR)
2) Close AOV-1728 (WASTE PANEL)

AOV-1728(CNMT sump) Perform the following:

1) Place BOTH CNMT Sump Pumps in PULL-STOP (MCB REAR)
2) Close AOV-1723 (WASTE PANEL)

AOV-951(PRZR STM samp) Close AOV-966A (MCB)

AOV-953(PRZR Liq samp) Close AOV-966B (MCB)

AOV-955 (Hot Leg samp) Close AOV-966C (MCB)

AOV-959(RHR samp)

(fuses normally pulled)

Close V-957 (PRIMARY SAMPLE ROOM, normally closed)

AOV-966A(PRZR STM samp) Close V-956F (SAMPLE HOOD)

AOV-966B(PRZR Liq samp) Close V-956E (SAMPLE HOOD)

AOV-966C(Hot Leg samp) Close V-956D (SAMPLE HOOD)

AOV-846(Accum N2) Close the following valves:

(BY SFP HX A)

  • V-8629
  • V-944A

EOP: TITLE:

REV: 9 ATT-3.0 ATTACHMENT CI/CVI PAGE 4 of 4 AUTO ISOL VALVE ALTERNATE ISOL AOV-8418(DI Water) Close V-5021 (IB BASEMENT CLEAN SIDE)

AOV-7971 (Mini-purge) Close AOV-7970 (MCB REAR)

AOV-7970 (Mini-purge) Close AOV-7971 (MCB REAR)

AOV-7445 (Mini-purge) Close AOV-7478 (MCB REAR)

AOV-7478 (Mini-purge) Close AOV-7445 (MCB REAR)

AOV-5879(CNMT purge) N/A FLANGED AOV-5869(CNMT purge) N/A FLANGED SOV-1B (10214S1) Close V-1080A (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-2B (10214S) Close V-1080A (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-3B (10211S1) Close V-1076B (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-5B (10213S1) Close V-1084B (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-lA (10215S1) Close V-1080A (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-2A (10215S) Close V-1080A (SAMPLE HOOD, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-3A (10205S1) Close V-1076A (IB BASEMENT CLEAN SIDE, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

SOV-5A (10209S1) Close V-1084A (IB BASEMENT CLEAN SIDE, (H2 recomb) NORMALLY LOCKED CLOSED)

(normally de-energized)

EOP: TITLE:

REV: 3 9 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 29 GINNA STATION CONTROLLED COPY NUMBER X_ _

RESPONSIBLO MANAGER

-/S-IE DATE EFC EFFECTIVE DATE' CATEGORY 1.0

)REVIEWED BY:

MOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 2 of 29 A. PURPOSE - This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.

B. ENTRY CONDITIONS/SYMPTOMS

1. The following are symptoms that require a reactor trip, if one has not occurred:

o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

2. The following are symptoms of a reactor trip:

o Any First Out reactor trip annunciator lit.

o A rapid decrease in core neutron level as indicated by nuclear instrumentation.

o MRPI indicates all control and shutdown rods on bottom.

o Reactor trip breakers indicate open.

3. The following are symptoms that require a reactor trip and safety injection, if one has not occurred:

o Any plant parameter reaches the Safety Injection setpoint and logic listed in procedure P-i, REACTOR CONTROL AND PROTECTION SYSTEM.

o Operator discretion.

4. The following are symptoms of a reactor trip and safety injection:

o Any SI annunciator lit.

o Safeguards sequencing started.

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE 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 reactor will NOT trip OR IF power range NIS indicates greater than 5%, THEN go to FR-S.1.

RESPONSE TO REACTOR RESTART/ATWS, Step 1 Verify Turbine Stop Valves - Manually trip turbine.

CLOSED IF turbine trip can NOT be verified, THEN close both MSIVs.

0 Verify Both Trains Of AC Emergency Busses Energized To Attempt to start any failed emergency D/G to restore power to At Least 420 VOLTS: all AC emergency busses.

o Bus 14 and Bus 18 IF Bus 14 AND Bus 16 are deenergized. THEN go to ECA-O.O, o Bus 16 and Bus 17 LOSS OF ALL AC POWER, Step 1.

TITLE:

EOP:

EOP: lTIRE: lREV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION l ~PAGE 4 of 29l STEP ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED 0 Check if SI is Actuated:

a. Any SI Annunciator - LIT a. IF any of the following conditions are met, THEN manually actuate SI and CI:

o PRZR pressure less than 1750 psig

-OR-o Steamline pressure less than 514 psig

-OR-o CNMT pressure greater than 4 psig

-OR-o SI sequencing started

-OR-o Operator determines SI required IF SI i NOT required. THEN go to ES-O.1, REACTOR TRIP RESPONSE. Step 1.

b. SI sequencing - BOTH TRAINS b. Manually actuate SI and CI.

STARTED.

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 29 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open and monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

5 Verify SI and RHR Pumps Running:

a. All SI pumps - RUNNING a. Manually start SI pumps. I
b. Both RHR pumps - RUNNING b. Manually start RHR pumps. I 6 Verify CNMT RECIRC Fans Running:
a. All fans - RUNNING a. Manually start fans.
b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED with relay rack key to locally open dampers by pushing in trip relay plungers.
  • AUX RELAY RACK RA-2 for fan A
  • AUX RELAY RACK RA-3 for fan C

EOP: TIRE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION l PAGE 6 of 29 SP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

  • 7 Verify CNMT Spray Not Verify CNMT spray initiated.

Required:

IF CNMT spray NOT initiated, THEN o Annunciator A-27, CNMT SPRAY - perform the following:

EXTINGUISHED

a. Depress manual CNMT spray o CNMT pressure - LESS THAN 28 PSIG pushbuttons (2 of 2).
b. Ensure CNMT spray pumps running.

IF no CNMT spray pump available, THEN go to Step 8.

c. Ensure CNMT spray pump discharge valves open for operating pump(s).

o CNMT spray pump A:

  • MOV-860A

. MOV-860B o CNMT spray pump B:

  • MOV-860C

. MOV-860D

d. Verify NaOH flow (FI-930)

IF NaOH flow NOT indicated. THEN place switches for NaOH tank outlet valves to OPEN.

  • AOV-836A
  • AOV-836B

EOP: TITLE:

REV: 3 9 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 29 8 Check If Main Steamlines Should Be Isolated:

a. Any MSIV - OPEN a. Go to Step 9.
b. Check CNMT pressure - LESS THAN b. Ensure BOTH MSIVs closed and go 18 PSIG to Step 9.
c. Check if ANY main steamlines c. Go to Step 9.

should be isolated:

o Low Tavg (5450F) AND high steam flow (0.4x106 lb/hr) from either S/G

-OR-o High-High steam flow (3.6x10 6 lb/hr) from either S/G

d. Verify MSIV closed on the d. Manually close valves.

affected S/G(s) 9 Verify MFW Isolation:

a. MFW pumps - TRIPPED a. Perform the following:.
1) Manually close MEW pump discharge valves and trip MFW pumps.
2) Continue with Step 9c. WHEN both MEPs are tripped, THEN perform Step 9b.
b. Depress MANUAL pushbuttons for A and B S/G MEW regulating valve and bypass valve controllers AND adjust to 0% demand.
c. SIG blowdown and sample valves - c. Place S/G blowdown and sample CLOSED valve isolation switch to CLOSE.

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 10 Verify Both MDAFW Pumps Manually start both MDAFW pumps.

Running IF less than 2 MDAFW pumps are running. THEN manually open TDANW pump steam supply valves.

  • MOV-3505A
  • MOV-3504A 11 Verify At Least Two SW Pumps Perform the following:

- RUNNING

a. Ensure one SW pump running on each energized screenhouse AC emergency bus:
  • Bus 17

. Bus 18

b. IF offsite power NOT available, THEN ensure SW isolation.
c. IF NO SW pumps running, THEN perform the following:
1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4. ATTACHMENT NO SW PUMPS.

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 29 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED I 12 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
b. Verify CI and CVI valve status b. Manually close affected CI and lights - BRIGHT CVI valve(s).

IF valve(s) can NOT be closed from the MCB, THEN close alternate isolation valve(s).

(Refer to ATT-3.0, ATTACHMENT CI/CVI).

c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

  • FCV-4561
  • FCV-4562
d. Letdown orifice valves - CLOSED d. Place affected valve switch to CLOSE. IF valves can NOT be
  • AOV-200A verified closed by MCB

. AOV-200B indication. THEN close alternate

  • AOV-202 isolation valve(s). (Refer to ATT-3.0, ATTACHMENT CI/CVI)

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 10 of 29 S y s t e mPStatu 1CkION/CCWON 13 Check CCW System Status:

a. Verify CCW pump - AT LEAST ONE a. IF offsite power available, THEN RUNNING manually start one CCW pump.
b. Place switch for excess letdown AOV-310 to CLOSE
c. Place switch for CCW from excess letdown, AOV-745 to CLOSE 14 Verify SI And RHR Pump Flow:
a. SI flow indicators - CHECK FOR a. IF RCS pressure less than ELOW 1400 psig, THEN manually start pumps and align valves. IF NOT, THEN go to Step 15.
b. RHR flow indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig, THEN manually start pumps and align valves. IF NOT.

THEN go to Step 15.

15 Verify AFW Valve Alignment: Manually align valves as necessary.

a. AFW flow - INDICATED TO BOTH SI/G(s)
b. AFW flow from each MDAFW pump -

LESS THAN 230 GPM

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 29 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED l

  • 16 Monitor Heat Sink:
a. Check SIG narrow range level - a. Perform the following:

GREATER THAN 7% [25% adverse CNMT] in any S/G 1) Verify total AEW flow -

GREATER THAN 200 GPM IF total AEW is less than 200 gpm, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow. IF AFW flow greater than 200 gpm can NOT be established. THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

2) Go to Step 17.
b. Check S/G narrow range level - b. Secure AEW flow to any S/G with BOTH S/G LESS THAN 50% level above 50%.
c. Control feed flow to maintain S/G narrow range level between 7% [25% adverse CNMTI and 50%.

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED -

17 Verify SI Pump And RHR Pump Emergency Alignment:

a. RER pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

  • MOV-852A
  • MOV-852B
b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
c. Verify SI pump A - RUNNING c. Perform the following:
1) Ensure SI pumps B and C running.. IF either pump NOT, running, THEN go to Step 17e.
2) Ensure SI pump C aligned to discharge ine A:

o MOV-871A open o MOV-871B closed

3) Go to Step 18.
d. Verify SI pump B - RUNNING d. Perform the following:
1) Ensure SI pumps A and C running. IF either pump NOT.

running, THEN go to Step 17e.

2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 18.
e. Verify SI pump C discharge e. Manually open valves as valves - OPEN necessary.
  • MOV-871A
  • MOV-871B

EOP: TITLE: REV: 39 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 29 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFESITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 18 Check CCW Flow to RCP Thermal IF CCW to a RCP is lost, THEN Barriers: perform the following:

o Annunciator A-7, RCP 1A CCW a. Stop affected RCPs.

RETURN HI TEMP OR LO FLOW -

EXTINGUISHED b. Reset SI.

o Annunciator A-15, RCP 1B CCW c. Verify adequate power available RETURN HI TEMP OR LO FLOW - to run one charging pump (75 kw).

EXTINGUISHED

d. Start one charging pump at minimum speed for seal injection.
e. Adjust HCV-142 to establish either of the following:

o Labyrinth seal D/P to each RCP greater than 15 inches of water.

-OR-o RCP seal injection flow to each RCP greater than 6 gpm.

f. IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.

EOP: TiTLE:REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 14 of 29 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped:

a. Both MDAFW pumps - RUNNING a. Go to Step 20.
b. PULL STOP TDAFW pump steam supply valves
  • MOV-3504A
  • MOV-3505A
  • 20 Monitor RCS Tavg - STABLE AT IF temperature less than 547%F and OR TRENDING TO 547° F decreasing, THEN perform the following:
a. Stop dumping steam.
b. Ensure reheater steam supply valves are closed.
c. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 7% [25%

adverse CNMT] in at least one S/G.

d. WHEN S/G level greater than 7%

[25% adverse CNMT] in one SIG, THEN limit feed flow to that required to maintain level in at least one S/G.

e. IF cooldown continues, THEN close both NSIVs.

IF temperature greater than 5470 F and increasing, THEN dump steam to stabilize and slowly decrease temperature to 5470F.

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 29 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDI 21 Check PRZR PORVs And Spray Valves:

a. PORVs - CLOSED a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

IF any valve can NOT be closed, THEN manually close its block valve.

  • MOV-516 for PCV-430
  • MOV-515 for PCV-431C IF block valve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Step 1.

b. Auxiliary spray valve (AOV-296) b. Manually close auxiliary spray

- CLOSED valve. IF valve can NOT be closed, THEN perform the following:

1) Decrease charging pump flow to minimum.
2) Ensure charging valve to loop B cold leg open (AOV-294).
c. Check PRZR pressure - LESS THAN c. Continue with Step 22. WHEN 2260 PSIG pressure less than 2260 psig.

THEN do Step 21d.

d. Normal PRZR spray valves - CLOSED d. Place controllers in MANUAL at 0% demand. IF valves can NOT be
  • PCV-431A closed, THEN stop associated
  • PCV-431B RCP(s).

EOP: TITLE:REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION l PAGE 16 of 29 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 22 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING a. Go to Step 23.
b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 23.
c. RCS pressure minus maximum SIG c. Go to Step 23.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs 23 Verify CREATS Actuation: I
a. At least one damper in each a. Depress both CREATS actuation flowpath - CLOSED pushbuttons
  • Normal Supply Air
  • CONTROL ROOM MANUAL ISOLATION A
  • Normal Return Air
  • CONTROL ROOM MANUAL ISOLATION B
  • Lavatory Exhaust Air
b. CREATS fans - BOTH RUNNING b. Start both CREATS fans 24 Check If SIG Secondary Side IF any S/G pressure decreasing in Is Intact:. an uncontrolled manner OR completely depressurized. THEN go o Pressure in both S/Gs - STABLE to E-2, FAULTED STEAM GENERATOR OR INCREASING ISOLATION. Step 1.

o Pressure in both S/Gs - GREATER THAN 110 PSIG

EOP: TITLE:

REV: 3 9 E-0 REACTOR TRIP OR SAFETY INJECTION 2

. ~PAGE 17 of 29l ACTION/EXPECTED RESPONSE STEP [RESPONSE NOT OBTAINED 25 Check If SIG Tubes Are Intact: Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL 26 Check If RCS Is Intact: Go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

a. CNMT area radiation monitors -

NORMAL

  • R-2
  • R-7
  • R-29
  • R-30
b. CNMT pressure - LESS THAN 0.5 PSIG
c. CNMT sump B level - LESS THAN 8 INCHES
d. CNMT sump A level o Level - STABLE o Annunciator C-19, CONTAINMENT SUMP A HI LEVEL - EXTINGUISHED

EOP: TITLE:

REV: 39 E-O REACTOR TRIP OR SAFETY INJECTION l PAGE 18 of 29

_ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check If SI Should Be Terminated:

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 28.

o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit TICs - GREATER THAN 0 0F Step 28.

USING FIG-1.O. FIGURE MIN SUBCOOLING

c. Secondary heat sink: c. IF neither condition met, THEN do NOT stop SI pumps. Go to o Total feed flow to S/Gs - Step 28.

GREATER THAN 200 GPM

-OR-o Narrow range level in at least one SIG - GREATER THAN 7%

d. PRZR level - GREATER THAN 10% d. Do NOT stop SI pumps. Perform the following:
1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
2) Go to Step 28.
e. Go to ES-1.1, SI TERMINATION.

Step 1.

EOP: TITLE:

REV: 3 9 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 19 of 29 WACTION/EXPECTED

-LEI§-

RESPONS RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o The Critical Safety Function Red Path Summary is available in APPENDIX 1.

28 Initiate Monitoring of Critical Safety Function Status Trees

  • 29 Monitor S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% than 200 gpm until narrow range level greater than 7% in at least one SIG.
b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.

30 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels - NORMAL RUPTURE, Step 1.

o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 29 CAUTION IF OFESITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFESITE POWER) 31 Reset SI 32 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26. CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 33 Verify Adequate SW Flow:

a. At least three SW pumps - RUNNING a. Manually start SW pumps as power supply permits (257 kw each).

IF less than three pumps running, THEN ensure SW isolation.

IF NO SW pumps running. THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

IF only one SW pump running, THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0, ATTACHMENT SD-1)

EOP: TITLE:

. REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 29 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE 34 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
2) Verify adequate emergency D/G capacity to run air compressor(s) (75 kw each).

IF NOT, THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped.

(Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS

3) WHEN bus 15 is restored, THEN reset control room lighting.
b. Check SW Pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)
2) Go to step 34d.

This Step continued on the next page.

EOP: TITLE:

REV: 39 E-O REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 29 S- ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I (Step 34 continued from previous page)

c. Verify SW isolation valves to c. Perform the following:

turbine building - OPEN

1) Manually align valves.

. MOV-4613 and NOV-4670

  • MOV-4614 and MOV-4664 2) Dispatch AO to locally reset compressors as necessary.
d. Verify adequate air d. Manually start electric air compressor(s) - RUNNING compressor(s) as power supply permits (75 kw each).

IF electric air compressor can NOT be started, THEN start diesel air compressor. (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

e. Check IA supply: e. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 35. WHEN IA restored, THEN do Steps 34f and g.

f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN

TITLE:

EOP:

EOP: TITLE: R V REV: 3 9 E-O REACTOR TRIP OR SAFETY INJECTION

. PAGE 24 of 29 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINEDl -

35 Check Auxiliary Building Evaluate cause of abnormal Radiation - NORMAL conditions.

  • Plant vent iodine (R-1OB) IF the cause is a loss of RCS
  • Plant vent particulate (R-13) inventory outside CNMT, THEN go to
  • Plant vent gas (R-14) ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
  • CCW liquid monitor (R-17)
  • LTD line monitor (R-9)
  • CHG pump room (R-4) 36 Check PRT Conditions Evaluate the following flowpaths for cause of abnormal conditions:

o PRT level (LI-442) - LESS THAN 84%

  • RCP seal return relief
  • PRZR PORVs o PRT temperature (TI-439) - LESS
  • PRZR safeties THAN 120 0 F
  • Letdown line relief o PRT pressure (PI-440A) - LESS IF excess letdown previously in THAN 3 PSIG service, THEN close AOV-310, excess letdown isolation valve from loop A cold.

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 29

  • * * * * * * * * * * * * * * * * * * * * * * * * * *D * * * * * * * * * * * * *
  • CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
  • * * * * * * * * * * * * * * * * * * * *~ * * * * * * * * * * * * * * * * * * * *
  • 37 Monitor If RHR Pumps Should Be Stopped:
a. Check RCS pressure:
1) Pressure - GREATER THAN 1) Go to E-1, LOSS OF REACTOR OR 250 PSIG SECONDARY COOLANT. Step 1.
2) Pressure - STABLE OR 2) Go to Step 38.

INCREASING

b. Stop both RHR pumps and place in AUTO 38 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker -

CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.0, ATTACHMENT CNMT RECIRC CLOSED FANS).

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 29 39 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO to close seal injection needle valve(s) to affected RCP:
  • V-300A for RCP A
  • V-300B for RCP B
2) Ensure HCV-142 open, demand at 0%.
b. Charging pump suction aligned to b. Manually align valves.

RWST:

IF LCV-112B can NOT be opened, o LCV-112B - OPEN THEN dispatch AO to locally open V-358, manual charging pump o LCV-112C - CLOSED suction from RWST (charging pump room).

IF LCV-112C can NOT be closed, THEN perform the following:

1) Direct AO to locally open V-358. manual charging pump suction from RWST (Charging Pump Room).
2) Verify charging pump A NOT running and place in PULL STOP.
3) WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 27 of 29 ACTION/EXPECTED RESPONSE IRESPONSE NOT OBTAINED 40 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

EOP: TITLE:

I REV: 39 E-O REACTOR TRIP OR SAFETY INJECTION I PAGE 28 of 29 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINEDl 41 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Perform the following:

energized by offsite power:

1) Verify non-safeguards bus tie o Emergency D/G output breakers breakers closed:

- OPEN

  • Bus 13 to Bus 14 tie o AC emergency bus voltage -
  • Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
2) Place the following pumps in o AC emergency bus normal feed PULL STOP:

breakers - CLOSED

  • EH pumps
  • Turning gear oil pump

. HP seal oil backup pump

3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:
  • A from Bus 13
  • B from Bus 15

. E from Bus 15

. F from Bus 15

5) Start HP seal oil backup pump.
6) Ensure D/G load within limits.
7) Refer to ATT-8.4. ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
8) Try to restore offsite power (Refer to ER-ELEC.I.

RESTORATION OF OFESITE POWER).

b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1. ATTACHMENT D/G STOP)

EOP: TITLE: REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 29 of 29 42 Return to Step 20

-END-

EOP: TITLE:

REV: 39l E-O REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 E-0 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)
3) ATTACHMENT CI/CVI (ATT-3.0)
4) ATTACHMENT SD-1 (ATT-17.0)
5) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
6) ATTACHMENT D/G STOP (ATT-8.1)
7) ATTACHMENT SI/U (ATT-8.4)
8) ATTACHMENT NO SW PUMPS (ATT-2.4)
9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
11) FOLDOUT

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%
b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 7%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 39 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
a. SI pumps - AT LEAST TWO RUNNING
b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG

[400 psig adverse CNMT]

2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

r EOP: TITLE:

REV: 3 3 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 23 GINNA STATION CONTROLLED COPY NUMBER C )

RESPONSIB E MANAGER i? -/§,a o EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 23 A. PURPOSE - This procedure provides actions to recover from a loss of reactor or secondary coolant.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-0, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
b. E-0, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
c. E-0, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.
d. ES-1.1, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
f. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.
g. ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.
h. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.
i. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.

EOP: TITLE: REV 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT l lPAGE 3 of 23 o ACTION/EXPECTED RESPObE iredPperiOdically.

NOTE: o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.)

o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-l.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNNT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

1 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING a. Go to Step 2.
b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 2.
c. RCS pressure minus maximum S/G c. Go to Step 2. I pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs
  • 2 Check If RHR Should Be Throttled: I
a. Check RWST level - LESS THAN 70% l a. Continue with Step 3. WHEN RWST
b. Direct an AO to perform level less than 70%. THEN perform step 2b.
b. Manually adjust RHR Hx outlet I

ATT-14.7, ATTACHMENT ADJUST RHR valves equally to reduce flow to FLOW to locally adjust HCV-624 less than 1500 gpm per operating and HCV-625. pump

  • RHR Hx A, HCV-625
  • RHR Hx B. HCV-624 I

.EOP: TITLE: RV E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 4 of 23 P

ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 3 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized, THEN o Pressure in both SIGs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

o Pressure in both S/Gs - GREATER

  • Steamlines THAN 110 PSIG
  • Feedlines IF NOT, THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION. Step 1.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

  • 4 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% [25% adverse CNMTI than 200 gpm until narrow range level greater than 7% [25%

adverse CNMT] in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an

[25% adverse CNMTI and 50% uncontrolled manner., THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

  • 5 Monitor If Secondary IF steamline radiation monitors NOT Radiation Levels Are Normal available, THEN dispatch AO to locally check steamline radiation.

o Steamline radiation monitor (R-31 and R-32) IF abnormal radiation levels detected in any S/G, THEN go to o Request RP sample S/Gs for E-3, STEAM GENERATOR TUBE RUPTURE, activity Step 1.

EOP: TIRE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 23 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 6B).

  • 6 Monitor PRZR PORV Status:
a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
  • MOV-515, MCC D position 6C
  • MOV-516, MCC C position 6C
b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.

  • MOV-515. MCC D position 6C
  • MOV-516, MCC C position 6C
c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 23 SP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED CAUTION -

IF OFESITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER)

- 7 Reset SI 8 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 23 ACTION/EXPECTED RESPONSEl RESPONSE NOT OBTAINED 9 Verify Adequate SW Flow:

a. Check at least two SW pumps - a. Manually start SW pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps running, THEN perform the following:

1) Ensure SW isolation.
2) IF NO SW pumps running. THEN perform the following:

a) Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

3) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.O. ATTACHMENT SD-1)

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 23 STP ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED 10 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR-

  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT, THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR

-OR-o Evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS).

3) WHEN bus 15 restored, THEN reset control room lighting.
b. Check SW pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)
2) Go to step lOd.

This Step continued on the next page.

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 10 continued from previous page)

c. Verify turbine building SW c. Perform the following:

isolation valves - OPEN

1) Manually align valves.
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664 2) Dispatch AO to locally reset compressors as necessary.
d. Verify adequate air compressors d. Manually start electric air

- RUNNING compressors as power supply permits (75 kw each). IF electric air compressors can NOT be started, THEN start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR).

e. Check IA supply: e. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 11. WHEN IA restored, THEN do Steps lOf and g.

f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 23l ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINEDl 11 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker -

CLOSED IF NOT. THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker - to ATT-4.O, ATTACHMENT CNMT RECIRC CLOSED FANS).

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 12 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offacale high, THEN dispatch AO to close seal injection needle valve(s) to affected RCP:
  • V-300A for RCP A
  • V-300B for RCP B
2) Ensure HCV-142 open, demand at 0%.
b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.

o LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN dispatch AO to locally open o LCV-112C - CLOSED V-358, manual charging pump suction from RWST (charging pump room).

IF LCV-112C can NOT be closed, THEN perform the following:

1) Direct AO to locally open V-358, manual charging pump suction from RWST (charging pump room).
2) Verify,charging pump A NOT running and place in PULL STOP.
3) WHEN V-358 open. THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

EOP: T1TLE:

E-1 LOSS OF REACTOR OR SECONDATRY COOLA7NT PAGE 12 of 23 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 13 Check If SI Should Be Terminated:

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 14.

o Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]

o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 0 0F Step 14.

USING FIG-1.O, FIGURE MIN SUBCOOLING

c. Secondary heat sink: c. IF neither condition satisfied, THEN do NOT stop SI pumps. Go o Total feed flow to intact to Step 14.

S/Gs - GREATER THAN 200 GPM

-OR-o Narrow range level in at least one intact S/G -

GREATER THAN 7% [25% adverse CNMT]

d. PRZR level - GREATER THAN 10% d. Do NOT stop SI pumps. Perform

[30% adverse CNMT] the following:

1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
2) Go to Step 14.
e. Go to ES-1.1. SI TERMINATION.

Step 1.

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 23 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 14 Monitor If CNMT Spray Should Be Stopped:
a. CNMT spray pumps - ANY RUNNING a. Go to Step 15.
b. Determine number of CNMT spray pumps required from table:

CNMT CNMT CNMT RECIRC FANS SPRAY PUMPS PRESSURE RUNNING REQUIRED GREATER THAN 60 PSIG 2 BETWEEN 28 PSIG AND 60 PSIG - 2 AND INCREASING BETWEEN 0 OR 1 2 28 PSIG AND 60 PSIG AND DECREASING 2, 3, OR 4 1 LESS THAN 28 PSIG 1 This Step continued on the next page.

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14 of 23 ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED I (Step 14 continued from previous page)

c. CNMT spray pumps running - EQUAL c. Start or stop CNMT spray pumps TO NUMBER REQUIRED as necessary to meet table requirements.

IF CNMT spray pump is to be stopped, THEN perform the following:

1) Place CNMT spray pump in PULL STOP.
2) IF CNMT pressure less than 28 psig, THEN perform the following:

a) Place NaOH Tank outlet valve switches to OPEN

  • AOV-836A
  • AOV-836B b) Reset CNMT spray c) Close discharge valves for idle CNMT spray pump.

o Pump A

. MOV-860A

  • MOV-860B

-OR-o Pump B

  • MOV-860C
  • MOV-860D
d. Verify CNMT pressure - STABLE OR d. IF all available CNMT spray DECREASING pumps are running. THEN go to Step 15.

IF NOT, THEN return to Step 14b.

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15 of 23 STE ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED a, * * *e * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

  • CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMTI, THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
  • * * * * * * * *
  • i* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • 15 Monitor If RHR Pumps Should Be Stopped:
a. RHR pumps - ANY RUNNING IN a. Go to Step 16.

INJECTION MODE

b. Check RCS pressure:
1) Pressure - GREATER THAN 1) Go to Step 17.

250 psig [465 psig adverse CNMT]

2) RCS pressure - STABLE OR 2) Go to Step 16.

INCREASING

c. Stop RHR pumps and place in AUTO 16 Check RCS And SIG Pressures
a. Check pressures in both S/Gs - a. Return to Step 1.

STABLE OR INCREASING

b. Check pressures in both S/Gs - b. Monitor RCS pressure.- IF RCS GREATER THAN 110 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.
c. Check RCS pressure - STABLE OR c. Return to Step 1.

DECREASING

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT l ~PAGE 16 o f 2 3 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl SP 17 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Perform the following:

energized by offsite power:

1) Close non-safeguards bus tie o Emergency DIG output breakers breakers as necessary:

- OPEN

  • Bus 13 to Bus 14 tie o AC emergency bus voltage -
  • Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
2) Place the following pumps in o AC emergency bus normal feed PULL STOP:

breakers - CLOSED

  • EH pumps
  • Turning gear oil pump
  • HP seal oil backup pump
3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:
  • A from Bus 13
  • B from Bus 15
  • E from Bus 15
  • F from Bus 15
5) Start HP seal oil backup pump.
6) Ensure DIG load within limits.
7) WHEN bus 15 restored, THEN reset control room lighting breaker.
8) Refer to ATT-8.4, ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
9) Try to restore offsite power (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER).

b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1. ATTACHMENT D/G STOP)

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 17 of 23 ACTION/EXPECTED RESPONSE STEP SPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:

a. Check RHR and CCW systems: a. IF at least one flowpath of cold leg recirculation capability can
1) At least one recirculation NOT be verified, THEN go to flowpath. including required ECA-1.1, LOSS OF EMERGENCY power supplies, from Sump B COOLANT RECIRCULATION, Step 1.

and back to RCS available per ATT-14.5, ATTACHMENT RHR SYSTEM

2) At least one CCW pump available.
3) At least one CCW Hx available.
b. Check SW pumps - AT LEAST 2 b. Attempt to restore at least 2 SW PUMPS AVAILABLE pumps to operable.

IF only 1 SW pump available, THEN refer to ATT-2.1, ATTACHMENT MIN SW for additional guidance.

IF no SW pumps are available.

THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3) Go to ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION.
c. Dispatch AO to check AUX BLDG c. IF any RHR pump seal leakage sub-basement for RHR system indicated. THEN leakage should leakage (AUX BLDG sub-basement be evaluated and isolated if key may be required) necessary.

EOP: TITLE: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT l PAGE 18 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 19 Evaluate Plant Status:

a. Check auxiliary building a. Notify RP and refer to radiation - NORMAL appropriate AR-RMS procedure.
  • Plant vent iodine (R-1OB) IF the cause is a loss of RCS
  • Plant vent particulate (R-13) inventory outside CNMT, THEN go
  • Plant vent gas (R-14) to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
  • CCW liquid monitor (R-17)
  • LTDN line monitor (R-9)
  • CHG pump room (R-4)
b. Direct RP to obtain following samples:
c. Verify adequate Rx head cooling:
1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
2) Verify one Rx compartment 2) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT l PAGE 19 of 23 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 20 Check If RCS Cooldown And Depressurization Is Required:

a. RCS pressure - GREATER THAN a. IF RHR pump flow greater than 250 psig [465 psig adverse CNMT] 475 gpm, THEN go to Step 21.
b. Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION. Step 1

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 20 of 23 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINEDl NOTE: IF D/Gs supplying emergency AC busses. THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.

21 Establish Adequate SW Flow:

a. Verify at least two SW pumps - a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only 1 SW pump operable, THEN perform the following:
1) Ensure ATT-2.1, ATTACHMENT MIN SW is in progress.
2) Go to Step 22.

IF no SW pumps are available, THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3) Go to ECA-1.l, LOSS OF EMERGENCY COOLANT RECIRCULATION.
b. Verify AUX BLDG SW isolation b. Manually align valves.

valves - OPEN

  • MOV-4615 and MOV-4734
  • MOV-4616 and MOV-4735 This Step continued on the next page.

EOP: TITLE:

REV: 3 3 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 23 SP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED]

(Step 21 continued from previous page)

c. Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs REQUIRED SW FLOW ALIGNMENT AVAILABLE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service EX Alternate 2 30 - 33 inches d/p across each HX Alternate 1 95 - 100 inches d/p across in-service HX

d. Direct AO to adjust SW flow to d. IF the required SW flow can NOT required value be obtained, THEN perform the following:

o IF on normal SW discharge:

1) Isolate SW to screenhouse and
  • MOV-4609/MOV-4780 - AT

-OR- LEAST ONE CLOSED

  • NOV-4663/MOV-4733 - AT o IF on alternate SW discharge: LEAST ONE CLOSED
  • V-4619C, CCW HX A 2) Direct AO to locally adjust
  • V-4620B, CCW EX B SW flow to required value.
3) Direct AO to locally isolate SW return from SEP Hxs:
  • SEP Ex A (V-4622) (for alternate SW discharge use V-4622A)
  • SEP Hx B (V-8689)
4) Verify SW portions of ATT-17.0, ATTACHMENT SD-1 are complete.

EOP: TITLE:

REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 22 of 23 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 22 Establish CCW flow to RHR Hxs:

a. Check both CCW pumps - RUNNING a. Perform the following:
1) Start CCW pumps as power supply permits (122 kw each)
2) IF both CCW pumps are running. THEN go to step 22b.
3) IF only one CCW pump is running. THEN perform the following:

a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR Loop o Open MOV-738A

-OR-o Open MOV-738B c) Go to step 23.

b. Manually open CCW valves to RHR b. Dispatch AO to locally open Hxs valves.
  • MOV-738A
  • MOV-738B

EOP: TITLE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 23 of 23 ACTION/EXPECTED RESPONSE- l RESPONSE NOT OBTAINED 23 Check If Transfer To Cold Leg Recirculation Is Required:

a. RWST level - LESS THAN 28% a. Return to Step 18.
b. Go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION, Step 1

-END-

IEOP: TITU: REV: 3 3 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)
3) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
4) ATTACHMENT D/G STOP (ATT-8.1)
5) ATTACHMENT SD-1 (ATT-17.0)
6) ATTACHMENT SI/IN (ATT-8.4)
7) ATTACHMENT MIN SW (ATT-2.1)
8) ATTACHMENT NO SW PUMPS (ATT-2.4)
9) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
11) ATTACHMENT RHR SYSTEM (ATT-14.5)
12) ATTACHMENT ADJUST RHR FLOW (ATT-14.7)
13) FOLDOUT

EOP: TITRE: REV: 33 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%
b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 700°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 7%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 3 3 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 2 FOLDOUT PAGE

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
a. Si pumps - AT LEAST TWO RUNNING
b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG [400 psig adverse CNMT]
2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling,AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start Si pumps as necessary:

o RCS subcooling based on core exit T/Cs - LESS THAN 0e F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 10% [30% adverse CNM

4. Si TERMINATION CRITERIA IF ALL conditions listed below occur,THEN go to ES-1.1, Si TERMINATION, Step 1:
a. RCS subcooling based on core exit T/Cs - GREATER THAN 0' F USING FIGURE MIN SUBCOOLING
b. Total feed flow to intact S/Gs - GREATER THAN 200 GPM

-OR-Narrow range level in at least one intact S/G - GREATER THAN 7% [25% adverse CNMT]

c. RCS pressure:

o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]

o STABLE OR INCREASING

d. PRZR level - GREATER THAN 10% (30% adverse CNMT]
5. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurizedAND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
6. E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation.THEN manually start SI pumps as necessaryAND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

EOP: TITLE:

REV: 3 3 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 2

7. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
8. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 25 GINNA STATION CONTROLLED COPY NUMBER 4 3 RESPONSI h MANAGER

/'d -/5-

/S I DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:.

I EOP: TITLE:

REV: 30

-ECA-0.0 LOSS OF ALL AC POWER PAGE 2 of 25 A. PURPOSE - This procedure provides actions to respond to a loss of all AC power.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure may be entered directly or from:
a. E-0, REACTOR TRIP OR SAFETY INJECTION, on the indication that both Bus 14 and Bus 16 are deenergized.
2. SYMPTOMS - Which indicate a loss of all AC power are:
a. Neither 480 volt AC emergency bus 14 nor 16 available.

I EOP: TITLE: RV l REV: 30 ECA-0.0 LOSS OF ALL AC POWER l lPAGE 3 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED CAUTION i DUE TO POTENTIALLY EXTREME ENVIRONMENTAL CONDITIONS, CAUTION SHOULD BE USED WHEN ENTERING THE INTERMEDIATE BLDG FOR LOCAL ACTIONS.

NOTE: o CSFSTs should be monitored for information only. FR procedures should not be implemented.

O Local actions may require portable lighting and communication devices.

o Verify Reactor Trip: Manually trip reactor.

o At least one train of 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.

O Verify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine trip can NOT be verified, THEN close both MSIVs.

TIThE:

EOP:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER l PAGE 4 of 25 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl STP NOTE: FOLDOUT page should be open and monitored periodically.

  • 3 Adjust SIG ARVs To Control Tavg At Approximately 5470F 4 Stop Both RCPs NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNNT radiation is greater than 10+05 R/hr.

5 Check If RCS Is Isolated:

a. PRZR PORVs - CLOSED a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
b. Verify RCS isolation valves closed:
1) Place letdown orifice valve switches to CLOSE
  • AOV-200A
  • AOV-200B
  • AOV-202
2) Place letdown isolation valve switches to CLOSE
  • AOV-371
  • AOV-427
3) Place excess letdown isolation valve switch to CLOSE (AOV-310)

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER A PAGE 5 of 25 ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINEDl 6 Verify Adequate TDAFW Flow:

a. Verify TDAFW pump - RUNNING a. Perform the following:
1) Verify governor valve, V-3652, latched.

IF governor valve tripped, THEN dispatch AO to locally reset valve.

2) Manually or locally open at least one TDAFW pump steam supply valve.
  • MOV-3505A
  • MOV-3504A
b. Verify TDAFW pump flow - GREATER b. Verify proper TDAFW valve THAN 200 GPM alignment:
1) TDAFW pump discharge valve (MOV-3996) open.
2) Intact S/G TDAFW pump flow control valves open.

IF NOT, THEN manually align valves as necessary.

rimE:

EOP:

EOP:

ECA--O.O TITLE:REV:

LOSS OF ALL AC POWER 30 PAGE 6 of 25 I

_STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o AO should increase surveillance of TDAFW pump until AC power is restored.

7 Try To Restore Power to Any Train Of AC Emergency Busses:

a. Verify emergency D/G aligned for a. Manually align switches on rear unit operation of MCB.

o Mode switch in UNIT o Voltage control selector in AUTO

b. Check emergency D/Gs - BOTH D/G b. WHEN non-running D/G available RUNNING for starting. THEN perform the following:
1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G starts. THEN go to Step 7c.
5) IF D/G will NOT start, THEN dispatch AO to locally start emergency D/Gs.

IF no emergency D/G available, THEN perform the following:

a) Direct AO to attempt to restore emergency D/G (Refer to ER-D/G.1, RESTORING D/G) b) Go to Step 8.

This Step continued on the next page.

EOP: TITLE:

REV- 30 ECA-O.O LOSS OF ALL AC POWER PAGE 7 of 25 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I (Step 7 continued from previous page)

c. Check D/G voltage and frequency
1) Voltage - APPROXIMATELY 480v 1) Adjust voltage control to restore voltage to approximately 480v
2) Frequency - APPROXIMATELY 60 2) Adjust governor to restore Hz frequency to approximately 60 Hz
d. Verify adequate D/G cooling d. Manually energize busses and start SW Pumps.

o Bus 17 and/or Bus 18 -

ENERGIZED IF adequate cooling can NOT be supplied to a running D/G. THEN o One SW Pump running for each perform the following:

running D/G

1) Pull stop the D/G AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Align alternate cooling (Refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs).
e. Verify at least one train of AC e. Manually energize AC emergency emergency busses - ENERGIZED busses.
  • Bus 14 and Bus 18 IF Bus 14 AND Bus 16 are
  • Bus 16 and Bus 17 deenergized, THEN go to Step 8.
f. Return to procedure and step in effect

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o WHEN POWER IS RESTORED TO BUS 14 AND/OR BUS 16, RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 27.

o IF AN SI SIGNAL EXISTS OR IF AN SI SIGNAL IS ACTUATED DURING THIS PROCEDURE, IT SHOULD BE RESET TO PERMIT MANUAL LOADING OF EQUIPMENT ON AN AC EMERGENCY BUS.

8 Establish The Following Equipment Alignment:

a. Pull stop AC emergency bus loads
  • RER pumps
  • Charging pumps
b. Evaluate non-vital loads (Refer to ATT-8.3, ATTACHMENT NONVITAL)
c. Place non-running SW pump switches to STOP, then return to AUTO
d. Place switch for MOV-313. RCP seal return isolation valve, to CLOSE
e. Momentarily place to CLOSE RCP CCW return valves
  • MOV-759A
  • MOV-759B

EOP: TITLE: REV: 30 ECA-0.O LOSS OF ALL AC POWER PAGE 9 of 25 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Temporary power may be provided to Bus 16 by performing procedure ER-ELEC.4 and to Bus 13 by performing procedure ER-ELEC.5 at the Shift Supervisor's discretion.

9 Try To Restore Offsite Power:

a. Consult RG&E Energy Control a. IF normal offsite power supply Center to determine if either NOT readily available, THEN normal offsite power supply - perform the following:

AVAILABLE

1) Restore IA system using the o 12B transformer via breaker Diesel Air Compressor (Refer 76702 to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR).

-OR-

2) Evaluate Main transformer o 12A transformer via breaker backfeed for long term 75112 concerns (Refer to ER-ELEC.3.

EMERGENCY OFESITE BACKEEED VIA MAIN & UNIT TRANSFORMER).

3) Go to Step 10.
b. Reset SI. if necessary
c. Restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER)

EOP: TITLE:REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 10 of 25 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP 10 Initiate Local Actions To Isolate RCS And To Provide Cooling To Vital Areas And Equipment

a. Open all Reactor Protection and Control System rack doors in the Control Room.
b. Direct Security personnel to open the following vital area doors to increase cooling:

' Control Room Door S51

  • Intermediate Bldg Door S37 (AFW pump area)
  • Intermediate Bldg Door F36 (Automatic fire door, Rod Drive MG set area)
  • Intermediate Bldg Door S44 (Steam Header area)
c. Dispatch AO To Locally Isolate RCP Seals and BASTs (Refer to ATT-21.0, ATTACHMENT RCS ISOLATION)
d. Dispatch AO to align backup cooling water to TDAFW Pump (Refer to ATT-5.2. ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 11 Isolate Makeup And Reject IF valves can NOT be manually From Hotwell To CST By closed. THEN dispatch AO to locally Placing Hotwell Level isolate makeup and reject lines.

Controller (LC-107) In Manual AT 50%

  • Makeup isolation V-4058
  • Reject isolation V-4055 12 Isolate S/G: IF valves can NOT be manually closed, THEN dispatch AO to locally
a. Manually close both MSIVs isolate the affected flow path.
b. Depress MANUAL pushbuttons AND manually close MEW flow control valves
  • MEW regulating valves
  • MEW bypass valves
c. Place MCB master switch for SIG blowdown and sample valves to CLOSE

ATIN/XPCTDRESPONSE NTOAIE

  • *t * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • CAUTION A FAULTED OR RUPTURED S/G THAT IS ISOLATED SHOULD REMAIN ISOLATED. STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM AT LEAST ONE S/G.

13 Check If S/G Secondary Side Perform the following:

Is Intact:

a. IF any S/G pressure decreasing o Pressure in both SIGs - STABLE in an uncontrolled manner OR OR INCREASING completely depressurized, THEN isolate faulted S/G unless o Pressure in both S/Gs - GREATER needed for RCS cooldown:

THAN 110 PSIG

1) Close faulted S/G MDAFW pump discharge valve.
  • S/G A, MOV-4007
  • S/G B, MOV-4008
2) Close faulted S/G TDAFW flow control valve.
  • S/G A. AOV-4297
  • S/G B, AOV-4298
3) Verify faulted S/G ARV controller in MANUAL with output at 0%.
  • S/G A, AOV-3411
  • S/G B, AOV-3410
4) Pull stop faulted S/G TDAFW pump steam supply valve.
  • S/G A, MOV-3505A
  • S/G B. MOV-3504A IF valve(s) can NOT be closed manually. THEN dispatch AO to locally close valve(s) to isolate flow.
b. Dispatch AO to complete faulted S/G isolation (Refer to ATT-10.0, ATTACHMENT FAULTED SIG).

EOP: TITLE:

REV: 30 ECA-0.O LOSS OF ALL AC POWER PAGE 13 of 25 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If S/G Tubes Are Intact: Try to identify ruptured S/G.

Continue with Step 15. WHEN o Dispatch RP tech or AO to ruptured S/G identified, THEN locally check steamline perform the following:

radiation - NORMAL

a. Isolate ruptured S/G unless needed for RCS cooldown:
1) Close ruptured S/G MDAFW pump discharge valve.
  • S/G A. MOV-4007
  • SIG B. MOV-4008
2) Pull stop ruptured SIG MDAFW pump.
3) Close ruptured SIG TDAFW flow control valve.
  • SIG A. AOV-4297
  • S/G B, AOV-4298
4) Adjust ruptured S/G ARV controller to 1050 psig in AUTO. WHEN S/G pressure less than 1050 psig, THEN ensure ruptured S/G ARV closed.
  • S/G A, AOV-3411
  • S/G B. AOV-3410
5) Pull stop ruptured S/G TDAFW pump steam supply valve.
  • SIG A, MOV-3505A
  • SIG B. MOV-3504A IF valve(s) can NOT be closed manually, THEN dispatch AO to locally close valve(s) to isolate flow.
b. Dispatch AO to complete ruptured S/G isolation (Refer to ATT-16.0, ATTACHMENT RUPTURED S/G).

EOP: TITLE: AREV: 30 ECA-0.O LOSS OF ALL AC POWER PAGE 14 of 25l ACIO/XPCTDRESPONSE NO BAN CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS, USING FIRE OR CITY WATER, WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE: TDAFW pump AOV flow control AOVs may drift open on loss of IA.

  • 15 Monitor Intact SIG Levels:
a. Narrow range level - GREATER a. Maintain maximum AFW flow until THAN 7% [25% adverse CNMT] narrow range level greater than 7% [25% adverse CNMT] in at least one S/G.
b. Control AFW flow by throttling b. Control ANW flow by throttling TDAFW flow control valves TDAFP discharge MOV-3996.
  • S/G A, AOV-4297 IF MOV-3996 can NOT be
  • S/G B, AOV-4298 controlled, THEN dispatch AO to locally control AFW flow by throttling TDAFW flow control valves.
  • S/G A, AOV-4297

. S/G B. AOV-4298 IF valves can NOT be throttled, THEN control ANW flow by starting and stopping TDAFW pump.

c. Control AEW flow to maintain c. IF narrow range level in any narrow range level between 17% intact S/G continues to increase

[25% adverse CNNT] and 50% in an uncontrolled manner, THEN return to Step 14.

P AX RESPONSE NOT OBTAINED NOTE: IF the loss of power is expected to continue beyond 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, THEN degassing of main generator should commence as soon as personnel become available (Refer to ATT-8.2. ATTACHMENT GEN DEGAS).

16 Check DC Bus Loads:

a. Place control switches for MFW pump AC oil pumps to OFF (allows timer to stop DC oil pumps)
b. Stop all large non-essential DC loads
1) Evaluate DC loads (Refer to ATT-8.0. ATTACHMENT DC LOADS).
2) WHEN turbine is stopped, THEN perform the following:

a) Locally close Turbine backup seal oil reg outlet valve V-5475J.

b) Stop Turbine DC lube oil pump (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).

c. Check DC bus voltage - GREATER c. IF either DC bus less than THAN 105 VOLTS DC 105 volts DC, THEN refer to ER-ELEC.2. RECOVERY FROM LOSS OF
  • Bus A A or B DC BUS.
  • Bus B
d. Direct electricians to locally monitor DC power supply

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 16 of 25 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify Source Range Dispatch personnel with relay rack Detector(s) - ENERGIZED key to turn off 125 VDC power switches in REACTOR PROTECTION

  • N-31 racks RLTR-1 and RLTR-2 to
  • N-32 deenergize source range block relays.

CAUTION WHEN POWER IS RESTORED TO BUS 14 AND/OR BUS 16. RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 27.

18 Check CST Level - GREATER Initiate makeup to CSTs using fire THAN 5 FEET or city water as a source. (Refer to ER-AEW.1. ALTERNATE WATER SUPPLY TO AFW PUMPS).

EOP: TITLE: REV:

RV 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 17 of 25

_STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o SIG PRESSURES SHOULD BE MAINTAINED GREATER THAN 200 PSIG TO PREVENT INJECTION OF SI ACCUM NITROGEN INTO THE RCS.

o SIG NARROW RANGE LEVEL SHOULD BE MAINTAINED GREATER THAN 7% [25% ADVERSE CNMT] IN AT LEAST ONE INTACT S/G. IF LEVEL CANNOT BE MAINTAINED, S/G DEPRESSURIZATION SHOULD BE STOPPED UNTIL LEVEL IS RESTORED IN AT LEAST ONE S/G.

NOTE: o The S/Gs should be depressurized at maximum rate to minimize RCS inventory loss.

o PRZR level may be lost and reactor vessel upper head voiding may occur due to depressurization of S/Gs. Depressurization should not be stopped to prevent these occurrences.

o S/G ARV nitrogen pressure should be monitored and nitrogen supply bottles changed as necessary.

19 Initiate Depressurization Of Intact SIGs To 300 PSIG:

a. Check S/G narrow range levels - a. Perform the following:

GREATER THAN 17% [25% adverse CNMT] IN AT LEAST ONE S/G 1) Maintain maximum AFW flow until narrow range level I greater than 17% [25% adverse CNMT] in at least one S/G.

2) Continue with Step 20. WHEN narrow range level greater than 17% [25% adverse CNMT]

in at least one S/G, THEN do Steps 19b and 20.

b. Manually dump steam from intact b. Locally dump steam from intact S/Gs at maximum rate using S/G S/Gs at maximum rate using S/G ARVs ARV.

EOP: TITLE:REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 18 of 25 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: o Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

o IF Instrument Bus D deenergized, THEN NIS SUR meters will NOT be available.

  • 20 Monitor Reactor For Subcriticality:
a. Verify Subcriticality using the a. IF unable to verify following indications: subcriticality using NIS. THEN perform the following:
1) Check source range(s). N-31 AND N-32 o Control S/G ARVs to stop S/G depressurization and allow o Indicator - ON SCALE RCS to heat up.

o Power - STABLE OR o Direct RP to sample RCS and DECREASING PRZR for boron concentration.

2) Check intermediate range, N-35 o Request plant staff assistance in evaluating core o Indicator - ON SCALE reactivity status o Power - STABLE OR DECREASING
3) Check power range, N-41 and N-43 o Indicators - LESS THAN 5%

o Power - STABLE OR DECREASING

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 19 of 25 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED NOTE: Depressurization of S/Gs will result in a SI actuation. SI should be reset to permit manual loading of equipment on emergency busses.

21 Check SI Signal Status:

a. Any SI annunciator - LIT a. Go to Step 25. WHEN SI actuated, THEN do Steps 21b, 22.

23 and 24.

b. Reset SI 22 Verify CI And CVI:
a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
b. Verify CI and CVI valve status b. Manually close affected CI and lights - BRIGHT CVI valves. I IF valves can NOT be verified closed by MCB indication, THEN close alternate isolation valves (Refer to ATT-3.0, ATTACHMENT CI/CVI).
c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

  • AOV-4561
  • AOV-4562
d. Verify RHR Pump Suction from d. IF sump recirculation NOT in CNNT Sump B valves - CLOSED progress, THEN manually close valves.
  • MOV-850A
  • MOV-850B IF valves can NOT be verified closed by MOB indication, THEN dispatch AO to locally close valves.

EOP: TITLE: REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 20 of 25 ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED 23 Check If SIG Depressurization Should Be Stopped:

a. Check RCS cold leg temperatures a. Perform the following:

- GREATER THAN 3150F

1) Control S/G ARVs to stop S/G depressurization.
2) Go to Step 24.
b. Check S/G pressures - LESS THAN b. Continue with Step 24. WHEN SIG 300 PSIG pressure decreases to less than 300 psig, THEN do Step 23c and d.
c. Check IA supply: c. Control S/G ARVs in manual to maintain S/G pressures at o Pressure - GREATER THAN 300 psig 60 PSIG IF manual control is NOT o Pressure - STABLE OR available, THEN locally control INCREASING S/G ARVs to maintain S/G pressures at 300 psig.
d. Control S/G ARVs to maintain S/G d. Control S/G ARVs in manual to pressures at 300 psig IN AUTO maintain S/G pressures at 300 psig IF manual control is NOT available, THEN locally control S/G ARVs to maintain SIG pressures at 300 psig.

STEPACTION/EXPECTED ~~RESOS EPNENTOTIE 24 Check CNMT Pressure - HAS IF CNMT pressure is less than 28 REMAINED LESS THAN 28 PSIG psi,THEN perform the following:

o Annunciator A-27, CNMT SPRAY - a. Reset CNMT spray.

EXTINGUISHED

b. Place CNMT spray pump discharge o CNMT pressure indicators - LESS valve switches to CLOSE to THAN 28 PSIG deenergize open contactor.

IF NOT, THEN continue with step 25.

WHEN CNMT pressure less than 28 psig, THEN reset CNMT spray and place CNMT spray pump discharge valve switches to CLOSE.

25 Check Core Exit T/Cs - LESS IF core exit temperatures greater THAN 12000F than 12000 F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

step 1.

26 Check If AC Emergency Power Continue to control RCS conditions Is Restored - BUSSES 14 and monitor plant status:

AND/OR 16 ENERGIZED

a. Check status of desired actions:

o AC power restoration o ARV nitrogen pressure o Diesel air compressor to IA system o RCP seal isolation o DC power supply

b. Return to Step 13.

EOP: TITLE: REV: 3O ECA-0.O LOSS OF ALL AC POWER PAGE 22 of 25 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Manually Control S/G ARVs To Locally control S/G ARVa.

Stabilize S/G Pressures

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 23 of 25 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: SW isolation may occur when power is restored to AC emergency busses.

28 Verify SW System Operation:

a. Check Bus 17 and Bus 18 - AT a. Perform the following:

LEAST ONE ENERGIZED

1) Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
3) Go to Step 29.
b. Verify two SW pumps - RUNNING b. IF normal power available, THEN establish two SW pumps running.

IF normal power NOT available, THEN establish one SW pump running for each operating D/G.

IF NO SW pumps running, THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

IF only one SW pump running, THEN perform the following:

1) Manually perform SW isolation.
2) Refer to AP-SW.2, LOSS OF SERVICE WATER.

EOP: TITLE:

REV: 3 0 ECA-0.0 LOSS OF ALL AC POWER PAGE 24 of 25 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.

29 Verify Following Equipment Manually load equipment as power Loaded On Available AC supply permits.

Emergency Busses:

o 480 volt MCCs - ENERGIZED

  • MCC C from Bus 14
  • MCC D from Bus 16 o Verify instrument busses -

ENERGIZED

  • Bus A from MCC C (A battery)
  • Bus B from MCC C
  • Bus C from MCC D (B battery) o Dispatch personnel to verify proper operation of battery chargers

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 25 of 25 ACTION/EXPECTED RESPONSE lRESPONSE SP NOT OBTAINEDl 30 Select Recovery Procedure:

a. Check RCS subcooling based on a. Go to ECA-0.2. LOSS OF ALL AC core exit T/Cs - GREATER THAN POWER RECOVERY WITH SI REQUIRED, 0F USING FIG-1.O. FIGURE MIN Step 1.

SUBCOOLING

b. Check PRZR level - GREATER THAN b. Go to ECA-0.2. LOSS OF ALL AC 10% [30% adverse CNMT] POWER RECOVERY WITH SI REQUIRED, Step 1.
c. Check SI and RHR Pumps - NONE c. Go to ECA-0.2, LOSS OF ALL AC RUNNING POWER RECOVERY WITH SI REQUIRED, Step 1.
d. Go to ECA-O.1. LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, Step 1

-END-

EOP: TITLE:

REV: 30 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 1 ECA-0.0 APPENDIX LIST TITLE

1) FIGURE MIN SUBCOOLING (EIG-1.o)
2) ATTACHMENT DC LOADS (ATT-8.0)
3) ATTACHMENT FAULTED S/G (ATT-10.0)
4) ATTACHMENT RUPTURED S/G (ATT-16.0)
5) ATTACHMENT CI/CVI (ATT-3.0)
6) ATTACHMENT NONVITAL (ATT-8.3)
7) ATTACHMENT GEN DEGAS (ATT-8.2)
8) ATTACHMENT RCS ISOLATION (ATT-21.0)
9) ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP (ATT-5.2)
10) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
11) ATTACHMENT NO SW PUMPS (ATT-2.4)
12) FOLDOUT

EOP: TITLE:

REV: 3 0 ECA-0.0 LOSS OF ALL AC POWER PAGE 1 of 1 FOLDOUT PAGE

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

EOP: TITLE:

C LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 ECA-0.2 REQUIRED i R~yIREDPAGE 1 of 9 GINNA STATION CONTROLLED COPY NUMBER 2 A

... -4 6 RESPONSIBIO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TIRE:

ECA-.2LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 REQUIREDPAGE 2 of 9 A. PURPOSE - This procedure provides actions to use engineered safeguards systems to recover plant conditions following restoration of AC emergency power.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. ECA-0.0, LOSS OF ALL AC POWER, when AC emergency power is restored and SI is required.
b. ECA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, if SI is required.

REV: 17 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o CSESTs should be monitored for information only. FR procedures should not be implemented prior to completion of Step 10.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

o FOLDOUT page should be open and monitored periodically.

1 Reset SI 2 Check RCP CCW Isolation Status:

a. CCW pumps - BOTH PUMPS OFF a. Go to Step 3.
b. RCP CCW return valves - CLOSED b. Manually close valves as necessary:
  • MOV-759A
  • MOV-759B o RCP CCW thermal barrier outlet valves
  • AOV-754A
  • AOV-754B

-OR-o RCP CCW supply valves

  • MOV-749A
  • MOV-749B

EOP: TITLE:

ECA-O.2 LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 REQUIRED PAGE 4 of 9 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 3 Check RWST Level - GREATER Go to ES-1.3, TRANSFER TO COLD LEG THAN 28% RECIRCULATION, Step 1.

NOTE: SI actuation to establish safeguards valve alignment is not recommended.

4 Manually Align SI And RHR Pumps To Establish SI Injection:

a. SI pump suction valves from RWST a. Ensure at least one SI pump

- OPEN suction valve from RWST open.

  • MOV-825A
  • MOV-825A
  • MOV-825B
  • MOV-825B
b. Verify SI pump C discharge b. Manually open valves as valves - OPEN necessary.
  • MOV-871A
  • MOV-871B
c. RHR pump discharge to Rx vessel c. Ensure at least one deluge valve deluge - OPEN open.
  • MOV-852A . MOV-852A
  • MOV-852B
  • MOV-852B

SP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED]

CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.

5 Manually Load Following Safeguards Equipment On AC Emergency Bus:

a. Start all SI pumps a. Perform the following:
1) Start available SI pumps.
2) IF SI pump A or B NOT available, THEN verify SI pump C aligned as follows:

o IF SI pump A NOT available, THEN ensure MOV-871B closed.

o IF SI pump B NOT available, THEN ensure MOV-871A closed.

b. Check RCS pressure: b. Manually start both RHR pumps and go to Step 5d.

o Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]

o Pressure - STABLE OR INCREASING

c. Place RHR pump switches in AUTO
d. Start all available CNMT RECIRC fans

EOP: TITLE:

EAO2LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 REQUIREDPAGE 6 of 9 S ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO ANW PUMPS).

o IF S/G NR LEVEL DECREASES TO LESS THAN 7% [25% ADVERSE CNMT] AND FEED FLOW IS LESS THAN 200 GPM, THEN THE MDAFW PUMPS SHOULD BE MANUALLY LOADED ON AC EMERGENCY BUS TO SUPPLY WATER TO THE S/G(S).

NOTE: o If MDAFW pump operation is not required, pump switches should be maintained in PULL-STOP to prevent automatic start.

o TDAFW pump flow control AOVs may drift open on loss of IA.

  • 6 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% {25% adverse CNMT] than 200 gpm until narrow range level greater than 7% [25%

adverse CNMT] in at least one S/G.

IF feed flow less than 200 gpm, THEN perform the following:

1) Verify MDAFW pump discharge valve to intact S/G(s) open.
  • S/G A. MOV-4007
  • S/G B. MOV-4008
2) Manually start MDAFW pumps as necessary (223 kw).
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

EOP: TITLE:REV: 17 LOSS OF ALL AC POWER RECOVERY WITH SI 2REQUIRED PAGE 7 of 9 7 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
b. Verify CI and CVI valve status b. Manually close affected CI and lights - BRIGHT CVI valves. I IF valves can NOT be verified closed by MCB indication, THEN close alternate isolation valves (Refer to ATT-3.O. ATTACHMENT CI/WVI).
c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights - valves.

BRIGHT

  • AOV-4561
  • AOV-4562

EOP: TITLE:

ECA-O.2 LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 REQUIRED PAGE 8 of 9 ACTION/EXPECTED RESPONSE ESPONSE NOT OBTAINEDl 8 Verify CNMT Spray Not IF CNMT pressure is less than 28 Required: psig. THEN perform the following:

o Annunciator A-27. CNMT SPRAY - a. Reset CNMT spray.

EXTINGUISHED

b. Place CNMT spray pump discharge o CNMT pressure - LESS THAN 28 PSIG valve switches to CLOSE to deenergize open contactor.

IF NOT, THEN perform the following:

a. Depress manual CNMT spray pushbuttons (2 of 2).
b. Ensure CNMT spray pump discharge valves open.

o CNMT spray pump A:

  • MOV-860A
  • MOV-860B o CNMT spray pump B:
  • MOV-860C
  • MOV-860D
c. Verify NaOH tank flow (FI-930).

IF NaOH flow NOT indicated, THEN place switches for NaOH tank outlet valves to OPEN.

  • AOV-836A
  • AOV-836B
d. Start both CNMT spray pumps.
e. Go to step 10.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Place CNMT Spray Pumps In AUTO 10 Check RCP Seal Injection Locally close valves before Needle Valves - CLOSED starting charging pump.

  • V-300A
  • V-300B NOTE: FR procedures may now be implemented as necessary.

11 Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1

-END-

EOP: TITLE:

lECA-.2 LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 REQUIREDPAGE 1 of 1 ECA-0.2 APPENDIX LIST TITLE

1) ATTACHMENT CI/CVI (ATT-3.O)
2) ATTACHMENT NO SW PUMPS (ATT-2.4)
3) FOLDOUT

I. I EOP: - TITLE:

LOSS OF ALL AC POWER RECOVERY WITH SI REV: 17 ECA-0.2 REQUIRED PAGE 1 of 1 FOLDOUT PAGE

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

EOP: TITRE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 23 GINNA STATION CONTROLLED COPY NUMBER __all RESPONSIBL AGER

/ EFE

-/CV d As E FFECT IVE DATE CATEGORY 1.0 REVIEWED BY:

EDP: TM~E:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 2 of 23 A. PURPOSE - This procedure provides the necessary instructions for transferring the Safety Injection system and Containment Spray system to recirculation modes of operation.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure may be entered from:
a. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, or,
b. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, or,
c. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or,
d. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, or,
e. FR-C.2, RESPONSE TO DEGRADED CORE COOLING, or,
f. FR-C.3, RESPONSE TO SATURATED CORE COOLING, or,
g. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, or,
h. FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE, on low RWST level.
i. Other procedures whenever RWST level reaches the switchover setpoint (28%).

EOP: TIlE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 3 of 23 ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINED I CAUTION o IF OFESITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFESITE POWER) o CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING. SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.

  • * * * * * * * * * * * * * * * * * * * * * * * * * * *t * * * * * * * * * * * *
  • NOTE: o FOLDOUT page should be open and monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

  • 1 Verify RWST level - GREATER IF sump recirculation NOT in THAN 15% progress, THEN pull-stop all pumps taking suction from RWST. EXCEPT one SI pump AND go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.

2 Verify CNMT Sump B Level - AT IF RWST level is less than 28% AND LEAST 113 INCHES CNMT sump B level is less than 113 inches, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.

NOTE: Steps 3 through 14 should be performed without delay. FR procedures should not be implemented prior to completion of these steps.

- 3 Reset SI

EOP: TIRIE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 4 of 23 STP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED CAUTION o THE RER HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.

o CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING. SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.

4 Throttle RHR Flow: Manually adjust RHR Hx outlet valves equally to reduce flow to o Direct an AO to perform less than 1500 gpm per operating ATT-14.7, ATTACHMENT ADJUST RHR pump FLOW, to locally adjust HCV-624 and HCV-625.

  • RER Hx A, HCV-625
  • RHR Hx B. HCV-624

fEOP: TITLE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION l PAGE 5 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check IF Unnecessary Pumps Can Be Stopped:- I

a. Three SI pumps - RUNNING I a. Go to Step 5c. I
b. Stop SI pump C and place both switches in PULL STOP I
c. Stop both RHR pumps and place in PULL STOP I
d. Both CNMT spray pumps - RUNNING I d. Pull stop any idle CNMT spray pump and go to Step 5f. I
e. Pull stop one CNMT spray pump
f. Check CNMT pressure - LESS THAN l f. Go to Step 6. I 28 PSIG.
g. Place NaOH Tank outlet valve switches to OPEN.

. AOV-836A

  • AOV-836B
h. Reset CNMT spray
i. Close discharge valves for idle CNMT spray pump(s) o Pump A
  • MOV-860A
  • MOV-860B o Pump B
  • MOV-860C
  • MOV-860D

EOP: TITLE:

. REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 6 of 23 NOTE: IF DIGs supplying emergency AC busses, THEN non-essential loads may be shed as necessary to allow start of additional SW pumps. I 6 Establish Adequate SW Flow:

a. Verify at least two SW pumps - a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only 1 SW pump operable, THEN perform the following:
1) Ensure SW aligned to one CCW Hx per ATT-2.1. ATTACHMENT MIN SW.
2) Go to Step 7.

IF no SW pumps are available, THEN perform the following:

1) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
2) Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
b. Verify AUX BLDG SW isolation b. Manually align valves.

valves - OPEN

  • MOV-4615 and MOV-4734
  • MOV-4616 and MOV-4735 This Step continued on the next page.

A EOP: TITLE:

REV: 3 9 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 7 of 23 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I (Step 6 continued from previous page) -

c. Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs REQUIRED SW FLOW ALIGNMENT AVAILABLE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service HX Alternate 2 30 - 33 inches d/p across each HX Alternate 1 95 - 100 inches d/p across in-service HX

d. Direct AO to adjust SW flow to d. IF the required SW flow can NOT required value be obtained, THEN perform the following:

o IF on normal SW discharge:

1) Isolate SW to screenhouse and
  • MOV-4609/MOV-4780 - AT

-OR- LEAST ONE CLOSED

  • MOV-4663/MOV-4733 - AT o IF on alternate SW discharge: LEAST ONE CLOSED
  • V-4619C. CCW HX A 2) Direct AO to locally adjust
  • V-4620B, CCW HX B SW flow to required value.
3) Direct AO to locally isolate SW return from SFP Hxs:
  • SFP Hx A (V-4622) (for alternate SW discharge use V-4622A)
  • SFP Hx B (V-8689)
4) Verify SW portions of ATT-17.0, ATTACHMENT SD-1 are complete.

EOP: TITLE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 8 of 23 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED-1 7 Establish CCW flow to RHR Hxs:

a. Check both CCW pumps - RUNNING a. Perform the following:
1) Start CCW pumps as power supply permits (122 kw each).
2) IF both CCW pumps are running. THEN go to step 7b.
3) IF only one CCW pump is running, THEN perform the following:

a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR loop.

o Open MOV-738A

-OR-o Open MOV-738B c) Go to step 8.

b. Open CCW valves to RHR Hxs b. Dispatch AO to locally open valves.
  • MOV-738A
  • MOV-738B Wi

EOP: TITLE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 9 of 23 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 8 Verify RHR System Alignment:

a. Verify the following valves - a. Ensure at least one suction CLOSED valve and one discharge valve closed.

o RHR suction valves from loop A hot leg

  • MOV-700
  • MOV-701 o RHR discharge valves to loop B cold leg
  • MOV-720
  • MOV-721
b. Verify RHR pump suction crosstie b. Manually open valves. If valves valves - OPEN can NOT be opened. THEN dispatch AO to locally open valves.
  • MOV-704A
  • MOV-704B
c. Verify the following valves - c. Ensure at least one valve in OPEN each set open.

o RHR pump discharge to Rx vessel deluge valves

  • MOV-852A
  • MOV-851A
  • MOV-851B
d. Verify RCDT pump suction valves d. Manually close valves.

from sump B - CLOSED

  • MOV-1813A
  • MOV-1813B

EOP: TIRE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 10 of 23 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED CAUTION RHR FLOW INDICATED ON FI-626 SHOULD BE LIMITED TO 1500 GPM PER OPERATING PUMP TO ENSURE OPTIMUM PUMP PERFORMANCE.

9 Initiate RHR Sump Recirculation:

a. Close RWST outlet valve to RHR a. Dispatch AO to locally close pump suction, MOV-856 (turn on valve and continue with Step 9b.

DC power key switch)

b. Open both RHR suction valves b. IF only one valve will open, from sump B (outside CNMT) THEN perform the following:

o MOV-850A - OPEN 1) Initiate only one train of RHR recirculation (Refer to o MOV-850B - OPEN ATT-14.3, ATTACHMENT RHR NPSH for further guidance).

2) Go to step 9e.

IF neither valve will open, THEN refer to ATT-14.6, ATTACHMENT RHR PRESS REDUCTION for further guidance.

c. Check MOV-738A AND MOV-738B - c. Perform the following:

BOTH OPEN

1) IF MOV-738A open, THEN start RHR Pump A and go to step 9e.
2) IF MOV-738B open. THEN start RHR Pump B and go to step 9e.
d. Start both RHR pumps
e. Verify at least one RHR pump - e. IF no RHR pump can be started.

RUNNING THEN go to ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.

EOP: TIRE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 11 of 23 ACTION/EXPECTED RESPONSENED

  • 10 Monitor Indications Of CNMT IF any SI pump running with suction Sump B Blockage aligned to RHR pump. THEN go to ECA-1.3, RESPONSE TO SUMP B o Check running RHR Pump motor BLOCKAGE.

current - STABLE IF NOT, THEN perform the following:

  • RHR Pump B. PPCS point I0685BD a. Stop all CNMT spray pumps taking suction from RHR pumps.

o Check running RHR pump discharge flows - STABLE b. Stop all but one RER pump.

o Check running SI pump discharge c. Reduce RHR flow as low as flows - STABLE FOR SI PUMPS possible but NOT less than TAKING SUCTION FROM RHR PUMPS requirements of FIG-6.0. FIGURE MIN RCS INJECTION.

o Check audible indications for RHR, SI or CNMT spray pump - NO d. Contact the TSC for additional SOUNDS OF CAVITATION guidance.

e. IF indications of cavitation continue, THEN go to ECA-1.3, RESPONSE TO SUMP B BLOCKAGE, Step 1.
  • * * * * * * * * * * * * * * * * * * * * * * * * * *t * * * * * * * * * * * * *
  • CAUTION SUMP RECIRCULATION FLOW TO RCS MUST BE MAINTAINED AT ALL TIMES. EXCEPT DURING ALIGNMENT FOR HIGH HEAD RECIRCULATION.
  • * * * *
  • It * * * * * * * * * * *a * * * * * * * * * * * *r * * * * *r * * * *r *
  • NOTE: The TSC should be requested to establish periodic monitoring of the AUX BLDG sub-basement, as radiological conditions permit, to monitor RHR pump operation.

11 Check RWST Level - LESS THAN DO NOT continue with this procedure 15% until RWST level is less than 15%.

ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl SP 12 Stop All Pumps Supplied From RWST:

a. Stop all SI pumps and place in PULL STOP
b. Stop all charging pumps
c. Stop operating CNNT spray pump and place in PULL STOP
d. Check CNMT pressure - LESS THAN d. Go to Step 13.

28 PSIG

e. Reset CNMT spray if necessary
f. Close CNMT spray pump discharge valves
  • MOV-860A
  • MOV-860B
  • MOV-860C
  • MOV-860D

EOP: TITLE:REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 13 of 23 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED

  • * *
  • A* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • CAUTION RHR FLOW MUST BE MAINTAINED LESS THAN 1500 GPM PER OPERATING RHR PUMP AS DETERMINED BY THE TOTAL OF FI-931A. FI-931B AND FI-626 INDICATIONS.
  • * * * * * * *i * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • 13 Align SI And CNMT Spray For Sump Recirculation:
a. Verify SI pump suction valves a. Ensure at least one valve in from BASTs - CLOSED each flowpath closed.
  • MOV-826A and MOV-826B
  • MOV-826C and MOV-826D
b. Close RWST outlet valves to SI b. Ensure at least one valve closed.

and CNMT spray pumps (turn on DC power key switches)

  • MOV-896A
  • MOV-896B
c. Close SI pump RECIRC valves c. Ensure at least one valve closed.
  • MOV-898
  • MOV-897
d. Verify SI pump suction valves d. Ensure at least one valve open.

from RWST - OPEN

  • MOV-825A
  • MOV-825B
e. Align operating RHR pump flow e. Ensure at least one flowpath path(s) to SI and CNMT spray aligned from RHR pump(s) to SI pump suction. and CS pump suction header (Refer to ATT-14.5, ATTACHMENT o IF RHR Pump A operating, RHR SYSTEM).

THEN open MOV-857A and MOV-857C IF neither flow path can be aligned, THEN refer to ATT-14.6, o IF RHR Pump B operating, ATTACHMENT RHR PRESS REDUCTION THEN open MOV-857B for further guidance.

EOP:

ES-1.3 TITLE:

I TRANSFER TO COLD LEG RECIRCULATION REV: 39 PAGE 14 of 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION SI PUMPS SHOULD BE STOPPED IF RCS PRESSURE IS GREATER THAN THEIR SHUTOFF HEAD PRESSURE.

  • * * * * * * * * * * * * * * * * * * * * * * * * * * * . * * * * * *
  • so * * *
  • NOTE: Operation of SI pump C is preferred since it delivers to both RCS loops.

14 Verify Adequate RCS Makeup Flow:

a. RCS pressure - LESS THAN a. Perform the following:

225 psig [425 psig adverse CNMTJ

1) Check RCS conditions:

o RCS subcooling based on core exit T/Cs greater than EIG-1.O, FIGURE MIN SUBCOOLING.

o PRZR level greater than 10% [30% adverse CNNTI.

IF either condition NOT met, THEN start one SI pump.

2) Go to Step 15.
b. RHR injection flow adequate: b. Start one SI pump.

o Core exit T/Cs - LESS THAN REQUIREMENTS OF FIG-5.0, FIGURE RHR INJECTION o Check RVLIS level (no RCPS) -

GREATER THAN 52% [55% adverse CNMTJ

EOP: TITLE:

j REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION l PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RSPONSE NOT OBTAINED

  • * * * * * * * * * * * * * * * * * * * *r * * * * * * * * * * * * * * * * * * *
  • CAUTION IF A CNMT SPRAY PUMP IS STARTED. THEN CNNT PRESSURE SHOULD BE CLOSELY MONITORED. CNMT PRESSURE SHOULD NOT BE REDUCED TO LESS THAN 22 PSIG.
  • 15 Check If CNMT Spray Is Required:
a. CNMT pressure - GREATER THAN a. Perform the following:

28 PSIG

1) IF CNMT spray previously actuated and NaOH tank level greater than 55%. THEN consult TSC to determine if CNMT spray should be restarted.
2) Go to Step 16.
b. Verify CNMT spray pump discharge b. Manually open valve(s) for valves - OPEN selected pump.
  • MOV-860A
  • CS pump A, MOV-860A or MOV-860B
  • MOV-860B
  • CS pump B. MOV-860C or MOV-860D
  • MOV-860C
  • MOV-860D
c. Start selected CNMT spray pump c. IF the selected CNMT spray pump will not start, THEN align and start the other CNMT spray pump.

IF neither pump will start, THEN continue with Step 16. WHEN a CNMT spray pump can be started, THEN do steps 15d, e and f.

d. Adjust RHR flow to maintain less than 1500 gpm per operating RHR pump as indicated by the total of FI-931A, FI-931B and FI-626 indications.

This Step continued on the next page.

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl (Step 15 continued from previous page)

e. Verify NaOH flow (FI-930) e. IF NaOH flow NOT indicated, THEN place switches for NaOH tank outlet valves to OPEN.
  • AOV-836A
  • AOV-836B
f. WHEN CNMT pressure decreases to 22 psig, THEN perform the following:
1) Reset CNNT spray
2) Check NaOH flow (FI-930) - NO 2) Place NaOH tank outlet valve FLOW switches to close
  • AOV-836A
  • AOV-836B
3) Stop CNMT spray pumps and place in PULL STOP
4) Close CNMT spray pump discharge valves
  • MOV-860A
  • MOV-860B

. MOV-860C

  • MOV-860D 16 Verify Adequate Core Cooling: IF both RHR pumps running. THEN ensure two SI pumps running.

o Core exit T/Cs - STABLE OR DECREASING IF only one RHR pump running. THEN perform the following:

o RVLIS level (no RCPs) - STABLE OR INCREASING a. Ensure one SI pump running.

o RVLIS level (no RCPs) - GREATER b. WHEN CNMT spray pumps stopped, THAN 52% [55% adverse CNMT] THEN start one additional SI pump.

EOP: TITLE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 17 of 23

-2 NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

  • 17 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% [25% adverse CNMTI than 200 gpm until narrow range level greater than 7% [25%

adverse CNMT] in at least one SIG.

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

EOP: TITLE:

REV: 3 9 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 18 of 23 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINEDl 18 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.
b. Perform the following:

o Open generator disconnects

  • 1G13A71
  • 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump
c. Verify adequate Rx head cooling:
1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
2) Verify one Rx compartment 2) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

d. Verify ATT-17.O. ATTACHMENT SD-i

- COMPLETE

EOP: TITLE:

.EOP: TIRE: 3 REV: 3 9 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION

. PAGE 19 of 23 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl -

19 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

o Emergency D/G output breakers

- OPEN o AC emergency bus voltage -

GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1, ATTACHMENT D/G STOP)

EOP: TITLE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 20 of 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAIN 20 Check If SI ACCUMs Should Be Isolated:

a. Both RCS hot leg temperatures - a. Continue with Step 21. WHEN LESS THAN 400 0E both RCS hot leg temperatures less than 4001F, THEN do Steps 20b through d.
b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves
  • MOV-841. MCC C position 12F
  • NOV-865, MCC D position 12C
c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
  • ACCUM A. MOV-841 1) Open vent valves for
  • ACCUM B. MOV-865 unisolated SI ACCUSs.
  • ACCUM A, AOV-834A
  • ACCUM B. AOV-834B
2) Open HCV-945.

IF an accumulator can NOT be isolated or vented, THEN consult TSC to determine contingency actions.

d. Locally reopen breakers for MOV-841 and MOV-865 ww

EOP:ln U: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 21 of 23 ACTION/EXPECTED RESPONSE INE

  • * * * * * * * * * * * * * * * * * * * * * * * * * *
  • A* * * * * * * * * * * *
  • CAUTION IF FUEL DAMAGE IS SUSPECTED. MAINTAIN S/G PRESSURE SLIGHTLY GREATER THAN RCS PRESSURE.
  • * * * * * * * * * * * * * * * * * * * *i * * * * * *t * * * * * * * * * * * * *
  • 21 Check If Intact SIGs Should Be Depressurized To RCS Pressure:
a. RCS pressure - LESS THAN INTACT a. Go to Step 22.

S/G PRESSURES

b. Direct RP to sample S/Gs for activity
c. Request TSC perform a dose projection on steaming S/Gs
d. Dose projection for each S/G - d. Do NOT dump steam from a S/G ACCEPTABLE with an unacceptable dose projection.
e. Dump steam to condenser from e. IF steam dump to condenser NOT intact S/G(s) until S/G pressure available, THEN dump steam using less than RCS pressure intact S/G ARVs until S/G pressure less than RCS pressure.

22 Consult TSC to Determine If Rx Vessel Head Should Be Vented

EOP: TITLE:

ESP : TITLE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION l PAGE 22 of 23 NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 23.

23 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary
b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

NOTE: The TSC should be consulted before changing recirculation lineups.

24 Check Event Duration - Consult TSC to evaluate long term GREATER THAN 19 HOURS AFTER plant status.

EVENT INITIATION 25 Secure CNMT Spray

a. Reset CNMT spray
b. Place NaOH Tank outlet valve switches in AUTO

. AOV-836A

  • AOV-836B
c. Place CNMT spray pumps in PULL STOP
d. Close discharge valves for idle CNMT spray pumps o Pump A
  • MOV-860A
  • MOV-860B o Pump B
  • MOV-860C

. MOV-860D

EOP: TITLE:

I REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION

. PAGE 23 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Verify Two SI Pumps - RUNNING Manually start pumps.

27 Check Core Exit T/Cs - LESS Perform the following:

THAN REQUIREMENTS OF FIG-5.0, FIGURE RHR INJECTION a. Manually open both PRZR PORVs and block valves.

b. Verify core exit T/Cs decreasing to less than requirements of FIG-5.O, FIGURE RHR INJECTION.

IF NOT. THEN dump steam from intact S/Gs until core exit T/Cs less than required.

28 Consult TSC To Evaluate Long Term Plant Status

-END-

EOP: TITLE:

REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 ES-1.3 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE RHR INJECTION (FIG-5.O)
3) FIGURE MIN SUBCOOLING (FIG-1.O)
4) FIGURE MIN RCS INJECTION (FIG-6.O)
5) ATTACHMENT DIG STOP (ATT-8.1)
6) ATTACHMENT SD-1 (ATT-17.0)
7) ATTACHMENT SD-2 (ATT-17.1)
8) ATTACHMENT RHR NPSH (ATT-14.3)
9) ATTACHMENT RHR SYSTEM (ATT-14.5)
10) ATTACHMENT MIN SW (ATT-2.1)
11) ATTACHMENT RHR PRESS REDUCTION (ATT-14.6)
12) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
13) ATTACHMENT NO SW PUMPS (ATT-2.4)
14) FOLDOUT

EOP: TITLE: REV: 39 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%
b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit T/Cs greater than 7000°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 7%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE: V: 3 lEw llRE lREV: 3 9 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 FOLDOUT PAGE

1. ECA-1.1 TRANSITION CRITERIA IF emergency coolant recirculation is established and subsequently lost AND the cause is something OTHER THAN sump blockage, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
2. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pusbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
c. Go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION.
3. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

i EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 19 GINNA STATION CONTROLLED COPY NUMBER 2k RESPONSI L MANAGER

/EF-EC TV DES EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

. REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 2 of 19 A. PURPOSE - This procedure provides actions to restore core cooling.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on a RED condition.

EOP: TITLE:

REV: 2 3 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 3 of 19 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED NOTE: o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

o Foldout Page should be open and monitored periodically.

  • 1 Monitor RWST Level - GREATER Perform the following:

THAN 28%

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 14 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
b. WHEN the SI system is aligned for sump recirculation, THEN go to Step 4.

2 Verify SI Pump Suction Aligned to RWST:

a. Verify SI pump suction valves a. Ensure at least one SI pump from RWST - OPEN suction valve from RWST open.
  • MOV-825A
  • MOV-825A
  • MOV-825B
  • MOV-825B

EOP: TITLE:

.EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING

. PAGE 4 of 19 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

3 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

  • MOV-852A
  • MOV-852B
b. Verify both RHR pumps - RUNNING b. Manually start pumps
c. Verify SI pump C - RUNNING c. Manually start pump on available bus.
d. Verify SI pump A - RUNNING d. Perform the following:
1) Ensure SI pumps B and C running.
2) Ensure SI pump C aligned to discharge line A:

o MOV-871B closed o MOV-871A open

3) Go to Step 4.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED (Step 3 continued from previous page)

e. Verify SI pump B - RUNNING e. Perform the following:
1) Ensure SI pumps A and C running.
2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 4.
f. Verify both SI pump C discharge f. Manually open valves as valves - OPEN necessary.
  • MOV-871A
  • MOV-871B 4 Verify SI Flow In Both Trains: Perform the following:

o SI line loop A and B flow a. Manually start pumps and align indicators - CHECK FOR FLOW valves as necessary.

o RER loop flow indicator - CHECK b. Establish maximum charging flow.

FOR FLOW

c. Continue efforts to establish SI or RHR flow.

.EOP: TITLE:

REV: 23 FR-C.1 T RESPONSE TO INADEQUATE CORE COOLING PAGE 6 of 19 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDl 5 Check RCP Support Conditions:

a. Verify Bus 11A or l1B - ENERGIZED a. Restore power to Bus 11A or l1B (Refer to ER-ELEC.1. RESTORATION OF OEPSITE POWER).
b. Check other RCP support b. Continue attempts to establish conditions (Refer to ATT-15.0, RCP support conditions.

ATTACHMENT RCP START) 6 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves - OPEN after ACCUM discharge. THEN go to Step 7. IF NOT, THEN perform the

  • MOV-841 following:
  • MOV-865
a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves.
  • MOV-841, MCC C position 12F
  • MOV-865, MCC D position 12C
b. Open SI ACCUM discharge valves.
  • ACCUM A, MOV-841
  • ACCUM B. MOV-865 7 Check Core Exit T/Cs - LESS Go to Step 10.

THAN 12000F

EOP: TITLE:

REV: 2 3 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 7 of 19 ACTION/EXPECTED RESPONSENED 8 Check RVLIS Indication:

a. RCPs - BOTH SECURED a. Return to procedure and step in effect
b. RVLIS level - GREATER THAN 52% b. IF RVLIS increasing, THEN return

[55% adverse CNMT] to Step 1. IF NOT, THEN go to Step 9.

c. Return to procedure and step in effect 9 Check Core Exit T/Cs:
a. Temperature - LESS THAN 7000F a. IF decreasing, THEN return to Step 1. IF NOT, THEN go to Step 10.
b. Return to procedure and step in effect CAUTION IF OFESITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 10 Reset SI

EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING

. PAGE 8 of 19 11 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following ISOLATION - EXTINGUISHED
1) Reset SI.
2) Depress CI reset pushbutton.

NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 12.

12 Check CNMT Hydrogen Concentration:

a. Direct RP to start CNMT hydrogen monitors as necessary
b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 9 of 19 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1. ALTERNATE WATER SUPPLY TO AFW PUMPS).

o A FAULTED OR RUPTURED S/G SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT S/G IS AVAILABLE.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

  • 13 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 7% [25% adverse CNMT] than 200 gpm until narrow range level greater than 7% [25%

adverse CNMT] in at least one S/G.

IF total feed flow greater than 200 gpm can NOT be established.

THEN perform the following:

1) Continue attempts to establish a heat sink in at least one S/G (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
2) Go to Step 23.
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

ESP: TITLE:I REV: 23 FR-C.1 T RESPONSE TO INADEQUATE CORE COOLING PAGE 10 of 19 ACTION/EXPECTED RESPONSE CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 14B).

14 Check RCS Vent Paths:

a. Power to PRZR PORV block valves a. Restore power to block valves

- AVAILABLE unless block valve was closed to isolate an open PORV:

  • MOV-515, MCC D position 6C
  • MOV-516, MCC C position 6C
b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any PORV can NOT be closed, THEN manually close its block valve.

c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
d. Rx vessel head vent valves - d. Manually close valves.

CLOSED

  • SOV-590
  • SOV-591
  • SOV-592
  • SOV-593 1%*

EOP: TITLE:

REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 11 of 19 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 15 Establish Condenser Steam Dump Manual Control

a. Verify condenser available: a. Place intact SIG ARV controller in MANUAL and go to Step 16.

o Intact S/G MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Place steam dump mode selector switch in MANUAL
c. Place steam dump controller in MANUAL NOTE: Partial uncovering of S/G tubes is acceptable in the following steps.

16 Depressurize All Intact S/Gs To 200 PSIG:

a. Dump steam to condenser at a. Manually or locally dump steam maximum rate at maximum rate using SIG ARVs.
b. Check SIG pressure - LESS THAN b. IF SIG pressure decreasing, THEN 200 PSIG return to Step 13.

IF NOT. THEN go to Step 23.

c. Check RCS hot leg temperatures - c. IF RCS hot leg temperatures BOTH LESS THAN 4000F decreasing, THEN return to Step 13.

IF NOT, THEN go to Step 23.

d. Stop S/G depressurization

EOP: TITLE: PEV 2 o FR-C.1 RESPONSE TO INADEQUATE CORE COOLING

. PAGE 12 of 19 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 17 Check If SI ACCUMs Should Be Isolated:

a. RCS hot leg temperatures - BOTH a. Go to Step 23.

LESS THAN 400 0F

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary
  • MOV-841 MCC C position 12F
  • MOV-865 MCC D position 12C
c. Verify SI reset c. Manually reset SI.
d. Close SI ACCUM discharge valves d. Perform the following to vent an unisolated accumulator:

a ACCUM A. MOV-841

  • ACCUM B. MOV-865 1) Reset CI.
2) Ensure adequate air compressor(s) running.
3) Establish IA to CNMT.
4) Open vent valves for unisolated SI ACCUMs.

. ACCUM A, AOV-834A

  • ACCUM B. AOV-834B
5) Open HCV-945.

IF an accumulator can NOT be isolated or vented. THEN consult TSC to determine contingency actions.

e. Locally reopen breakers for MOV-841 and MOV-865

EOP: TITLE: REV 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 13 of 19 18 Stop Both RCPs 19 Dump Steam to Condenser At Manually or locally dump steam at Maximum Rate To Depressurize maximum rate using S/G ARVs.

All Intact S/Gs To Atmospheric Pressure 20 Verify SI Flow: Perform the following:

o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW or RHR flow.

-OR- b. Try to establish charging flow.

o RHR loop flow indicator - CHECK c. IF core exit T/Cs less than FOR FLOW 1200 0F, THEN return to Step 19.

IF NOT, THEN go to Step 23.

21 Check Core Cooling:

a. Core exit T/Cs - LESS THAN 12000F a. Go to Step 23.
b. RCS hot leg temperatures - BOTH b. Return to Step 19.

LESS THAN 320 0F

c. RVLIS level (no RCPs) - GREATER c. Return to Step 19.

THAN 77% [82% adverse CNMT]

EOP: TITLE: RV FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 14 of 19 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 22 Go to Appropriate Plant Procedure

a. Check RWST level - GREATER THAN a. Go to ES-1.3, TRANSFER TO COLD 28% LEG RECIRCULATION, Step 1.
b. Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT. Step 18

EOP: TITLE:REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING 4 l PAGE 15 of 19 STCTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl NOTE: Normal conditions are desired but not required for starting the RCPs.

23 Check If RCPs Should Be Started:

a. Core Exit T/Cs - GREATER THAN a. Go to Step 24.

1200FF

b. Check if an idle RCS cooling b. Perform the following:

loop is available

1) Reset SI.

o Narrow range S/G level -

GREATER THAN 7% [25% adverse 2) Reset CI.

CNMT]

3) Ensure adequate air o RCP in associated loop - compressorfs) running.

AVAILABLE AND NOT OPERATING

4) Establish IA to CNMT.
5) Open all PRZR PORVs and block valves a) IF any block valve can NOT be opened, THEN ensure power supplied to block valve.

b) IF IA NOT available, THEN refer to ATT-12.0.

ATTACHMENT N2 PORVS.

6) IF core exit T/Cs remain greater than 1200 0F, THEN open Rx vessel head vent valves.
  • SOV-590
  • SOV-591
  • SOV-592
  • SOV-593
7) Go to Step 24.
c. Start RCP in one idle RCS cooling loop
d. Return to Step 23a

EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING

l. PAGE 16 of 19 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINEDl 24 Dump Steam To Condenser At Manually or locally dump steam from Maximum Rate To Depressurize all intact S/Gs using ARVs.

All Intact S/Gs To Atmospheric Pressure: IF ARVs not available on intact S/Gs. THEN:

o Open TDAFW pump steam supply valve from intact S/G(s)

. S/G A. MOV-3505A

  • S/G B. MOV-3504A

-OR-o Perform the following:

a. Open intact SIG MISV bypass valves
b. Open both priming air ejector steam inlet valves

. V-3580

  • V-3581 IF no intact S/G available, THEN use faulted or ruptured S/G.

25 Check Core Exit T/Cs - LESS IF core exit temperatures THAN 12000F decreasing. THEN return to step 23.

IF core exit temperatures increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, step 1.

EOP: TITLE: REV: 2 3 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 17 of 19 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If SI ACCUMs Should Be Isolated:

a. RHR loop flow indicator - AT a. Go to Step 28.

LEAST INTERMITTENT FLOW

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary
  • MOV-841 MCC C position 12F
  • MOV-865 MCC D position 12C
c. Reset SI.
d. Close SI ACCUM discharge valves d. Perform the following to vent an unisolated accumulator:
  • ACCUM A. MOV-841
  • ACCUM B, MOV-865 1) Reset CI.
2) Ensure adequate air compressor(s) running.
3) Establish IA to CNMT.
4) Open vent valves for unisolated SI ACCUMs.
  • ACCUM A, AOV-834A
  • ACCUM B, AOV-834B
5) Open HCV-945.

IF an accumulator can NOT be isolated or vented. THEN consult TSC to determine contingency actions.

e. Locally reopen breakers for MOV-841 and MOV-865

EOP: TITLE: REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 18 of 19 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl STP 27 Check If RCPs Should Be Stopped:

a. Both RCS hot leg temperatures - a. Go to Step 28.

LESS THAN 320 0F

b. Stop all RCPs 28 Verify SI Flow: Perform the following:

o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW or RHR flow.

-OR- b. Try to establish charging flow.

o RHR loop flow indicator - CHECK c. Return to Step 23.

FOR FLOW 29 Check Core Cooling:

a. RCS hot leg temperatures - LESS a. Return to Step 23.

THAN 320 0F

b. RCPs - BOTH SECURED b. Stop all RCPs.
c. RVLIS level - GREATER THAN 77% c. Return to Step 23.

[82% adverse CNMT]

EOP: TITLE:

REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 19 of 19 RESPONSE NOT OBTAINED SOD 30 Go to Appropriate Plant Procedure

a. IF PRZR PORVs and head vents were opened in Step 23. THEN consult TSC to evaluate long term status AND continue with transitions.
b. Check RWST level - GREATER THAN b. Go to ES-1.3, TRANSFER TO COLD 28% LEG RECIRCULATION. Step 1.
c. Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 18.

-END-

EOP: TITLE:

REV: 2 3 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 1 FR-C.1 APPENDIX LIST TITLE

1) ATTACHMENT RCP START (ATT-15.0)
2) ATTACHMENT N2 PORVS (ATT-12.0)
3) ATTACHMENT LOSS OF OFFSITE POWER (ATT-e.5)
4) ATTACHMENT NO SW PUMPS (ATT-2.4)
5) FOLDOUT PAGE

EOP: TITLE:

REV: 23 FR-C.1 RESPONSE TO INADEQUATE CORE COOLING PAGE 1 of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-C series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

.EOP: TITLE: REV: 21 FR-C.2 T RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 14 GINNA STATION CONTROLLED COPY NUMBER 013 RESPONSI MANAGER

/a -/E-ojCDATE E FFECT IVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions to restore adequate core cooling.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. F-0.2, CORE COOLING Critical Safety Function Status Tree, on any ORANGE condition.

{E3- ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

o Normal conditions for running RCPs are desired, but RCPs should NOT be tripped if normal conditions cannot be established or maintained.

o Foldout Page should be open and monitored periodically.

  • 1 Monitor RWST Level - GREATER Perform the following:

THAN 28%

a. Ensure SI system aligned for cold leg recirculation using Steps 1 through 14 of ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
b. Go to Step 4.

2 Verify SI Pump Suction Aligned To RWST:

a. SI pump suction valves from RWST a. Ensure at least one SI pump

- OPEN suction valve from RWST open

  • MOV-825A
  • MOV-825A
  • MOV-825B
  • MOV-825B

EOP: TIRE: REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify SI Pump And RHR Pump Emergency Alignment:

a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.

deluge - OPEN

  • MOV-852A
  • MOV-852B
b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
c. Verify SI pump A - RUNNING c. Perform the following:
1) Ensure SI pumps B and C running.
2) Ensure SI pump C aligned to discharge line A:

o MOV-871B closed o MOV-871A open

3) Go to Step 4.
d. Verify SI pump B - RUNNING d. Perform the following:
1) Ensure SI pumps A and C running.
2) Ensure SI pump C aligned to discharge line B:

o MOV-871B open o MOV-871A closed

3) Go to Step 4.
e. Verify both SI pump C discharge e. Manually open valves as valves - OPEN necessary.
  • MOV-871A
  • MOV-871B

EOP: TITLE:

lREV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 5 of 14 4 Verify SI Flow In Both Trains:

a. SI line loop A and B flow a. Perform the following:

indicators - CHECK FOR FLOW

1) Manually start SI pumps and align valves as necessary.
2) Establish maximum charging flow.
b. RCS pressure - LESS THAN b. Go to Step 5.

250 psig [465 psig adverse CNMT]

c. RER loop flow indicator - CHECK c. Manually start RHR pumps and FOR FLOW align valves.

EOP: TITE: REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 6 of 14 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINEDl CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE. IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

5 Check RCS Vent Paths:

a. Power to PRZR PORV block valves a. Restore power to block valves

- AVAILABLE unless block valve was closed to isolate an open PORV:

  • MOV-515, MCC D position 6C
  • MOV-516, MCC C position 6C
b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

IF any PORV can NOT be closed, THEN manually close its block valve.

c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
d. Rx vessel head vent valves - d. Manually close valves.

CLOSED

  • SOV-590
  • SOV-591
  • SOV-592
  • SOV-593

EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 7 of 14 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl SP 6 Check RCP Status:

a. At least one RCP - RUNNING a. Go to Step 9.
b. Support conditions for the b. Try to establish support operating RCP(s) available conditions for the operating RCP.

(Refer to ATT-15.O, ATTACHMENT RCP START) 7 Check RVLIS Fluid Fraction

a. Fluid fraction (any RCP on) - a. IF increasing, THEN return to GREATER THAN 66% Step 1.

IF NOT, then go to Step 8.

b. Return to procedure and step in effect.

8 Check If One RCP Should Be Stopped:

a. Both RCPs - RUNNING a. Go to Step 10.
b. Stop one RCP
c. Go to Step 10 9 Check Core Cooling:
a. RVLIS level (no RCPs) - GREATER a. IF increasing, THEN return to THAN 52% [55% adverse CNMT] Step 1. IF NOT, THEN go to Step 10.
b. Core exit T/Cs - LESS THAN 700 0F b. IF decreasing, THEN return to Step 1. IF NOT. THEN go to Step 10.
c. Return to procedure and step in effect

EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 8 of 14 STEP AcTIon/ExPEcTED RESPONSE lRESPONSE NOT OBTAINED 10 Check SI ACCUM Discharge IF SI ACCUM discharge valves closed Valves - OPEN after ACCUM discharge, THEN go to Step 11. IF NOT, THEN perform the

  • MOV-841 following:
  • MOV-865
a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves.
  • MOV-841, MCC C position 12F
  • MOV-865, MCC D position 12C
b. Open SI ACCUM discharge valves.
  • ACCUM A. MOV-841
  • ACCUM B. MOV-865 CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AEW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1. ALTERNATE WATER SUPPLY TO AFW PUMPS).

o A FAULTED OR RUPTURED S/G SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT SIG IS AVAILABLE.

NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

I *11 Monitor Intact SIG Levels:

a. Narrow range level - GREATER a. Increase total feed flow to THAN 7% [25% adverse CNMT] restore narrow range level greater than 7% [25% adverse CNMT] in at least one SIG.
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 9 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 12 Establish Condenser Steam Dump Manual Control

a. Verify condenser available: a. Place intact S/G ARV controller in MANUAL and go to Step 13.

o Intact S/G MSIV - OPEN o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Place steam dump mode selector switch in MANUAL
c. Place steam dump controller in MANUAL

STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED CAUTION THE FOLLOWING STEP WILL CAUSE SI ACCUMULATOR INJECTION WHICH MAY RESULT IN A RED PATH CONDITION IN F-0.4. INTEGRITY STATUS TREE. THIS PROCEDURE SHOULD BE COMPLETED BEFORE TRANSITION TO FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.

13 Depressurize All Intact SIGs To 200 PSIG:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 1000F/HR
b. Dump steam to condenser b. Manually or locally dump steam from intact S/Gs:

o Use S/G ARVs.

-OR-o Open TDAFW pump steam suppl valve(s) for affected S/G(S):

  • S/G A. MOV-3505A
  • S/G B. MOV-3504A

-OR-o Locally perform the following:

o Open intact S/G MSIV bypass valve.

o Open priming air ejector steam isolation valves.

  • V-3580
  • V-3581
c. Check S/G pressures - LESS THAN c. Return to Step 11.

200 PSIG

d. Check RCS hot leg temperatures - d. Return to Step 11.

BOTH LESS THAN 4000 F

e. Stop S/G depressurization

EOP: TITLE:

. . REV: 21l FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 11 of 14 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl STP CAUTION RHR PUMPS SHOULD NOT BE RUN LONGER THAN 1 HOUR WITHOUT CCW TO THE RHR HEAT EXCHANGERS.

14 Check RHR Pumps - RUNNING Manually start pumps as necessary.

EOP: TITL.E:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 12 of 14 SP RESPONSE NOT OBTAINED 15 Isolate Both SI ACCUMs

a. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves if necessary
  • MOV-841, MCC C position 12F
  • MOV-865, MCC D position 12C
b. Reset SI
c. Close SI ACCUM discharge valves c. Perform the following to vent an unisolated accumulator:
  • MOV-841
  • MOV-865 1) Reset CI
2) Ensure adequate air compressor(s) running
3) Establish IA to CNMT
4) Open vent valves for unisolated SI ACCUMs.
  • ACCUM A. AOV-834A
  • ACCUM B. AOV-834B
5) Open HCV-945.

IF an accumulator can NOT be isolated or vented, THEN consult TSC to determine contingency actions.

d. Locally reopen breakers for MOV-841 and MOV-865

EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 1

. PAGE 13 of 14 S ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION SYMPTOMS FOR FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, SHOULD BE CLOSELY MONITORED DURING SUBSEQUENT STEPS.

16 Stop All RCPs 17 Depressurize All Intact S/Gs To Atmospheric Pressure:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 1000F/HR
b. Dump steam to condenser b. Manually or locally dump steam from intact S/Gs:
1) Use S/G ARVs.
2) Open TDAFW pump steam supply valve(s) for affected S/G(s):
  • S/G A. MOV-3505A
  • S/G B. MOV-3504A
3) Locally perform the following:

o Open intact S/G MSIV bypass valve.

o Open priming air ejector steam isolation valves.

  • V-3580
  • V-3581

EOP: TITLE: REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING

. .PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify SI Flow: Perform the following:

o SI line loop A and B flow a. Continue efforts to establish SI indicators - CHECK FOR FLOW or RHR flow.

-OR- b. Try to establish maximum charging flow.

o RER loop flow indicator - CHECK FOR FLOW c. Return to Step 17.

19 Check Core Cooling: Return to Step 17.

o RVLIS level (no RCPs) - GREATER THAN 77% [82% adverse CNMTI o Both RCS hot leg temperatures -

LESS THAN 3200F 20 Go to Appropriate Plant Procedure

a. Check RWST level - GREATER THAN a. Go to ES-1.3. TRANSFER TO COLD 28% LEG RECIRCULATION. Step 1.
b. Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 18

-END-

a -0 EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FR-C.2 APPENDIX LIST TITLE

1) ATTACHMENT RCP START (ATT-15.0)
2) ATTACHMENT NO SW PUMPS (ATT-2.4)
3) FOLDOUT

EOP: TITLE:

REV: 21 FR-C.2 RESPONSE TO DEGRADED CORE COOLING PAGE 1 of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-C series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

GINNA STATION CONTROLLED COPY NUMBER O RESPONSIBIO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 2 of 13 A. PURPOSE - This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-0, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.
b. F-0.1, SUBCRITICALITY, Critical Safety Function Status Tree on either a RED or ORANGE condition.

_STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED v

NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

Verify Reactor Trip: Manually trip reactor.

0 o At least one train of reactor IF reactor trip breakers NOT open.,

trip breakers - OPEN THEN manually insert control rods.

o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM

.0 Verify Turbine Stop Valves -

CLOSED Manually trip turbine.

IF turbine trip can NOT be verified, THEN close both MSIVs.

0 Check AFW Pumps Running:

a. MDAFW pumps - RUNNING a. Manually start MDAFW pumps.
b. TDAFW pump - RUNNING IF b. Manually open steam supply NECESSARY valves.
  • MOV-3505A
  • MOV-3504A

ACTION/EXPECTED RESPONSE NOT OBTAINED

  • * * * * * *t * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING STEPS 1 THROUGH 12 OF E-O. REACTOR TRIP OR SAFETY INJECTION.

NOTE: o If offsite power is lost coincident with SI, then MCC C and MCC D lockout relays must be reset to restore BA and RNW pumps.

o Foldout page should be open and monitored periodically.

4 Initiate Emergency Boration Of RCS:

a. Check SI status: a. Perform the following:

o All SI annunciators - 1) Complete steps 1 through 12 EXTINGUISHED of E-0. REACTOR TRIP OR SAFETY INJECTION, while

. * . X I A, + , ....

.. n . - I W-LL11@ a. 1. 1 .... e-Al A 1T .,_ ATTAINSfl T11 ,.4 xUUOL+/-11U.L116 _

a UnL-L >pumps r--r

-'! -N -ulv ) ...... l l l

%1.U pLUc:UULs I

2) IF SI flow indicated, THEN go to Step 5. IF NOT, THEN go to Step 4b.
b. Verify at least one charging b. Perform the following:

pump - RUNNING

1) Reset SI if necessary.
2) Start one charging pump.
c. Align boration path: c. Initiate normal boration at maximum rate using the boric
1) Start two BA transfer pumps acid flow control valve, FCV-11OA. IF flow can NOT be
2) Open MOV-350 established. THEN refer to ER-CVCS.1, REACTOR MAKEUP
3) Verify BA flow CONTROL MALFUNCTION.
d. Verify charging flow path: d. Manually align valves and verify flow.

o Charging valve to loop B cold leg (AOV-294) - OPEN o Charging flow control valve (HCV-142) - DEMAND AT 0%

. EOP: TITLE:

I REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS

. PAGE 5 of 13 ACTION/EXPECTED RESPONSE P lRESPONSE NOT OBTAINEDl 5 Check PRZR PORV Status:

a. RCS pressure - LESS THAN a. Verify PRZR PORVs and block 2335 PSIG valves open. IF NOT, THEN open PRZR PORVs and block valves as necessary until PRZR pressure less than 2335 psig.
b. Check PORVs - BOTH CLOSED b. IF PRZR pressure less than 2335 psig. THEN manually close PORVs.

IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.

  • MOV-515. MCC D position 6C
  • MOV-516, MCC C position 6C 6 Verify CNMT Ventilation Isolation
a. CVI annunciator - LIT a. Momentarily deenergize CNMT particulate monitor. R-l1, to

VENTILATION ISOLATION

b. Verify CVI valve status lights - b. Manually close affected CVI BRIGHT valves I IF valves can NOT be verified closed by MCB indication. THEN close alternate isolation valves (Refer to ATT-3.0. ATTACHMENT CI/CVI for alternate isolation valves).

EOP: TITLE:

REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 6 of 13 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 7 Check If The Following Trips Have Occurred:

a. Reactor trip a. Dispatch AO to locally trip reactor:

o Trip MG set breakers at bus 13 and bus 15.

-OR-o Open reactor trip breakers locally.

b. Turbine trip b. Dispatch AO to locally trip turbine using manual trip lever on west end of HP turbine.
  • 8 Check If Reactor Is Subcritical:
a. Energize MCC A AND B
b. Check power range channels - b. Go to Step 9.

LESS THAN 5%

c. Check Intermediate range channels c. Go to Step 9.

o Startup rate - NEGATIVE

-OR-o Intermediate range channels -

DECREASING

d. Go to Step 18.

EOP: TITLE: REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR ANW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AEW PUMPS).

  • 9 Monitor S/G Level:
a. Narrow range level in at least a. Perform the following:

one S/G - GREATER THAN 7% [25%

adverse CNMT] 1) Verify total feed flow greater than 400 gpm.

IF NOT. THEN manually start pumps and align valves as necessary.

IF AEW can NOT be established, THEN establish SAFW (Refer to ATT-5.1.

ATTACHMENT SAFW)

2) Maintain total feed flow greater than 400 gpm until narrow range level greater than 7% [25% adverse CNMT] in at least one S/G.
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

EOP: TITLE:

.I REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS

. PAGE 8 of 13 ACTION/EXPECTED RESPONSE P lRESPONSE NOT OBTAINEDl 10 Verify Dilution Paths -

ISOLATED

a. Place RNW mode switch to BORATE
b. Stop RMW pumps b. Perform the following:
1) Close RMW to blender (AOV-111)
2) Direct AO to locally open RMW pump breaker
  • RMW Pump A. MCC C Pos 13B
  • RMW Pump B. MCC D Pos 1B 11 Stabilize RCS Temperature:
a. Control steam dump as necessary
b. Verify the following: b. IF RCS cooldown can NOT be controlled. THEN close both o Core exit T/Cs - STABLE OR MSIVs and go to Step 12.

INCREASING o Pressure in both SIGs -

STABLE OR INCREASING o Pressure in both S/Gs -

GREATER THAN 110 PSIG

c. Go to Step 16

EOP: TITLE:

REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 9 of 13 SE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify MFW Isolation:

a. MFW pumps - TRIPPED a. Manually close MFW pump discharge valves and trip MFW pumps.
b. Depress MANUAL pushbutton for A and B S/G MFW regulating valve and bypass valve controllers AND adjust to 0% demand.

13 Identify Faulted S/G: Go to Step 16.

o Any S/G Pressure - DECREASING IN AN UNCONTROLLED MANNER

-OR-o Any SIG Pressure - LESS THAN 110 PSIG

CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

o IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.

14 Isolate Feed Flow To Faulted Manually close valves.

S/G:

IF valves can NOT be closed, THEN o Close faulted S/G MDAFW pump dispatch AO to locally isolate discharge valve flowpaths as necessary.

  • S/G A, MOV-4007
  • SIG B, MOV-4008 o Pull stop faulted S/G MDAFW pump o Close faulted S/G TDAFW flow control valve
  • SIG A, AOV-4297
  • S/G B, AOV-4298 o Verify faulted S/G MFW regulating valve and bypass valve - CLOSED
  • S/G A. HCV-466 and HCV-480
  • S/G B. HCV-476 and HCV-481 o Verify MDAFW pump crosstie valves - BOTH CLOSED
  • MOV-4000A
  • MOV-4000B o Close faulted S/G SAFW pump discharge valve
  • S/G A. MOV-9701A
  • S/G B. MOV-9701B

RESPONSE RESPONSE NOT OBTAINED

+/-cTION/EEcTED -

CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE SIG.

15 Isolate Steam Flow From Manually close valves.

Faulted SIG:

IF valves can NOT be closed, THEN o Verify faulted SIG ARV - CLOSED dispatch AO to locally isolate flowpaths as necessary.

  • SIG A. AOV-3411
  • S/G B. AOV-3410 o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP
  • SIG A. MOV-3505A
  • S/G B, MOV-3504A o Verify faulted SIG blowdown and sample valves - CLOSED
  • SIG A, AOV-5738 and AOV-5735
  • S/G B. AOV-5737 and AOV-5736 o Dispatch AO to complete faulted SIG isolation (Refer to ATT-10.0, ATTACHMENT FAULTED SIG)

EOP: TITLE:

REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 12 of 13 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 16 Check Core Exit T/Cs - LESS IF core exit temperatures greater THAN 12000F than 12001F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, step 1.

NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

17 Verify Reactor Subcritical: Perform the following:

o Power range channels - LESS THAN a. Stabilize RCS temperature.

5%

b. Continue to inject boric acid.

o Intermediate range channels STABLE OR DECREASING c. Perform actions of other FR procedures in effect which do o Intermediate range channels NOT cooldown or otherwise add startup rate - NEGATIVE positive reactivity to the core.

o Core exit TICs - STABLE d. Direct RP to sample RCS and PRZR for boron concentration.

e. Verify boron concentration greater than FIG-2.0, FIGURE SDM.

IF adequate shutdown margin verified, THEN go to Step 18.

IF NOT, THEN perform the following:

a. Allow RCS to heat up.
b. Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.
c. Return to Step 4.

I I SE ACTION/EXPECTED RESPONSE REPNENTOTIE CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.

18 Return to Procedure And Step In Effect

-END-

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REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE

1) FIGURE SDM (FIG-2.0)
2) ATTACHMENT FAULTED S/G (ATT-10.0)
3) ATTACHMENT CI/CVI (ATT-3.0)
4) ATTACHMENT SAFW (ATT-5.1)
5) ATTACHMENT NO SW PUMPS (ATT-2.4)
6) FOLDOUT

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REV: 18 FR-S.1 RESPONSE TO REACTOR RESTART/ATWS PAGE 1 of 1 FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-S series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.
b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

and a EOP: TITLE:

REV: 10 FR-Z .1 RESPONSE TO HIGH CONTAINMENT PRESSURE PAGE 1 of 7 I.

GINNA STATION CONTROLLED COPY NUMBER _

X~Q W RESPONSIa MANAGER I/ EF F/C V- DA T EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides actions to respond to a high CNMT pressure.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. F-0.5, CONTAINMENT Critical Safety Function Status Tree, on a RED or ORANGE condition.

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REV: 1 0 F`R-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE PAGE 3 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: FOLDOUT Page should be open and monitored periodically.

1 Verify All CI And CVI Valve IF flow path NOT required, THEN Status Lights - BRIGHT manually close affected CI and CVI valves.

IF valves can NOT be verified closed by MCB indication, THEN close alternate isolation valves.

(Refer to ATT-3.O, ATTACHMENT CI/CVI).

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • * * * * * * * * * * *
  • I* * * * * * * * * * * * * * * * * * * * * * * * * * *
  • CAUTION o IF ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, IS IN EFFECT, THEN CNMT SPRAY SHOULD BE OPERATED AS DIRECTED IN ECA-1.., RATHER THAN STEP 2 BELOW.

o IF E-1, LOSS OF REACTOR OR SECONDARY COOLANT, IS IN EFFECT, THEN CNMT SPRAY SHOULD BE OPERATED AS DIRECTED IN E-1, LOSS OF REACTOR OR SECONDARY COOLANT, RATHER THAN STEP 2 BELOW.

  • * * * * * * * * * * * * * * * *e * * * * * * * * * * * * * * * * * * * * * *
  • 2 Verify CNMT Spray Actuated:
a. Verify RWST outlet to SI and a. IF in RHR recirculation mode, CNMT spray pumps - OPEN THEN perform the following:

. MOV-896A 1) Operate SI pumps and one CNMT

  • MOV-896B spray pump as directed in ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 15.
2) Go to Step 3.
b. Verify CNMT spray pumps - RUNNING b. Manually start pumps.
c. Verify NaOH flow (FI-930) c. IF NaOH flow NOT indicated, THEN place switches for NaOH tank outlet valves to OPEN.
  • AOV-836A
  • AOV-836B
d. Verify CNMT spray pump discharge d. Ensure at least one in each set valves - OPEN open.
  • MOV-860A
  • MOV-860A or MOV-860B
  • MOV-860B
  • MOV-860C or MOV-860D
  • MOV-860C
  • MOV-860D

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 3 Verify CNMT RECIRC Fans Running:

a. All fans - RUNNING a. Manually start fans.
b. Charcoal filter dampers green b. Dispatch personnel to relay room status lights - EXTINGUISHED with relay rack key to locally open dampers by pushing in trip relay plungers.
  • AUX RELAY RACK RA-2 for fan A
  • AUX RELAY RACK RA-3 for fan C 4 Verify MSIVs - CLOSED Manually close valves.

P ION/EXPECTED RESPONSE SPONSE NOT OBTAINED

  • * * * * * * * * * * * * * * * * * * * * * *F * * * * * * * * * * * * * * * * *
  • CAUTION o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

o IF BOTH S/GS ARE FAULTED, THEN AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.

5 Check If SIG Secondary Side Isolate feed flow to faulted S/G:

Is Intact:

a. Ensure faulted S/G MDAFW pump o Pressure in both S/Gs - STABLE discharge valve closed.

OR INCREASING

  • S/G A, MOV-4007 o Pressure in both S/Gs - GREATER
  • S/G B. MOV-4008 THAN 110 PSIG
b. Ensure faulted SIG TDAFW flow control valve closed.
  • S/G A, AOV-4297
  • S/G B. AOV-4298
c. Depress MANUAL pushbuttons for faulted S/G MFW regulating valve and bypass valve AND ensure valves closed.
  • S/G A. HCV-466 and HCV-480
  • S/G B. HCV-476 and HCV-481
d. Ensure MFW pump discharge valves closed.

IF valves can NOT be closed, THEN dispatch AO to locally close valves as necessary to isolate flow.

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REV: 10 FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE PAGE 7 of 7 STEP ACTION/EXPECTED RESPONSE [RESPONSE NOT OBTAINED 6 Return To Procedure And Step In Effect

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FR-Z.1 APPENDIX LIST TITLE

1) ATTACHMENT CI/CVI (ATT-3.O)
2) ATTACHMENT NO SW PUMPS (ATT-2.4)
3) FOLDOUT

FOLDOUT PAGE NOTE: This Foldout Page applies to all FR-Z series procedures.

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:
a. Pull stop any D/G that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE .

SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
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