ML050830347

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R. E. Ginna, Emergency Operating Procedures
ML050830347
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/11/2005
From: Marlow T
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050830347 (73)
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Text

1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC March 11, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Subject:

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

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

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

AP Index FR Index AP-RCS.4, Rev 16 FR-H.1, Rev 32

(

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Fri 3111/2005 10:26:30 am' Pale1 of 2 NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDUREINDE)

INPUT PARAMETERS: TYPE:

PRAP STATUSVALUE(S):

EFQU 6 YEARS ONLY:

, i PRAP ABNORMAL PROCEDURE PROCEDURE NUMBER AP-CCW.1 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP-CW.1 AP-ELEC.1 AP-ELEC.2 AP-ELEC.3 AP-ELEC.13/15 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC.2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 PROCEDURE TTTLE LEAKAGE INTO THE COMPONENT COOLING LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW-PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12AAND/OR 12B BUSSES SAFEGUARD BUSSES LOWlVOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)

LOSS OF BUS 13115 LOSS OF SAFEGUARDS BUS 14116 LOSS OF SAFEGUARDS BUS 17118 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWALIINSERTION RCCIRPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTMTY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDlTIONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WITHOUT RX TRIP REQUIRED EFFECT LAST REV DATE REVIEW 017 0613012004 06126/2002 019 06t3012004 06/26/2002 016 06/3012004 06/2612002 020 06130/2004 06126/2002 014 06130/2004 06/0312002 004 08/2612003 0212712004 012 09/17t2004 0411612003 028 01121t2005 06/26/2002 011 06/10/2004 0612612002 013 01/2112005 06126/2002 001 06130/2004 0912412003 009 01121/2005 06/2612002 008 01t2112005 06/2612002 016 0613012004 06126/2002 018 06126/2002 04/16/2003 015 06130/2004 06126t2002 009 0613012004 04t16/2003 011 06130/2004 21/20151/2 006 02125/2003 0212512003 017 0613012004 0412412003 017 06/3012004 04/16/2003 012 0613012004 04/1612003 01 06/3012004 0410112002 016 03/11/2005 0413012003 019 04/30/2003 0413012003 014 06/30/2004 04/30/2003 003 1112112002 06/26t2002 021 09/17/2004 04/21/2003 007 01121/2005 1//20/50t3 013 06/30/2004 06/26/2002 NEXT REVIEW 06126/2007 0612612007 0612612007 06t26/2007 06/0312007 02/27/2009 04/1612008 0612612007 06126/2007 0612612007 0912412008 06/26/2007 0612612007 06126/2007 04/16/2008 06/2612007 04116/2008 0112212007 02/25/2008 04/24/2008 04/16/2008 04/16/2008 01/22/2007 04/30/2008 04/3012008 04130/2008.

06/2612007 04t2112008 10/31/2006 06/26/2007 ST EF EF EF EF EF

.EF EF EF EF EF EF EF EF EF EF EF EF IEF EF EF EF EF EF EF EF EF EF EF EF EF 6k, k

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I NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Fri 3/11/2005 10:26:30 am Page 2 of 2 INPUT PARAMETERS: TYPE.,

PRAP STATUSVALUE(S):

EF.QU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE, PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 020 01t21/2005 06/2612002 06t26/2007 EF AP-TURB.3 TURBINEVIBRATION 012 06t30/2004 06126t2002 06t26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 017 04t3012003 04130t2003 04130t2008 EF AP-TURB.5 RAPID LOAD REDUCTION 007 06t3012004 06/26t2002 06/26/2007 EF PRAP TOTAL:

34 GRAND TOTAL 34

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NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Fri 3/11/2005 10:26:15 am Page 1 of 1 INPUT PARAMETERS: TYPE:

PRFR STATUSVALUE(S):

EF,QU O

5 YEARS ONLY:

IiPRFR FUNCTIONAL RES§TORAlhON GUIDEN PROC6 PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FR-C.1 FR-C2 FR-C.3 FR-H.1 FR-H.2 FR-H.3 FR-H.4 FR-H.5 FR-4.1 FR-4.2 FR4.3 FR-P.1 FR-P2 FR-S.1 FR-S.2 FR-Z.1 FR-Z.2 FR-Z.3 RESPONSE TO INADEQUATE CORE COOLING RESPONSE TO DEGRADED CORE COOLING RESPONSE TO SATURATED CORE COOLING RESPONSE TO LOSS OF SECONDARY HEAT SINK RESPONSE TO STEAM GENERATOR OVERPRESSURE RESPONSE TO STEAM GENERATOR HI-GH LEVEL RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES RESPONSE TO STEAM GENERATOR LOW LEVEL RESPONSE TO HIGH PRESSURIZER LEVEL RESPONSE TO LOW PRESSURIER LEVEL RESPONSE TO VOIDS IN REACTOR VESSEL RESPONSE TO IMMINENT PRESSURIED THERMAL SHOCK CONDmON

  • RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDmON RESPONSE TO REACTOR RESTART/ATWS RESPONSE TO LOSS OF CORE SHUTDOWN RESPONSE TO HIGH CONTAINMENT PRESSURE RESPONSE TO CONTAINMENT FLOODING RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 021 11117/2004 03124/2003 03/2412008 019 11117/2004 03/24/2003 03/24/2008 009 05130/2003 03/24/2003 03124/2008 032 03111/2005 03/24/2003 03/24/2008 006 10/10/2003 03124/2003 03/2412008 008 11117/2004 03124/2003 03/24/2008 005 05/3012003 03/24/2003 03/24/2008 010 11117/2004 03/24/2003 03/24/2008 017 01107/2004 03/24/2003 03/24/2008 012 11/17(2004 03/24/2003 03/24/2008 020 11/1712004 03/24/2003 03/2412008 029 11117/2004 03/24/2003 03/2412008 EF EF EF EF EF EF EF EF EF EF EF EF 009 11/17/2004 03/24/2003 017 11/1712004 03/24/2003 009 05130/2003 03/24/2003 008 10/10/2003 03/24/2003 005 05/30/2003 0312412003 005 05/30/2003 03/24/2003 03/24/2008 EF 03/24/2008 EF 03/24/2008 EF 03/24/2008 EF 03/2412008 EF 03/24/2008 EF PRFR TOTAL 18 GRAND TOTAL 18 CA

I l EP:

TITLE:RE:

1 EAP-RCS.4 SHUTDOWN LOCA PAGE 1 of 35 I

GINNA STATION CONTROLLED COPY NUMBER RESPONSI*E MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

TITLE:

REV: 16 AP-RCS.4 SHUTDOWN LOCA PAGE 2 of 35 A. PURPOSE -

This procedure provides actions for protecting the reactor core in the event of a loss of coolant accident (LOCA) that occurs during Mode 3 after the SI accumulators are isolated or Mode 4.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS -

This procedure is entered from:

a. AP-RHR.1, LOSS OF RHR, when RCS leak is indicated with RCS temperature greater than 2000F, or
b. AR-RMS-2, R2 CONTAINMENT, if other CNMT rad monitors increasing, or
c. AR-RMS-7, R7 INCORE DETECTION AREA, if other CNMT rad monitors increasing, or
d. AR-RMS-1OA, R1OA CNMT IODINE, if R-11, R-12 increasing, or
e. AR-RMS-11, R11 CNMT PARTICULATE MON, if RCS leak is suspected, or
f. AR-RMS-12, R12 CNMT GAS, if RCS leak is suspected, or
g. AR-C-18, CONTAINMENT SUMP A PUMP AUTO START, if RCS leak is suspected, or
h. AR-C-19, CONTAINMENT SUMP A HI LEVEL, if RCS leak is suspected, or
i. AR-C-20, CONTAINMENT SUMP B HI LEVEL, if RCS leak is suspected.
2. SYMPTOMS -

The symptoms of shutdown loss of coolant accident during Modes 3 and 4 are:

a. Uncontrolled decrease in PRZR level, or
b. Uncontrolled decrease in RCS subcooling, or

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT *OBTAINEDl NOTE:

o Conditions should be evaluated for site contingency reporting (Refer to EPIP-l.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

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

  • 1 Monitor RCS Conditions:

o RCS subcooling based on core exit T/Cs - GREATER THAN 00F FIG-1.O. FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 10%

[30% adverse CNMT]

Perform the following:

a. Stop RHR pumps and place in PULL STOP.
b. Close RHR discharge valves to SI pump suction
  • MOV-857A
  • MOV-857B
  • MOV-857C 2 Isolate RCS Letdown:
a. Close letdown isolation, AOV-427
b. Place letdown orifice valve switches to CLOSE (AOV-200A.

AOV-200B, and AOV-202)

c. Close letdown isolation. AOV-371
d. Close RHR letdown to CVCS.

HCV-133

e. Place letdown pressure controller, PCV-135. in MANUAL and close valve (demand at 100%)
f. Close excess letdown isolation valve, AOV-310

EOP:

TITLE:

REV: 16 AP-RCS.4 SHUTDOWN LOCA PAGE 4 of 35 ACTION/EXPECTED RESOE RESPONSE NOT OBTAINEDl NOTE:

IF the RCS is water solid, THEN charging should be controlled to maintain RCS pressure.

3 Establish Required RCS Injection Flow:

a. Charging pumps - ANY RUNNING
a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any #1 seal outlet temperature offscale hilh. THEN dispatch AO to local y isolate seal injection to affected RCP.
2) Ensure HCV-142 open, demand at 0%.
b. Align charging pump suction to
b. IF LCV-112B can NOT be opened, RWST:

THEN dispatch AO to locally open V-358. manual charging pump K

o LCV-112B -OPEN suction from RWST (charging pump room).

o LCV-112C -CLOSED 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 (75 kw) and adjust charging flow to maintain PRZR level

4 Verify Charging Flow Adequate:

a. Check the following:
a. Go to Step 5.

o RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-l.O. FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 10%

[30% adverse CNMT]

o PRZR level - STABLE OR

  • INCREASING
b. Verify charging flow needed to maintain PRZR level stable -

LESS THAN 75 gpm (PPCS point FCHG)

c. Go to AP-RCS.1. REACTOR COOLANT LEAK
b. Go to Step 7.

EOP:

TITLE:

REV: 1 6 AP-RCS.4 SHUTDOWN LOCA PAGE 6 of 35 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED CAUTION o IF RWST LEVEL DECREASES TO LESS THAN 28%. THEN THE SI SYSTEM SHOULD BE ALIGNED FOR SUMP RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. STEPS 1 THROUGH 13.

o RP TECH SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.

5 Verify SI Injection Capability:

a. Check RCS temperature - LESS THAN 350 0F
a. Perform the following:
1) Ensure SI pump discharge valves'to RCS cold legs - OPEN
  • SI Pump A. MOV-878B

. SI Pump B. MOV-878D

2) Go to Step 5c.
b. SI pump discharge valves to RCS OPEN

. SI pump A. MOV-878A and MOV-878B

. SI pump B. MOV-878C and MOV-878D

b. Manually open valves. Dispatch AO to locally restore power to the,following if necessary (locked valve key required):
  • MOV-878A.
  • MOV-878B.

. MOV-878C.

MOV-878D.

MCC MCC MCC MCC C position 8C D position 8C C position 8F D position 8F

c. SI pumps -

AT LEAST TWO PUMPS AVAILABLE

c. Dispatch AO to restore power to at least two SI pump(s), if necessary.
  • SI pump A. Bus 14 position 20A

. SI pump B. Bus 16 position 12A

  • SI pump C. Bus 14 position 19A OR Bus 16 position 13A

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 6 Establish SI Flow:

a. Verify the following valves -

OPEN

. RWST outlet valves (MOV-896A and MOV-896B)

  • SI pump C suction valves (MOV-1815A and MOV-1815B)
b. Open SI pump suction valves from RWST:

. MOV-825A

. MOV-825B

c. Start ONE SI pump
a. Manually open valves.
b. Ensure at least one SI pump suction valve from RWST open.
  • MOV-825A

. MOV-825B 7 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate personnel from CNMT
b. Periodically monitor CNMT radiation

EOP:

TITLE:

REV: 1 6 AP-RCS.4 SHUTDOWN LOCA P

PAGE 8 of 35 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED 8 Establish Required CNMT Conditions:

a. Depress MANUAL CNMT ISOLATION pushbutton
b. Verify CI/CVI valves -

CLOSED

b. Manually close affected CI and 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. Start all available CNMT RECIRC fans (205 kw each)
d. Dispatch AO to locally fail open CNMT RECIRC fan cooler SW outlet valves (INT BLDG basement by MG sets)
  • FCV-4561

. FCV-4562

SACTION/EXPECTEDRESPONSE lRESPONSE NOT OBTAINED l

  • 9 Monitor RCP Operation:
a. RCPs - ANY RUNNING
b. Check RCP #1 seal D/P - GREATER THAN 220 PSID
c. Check RCP #1 seal leakoff -

WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0. FIGURE RCP SEAL LEAKOFF

a. Go to Step 10.
b. Stop affected RCP(s) and go to Step 9d.
c. IF RCP #1 seal failure is suspected. THEN stop affected RCP(s).
d. Ensure PRZR spray valves - CLOSED

. PCV-431A

. PCV-431B 10 Check RHR Pump Status:

a. RHR pumps aligned for injection mode:
a. Go to Step 11.

o RWST to RHR pump suction valve, MOV-856 - OPEN

_ o RHR suction valves from loop A hot leg (MOV-700 and MOV-701) - CLOSED

b. Go to Step 12

EOP:

TITLE:

16 AP-RCS.4 SHUTDOWN LOCA :-

PAGE 10 of 35 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINED NOTE: Continue with this procedure starting at Step 13 while aligning RHR for injection.

WHEN RHR aligned, THEN do Step 12.

11 Establish RHR Injection Alignment:

a.

b.

Stop any running RHR pump Close RHR normal cooling valves:

b. Ensure at least one suction valve and one discharge valve closed.

o RHR suction valves from loop A hot leg (MOV-700 and MOV-701) - CLOSED o RHR discharge valves to loop B cold leg tMOV-720 and MOV-721) - CLOSED

c. Verify alignment of RHR suction valves from sump B:
1) MOV-850A and MOV-850B (outside CNMT) -

CLOSED

2) MOV-851A and MOV-851B (inside CNMT) - OPEN
d. Verify open RHR pump suction valves (MOV-704A and MOV-704B)
e. Check RHR pump suction temperature - LESS THAN 280'F (PPCS point T0684A or T0684B)
  • 1) Close MOV-850A and MOV-850B.

Do NOT continue until valves closed.

2) Open MOV-851A and MOV-851B.
d. Manually open valves.
e. Go to Step 13.
f. Open RWST to RHR pump suction valve. MOV7856 (energize DC control power key switch)
g. Place RHR Hx bypass valve.

HCV-626. to MANUAL and close valve

h. Open RHR Hx flow control valves (HCV-624 and HCV-625)
i. Open RHR core deluge valves (MOV-852A and MOV-852B)

EOP:

TIRE:

I AP-RCS.4 SHUTDOWN LOCA..

1 I -

PAGE 11 of 35 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 12 Check If RHR Injection Flow Required:

a. RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-1.0. FIGURE MIN SUBCOOLING
a. Perform the following:
1) Open RHR core deluge valves
  • MOV-852A
  • MOV-852B
2) Start one RHR pump.

13 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE
b. Check RVLIS indication:

o Level (no RCPs) - GREATER THAN 77% [82% adverse CNMT]

a. IF PRZR level greater than 10%

[30% adverse CNMT] and stable or increasing. THEN go to Step 13c.

IF NOT, THEN start two SI pumps to restore PRZR level to greater than 10% [30% adverse CNMT] and stable or increasing and go to Step 14.

b. Start SI pump(s) to restore RVLIS level (no RCPs) or fluid fraction (any RCP running) and go to Step 14.

-OR-'

o Fluid fraction (any RCP running) - GREATER THAN 84%

c. Core exit T/Cs - STABLE OR DECREASING
c. Start SI pump(s) to stabilize or decrease core exit T/Cs.

SP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED l 14 Check RCS Hot Leg Temperatures -

STABLE Control steam dump (or ARVs) and total feed flow to stabilize RCS temperature.

15 Initiate Evaluation Of Plant Status:'

a. Attempt to identify and isolate RCS break
b. Check AUX BLDG radiation - NORMAL
  • Plant vent particulate (R-13)
  • Plant vent gas (R-14)
  • CCW liquid monitor (R-17)

. CHG pump room (R-4)

b. Attempt to identify and isolate leakage to AUX BLDG (Refer to AP-RCS.1, REACTOR COOLANT LEAK).
c. Direct RP to obtain the following samples:

. CNMT hydrogen

. CNMT sump

d. Evaluate and operate equipment as necessary:
  • Charging pumps

. CNMT RECIRC fans

. Steam dump/ARVs

  • VCT makeup system

16 Reset SI 17 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED 18 Verify Adequate Service Water Flow:
a. Check at least two SW pumps -

RUNNING

a. Manually start supply permits pumps as power (257 kw each).
b. SW header pressure - GREATER THAN 40 PSIG IN EACH LOOP
b. Manually align valves to restore SW pressure greater than 40 psig in each loop.

(Refer to AP-SW.2, LOSS OF SERVICE WATER)

19 Establish IA To CNMT:

,a.

Verify non-safeguards busses energized from offsite power o Bus 13 normal feed - CLOSED

-OR-o Bus 15 normal feed - CLOSED

a. Restore IA supply as follows:
1) IF electric air compressor is desired. THEN perform the following:

a) Close non-safeguards bus tie breakers:

  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie b) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT. THEN evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0.

ATTACHMENT CNMT RECIRC FANS).

c) WHEN bus 15 restored. THEN reset control room lighting.

d) Go to step 19b.

2) IF diesel air compressor is desired, THEN restore IA supply using the diesel air compressor.. (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)
b. Verify turbine building SW isolation valves - OPEN
b. Manually align valves.
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664 This Step continued on the next page.

EOP:

TITLE:l RE:V: 16 AP-RCS.4 SHUTDOWN LOCA:

PAGE 15 of 35 (Step 19 continued from previous page)

c. Verify adequate air compressor(s) - RUNNING
c. Manually start air compressors as power supply permits (75 kw each).

IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

IF electric air compressor can NOT be started. THEN use diesel air compressor.

(Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)

d. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o

Pressure - STABLE OR INCREASING

d. Perform the following:
1) Continue attempts to restore IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).
2) Continue with Step 20.

WHEN IA restored, THEN do Steps 19e and f.

e. Reset both trains of XY relays for IA to CNMT AOV-5392
f. Verify IA to CNMT AOV-5392 - OPEN 20 Check PRZR PORV Block Valves:
a. Power to PORV block valves -

AVAILABLE

a. Restore power to block valves unless block valve was closed to isolate an open PORV:

. MOV-515, MCC D position 6C

. MOV-516, MCC C position 6C

b. Block valves - AT LEAST ONE OPEN
b. Open one block valve unless it was closed to isolate an open PORV.

SE ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRESSURE. THEN STEP 21 SHOULD BE PERFORMED AFTER PRESSURE DECREASES TO LESS THAN THE APPLICABLE PORV SETPOINT.

  • S*

21 Monitor PRZR PORV Status:

a. Check Reactor Vessel overpressure protection system -

IN SERVICE

b. Check RCS pressure - LESS THAN 410 PSIG
a. Go to Step 21d.
b. Verify at least one PRZR PORV open.

Continue with Step 22.

WHEN pressure less than oetpoint, THEN do Step 21e.

c. Go to Step 21e
d. Check PRZR pressure - LESS THAN 2335 PSIG
e. Verify PRZR PORVo - CLOSED
d. Verify at least one PRZR PORV open.

Continue with Step.22.

WHEN pressure less than setpoint. THEN do Step 21e.

e. Manually close PORVs. IE any PORV can NOT be closed, THEN manually close ito block valve.

ACTON/EPECTD REPONS l

lRESPNSENOT OBTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED.

IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

  • 22 Monitor If RHR Pumps Should Be Stopped:
a. RHR Pump running in injection mode
b. Check RCS pressure:
a. Go to Step 23.

b.

Go to Step 23.

1) Pressure -. GREATER THAN 250 prig [465 prig adverse CNMTI
2) Pressure - STABLE OR INCREASING
c. Stop RHR pumps and place AUTO

ATO/XPECTED RESPONSEIREPNE OT BAND CAUTION 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 AEW PUMPS).

NOTE:

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

23 Monitor S/G Levels:

a. Narrow range level - GREATER THAN 7% [25% adverse CNMT]
b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 17% [25%

adverse CNMT] in at least one S/G.

b. IF narrow range level in any S/G continues to increase, THEN stop feed to that S/G.

24 Check If RCS Overpressure Protection Should Be Placed In Service:

a. Check the following:

o RCS cold leg temperature -

LESS THAN 3500F o RCS pressure - LESS THAN 400 psig [300 psig adverse CNMTI

b. Place RCS overpressure protection in service (Refer to 0-7. ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
a. Go to Step 25.

EOP:

TITLE:

REV: 16 AP-RCS.4 SHUTDOWN LOCA ;....

PAGE 19 of 35 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check core exit T/Cs -

-GREATER THAN 2000F Go to Step 27.

NOTE:

Shutdown margin should be monitored during RCS cooldown (Refer to FIG-2.0. FIGURE SDM).

26 Initiate RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 1000F/HR
b. Use RHR system if in service
c. Dump steam to condenser from S/Gs 27 Check RCS Subcooling Based On Core Exit T/Cs -

GREATER THAN 0-F USING FIG-1.0, FIGURE MIN SUBCOOLING 28 Check If SI-In Service:

c. Manually or locally dump steam using S/G ARVs.

Go to Step 46.

Go to Step 38.

o SI pumps - ANY RUNNING

-OR-o RHR pumps - ANY RUNNING IN INJECTION MODE

ACTON/EPECED RSPONE lRESPNSENOT OBTAINEDI1 29 Place PRZR Heater Switches In The Following Positions:

o PRZR proportional heaters -

PULL STOP o PRZR backup heaters - OFF 30 Check PRZR level -

LESS THAN 20% [40% adverse CNMT]

Go to Step 32.

CAUTION RCS SUBCOOLING MAY BE LOST TEMPORARILY WHILE PERFORMING DEPRESSURIZATION TO RESTORE PRZR LEVEL..

NOTE:

o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o WHEN using a PRZR PORV, THEN select one with an operable block valve.

31 Depressurize RCS To Refill PRZR:

a. Depressurize using normal PRZR spray if available
a. IF normal spray NOT available.

THEN use one PRZR PORV.

IF IA NOT available. THEN refer to ATT-12.0, ATTACHMENT N2 PORVS.

IF NO PORV available. THEN use auxiliary spray valve (AOV-296).

b. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

b. Continue with Step 32.

level greater than 20%

  • adverse CNMT]. THEN do WHEN

[40%

Step 31c.

c. Stop RCS depressurization

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 32 Check If An RCP Should Be Started:

a. Both RCPs - STOPPED
a. Perform the following:
1) Stop all but one RCP.
2) Place spray valve controller for idle RCP in MANUAL at 0%

demand.

3) Go to Step 33.
b. RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING EIG-l.O, FIGURE MIN SUBCOOLING
c. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

d. Try to start an RCP
1) Establish conditions for starting an RCP a) Bus 11A or l1B energized b) Refer to ATT-15.0.

ATTACHMENT RCP START

b. Go to Step 46.
c. Return to Step 30.
d. IF an RCP can NOT be started.

THEN perform the following:

1) Ensure at least one control rod shroud fan running (45 kw).
2) Ensure one Rx compartment cooling fan running (23 kw).
2) Start one RCP

EOP:

TITLE:

REV: 1 6 AP-RCS.4 '

SHUTDOWN LOCA I.

PAGE 22 of 35 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Check RCS Cold Leg Temperature -

GREATER THAN 2850F Go to Step 37.

CAUTION IF RHR PUMP SUCTION TEMPERATURE IS GREATER THAN 2500F (PPCS POINT ID T0684A OR T0684B), THEN CONSULT TSC BEFORE STARTING AN RHR PUMP.

34 Check SI Pump Status:

a. Three SI pumps - RUNNING
b. RCS subcooling Based.on core exit T/Cs - GREATER THAN 35°F

[900F adverse CNMT] using FIG-1.0. FIGURE MIN SUBCOOLING

a. Go to Step 35.
b. IF RCS hot leg temperature greater than 320 0F [310%

adverse CNMT] OR IF RHR normal cooling in service, THEN go to Step 46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 320'F

[3100F adverse CNMT], AND RHR pump suction temperature less than 250°F, THEN ensure at least one RHR pump running in injection mode and go to Step 34c.

IF no RHR pump can be operated in injection mode, THEN go to Step 46.

c. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

c.. DO NOT stop SI pump.. Return to Step 31.

d. Stop one SI pump

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 35 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING
b. Determine required RCS subcooling from table
a. Go to Step 36.

Charging Pump RCS Subcooling Criteria Availability NONE 1200F [2000F adverse CNMT]

ONE 115'F [1900F adverse CNMT]

TWO 105'F [180'E adverse CNMT]

THREE 1000F [1751F adverse CNMT]

c. RCS subcooling based on core exit TICs - GREATER THAN VALUE FROM TABLE ABOVE USING EIG-1.0, FIGURE MIN SUBCOOLING
c. IF RCS hot leg temperature greater than 320'F [310'F adverse CNMT] OR IF RHR normal cooling in service, THEN go to Step.46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 3201F

[310'F adverse CNMTJ, AND RHR pump suction temperature less than 2500F. THEN ensure at least one RHR pump running in injection mode and go to Step 35d.

IF no RHR pump can be operated in injection mode, THEN go to Step 46.

d. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

d. DO NOT stop SI pump.

Return to Step 31.

e. Stop one SI pump
  • SE ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 36 Check If Last SI Pump Should Be Stopped:
a. Any SI pump - RUNNING
b. Determine required RCS subcooling from table
a. Go to Step 38.

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 2551F [2951F adverse CNMT]

TWO 2351F [2850F adverse CNMT]

THREE 210'F [270'F adverse CNMT]

c. RCS subcooling based on core exit T/Cs - GREATER THAN REQUIRED SUBCOOLING USING FIG-l.0. FIGURE MIN SUBCOOLING
c. IF RCS hot leg temperature greater than 3200 F [3100F adverse CNMT] OR IF RHR normal cooling in service. THEN go to Step 46.

IF RHR normal cooling NOT in service AND RCS hot leg temperature less than 3200F

[310OE adverse CNMT], AND RHR pump suction temperature less than 2500F, THEN ensure at least one RHR pump running in injection mode and go to Step 36d.

IF no RHR pump can be operated in injection mode.

THEN go to Step 46.

d. PRZR level - GREATER THAN 20%

[40% adverse CNMTI

d. DO NOT stop SI pump.

Step 31.

Return to

e. Stop SI pump
f. Go to Step 38

SP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Check If SI Pump Should Be Stopped:

a. Any SI pump - RUNNING
b. RCS pressure - GREATER THAN 295 psig [510 psig adverse CNMT]
a. Go to Step 38.
b. Go to Step 46.
c. PRZR level - GREATER THAN 20%

[40% adverse CNMT1

c. Do NOT stop SI pump.

Step 31.

Return to

d. Stop one SI pump
e. Return to Step 37a 38 Check If Charging.Flow Should Be Controlled To Maintain PRZR Level:
a. Check RHR pumps - ANY RUNNING IN INJECTION MODE
a. Start charging pumps and control charging flow to maintain PRZR level and go to Step 39.
b. Go to Step 46.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 39 Check RCP Status:

a. RCPs - AT LEAST ONE RUNNING
a. Try to start one RCP
1) Establish conditions for starting an RCP a) Bus 11A or lB energized b) Refer to ATT-15.0, ATTACHMENT RCP START
2) Start one RCP.

IF an RCP can NOT be started. THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).

IF natural circulation NOT verified, THEN increase dumping steam.

3) Go to Step 40.
b. Stop all but one RCP

ACTON/EPECTD REPONS 1

lRESPNSENOT OBTAINED CAUTION DEPRESSURIZING THE RCS MAY RESULT IN LOSING THE MINIMAL RCP #1 SEAL OPERATING CONDITIONS.

THIS WILL REQUIRE THE RCPS TO BE TRIPPED.

NOTE:

o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o WHEN using a PRZR PORV. THEN select one with an operable block valve.

40 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR
a. IF normal spray NOT available, spray if available THEN use one PRZR PORV.

IF IA NOT available. THEN refer to ATT-12.0, ATTACHMENT N2 PORVS.

IF NO PORV available. THEN use auxiliary spray valve (AOV-296).

b. Energize PRZR heaters as necessary
c. Depressurize RCS until EITHER of the following conditions satisfied:

o *PRZR level - GREATER THAN 75%

[65% adverse CNMT]

-OR-o RCS subcooling based on core exit T/Cs - LESS THAN 100F USING FIG-1.O, FIGURE MIN SUBCOOLING

d. Stop RCS depressurization

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 41 Verify Adequate Shutdown Margin

a. Direct RP to sample RCS for boron concentration
b. Verify boron concentration -

GREATER THAN REQUIREMENTS OF EIG-2.0. FIGURE SDM

b. Borate as necessary.

42 Check If Letdown Can Be Established:

a. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

b. Charging flow - LESS THAN 20 GPM 43 Establish Normal Letdown (Refer to ATT-9.0, ATTACHMENT LETDOWN)
a. Go to Step 46.
b. Go to Step 46.

IF RCP seal return has been established, THEN establish excess letdown (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

IF RCP seal return NOT established.

THEN consult TSC to determine if excess letdown should be placed in service.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 44 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
b. Adjust RMW flow control valve in AUTO to 40 gpm
c. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
d. Check VCT level:

o Level - GREATER THAN 20%

-OR-o Level - STABLE OR INCREASING

d. Manually increase VCT makeup flow as follows:
1) Ensure BA transfer pumps and RMW pumps running.

IF NOT, THEN reset MCC C and MCC D UV lockouts.

2) Place RMW flow control valve HCV-11l in MANUAL and increase RMW flow until VCT level greater than 20% OR stable or increasing.

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 45 Check Charging Pump Suction Aligned To VCT:

a. VOT level - GREATER THAN 20%
a. IF VCT level can NOT be maintained greater than 5%. THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 46.

WHEN VCT level greater than 40%.

THEN do Step 45.

b. Align charging pumps to VCT o LCV-112C - OPEN o LCV-112B - CLOSED
  • 46 Monitor RCS Inventory:
a. Check the following:

o RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-1.O, FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 10%

[30% adverse CNMT]

a. Perform the following:
1) Manually operate SI pumps to restore inventory and/or subcooling. DO NOT operate more than two SI pumps.
2) Go to Step 47.
b. Go to Step 48

EOP:

TITLE:

REV: 16 AP-RCS.4 SHUTDOWN LOCA PAGE 31 of 35 STEP ACTION/EXPECTED RESPONSE

_RESPONSE NOT OBTAINE 47 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE
b. Check RVLIS indication:

o Level'(no RCPs)

- GREATER THAN 77% [82% adverse CNMT]

a. IF PRZR level greater than 10%

[30% adverse CNMTI and stable or increasing. THEN go to Step 47c.

IF NOT, THEN start SI pumps as necessary to restore PRZR level to greater than 10% [30% adverse CNMT] and stable or increasing and go to Step 48.

b. Start SI pumps as necessary to restore RVLIS level (no RCPs) or fluid fraction (any RCP running) and go to Step 48.

-OR-o Fluid fraction (any RCP running) - GREATER THAN 84%

c. Core exit T/Cs - STABLE OR DECREASING
c. Start SI pumps as necessary to stabilize or decrease core exit T/Cs.

48 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses energized by offsite power:

.o Emergency D/G output breakers OPEN

a. Try to restore offsite power (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

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 16 AP-RCS. 4 SHUTDOWN LOCA PAGE 32 of 35 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 49 Check RCP Cooling:

a. Check CCW to RCPs Establish normal cooling to RCPs (Refer to ATT-15.2. ATTACHMENT SEAL COOLING).

o Annunciator A-7, RCP A CCW RETURN HIGH TEMPERATURE OR LOW FLOW - EXTINGUISHED o Annunciator A-15, RCP B CCW RETURN HIGH TEMPERATURE OR LOW FLOW - EXTINGUISHED

b. Check RCP seal injection o Labyrinth seal D/P - GREATER THAN 15 INCHES o RCP seal injection flow -

GREATER THAN 6 GPM

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • 50 Check If Seal Return Flow Should Be Established:
a. Verify instrument bus D -

ENERGIZED

b. Verify RCP #1 veal outlet temperature - LESS THAN 2351F
a. Restore power to instrument bus D from MCC B or MCC A (maintenance supply).
b. Go to Step 51.
c. Verify RCP SEAL DISCH VLVS - OPEN
  • AOV-270A
  • AOV-270B
d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
e. Open RCP seal return isolation valve MOV-313
e. Perform the following:
1) Place MOV-313 switch to open.
2) Dispatch AO to locally open 1MOV-313.
f. Verify RCP #1 seal leakoff flow

- LESS THAN 6.0 GPM

f. Perform the following:
1) Trip the affected RCP
2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve.
  • RCP A. AOV-270A
  • RCP B. AOV-270B IF both RCP SEAL DISCH VLVS closed, THEN go to Step 51
g. Verify RCP #1 seal leakoff flow

- GREATER THAN 0.8 GPM

g. Refer to AP-RCP.1, RCP SEAL MALFUNCTION.

STE ACTION/EXPECTED RESPONSE 1

RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in step 51.

51 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.

52 Check If Normal RHR Cooling Can Be Established:

a. Check the following:
a. Go to Step 53.

o RCS cold leg temperature -

LESS THAN 3500F o RCS pressure - LESS THAN 400 psig [300 psig adverse CNMT]

b. Place RCS overpressure protection in service (Refer to 0-7. ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
c. Consult plant staff to determine if RHR normal cooling should be established using ATT-14.1.

ATTACHMENT RHR COOL

EOP:

TITLE:

AP-RCS.4 SHUTDOWN LOCA 53 Check core exit T/Cs -

LESS Return to Step 22.

THAN 2000F 54 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions
b. Consult plant staff NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

55 Notify Higher Supervision

-END-

EOP:

TITLE:

a REV: 16 AP-RCS.4 SHUTDOWN LOCA PAGE 1 of 1 AP-RCS.4 APPENDIX LIST TITLE

1)

FIGURE MIN SUBCOOLING (EIG-1.0)

2)

FIGURE SDM (FIG-2.0)

3)

FIGURE RCP SEAL LEAKOFF (EIG-4.0)

4)

ATTACHMENT RHR COOL (ATT-14.1)

5)

ATTACHMENT RCP START (ATT-15.0)

6)

ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

7)

ATTACHMENT NC (ATT-13.0)

8) ATTACHMENT SEAL COOLING (ATT-15.2)
9) ATTACHMENT D/G STOP (ATT-8.1)
10) ATTACHMENT N2 PORVS (ATT-12.0)
11) ATTACHMENT CI/CVI (ATT-3.0)
12) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
13) ATTACHMENT EXCESS L/D (ATT-9.1)
14) ATTACHMENT LETDOWN (ATT-9.0)

j I

I EOP:

TITLE:r TTL

lREV:

32ll FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK R

PAGE 1 of 31 GINNA STATION CONTROLLED COPY NUMBER C2i R

kBLE MANAGER E

-F T

-IVzE DA EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

TITLE:

REV: 3 2 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 2 of 31 A. PURPOSE -

This procedure provides actions for responding to a loss of secondary.heat sink in both S/Gs.

  • B. ENTRY CONDITIONS/SYMPTOMS
1. ENTRY CONDITIONS -

This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when minimum AFW flow is'not verified AND narrow range level in both S/Gs is less than 7% [25% adverse CNMT]

I

b. F-0.3, HEAT SINK Critical Safety Function Status Tree on a RED condition.

EOP:

TITLE:

REV: 32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK

.PAGE 3 of 31 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl CAUTION o IF TOTAL FEED FLOW IS LESS THAN 200 GPM DUE TO OPERATOR ACTION. THIS PROCEDURE SHOULD NOT BE PERFORMED.

o FEED FLOW SHOULD NOT BE REESTABLISHED TO A FAULTED S/G IF A NON-FAULTED S/G IS AVAILABLE.

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 Check If Secondary Heat Sink Is Required:

a. RCS pressure - GREATER THAN-ANY
a. IF RWST level greater than 28%.

NON-FAULTED S/G PRESSURE THEN return to procedure and step in effect.

IF RWST level less than 28%,

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION, Step 1.

This Step continued on the next page.

7 S P ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I (Step 1 continued from previous page)

b. Check RCS cold leg temperature -

GREATER THAN 3500F

b. IF RCS pressure less than 400 psig [300 puig adverse CNMT], THEN try to place RHR System in service while continuing with this procedure:
1) Reset SI.
2) Place letdown pressure controller in MANUAL CLOSED.
3) Open the following valves (reset xy relays):
  • AOV-371. letdown isolation valve

. AOV-427. loop B cold leg to REGEN Hx

  • At least one letdown orifice valve (AOV-200A.

AOV-200B. or AOV-202)

4) IF pressure on PI-135 less than 400 psig. THEN establish RHR normal cooling (Refer to ATT-14.1. ATTACHMENT RHR COOL).
5) IF adequate cooling system established.

return to procedure in effect.

with RHR THEN and step

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 2 Monitor Secondary Heat Sink:

o Verify either S/G level - WIDE RANGE GREATER THAN 50 inches

[100 inches adverse CNMT]

o Verify PRZR pressure - LESS THAN 2335 PSIG IF a loss of heat sink is indicated, THEN perform the following:

a. Trip both RCPE.
b. Go to Step 13 to initiate bleed and feed cooling.

7 CAUTION 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).

11 w

3 Try to Establish AFW Flow To At Least One S/G:

a. Check S/G blowdown and samples valves - CLOSED
a. Place SIG blowdown and sample valve isolation switch to CLOSE.
b. Check MCB indications for cause of AFW failure:
1) Verify CST level - GREATER THAN 5 FEET
2) Verify busses supplying power to MDAFW pumps - ENERGIZED
1) Refer to ER-AFW.l. ALTERNATE WATER SUPPLY TO AFW PUMPS.
2) Continue attempts to restore power to MDAFW pumps.

. Bus 14

  • Bus 16
3) Determine AEW flow requirements per ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

4) Check AFW valve alignment o AFW pump discharge valves

- OPEN

4) Dispatch AO to locally align valves.
  • MOV-4007

. MOV-4008

  • MOV-3996 o TDAFW pump flow control valves - OPEN
  • AOV-4297
  • AOV-4298 This Step continued on the next page.

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I (Step 3 continued from previous page)

c. Check AFW pumps - ALL RUNNING
c. Perform the following:
1) Manually start MDAFW pumps.
2) Check. TDAFW pump steam supply valves OPEN.

. MOV-3504A

- MOV-3505A

3) If necessary dispatch AO to locally reset TDAFW pump governor valve.
4) IF NO AEW pumps operable, THEN go to Step 4..
d. Control AFW flow per requirements of ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

e. Check total flow to S/GS -

GREATER THAN 200 GPM

e. Continue attempts to restore AFW flow and go to Step 4.
f. Return to procedure and step in effect 4 Stop Both RCPs CAUTION IF OFFSITE POWER IS LOST AFTER SI TO RESTART SAFEGUARDS EQUIPMENT.

OFFSITE POWER)

RESET.

THEN MANUAL ACTION MAY BE REQUIRED (REFER TO ATT-8.5. ATTACHMENT LOSS OF 5 Reset SI If Actuated

EOP:

TITLE:

FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 8 of 31 P

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Try To Establish MFW Flow To At Least One S/G:

a. Check any MEW pump - AVAILABLE
b. Check condensate system:

o Condensate pump - ANY RUNNING o MEW pump suction pressure -

GREATER THAN 185 PSIG

c. Establish MEW flow:
1) Check MEW pump discharge valves -

CLOSED

2) Verify MEW regulating or bypass valves - OPERABLE
3) Depress MANUAL pushbuttons for A and B MEW regulating valve and bypass valve controllers AND adjust to 0%

demand.

4) Dispatch AO to restore MEW pump SW cooling
5) Verify S/G blowdown key switches in NORMAL
6) Ensure Annunciator H-4,MAIN EEED PUMP OIL SYSTEM -

EXTINGUISHED

7) Close Condensate Bypass valve, AOV-3959.
8) Ensure Annunciator H-ll, FEED PUMP SEAL WATER LO DIFF PRESS 15 PSI - EXTINGUISHED
9) Ensure one MFW pump recirc valve -

OPEN This Step continued on the next page.

a. Go to Step 7.-

b.- IF offsite power available, THEN try to place condensate system in service.

IF NOT. THEN go to Step 7.

c. IF MEW flow can NOT be established, THEN go to Step 7.

.1 EOP:

TITLE:

REV: 3 2 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 9 of 31 ACTION/EXPECTED RE RESPONSE NOT OBTAINED (Step 6 continued from previous page)

10) Start selected MEW pump
11) Open MFW pump discharge valve
12) Adjust MEW regulating or bypass valves to control MFW flow per requirements of ATT-22.0. ATTACHMENT RESTORING FEED FLOW
d. Go to Step 11 7 Establish SAFW Flow:
a. Perform the following:
1) Align SAFW system for operation (Refer to ATT-5.1.

ATTACHMENT SAFW)

2) Determine SAFW flow requirements per ATT-22.0.

ATTACHMENT RESTORING FEED FLOW

3) Start both SAFW pumps
4) Control SAFW flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW
5) Verify SAFW total flow -

GREATER THAN 200 GPM

b. Go to Step 11
  • a. IF greater than 200 gpm total SAFW flow can NOT be established. THEN go to Step 8.

CAUTION IF WIDE RANGE LEVEL IN BOTH S/GS DECREASES TO LESS THAN 50 INCHES [100 INCHES ADVERSE CNMT] OR IF PRZR PRESSURE INCREASES TO GREATER THAN 2335 PSIG DUE TO LOSS OF HEAT SINK. THEN STEPS 13 THROUGH 15 SHOULD BE IMMEDIATELY INITIATED FOR BLEED AND FEED.

8 Establish Conditions to Feed SIG(s)- From Condensate System:

a. Check condensate pumps - ANY RUNNING
a. IF offsite power available. THEN manually start at least one condensate pump.

IF a condensate pump can NOT be started. THEN go to Step 12.

b. Establish condensate flowpath (Refer to ATT-5.0. ATTACHMENT COND TO SIG)
c. De-energize PRZR heaters 9 Establish Condenser Steam Dump Pressure Control:
a. Verify condenser available:

o Any MSIV - OPEN

  • a. Place SIG ARV controllers in AUTO at desired pressure and go to Step 10.

o Annunciator G-15. STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to highest S/G pressure
c. Verify condenser steam dump controller HC-484 in AUTO
d. Place steam dump mode selector switch to MANUAL

CAUTION FOLLOWING BLOCK OF AUTOMATIC SI ACTUATION, MANUAL SI ACTUATION MAY BE REQUIRED IF CONDITIONS DEGRADE.

NOTE:

If auxiliary spray is in use. spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

10 Establish Condensate Flow to S/G:

a. Check RCS pressure - GREATER THAN 1950 PSIG
b. Depressurize RCS to less than 1950 psig:
a. Go to Step lOc.
1) Check letdown -

IN SERVICE

1) Use one PRZR PORV.

IF IA to CNMT. AOV-5392, NOT open.

THEN refer to ATT-12.0.

ATTACHMENT N2 PORVS.

a) IF PORV NOT available, THEN use auxiliary spray valve..AOV-296 and go to step. lOc.

2) Depressurize using auxiliary spray valve (AOV-296)
2) Use one PRZR PORV.

IF IA to CNMT. AOV-5392, NOT open.

THEN refer to ATT-12.0.

ATTACHMENT N2 PORVS.

c. WHEN PRZR pressure less than 1950 psig, THEN place SI block switches to BLOCK
  • Train A
  • Train B
d. Verify SAFETY INJECTION BLOCKED status light - LIT This Step continued on the next page.

EOP:

TITLE:

32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 12 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 10 continued from previous page)

e. Stop depressurizing RCS and maintain RCS pressure less than 1950 psig
f. Depress MANUAL pushbuttons AND manually adjust MEW regulating or bypass valves to control feed flow per requirements of ATT-22.0. ATTACHMENT RESTORING FEED FLOW
g. Dump steam to condenser at maximum rate to depressurize at least one SIG to less than 380 psig
h. Verify condensate flow to S/Gs
g. Manually or locally dump steam using intact S/G ARV at maximum rate to depressurize at least one SIG to less than 380 psig.
h. Go to Step 12.

11 Check S/G Levels:

a. Narrow range level in at least one S/G - GREATER THAN 7% [25%

adverse CNMT]

a. IF feed flow verified and level increasing in at least one S/G.

THEN maintain flow to restore narrow range level greater than 7% [25% adverse CNMT].

IF NOT verified, THEN go to Step 12.

b. Return to procedure and step in effect

12 Verify Secondary Heat Sink:

a. Check the following:

o Either S/G level - WIDE RANGE GREATER THAN 50 inches

[100 inches adverse CNMT]

o PRZR pressure - LESS THAN 2335 PSIG

a. IF loss of heat sink is indicated. THEN perform the following:
1) Go to Step 13 to initiate bleed and feed cooling.
b. Return to Step 1 CAUTION STEPS 13 THROUGH 15 MUST BE PERFORMED QUICKLY IN ORDER TO ESTABLISH RCS HEAT REMOVAL BY RCS BLEED AND FEED.

13 Actuate SI and CI 14 Verify RCS Feed Path:

a. Check SI pumps - AT LEAST ONE RUNNING
b. Check valve alignment for operating SI pumps - PROPER EMERGENCY ALIGNMENT Manually start pumps and align valves as necessary to establish RCS feed path.
  • IF a feed path can NOT be established, THEN continue attempts to establish feed flow. Return to Step 3.

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REV: 32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 14 of 31 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED l 15 Establish RCS Bleed Path:

a. Open both PRZR PORV block valves
a. Ensure power to MCCs supplying block valves.
  • MCC D for MOV-515
  • MCC C for MOV-516 IF any block valve can NOT be opened. THEN dispatch AO to locally check breaker:
  • MOV-515, MCC D position 6C

. MOV-516. MCC C position 6C

b. Place both PRZR PORV switches to OPEN
c. Align RCS overpressure protection system to open both PRZR PORVs (Refer to ATT-12.0, ATTACHMENT N2 PORVS)
d. Verify PORVs - BOTH OPEN
d. IF BOTH PRZR PORVs can NOT be opened. THEN ensure both PORV switches in OPEN.

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TIRE:

REV: 32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK' PAGE 15 of 31 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED CAUTION-IF OFESITE POWER IS LOST AFTER SI RESET, TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 16 Check If SI Can Be Reset:

a. Check SI blocked status light -

EXTINGUISHED

b. Check the following:

o PRZR pressure - LESS THAN 1750 PSIG

-OR-o Either steamline pressure -

LESS THAN 514 PSIG

a. Place SI block switches to UNBLOCK
b. IF PRZR pressure stable or increasing. THEN reset SI and go to Step 17.

IF PRZR pressure decreasing, THEN perform the following:

1) WHEN PRZR pressure less than 1750 psig, THEN reset SI.
2) Go to Step 17.
c. Reset SI 17 Reset CI:
a. Depress CI reset pushbutton
b. Verify annunciator A-26.

CONTAINMENT ISOLATION -

EXTINGUISHED

b. Perform the following:
1) Reset SI.
2) Depress CI reset pushbutton

18CVerifEXPEqTEDRESPONSE eO 18 Verify Adequate SW Flow:

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

IF less than two SW pumps can be operated. THEN perform the following:

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

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

b) Refer to ATT-2.4.

ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running.

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

3) Go to Step 19.
b. Verify AUX BLDG SW isolation valves - AT LEAST ONE SET OPEN
b. Manually align valves.

. MOV-4615 and MOV-4734

. MOV-4616 and MOV-4735

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REV: 32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 1

o PAGE 17 of 31.

19 Establish IA to CNMT:

a. Verify non-safeguards busses energized from offsite power
a. Perform the following:
1) Close non-safeguards bus tie breakers:

Bus 13 normal feed - CLOSED 0

-OR-o Bus 15 normal feed - CLOSED

  • Bus 13 to Bus 14 tie a Bus 15 to Bus 16 tie
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 RECIRG FANS):

3) Start HP seal oil backup pump.
4) WHEN bus 15 restored, THEN reset control room lighting.
b. Check SW pumps - AT LEAST TWO PUMPS RUNNING
b. Perform the following:
1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR).
2) Go to Step 19d.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 19 continued from previous page)

c. Verify turbine building SW isolation valves - OPEN
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664
d. Verify adequate air.

compressor(s) -, RUNNING

e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

c. Perform the following:
1) Manually align valves.
2) Dispatch AO to locally reset compressors as necessary.
d. Manually start electric air 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. Perform the following:
1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
2) Continue with Step 21. -WHEN IA restored. THEN do Steps 19f, g and 20.
f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN
g. Continue restored Step 20.

with Step 21. WHEN IA to CNMT, THEN do

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE: PRZR PORVs may close temporarily-until adequate IA pressure is restored in CNMT.

20 Restore RCS Overpressure Protection System To Standby:

a. Verify instrument bus D -
a. Perform the following:

ENERGIZED

1) Ensure steam dump mode control in MANUAL.
2) Restore power to instrument bus D from MCC B or MCC A (maintenance supply).
b. Place PORV PCV-430 and PCV-431C N2 arming switches to BLOCK

. SOV-8619A

. SOV-8619B

c. Close PORV PCV-430 and PCV-431C N2 SURGE TK VLVs

. SOV-8616A

  • SOV-8616B

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Verify Adequate RCS Bleed Path:

o Core exit T/Cs - STABLE OR DECREASING o RVLIS Level (no RCPs) - GREATER THAN 77% [82% adverse CNMT]

Perform the following:

a. Open Rx head vent valves.
  • SOV-590
  • SOV-591

. SOV-592 a SOV-593

b. Align any available low pressure water source to intact S/Gs.

IF no low pressure water source can be aligned. THEN go to Step 22.

c. Depressurize at least one intact S/G to atmospheric pressure using S/G ARV.

CAUTION ACTIONS TAKEN TO PERFORMING STEPS INITIATE RCS BLEED AND FEED SHALL NOT BE REVERSED WHEN 1 THROUGH 12 OF E-O. REACTOR TRIP OR SAFETY INJECTION.

22 Complete Steps 1 through 12 Of E-0, REACTOR TRIP OR SAFETY INJECTION, While Continuing With This Procedure

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REV: 3 2 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 21 of 31 SP ACTION/EXPECTED RESPONSE lCRESPONSE NOT OBTAINEDU CAUTION THE RCS BLEED PATH MUST BE MAINTAINED EVEN THAN SI PUMP SHUTOFF HEAD.

IF RCS PRESSURE REMAINS GREATER 23 Maintain RCS Heat Removal:

o Maintain SI flow o Maintain both PRZR PORVs and block valves - OPEN 24 Check Normal Power Available To Charging Pumps:

o Bus 14 normal feed breaker -

CLOSED o Bus 16 normal feed breaker -

CLOSED Verify adequate emergency DIG capacity to run charging pumps (75 kw each).

IF NOT, THEN evaluate if CNMT-RECIRC fans can be stopped (Refer to ATT-4.0. ATTACHMENT CNMT RECIRC FANS).

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REV: 3 2 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 22 of 31 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 25 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 locally close seal injection needle valve(s) to affected RCP:

2) Ensure HCV-142 open, demand at 0%.
b. Align charging pump suction to
b. IF LCV-112B can NOT be opened, RWST:

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

o LCV-112C - CLOSED 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 to establish maximum charging flow

CAUTION o IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING STEPS 1 THROUGH 13 OF ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.

o IF CONTAINMENT PRESSURE INCREASES TO GREATER THAN 28 PSIG. CONTAINMENT SPRAY SHOULD BE VERIFIED.

o RHR PUMPS SHOULD NOT BE RUN LONGER THAN EXCHANGERS.

I 1 HOUR WITHOUT CCW TO THE RHR HEAT

  • 26 Monitor If CNMT Spray Should Be Stopped:
a. CNMT spray pumps

- RUNNING

b. Check the following:

o CNMT pressure - LESS THAN 4 PSIG

a. Go to Step 27.
b. Continue with Step 27. WHEN BOTH conditions satisfied. THEN do Steps 26c through 26f.

o Sodium hydroxide tank level -

LESS than 55%

c. Reset CNMT spray
d. Check NaOH flow (FI-930) - NO FLOW
d. Place NaOH tank outlet valve switches to CLOSE.

. AOV-836A

  • AOV-836B
e. Stop CNMT spray pumps and place in AUTO
f. Close CNMT spray pump discharge valves
  • MOV-860A

-* MOV-860B

  • MOV-860C
  • MOV-860D

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I REV: 3 2 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 24 of 31 XPETE REPOSE RESPONSE NOT OBTAINED I I

27 Continue Attempts To Establish Secondary Heat Sink In At Least One S/G:

a. Attempt to restore one or more of the following:
  • AEW flow
  • Main FW flow
  • Standby AEW flow

. Condensate flow

b. WHEN a feed source is available.

THEN control feed flow per requirements of ATT-22.0, ATTACHMENT RESTORING FEED FLOW 28 Check For Adequate Secondary Heat Sink:

a. Check narrow range level in at least one SIG - GREATER THAN 7%

[25% adverse CNMT]

a. Return to Step 27.
b. Adjust S/G ARV controllers to existing S/G pressure CAUTION IF THE RCS IS WATER SOLID. THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE.

RCS HEATUP SHOULD BE PREVENTED.

29 Monitor RCS Temperatures:

o Core exit T/Cs - DECREASING o RCS hot leg temperatures -

DECREASING Perform the following:

a. Control steam dump and feed flow to establish natural circulation and stabilize RCS temperature.
b. Return to Step 27.

ACTIN/EXECTE REPONS 1 1RESPNSENOT OBTAINED 30 Check CCW Pumps -

ANY RUNNING Perform the following:

a. IF any RCP #1 seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).
  • RCP A. MOV-749A and MOV-759A
  • RCP B. MOV-749B and MOV-759B
b. Manually start one CCW pump (122 kw).

CAUTION IF RCS IS SOLID. CLOSURE OF HEAD VENTS MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

31 Verify Reactor Head Vent Manually close valves.

Valves -

CLOSED

  • SOV-590
  • SOV-591

. SOV-592

. SOV-593

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RCS IS SOLID. THEN TERMINATION OF BLEED AND FEED MAY RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

32 Check If One Of Three SI Pumps Should Be Stopped:

a. Three SI pumps - RUNNING
b. RCS subcooling based on core exit T/Cs - GREATER THAN 350F

[900F adverse CNMT] USING' FIG-1.O. FIGURE MIN SUBCOOLING

a. Go to Step 33.
b. Check the following:

o RCS pressure greater than 1625 psig [1825 prig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 00F using FIG-1.O, FIGURE MIN SUBCOOLING IF NOT. TTHEN go to Step 35.

c'. Check PRZR level - GREATER THAN 20% [40% adverse CNMT]

c. Do NOT stop SI pump.

Go to Step 35.

d. Stop one SI pump

STP ACTION/EXPECTED RESPONSE H

RESPONSE NOT OBTAINED 33 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING
b. Determine required RCS subcooling from table:
a. Go to Step 34.

Charging Pump RCS Subcooling Criteria Availability NONE 120'F [2000F adverse CNMT]

ONE 115'F [190F adverse CNMT]

TWO 105'F [180F adverse CNMT]

THREE '

100-F [1750F adverse CNMT]

c. RCS subcooling based on core exit T/Cs - GREATER THAN VALUE FROM TABLE ABOVE USING FIG-1.O, FIGURE MIN SUBCOOLING
c. Check the following:

o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

o RCS subcooling based on core exit T/Cs greater than 0 0E using FIG-1.O. FIGURE MIN SUBCOOLING IF NOT, THEN go to Step 35.

d. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

d. Do NOT stop SI pump.

Go to Step 35.

e. Stop one SI pump

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 34 Check If Last SI Pump Should Be Stopped:

a. One SI pump -

RUNNING

b. Check the following:

o RCS subcooling based on core exit T/Cs greater than 0F using FIG-l.0. FIGURE MIN SUBCOOLING o RCS pressure greater than 1625 psig [1825 psig adverse CNMT]

a. Go to Step 37.

.b. Go to Step 35.

c. PRZR level - GREATER THAN 20%

[40% adverse CNMT]

c. Do NOT stop SI pump.

Step 35.

Go to

d. Stop running SI pump
e. Go to Step 37 NOTE:

After closing a PORV. it may be necessary to wait for RCS pressure to increase to permit stopping SI pumps in SI reduction steps.

35 Check PRZR Associated BLEED PATH PORVs And Block Valves OPEN

- ANY Go to appropriate plant procedure:

o IF RWST level greater than 28%.

THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT.

-OR-o IF RWST level less than 28%.

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.

ACTON/EPECTD REPONS l

lRESPNSENOT OBTAIiNED1-CAUTION IF RCS IS SOLID. CLOSURE OF PORVS WILL RESULT IN RAPID RCS PRESSURE INCREASE UNLESS RCS TEMPERATURE AND RCS INFLOW AND OUTFLOW ARE CAREFULLY CONTROLLED.

36 Isolate PRZR Bleed Paths:

a. PRZR PORVs -

BOTH OPEN

a. Perform the following:
1) Stop all but one charging pump.
2) Control charging flow as necessary to maintain RCS pressure and PRZR level.
3) Establish excess letdown as follows:

a) Place AOV-312 to NORMAL.

b) Ensure CCW pump running.

c) Manually open CCW from excess letdown Hx open (AOV-745).

d) Ensure excess letdown flow control valve. HCV-123 is closed, demand at 0.

e) Reset both trains of XY relays for MOV-313.

f)

Open MOV-313.

g) Open excess letdown isolation valve AOV-310.

h) Slowly open HCV-123.

This Step continued on the next page.

S P ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED (Step 36 continued from previous page)

b. Close one open PRZR PORV
b. Close PORV block valve.

IF block valve can NOT be closed.

THEN go to appropriate plant procedure:

o IF RWST level greater than 28%. THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

-OR-o IF RWST level lees than 28%,

THEN go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.

c. Return to Step 32 37 Check PRZR PORVs -

BOTH CLOSED Close both PRZR PORVs.

IF any.

PRZR PORV can NOT be closed. THEN manually close its block valve.

38 Check If RHR Pumps Should Be Stopped:

a. RUR pumps - ANY RUNNING IN INJECTION MODE
b. Check RCS pressure:
1) Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
2) Pressure - STABLE OR INCREASING
a. Go to Step 39.
b. Go to appropriate plant procedure:

o IF RWST level greater than 28%. THEN go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

-OR-o IF RWST THEN go TO COLD Step 1.

level less than 28%.

to ES-1.3. TRANSFER LEG RECIRCULATION,

c. Stop RHR pumps and place in AUTO

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED l 39 Start Charging Pumps As Necessary And Control Charging Flow To Maintain PRZR Level 40 Go To ES-1.1, SI TERMINATION, Step 8

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E REV: 32 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE 1 of 1 FR-H.1 APPENDIX LIST TITLE 1)'

2) 3)

4) 5)

6) 7)

8) 9)

10) 11)

FIGURE MIN ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT SUBCOOLING (FIG-1.0)

CNMT RECIRC FANS (ATT-4.0)

COND TO S/G.

(ATT-5.0)

N2 PORVS (ATT-12.0)

RHR COOL (ATT-14.1)

SAFW (ATT-5.1)

RESTORING FEED FLOW (ATT-22.0)

NO SW PUMPS (ATT-2.4)

LOSS OF OFFSITE POWER (AT-8.5)

DIESEL AIR COMPRESSOR (ATT-11.2)

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TITLE:

i l

~REV: 32l FR-H.1 RESPONSE TO LOSS OF'SECONDARY HEAT SINK PAGE 1 of 1 FOLDOUT PAGE NOTE:

This Foldout Page applies to all FR-H 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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