ML050890398

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Revisions to Emergency Operating Procedures
ML050890398
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/18/2005
From: Marlow T
Constellation Energy Group, Ginna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050890398 (39)


Text

1503 Lake Road Ontario, NewYork 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC March 18, 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, omas A. Marlow TAM/jdw xc:

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

AP Index AP-RCS.4, Rev 17

C C.

(

NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Fri 3/18/2005 8:03:34 am Page 1 of 2 INPUT PARAMETERS: TYPE:

PRAP STATUSVALUE(S):

EF, QU 5 YEARS ONLY:

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.13115 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.l AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR.2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 PROCEDURE TITLE LEAKAGE INTO THE COMPONENT COOUNG LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW-PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW"VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12AAND/OR 12B TRANSFORMER (BELOW350 F)

LOSS OF BUS 13115 LOSS OF SAFEGUARDS BUS 14116 LOSS OF SAFEGUARDS BUS 17/18 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD VWTHDRAWALJJNSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WMILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WITHOUT RX TRIP REQUIRED EFFECT LAST REV DATE REVIEW 017 06/30/2004 06/2612002 019 06130/2004 06/26/2002 016 06130/2004 06/2612002 020 06130/2004 06/2612002 014 06130/2004 06(03/2002 004 08/26/2003 02/2712004 012 09117/2004 04/16/2003 028 0112112005 06126/2002 011 06/1012004 06126/2002 013 0112112005 0612612002 001 0613012004 0912412003 009 0112112005 06126/2002 008 01(21/2005 0612612002 016 06130/2004 0612612002 018 06126/2002 04116/2003 015 06130/2004 06/26/2002 009 06130/2004 0411612003 011 06130/2004 2/12015112 006 02125/2003 02/25/2003 017 06/3012004 04124/2003 017 0613012004 04/1612003 012 06/30/2004 0411612003 011 0613012004 04(0112002 017 03/1812005 04/30/2003 019 04/30/2003 04/30/2003 014 06130/2004 04/30/2003 003 11I21I2002 06/26/2002 021 09/17/2004 04121(2003 007 0112112005 1//20/5013 013 06/30/2004 06/26/2002 NEXT REVIEW 06/2612007 06/2612007 06/26/2007 06/26/2007 06/03/2007 02/2712009 0411612008 06126(2007 06126/2007 06126/2007 09/2412008 0612612007 06126/2007 06126/2007 04116/2008 0612612007 04(1612008 01/22/2007 02/2512008 04/2412008 04(16/2008 04(16/2008 01/22(2007 04/30/2008 04/30/2008 04(30(2008 06/26(2007 04/21(2008 10131/2006 06/26/2007 ST E:

E:

E:

E:

EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF Cr

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(

c NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Fri 3118/2005 8:03:34 am Page 2 of 2 INPUTPARAMETERS: TYPE:

PRAP STATUSVALUE(S):

EF,QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 020 01/21/2005 06/26/2002 06/26/2007 EF AP-TURB.3 TURBINEVIBRATION 012 06130/2004 06/26/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 017 04/30/2003 04/30/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 007 06/30/2004 06/26/2002 06/26/2007 EF PRAP TOTAL 34 GRAND TOTAL 34

I GINNA STATION CONTROLLED COPY NUMBER 23 RESPONSIB3 MANAGER

,3-1 r-

/

o6 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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, R10A 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

ACTION/EXPECTED RESPONSEOT OBTAINE NOTE:

o Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

o 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 0 0F FIG-l.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

STEP ACTION/EXPECTED RESPONSE lRESPONSE 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 high, THEN dispatch AO to locally isolate seal injection to affected RCP.

. RCP A. V-300A

. RCP B. V-300B

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 (75 kw) and adjust charging flow to maintain PRZR level

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 4 Verify Charging Flow Adequate:

a. Check the following:

o RCS nubcooling 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]

o PRZR level - STABLE OR INCREASING

a. Go to Step 5.
b. Verify charging flow needed to maintain PRZR level stable -

LESS THAN 75 gpm (PPCS point FCHG)

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

STEP ACTION/EXPECTED RESPONSE RESPONSE 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 3500 F
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
c. SI pumps -

AT LEAST TWO PUMPS AVAILABLE

b. Manually open AO to locally the following (locked valve valves.

Dispatch restore power to if necessary key required):

  • MOV-878A, MCC C position 8C
  • MOV-878B, MCC D position 8C
  • MOV-878C, MCC C position 8F
  • MOV-878D, MCC D position 8F
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

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 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)

a. Manually open valves.
b. Open SI pump suction valves from RWST:
b. Ensure at least one SI pump suction valve from RWST open.

. MOV-825A

  • MOV-825B
  • MOV-825A
  • MOV-825B
c. Start ONE SI pump 7 Initiate Actions To Protect Personnel In CNMT:
a. Evacuate personnel from CNMT
b. Periodically monitor CNMT radiation

STP ACTION/EXPECTED RESPONSE llRESPONSE 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

  • 9 Monitor RCP Operation:
a. RCPs - ANY RUNNING
b. Check RCP #1 seal D/P - GREATER THAN 220 PSID
a. Go to Step 10.
b. Stop affected RCP(s) and go to Step 9d.
c. Check RCP #1 seal WITHIN THE NORMAL RANGE OF FIG-4.0, SEAL LEAKOFF leakoff -

OPERATING FIGURE RCP

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

ACTIN/EXECTE REPONS 1

[ESPOSE OT OBTAINED I 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. Stop any running RHR pump
b. Close RHR normal cooling valves:

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

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

o RHR discharge valves to loop B cold leg (MOV-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 2800F (PPCS point T0684A or T0684B)
f. Open RWST to RHR pump suction valve, MOV-856 (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)
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.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 12 Check If RHR Injection Flow I Required:

a. RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-l.O, 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 SI pumps to restore PRZR level to greater than 10% [30% adverse CNMT] and stable or increasing and go to Step 13c.

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

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

c. Core exit T/Cs - STABLE OR DECREASING
c. Perform the following:.
1) Increase dumping steam.
2) IF core exit T/Cs continue to increase, THEN start SI pump(s) to stabilize or decrease core exit T/Cs.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 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:

. RCS boron

. RCS activity

. CNMT hydrogen

. CNMT sump

d. Evaluate and operate equipment as necessary:

. CCW pumps

. SW pumps

. Charging pumps

. 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:

RESPONSE NOT OBTAINED

a. Check at least two SW pumps -

RUNNING

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

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

SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 19 Establish IA To CNMT:

a. Verify non-safeguards busses energized from offoite 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 D/G capacity to compressors (75 emergency run air 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.

(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.

ACTON/XPETEDRESONS l

ESPNSENOT OBTAINED I 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.

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 setpoint, THEN do Step 21e.

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

Continue with Step 22.

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

e. Manually close PORVc.

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

ACTON/XPETED ESPNSEl l

ESPNSENOT OBTAINEDlI 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 psig [465 psig adverse CNMT]
2) Pressure - STABLE OR INCREASING
c. Stop RHR pumps and place AUTO

EOP:

TITLE:

REV: 17 AP-RCS.4 SHUTDOWN LOCA PAGE 18 of 35 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 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 SIG.

b. IF narrow range level in any SIG 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 350 0F o RCS pressure - LESS THAN 400 psig [300 poig adverse CNMT]

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

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check core exit T/Cs -

GREATER THAN 2000F NOTE: Shutdown margin should be monitored FIG-2.0, FIGURE SDM).

Go to Step 27.

during RCS cooldown (Refer to 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 I

ACTIN/EPECED ESPOSE l ESPNSENOT OBTAINIEDI 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

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

a. Both RCPs - STOPPED
b. RCS subcooling based on core exit T/Cs - GREATER THAN 00F USING FIG-1.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 lB energized b) Refer to ATT-15.O.

ATTACHMENT RCP START

2) Start one RCP
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. 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).

ACTION/EXPECTED RESPONSET OBTAI 33 Check RCS Cold Leg Temperature -

GREATER THAN 2850 F 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 Pnump Status:

a. Three SI pumps - RUNNING
b. RCS subcooling Based on core exit T/Cs - GREATER THAN 351F

[900F adverse CNMTI using FIG-l.., FIGURE MIN SUBCOOLING

a. Go to Step 35.
b. 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 RUR normal cooling NOT in service AND RCS hot leg temperature less than 3200F

[310'F 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 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 IS

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl 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 1050F [1800F adverse CNMTI 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. IF RCS hot leg temperature greater than 3201F [3101F 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 CNMTI, AND RHR pump suction temperature less than 250 0F, 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

P ACTION/EXPECTED RESPONSE,l RESPONSE NOT OBTAINEDl 36 Check If Last SI Pump Should Be Stopped:

a. Any SI pump - RUNNING
a. Go to Step 38.
b. Determine required RCS subcooling from table Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump..

ONE 2550F [2950F adverse CNMT]

TWO 235E [2850F adverse CNMT]

THREE 2100 F [2700F adverse CNMT]

c. RCS subcooling based on core exit T/Cs - GREATER THAN REQUIRED SUBCOOLING USING FIG-1.O, FIGURE MIN SUBCOOLING
c. IF RCS hot leg temperature greater than 320 0F [310F 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

[3100E adverse CNMT], AND'RHR pump suction temperature less than 2501F, 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 CNMT]

d. DO NOT stop SI pump.

Return to Step 31.

e. Stop SI pump
f. Go to Step 38

SE ACION/EXPECTED RESPONSE rRESPONSE NOT OBTAINEDl 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 CNMTI

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.

ACTION/EXPECTED RESPONSENED 39 Check RCP Status:

a. RCPs - AT LEAST ONE RUNNING
a. Try to start one RCP
1) Eotablish conditions for starting an RCP a) Bus 11A or l1B 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

SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINEDl 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-l.O, FIGURE MIN SUBCOOLING

d. Stop RCS depressurization

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 41 Verify Adequate Shutdown Margin

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

GREATER THAN REQUIREMENTS OF FIG-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.

EOP:

TITLE:

REV: 17 AP-RCS.4 SHUTDOWN LOCA PAGE 29 of 35 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 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-l11 in MANUAL and increase RMW flow until VCT level greater than 20% OR stable or increasing.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 45 Check Charging Pump Aligned To VCT:

Suction

a. VCT 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 0 0F 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

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 CNMT] 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 offaite 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)

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 49 Check RCP Cooling:

Establish normal cooling to RCPs (Refer to ATT-15.2, ATTACHMENT SEAL

a. Check CCW to RCPs 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 llRESPONSE NOT OBTAINEDl 50 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D -

ENERGIZED

b. Verify RCP #1 seal outlet temperature - LESS THAN 2350F
a. Restore power to instrument D from MCC B or MCC A (maintenance supply).
b. Go to Step 51.

bus

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 MOV-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.

EOP:

TITLE:

REV:

17 AP-RCS.4 SHUTDOWN LOCA PAGE 34 of 35 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 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 poig [300 pcig 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

ACTIN/EXECTE REPONS l lRESPNSENOT OBTAIND 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-

AP-RCS.4 APPENDIX LIST 1) 2)

3) 4)

5) 6)

7) 8)

9) 10) 11) 12) 13) 14)

TITLE FIGURE MIN FIGURE SDM FIGURE RCP ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT SUBCOOLING (EIG-1.0)

(FIG-2.0)

SEAL LEAKOFF (FIG-4.0)

RHR COOL (ATT-14.1)

RCP START (ATT-15.0)

CNMT RECIRC FANS (ATT-4.0)

NC (ATT-13.0)

SEAL COOLING (ATT-15.2)

D/G STOP (ATT-8.1)

N2 PORVS (ATT-12.0)

CI/CVI (ATT-3.0)

DIESEL AIR COMPRESSOR (ATT-11.2)

EXCESS L/D (ATT-9.1)

LETDOWN (ATT-9.0)