ML041940476

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R. E. Ginna, Emergency Operating Procedures
ML041940476
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/30/2004
From: Widay J
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041940476 (334)
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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 June 30, 2004 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,

. Widay JAW/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-ELEC. I, Rev 17 AP-RCC. I, Rev 9 AP-RCS.4, Rev 15 AP-CCW.1, Rev 17 AP-ELEC.13/15. Rev I AP-RCC.2, Rev 11 AP-RHR.2, Rev 14 AP-CCW'.2, Rev 19 AP-ELEC.14/16, Rev 8 AP-RCP.1, Rev 17 AP-TURB. 1, Rev 13 AP-CCW.3, Rev 16 AP-ELEC.17/18, Rev 7 AP-RCS.I, Rev 17 AP-TURB.2, Rev 19 AP-CR. 1, Rev 20 AP-FW.1, Rev 16 AP-RCS.2, Rev 12 AP-TURB.3, Rev 12 AP-CVCS.1, Rev 14 AP-PRZR.1, Rev 15 AP-RCS.3, Rev 11 AP-TURB.5, Rev 7 AD"--

C, (7 C.

NPSP0200 Ginna Nuclear Power Plant Wed 6/3012004 9:14:21 am E66429 PROCEDURE INDE> Page 1 of 2

- w -- 7 - ;~ -""-Il i m --Ir-,t_ r tn t INPUT PARAMETERS: T YPE: PRAP STATUS VALUE(S): EF, OU 5 YEARS ONLY:

PRAP ABN1 iORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT _ _

NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW.1 LEAKAGE INTO THE COMPONENT COOUNG LOOP 017 06/30/2004 06126/2002 06/26/2007 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 019 0603012004 0612612002 06/26/2007 EF AP-CCW.3 LOSS OF CCW- PLANT SHUTDOWN 016 06130/2004 06126/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 020 0613012004 0612612002 06/2612007 EF AP-CVCS.1 CVCS LEAK 014 0613012004 0610312002 06/03/2007 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 004 0812612003 0212712004 0212712009 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 011 06/26/2002 04116/2003 04/1612008 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 027 06130/2004 06/26/2002 06/26/2007 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 011 06/10/2004 06/20/2002 06/26/2007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 012 05/30/2003 06/26/2002 06/26/2007 EF AP-ELEC.13115 LOSS OF BUS 13/15 001 06130/2004 0912412003 09/24/2008 EF AP-ELEC.14116 LOSS OF SAFEGUARDS BUS 14116 008 06/30/2004 06126/2002 06/26)2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 007 06/30)2004 06/2612002 06126/2007 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 016 06130/2004 06/26/2002 06/26/2007 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 0626/2002 04116/2003 04116/2008 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 015 06/3012004 06/26/2002 0612612007 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWALANSERTION 009 06/30/2004 04116/2003 04/1612008 EF AP-RCC.2 RCCIRPI MALFUNCTION 011 06/3012004 2/120151/2 01/22/2007 EF AP-RCC.3 DROPPED ROD RECOVERY 006 02125/2003 0212512003 02/25/2008 EF AP-RCP.1 RCP SEAL MALFUNCTION 017 06130/2004 04/24/2003 04/2412008 EF AP-RCS.1 REACTOR COOLANT LEAK 017 06/30/2004 04/1612003 04116/2008 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 012 06/30/2004 0411612003 0411612008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 011 06/30/2004 04/01/2002 01/2212007 EF AP-RCS.4 SHUTDOWN LOCA 015 06130t2004 04/3012003 04/30)2008 EF AP-RHR.1 LOSS OF RHR 019 04130/2003 04130/2003 04/30/2008 EF AP-RHR.2 LOSS OF RHR MIHLE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 014 06/30/2004 04130/2003 04/3012008 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 003 11/2112002 06/26/2002 06/26/2007 EF AP-SW.1 SERVICE WATER LEAK 019 05130/2003 04/2112003 0412112008 EF AP-SW.2 LOSS OF SERVICE WATER 004 05/30/2003 10/31/2001 10/31/2006 EF

'0MrF RIP W1THOUT RX TRIP REQUIRED 013 06/30/2004 06/26/2002 06/2612007 EF

I I "-

(7 ( C NPSP0200 Ginna Nuclear Power Plant Wed 6/30/2004 9:14:21 am E66429 PROCEDURE INDE) Page 2 of 2 V 01 m - - I ... - R I p2 1 enn.., I'- .. - ._. - -, , - . .. ,____

INPUT PARAMETERS: TYPE: PRAP STATUSVALUE(S): EFQU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 019 0613012004 06/26/2002 06/26/2007 EF AP-TURB.3 TURBINE VIBRATION 012 06130/2004 06/26/2002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 017 04/3012003 04130/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 007 06/30/2004 06/26/2002 06126/2007 EF PRAP TOTAL 34 GRAND TOTAL: 34

EOP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 1 of 15 GINNA STATION CONTROLLED COPY NUMBER -

RESPONSIBLO MANAGER L 0o C EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EDP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 2 of 15 A. PURPOSE - This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from;
a. AP-CVCS.1, CVCS LEAK, or,
b. AP-RCS.1, RCS LEAK, or,
c. AP-RCP.1 RCP SEAL MALFUNCTION, when CCW surge tank level increasing, or
d. AR-RMS-17, R-17 COMPONENT COOLING, upon entry.
2. SYMPTOMS - The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;
a. Annunciator A-5, CCW SURGE TANK HI LEVEL 58.8%,

lit or

b. CCW radiation monitor (R-17) alarm, or
c. Annunciator A-7 (15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250F, lit or
d. Erratic RCP labyrinth seal D/P, or
e. Annunciator A-21, COMP COOLING HX OUT HI TEMP 1000F, alarm lit, or
f. Annunciator A-30, CCW PUMP INLET HEADER HI TEMP 1500F, alarm lit.

EOP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 3 of 15 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

, , * , . , . 4 , 4 , , , . , . , . , . * , 4 4 . 4 4 , . , , ,

  • 4 * . 4 4 .
  • 4 CAUTION IF CCW SYSTEM RADIATION MONITOR ALARMS. THEN VERIFY CCW SURGE TANK VENT.

RCV-017. CLOSES.

  • . Check . CW , I. n d * . . * . , 4 * . . . . . . . 4 . . . . . 4 . . . . . 4 1 Check CCW Indications
a. Check CCW surge tank level - a. IF level decreasing. THEN go to INCREASING AP-CCW.2. LOSS OF CCW DURING POWER OPERATION or AP-CCW.3.

LOSS OF CCW - PLANT SHUTDOWN.

IF level stable. THEN return to procedure or step in effect.

b. Direct RP tech to perform CH-PRI-CCW-LEAK. DETERMINATION OF CCW SYSTEM LEAKAGE
c. CCW radiation monitor. R-17. - c. Check RCS leakrate. IF RCS INCREASING leakrate increasing. THEN go to Step 2 (Refer to RCS Leakage Surveillance Sheet).

IF RCS leakage and R-17 indication normal. THEN go to Step 13.

ACTI~ON/XETE RESPONSE I

  • 4*, *
  • 4 4 4
  • 4 4
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  • 4 4
  • 4
  • 4 * .
  • S S
  • 4 * . 4 * *
  • 4 4
  • 4
  • CAUTION IF EITHER RCP #1 SEAL OUTLET TEMPERATURE EXCEEDS 2150F. THEN THE AFFECTED RCP(S) SHOULD BE STOPPED.

4

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  • 4 4
  • 4 * * * * * *
  • 4 S 4
  • 4 4 *
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  • 4 4
  • 4 NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flow is maintained.

2 Check RCP Thermal Barrier IF either pump has indication of a Indications: thermal barrier leak, THEN perform the following:

o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER AND a. Verify seal injection flow to APPROXIMATELY EQUAL affected RCP.

o RCP #1 seal leak off flows - b. Close CCW return from affected WITHIN THE NORMAL OPERATING RCP thermal barrier (labyrinth RANGE OF FIG-4.0. FIGURE RCP seal D/P should increase).

SEAL LEAKOFF

  • RCP B. AOV-754B CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250 F - EXTINGUISHED c. Evaluate CCW surge tank level trend. IF leakage into the CCW system has stopped. THEN go to Step 17.

3 Check RCS temperature - Go to Step 7.

GREATER THAN 3500F

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I 4 Check NRHX For Leakage:

a. Normal letdown - IN SERVICE a. Perform the following:
1) IF excess letdown in service, THEN perform the following:

a) Close excess letdown flow control valve, HCV-123.

b) Close excess letdown isolation valve. AOV-310.

2) Go to Step 5.
b. Check Letdown Indications: b. Isolate Normal Letdown:

o Letdown line flow - 1) Close letdown isolation.

APPROXIMATELY 40 GPM (60 GPM AOV-427.

IF AOV-202 OPEN)

2) Close letdown orifice valves o Low press LTDN pressure - (AOV-200A. AOV-200B, and APPROXIMATELY 250 PSIG AOV-202).

o Letdown pressure control 3) Close letdown isolation.

valve. PCV-135. demand - AOV-371.

APPROXIMATELY 35% OPEN (40%

OPEN IF AOV-202 OPEN) 4) Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

a RCP labyrinth seal D/P between 15 inches and 80 inches.

. PRZR level at program

5) Go to Step 5.
c. Go to Step 6

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 5 Check If CCW Inleakage Has Stopped:

a. CCW surge tank level - STABLE a. IF CCW surge tank level still increasing, THEN perform the following:
1) Restore letdown flowpath previously isolated (Refer to ATT-9.0, ATTACHMENT LETDOWN OR ATT-9.1. ATTACHMENT EXCESS L/D).
2) Adjust charging flow to restore PRZR level.
3) Go to Step 13.
b. Restore an intact letdown flowpath if available (Refer to ATT-9.O. ATTACHMENT LETDOWN OR ATT-9.1. ATTACHMENT EXCESS L/D)
c. Check any letdown flowpath - c. IF no letdown flowpath RESTORED available. THEN consult Plant Staff.
d. Adjust charging flow to restore PRZR level

EOP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 7 of 15 STP ACTION/EXPECTED RESPONSE REPNENTOTIE NOTE: WIth PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 6 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:

. Insert control rods

. RCS boration IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following:

  • Reduce turbine load
  • Dilution of RCS
b. Check PRZR pressure - TRENDING b. Control PRZR pressure by one of TO 2235 PSIG IN AUTO the following:

a 431K in MANUAL

  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. Check PRZR level - TRENDING TO c. Perform the following:

PROGRAM IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

d. Go to Step 17

SP ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINED-l

  • . . . . . . . . * . . . . . a . a . . . . . . . .a
  • a CAUTION UNFILTERED WATER MAY DAMAGE RCP SEAL SURFACES.

. . . . . . '. . . . . . . . . a . * . * . . a 7 Check NRHX For Leakage:

a. Narrow range PRZR level - ON a. IF the RCS is solid, THEN SCALE perform the following:

l) Stop any running RCP.

2) WHEN RCPs stopped. THEN stop any running charging pump.
b. Isolate letdown flow to NRHX:

o Ensure the following valves -

CLOSED

  • Letdown isolation. AOV-427
  • Letdown orifice valves (AOV-200A. AOV-200B. and AOV-202)

. RHR letdown flow control valve. HCV-133 o Close letdown isolation valve. AOV-371 o Place letdown pressure controller. PCV-135. in MANUAL and close valve (demand at 100%).

ACTION/OTEOBTAIED IEPNE

  • * * *
  • 4 4
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  • X 4
  • 4 * * * *
  • 4 *
  • 4 4 4 4
  • 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.
  • *
  • 4 4 * *
  • 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4
  • 4 4 4 4
  • 4 8 Check If CCW Inleakage Has Stopped:
a. CCW surge tank level - STABLE a. IF CCW inleakage continues, THEN go to Step 9.
b. Narrow range PRZR level - ON b. IF RCS is solid, THEN perform SCALE the following:
1) Ensure both RCPs off.
2) Cycle charging pumps to control RCS pressure.
c. Establish excess letdown (Refer to ATT-9.1. ATTACHMENT EXCESS L/D)
d. Start one charging pump
e. Adjust charging flow to restore PRZR level
f. Check RCS temperature - STABLE f. Adjust RHR cooling to stabilize RCS temperature.
g. Go to Step 17

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Restore Letdown:

a. Check RHR - IN SERVICE a. Perform the following:
1) Establish normal letdown (Refer to ATT-9.0, ATTACHMENT LETDOWN).
2) Go to Step 10.
b. Open letdown isolation valve.

AOV-371

c. Place letdown controllers in MANUAL at 40% open
  • TCV-130

. PCV-135

d. Manually open RHR LETDOWN TO CVCS, HCV-133
e. Place PCV-135 in AUTO at desired pressure
f. Place TCV-130 in AUTO at the normal setpoint
g. Start one charging pump
h. Adjust charging flow to restore PRZR pressure/level

EOP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 11 of 15 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED-

  • t * * * * * * * * ** ** . ** ** *
  • 4 * * *
  • 4 * * * .* *
  • 4 *. 4 CAUTION o ONE TRAIN OF RHR SHALL BE OPERABLE AT ALL TIMES.

o IF AN RHR PUMP OR HX IS REMOVED FROM SERVICE. THEN OPERABILITY REQUIREMENTS SHOULD BE EVALUATED (REFER TO ITS SECTIONS 3.4 AND 3.5).

  • * * * * * * * * * * *
  • 4
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  • 4 *
  • 4 * . . . * * . .* . .* . *
  • 4 4 4
  • 10 Check RHR System For Leakage:
a. Both RHR loops - ALIGNED AND a. IF any loop isolated for this OPERABLE leak investigation. THEN perform the following:
1) Restore isolated loop to service (Refer to ATT-14.2.

ATTACHMENT RHR ISOL and S-13A. RHR LINEUP FOR SAFETY INJECTION).

2) WHEN loop restored. THEN isolate other RHR loop (Refer to ATT-14.2. ATTACHMENT RHR ISOL).
3) Go to Step 11.
b. Isolate selected RHR loop (Refer to ATT-14.2. ATTACHMENT RHR ISOL)

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 11 Verify RCS temperature - Increase cooling from available RHR STABLE OR DECREASING loop. Attempt to establish S/G cooling if necessary.

12 Check If CCW Inleakage Has Stopped:

a. CCW surge tank level - STABLE a. IF any RHR loop has NOT been checked for leakage. THEN return to Step 10.

IF both RHR loops have been checked. THEN restore RHR loops to operable and go to Step 13.

b. Go to Step 17 13 Check RMW to CCW Surge Tank: IF RMW to CCW surge tank. MOV-823.

open OR RMW pump running. THEN o Verify CCW surge tank fill perform the following:

valve. MOV-823 - CLOSED

a. Close CCW surge tank fill valve.

o Verify RMW pump(s) - OFF MOV-823.

b. Shut off running RMW pumps.
c. IF CCW inleakage stops. THEN go to Step 17.

ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINEDl 14 Check For Sample Hx Leaks:

a. Direct AO to locally check a. Determine which sample Hx CCW nuclear sample room Hxs outlet temperature is high. THEN perform the following:

o Sample Hx (TI-602) common CCW return temperature from 1) Isolate the affected Hx.

sample Hxs - NORMAL (Refer to Aux Bldg log sheet. 3 of 3) 2) IF CCW inleakage has stopped.

THEN go to Step 17.

o Sample Hx (FI-603) common CCW return flow from sample Hxs -

NORMAL (Refer to Aux Bldg log sheet. 3 of 3)

b. Direct RP Tech to check PASS - b. Go to Step 15.

SAMPLING IN PROGRESS

c. Direct RP Tech to terminate PASS sampling
d. Verify CCW inleakage - STOPPED 15 Check SW Header Pressure - Dispatch AO to check CCW pump LESS THAN 60 PSIG discharge pressure. IF SW pressure greater than CCW pressure. THEN investigate possible SW leak into CCW system.

CAUTION IF A SAFEGUARDS PUMP IS TO BE REMOVED FROM SERVICE DURING AN EMERGENCY CONDITION. THEN CONSULT WITH PLANT STAFF PRIOR TO STOPPING PUMP.

. * *

  • a * * * * * * * * * * * * * * * *
  • a a * ** * * * * * * * *
  • a
  • 16 Check Safeguards Pump Status IF any event in progress requiring

- ALL SAFEGUARDS PUMPS OFF safeguards pump operation, THEN consult Plant Staff for guidance on

  • SI pumps checking safeguards pumps for CCW
  • RHR pumps leakage.

17 Evaluate Plant Conditions:

a. CCW inleakage - IDENTIFIED AND a. Return to Step 2.

ISOLATED

b. Determine if operation can b. IF plant shutdown is required.

continue (Consult Plant staff if THEN refer to 0-2.1. NORMAL necessary) - OPERATION CAN SHUTDOWN TO HOT SHUTDOWN.

CONTINUE 18 Check CCW Surge Tank Level - Consult RP tech to determine method APPROXIMATELY 50% to drain and dispose of excess CCW.

19 Establish Control Systems In Auto

a. Verify rods in AUTO a. Place rods in AUTO, if desired.
b. Verify 431K in AUTO b. Place 431K in AUTO, if desired.
c. Verify PRZR spray valves in AUTO c. Place PRZR spray valves in AUTO.

if desired.

d. Verify PRZR heaters restored: d. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

e. Verify one charging pump in AUTO e. Place one charging pump in AUTO.

if desired.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 20 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

21 Notify Higher Supervision 22 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 17 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 1 of 1 AP-CCW.1 APPENDIX LIST TITLE

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)
2) ATTACHMENT RHR ISOL (ATT-14.2)
3) ATTACHMENT LETDOWN (ATT-9.0)
4) ATTACHMENT EXCESS L/D (ATT-9.1)

EOP: TITLE-REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 10 GINNA STATION CONTROLLED COPY NUMBER X

  • E1L n RESPONSIBLE NAGER 6 gooL EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 2 of 10 A. PURPOSE - This procedure provides the steps necessary to respond to a loss of CCW while the plant is at power.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING SYSTEM, when CCW surge tank level decrease indicated at power.
2. SYMPTOMS - The symptoms of LOSS OF CCW DURING POWER OPERATION are;
a. Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LOW FLOW 15 GPM, lit or
b. Annunciator A-7 (A-15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250F, lit or
c. Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit or
d. Annunciator A-12, NON-REGEN HX LETDOWN OUT HI TEMP 1450F lit or,
e. Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%,

lit, or

f. Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit or
g. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
h. Annunciator A-18, VCT HI TEMP 1450, lit or
i. Annunciator A-21, COMP COOLING HX OUT HI TEMP 1000F, lit or,
j. Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
k. Annunciator A-24 (A-32), RCP A (B) OIL LEVEL + 1.25, lit or,
1. Annunciator B-21, RCP TEMP RECORDER, lit.

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 3 of 10 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED

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  • CAUTION o IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

o IF CCW IS LOST, THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)

UNTIL RCS TEMPERATURE IS LESS THAN 1500 F. OR UNTIL CCW IS RESTORED.

a , * * * * * * * * * .*

  • a * * * * * * * * * * * * * * * * * * * * * * * *
  • 1 Check CCW Pump Status: Perform the following:

o Both CCW pump breaker white a. Ensure standby CCW pump running.

lights - EXTINGUISHED IF no CCW pump can be operated.

o Annunciator A-17. MOTOR OFF RCP THEN perform the following:

CCWP - EXTINGUISHED

1) Trip the reactor.
2) WHEN all E-0 Immediate Actions done. THEN trip BOTH RCPs.
3) Close letdown isol. AOV-427.
4) Close excess letdown. HCV-123.
5) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.
b. IF annunciator A-22. CCW PUMP DISCHARGE LO PRESS 60 PSI, lit.

THEN check closed CCW to RHR HXs (MOV-738A and MOV-738B).

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 10 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl NOTE: MCB CCW surge tank level indication should be verified locally in the AUX BLDG. if possible.

  • 2 Monitor.CCW Surge Tank Level Perform the following:

- APPROXIMATELY 50% AND STABLE

a. Open RMW to CCW surge tank.

MOV-823.

b. Start RMW pump(s).
c. IF surge tank level stable or increasing, THEN control level at approximately 50% while continuing with Step 3.

IF CCW surge tank level can NOT be maintained greater than 10%.

THEN perform the following:

1) Close letdown isol. AOV-427.
2) Close excess letdown. HCV-123.
3) Trip the reactor.
4) WHEN all E-0 Immediate Actions done. THEN trip BOTH RCPs.
5) Place both CCW pumps in pull stop.
6) Go to E-0, REACTOR TRIP OR SAFETY INJECTION.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 3 Check CCW To Both RCPs: IF CCW lost to RCP(s). THEN perform the following:

o Annunciator A-7 (A-15). RCP 1A (IB).CCW return Hi temp or low a. Trip the reactor.

flow 165 gpm 1251F alarm -

EXTINGUISHED b. WHEN all E-0 Immediate Actions done. THEN trip affected RCP(s).

o RCP motor bearings temperature (PPCS Group Display-RCPS OR RCP c. Go to E-0. REACTOR TRIP OR temperature monitor RK-30A SAFETY INJECTION.

recorder) -

  • 2000F
  • 4 Monitor If Letdown Should Be Isolated:
a. Check annunciator A-12. a. Isolate Normal Letdown:

Non-Regen Hx Letdown Out Hi Temp 1450 - EXTINGUISHED 1) Close letdown isolation.

AOV-427.

2) Close letdown orifice valves (AOV-200A. AOV-200B. and AOV-202).
3) Close letdown isolation.

AOV-371.

4) Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:
  • RCP labyrinth seal D/P between 15 inches and 80 inches
  • PRZR level at program
b. Check excess letdown temperature b. Isolate Excess Letdown:

- LESS THAN 195 0F

1) Close excess letdown flow control valve. HCV-123.
2) Close excess letdown isolation valve. AOV-310.

EOP: TITLE: REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 6 of 10 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 5 Check CCW Valve Alignment -

NORMAL

a. Check.MCB CCW valves (Refer to a. Align CCW valves as necessary.

ATT-1.O. ATTACHMENT AT POWER CCW ALIGNMENT)

b. Direct AO to check local flow indications per ATT-l.1.

ATTACHMENT NORMAL CCW FLOW NOTE: o IF Seal Water Hx will be bypassed. THEN an increase in VCT temperature is expected.

o IF Seal Water Hx will be isolated. THEN seal return and excess letdown (if in service) will be to the PRT through RV-314.

6 Check Seal Water Hx For Tube IF a tube leak is indicated. THEN Leak: bypass and isolate Seal Water Hx and. if desired. isolate Seal o Locally check Seal Water Hx CCW Return.

outlet flow - NORMAL (FI-605.

refer to AO log) a. To bypass and isolate Hx perform the following:

o Locally check Seal Water Hx CCW outlet temperature - NORMAL 1) Open seal bypass V-394 (TI-604. refer to AO log)

2) Close seal inlet V-265 o VCT level - NO UNEXPLAINED INCREASE 3) Close seal outlet V-321
4) Close CCW inlet V-763
5) Close CCW outlet V-767
b. IF desired to isolate seal return line, THEN close MOV-313.
c. Notify RP to sample RCS for chromates.

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 10 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINEDl NOTE: Operation may continue with the reactor support coolers isolated. If this occurs, notify higher supervision.

7 Check For CCW Leakage In CNMT:

a. Check CNMT sump A level: a. IF abnormal increase in CNMT sump level. THEN perform the o Level - STABLE following:

o Sump A pumps - OFF 1) Direct RP Tech to sample sump A for chromates.

2) Prepare to make CNMT entry to check for CCW leak.
b. RCP oil levels - STABLE b. IF any RCP oil level increasing uncontrollably. THEN perform the following:
1) Trip the reactor.
2) WHEN all E-O Immediate Actions done. THEN trip affected RCP(s).
3) Close CCW supply and return for affected RCP(s).

. RCP A. MOV-749A and MOV-759A

  • RCP B. MOV-749B and MOV-759B
4) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

I EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION

.. PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check for CCW Leakage In AUX Dispatch AO to investigate AUX BLDG BLDG: for CCW leakage.

o Start frequency of AUX BLDG sump pump(s) - NORMAL (Refer to RCS daily leakage log) o Waste holdup tank level - STABLE OR INCREASING AS EXPECTED 9 Verify CCW System Leak -

IDENTIFIED

a. Leak identified a. Perform the following:
1) Direct RP Tech to sample CCW HX SW outlet for chromates.
2) Return to Step 2.
b. Isolate leak if possible
c. Refer to IP-ENV-3. RESPONSE TO A SPILL OF HAZARDOUS MATERIAL/WASTE 10 Check Normal Or Excess IF normal letdown desired. THEN Letdown - IN SERVICE establish normal letdown (refer to ATT-9.O. ATTACHMENT LETDOWN).

IF normal letdown NOT available.

THEN establish excess letdown if desired. (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D)

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 9 of '10 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED 11 Check CCW System Leak Isolated

a. Surge tank level - APPROXIMATELY a. IF level less than 50%. THEN 50% continue filling.

IF 2 50%. THEN perform the following:

1) Stop RMW pump(s).
2) Close MOV-823.
b. Surge tank level - STABLE b. Return to Step 2.

12 Direct RP To Sample CCW System For Chromates 13 Evaluate MCB Annunciator Status (Refer to AR Procedures) 14 Evaluate Plant Conditions:

a. CCW system malfunction - a. Return to Step 1.

IDENTIFIED AND CORRECTED

b. CCW system status adequate for b. IF shutdown required. THEN refer power operation (Refer to ITS to 0-2.1. NORMAL SHUTDOWN TO HOT Section 3.7.7). SHUTDOWN.

. EOP: TITLE:

I REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION

. PAGE 10 of 10 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

15 Notify Higher Supervision 16 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 19 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 1 AP-CCW.2 APPENDIX LIST TITLE

1) ATTACHMENT AT POWER CCW ALIGNMENT (ATT-1.0)
2) ATTACHMENT EXCESS L/D (ATT-9. 1)
3) ATTACHMENT NORMAL CCW FLOW. (ATT-1.1)
4) ATTACHMENT LETDOWN (ATT-9.0)

Eop: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 1 of 12 GINNA STATION CONTROLLED COPY NUMBER m RESPONSIBLE YANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EDP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 2 of 12 A. PURPOSE - This procedure provides the steps necessary to respond to a loss of CCW while the plant is shut down.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP, or
b. AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F), or
c. AP-RHR.1, LOSS OF RHR, or
d. AP-RHR.2, LOSS OF RHR WHILE OPERATING AT REDUCED RCS INVENTORY CONDITIONS, when CCW malfunction indicated.
2. SYMPTOMS - The symptoms of LOSS OF CCW - PLANT SHUTDOWN are:
a. Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LO FLOW 15 GPM, lit, or
b. Annunciator A-7, (A-15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250F, lit, or
c. Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit, or
d. Annunciator A-12, NON-REGEN HX LETDOWN OUT HI TEMP 1450F lit, or
e. Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%,

lit, or

f. Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit, or
g. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
h. Annunciator A-18, VCT Hi Temp 1450F, lit or
i. Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
j. Annunciator A-24, (A-32), RCP A (B) OIL LEVEL

+/- 1.25, lit, or

k. Annunciator A-31, CCW SYSTEM LO FLOW 1800 GPM, lit or
1. Annunciator B-21, RCP TEMP RECORDER, lit. I

EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 3 of 12

  • * * * * * * * * *
  • a ** a * *
  • a * ** * ** ** a a a * * *
  • a a a *
  • CAUTION o IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

o IF CCW IS LOST. THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP.(S)

UNTIL RCS TEMPERATURE IS LESS THAN 1500 F. OR UNTIL CCW IS RESTORED.

a * * * * * * *

  • a * *
  • a * * * * * * * * * * * * * *
  • a * * *
  • a
  • a
  • a a a NOTE: IF CCW is lost to operating CS. RHR. or SI pumps, they may be left running for brief periods while isolating a CCW leak.

1 Check CCW Pump Status: IF a CCW pump has tripped, THEN perform the following:

o Both CCW pump breaker white lights - EXTINGUISHED a. Ensure standby CCW pump running.

o Annunciator A-17. MOTOR OFF. RCP b. Attempt to reset and start the CCWP - EXTINGUISHED affected CCW pump if required for cooling.

c. IF no CCW pumps available, THEN trip BOTH RCPs.

NOTE: MCB surge tank level indication should be verified locally in the Aux Bldg. if possible.

2 Check CCW Surge Tank Level - IF CCW surge tank level is APPROXIMATELY 50% AND STABLE decreasing, THEN perform the following:

a. Open RMW to CCW surge tank.

MOV-823.

b. Start RMW pump(s).
c. Dispatch AO to AUX BLDG to investigate for CCW leak
d. Control CCW surge tank level at approximately 50% while continuing with Step 3.

EOP: TITLE: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 4 of 12 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 3 Check CCW Cooling To RCPs:

a. RCPs - BOTH RUNNING a. Perform the following:
1) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

2) IF no RCPs running, THEN verify natural circulation (refer to ATT-13.0, ATTACHMENT NC) AND go to Step 4.
b. Check RCP indications: b. IF CCW lost to RCP(s), THEN perform the following:

o Annunciator A-7 (A-15). RCP A (B) CCW RETURN HI TEMP OR LOW 1) Stop the affected RCP(s).

FLOW 165 GPM 125 0F -

EXTINGUISHED 2) IF no RCPs running. THEN verify natural circulation o Verify RCP motor bearing (Refer to ATT-13.0, temperatures (PPCS Group ATTACHMENT NC).

Display - RCPS or RK-30A recorder) - LESS THAN 2000F 3) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 5 of 12 ACTION/EXPECTED RESPONSE l[RESPONSE STP NOT OBTAINED

  • 4 Monitor If Letdown Should Be Isolated:
a. Check annunciator A-12. a. Isolate Normal Letdown:

Non-Regen Hx Letdown Out Hi Temp 1450 - EXTINGUISHED 1) Close letdown isolation, AOV-427.

2) Close letdown orifice valves (AOV-200A. AOV-200B. and AOV-202).
3) Close letdown isolation.

AOV-371.

4) IF PRZR solid, THEN perform the following:

a) Stop all charging pumps.

b) IF CCW lost to RCP thermal barrier Hx. THEN close seal injection V-300A and V-300B.

c) Start and stop charging pump to maintain RCS at desired pressure.

d) Go to Step 4b.

5) Close charging flow control valve. HCV-142, WHILE adjusting charging pump speed to control:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at desired level

6) Establish excess letdown, if desired (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D).

b. Check excess letdown temperature b. Isolate Excess Letdown:

- LESS THAN 1950 F.

1) Close excess letdown flow control valve. HCV-123.
2) Close excess letdown isolation valve. AOV-310.

COP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 6 of 12 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 5 Check CCW Pump Discharge Pressure

a. At least one CCW pump - RUNNING a. Go to Step 6.
b. Verify Annunciator A-22. CCW b. Dispatch AO to the AUX BLDG to PUMP DISCHARGE LO PRESS 60 PSIG perform the following:

- EXTINGUISHED

1) Throttle CCW to RHR Hxs as necessary to restore CCW pump discharge pressure.
  • MOV-738A
  • MOV-738B
2) Investigate for CCW leaks.

6 Check RCS Temperature - IF RHR cooling available. THEN STABLE OR DECREASING adjust RHR cooling to stabilize RCS temperature AND go to Step 7.

IF S/G cooling available. THEN control S/G ARVs to stabilize RCS temperature. IF S/G ARVs do NOT provide adequate cooling. THEN perform the following:

a. Stop all but one RCP.
b. Initiate S/G blowdown from both S/Gs. (Refer to T-14 series)
c. Maintain both S/G levels stable by controlling AFW flow.

j . i Eke; 1

EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 7 of 12 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED

  • 7 Monitor CCW Surge Tank Level Perform the following:

- GREATER THAN 10%

a. Stop any running RCP.
b. Close letdown isolation. AOV-427.
c. IF RHR pump(s) running in shutdown cooling mode, THEN stop both RHR pumps AND refer to AP-RHR.1. LOSS OF RHR or AP-RHR.2. LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.
d. Pull stop both CCW pumps.
e. Verify natural circulation (Refer to ATT-13.0. ATTACHMENT NC).

8 Check CCW System Leakage - Go to Step 13.

ANY LEAKAGE INDICATED

l EOP: TITLE:

I IREV: 16 I

l AP-CCW.3 IPAGE LOSS OF CCW - PLANT SHUTDOWN 8 of 12 ACTIN/EXECTE ORESOBNSE I NOTE: o IF Seal Water Hx will be bypassed. THEN an increase in VCT temperature is expected.

o IF Seal Water Hx will be isolated. THEN seal return will be to the PRT through RV-314.

9 Check Seal Water Hx For Tube IF a tube leak is indicated, THEN Leak: bypass and isolate Seal Water Hx and. if desired. isolate Seal

  • Locally check Seal Water Rx CCW Return as follows.

outlet flow - NORMAL (FI-605.

refer to AO log) a. To bypass and isolate Hx perform

  • Locally check Seal Water Hx CCW the following:

outlet temperature - NORMAL (TI-604. refer to AO log) 1) Open seal bypass V-394

  • VCT level - NO UNEXPLAINED INCREASE 2) Close seal inlet V-265
3) Close seal outlet V-321
4) Close CCW inlet V-763
5) Close CCW outlet V-767
b. If desired to isolate seal return line close MOV-313.
c. Notify RP to sample RCS for chromates.

. EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 9 of 12 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 10 Check For CCW Leakage In CNMT:

a. Check CNMT sump A level: a. IF abnormal increase in CNMT sump level. THEN perform the o Level - STABLE following:

o Sump A pumps - OFF 1) Direct RP Tech to sample sump A for chromates.

2) Prepare to make CNMT entry to check for CCW leak.
b. RCP oil levels - STABLE b. IF any RCP oil level increasing uncontrollably. THEN perform the following:
1) Stop affected RCP.
2) Close CCW supply and return for affected RCP(s).

. RCP A. MOV-749A and MOV-759A

  • RCP B. MOV-749B and MOV-759B
3) IF no RCPs running. THEN verify natural circulation (Refer to ATT-13.0.

ATTACHMENT NC).

4) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

[EOP: TITLE: REV: 16 LOSS OF CCW - PLANT SHUTDOWN

[ AP-CCW.3 PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Check for CCW Leakage In AUX Dispatch AO to investigate AUX BLDG BLDG: for CCW leakage.

o Start. frequency of AUX BLDG sump pump(s) - NORMAL (Refer to RCS daily leakage log) o Waste holdup tank level - STABLE OR INCREASING AS EXPECTED 12 Verify CCW System Leak -

IDENTIFIED

a. Leak identified a. Perform the following:
1) Direct RP Tech to sample CCW HX SW outlet for chromates.
2) Return to Step 2.
b. Isolate leak if possible
c. Refer to IP-ENV-3. RESPONSE TO A SPILL OF HAZARDOUS MATERIAL/WASTE 13 Check CCW Valve Alignment And Realign valves to restore CCW to Flow Rates - AS REQUIRED FOR individual components.

PLANT CONDITIONS (Refer to ATT-1.1, ATTACHMENT NORMAL CCW FLOW)

. EOP: TITLE:

I REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 11 of 12 STEvP ACTION/EXPECTED RESPONSER 14 Evaluate Plant Conditions:

a. RHR normal cooling - IN SERVICE a. Adjust S/G ARVs to stabilize RCS temperature and go to Step 15.
b. Check RCS Cooling: b. Perform the following:

o RCS temperature - STABLE OR 1) Increase SW from CCW Rx DECREASING

  • CCW Hx A. V-4619 o CCW system status - ADEQUATE . CCW Hx B. V-4620 FOR RHR NORMAL COOLING
2) Adjust CCW to RHR Hxs.

MOV-738A and MOV-738B to maintain RCS temperature stable or decreasing.

3) IF > 4900 gpm CCW flow required for desired RHR cooling (FI-619). THEN notify the Shift Supervisor.
4) IF CCW inadequate for RHR normal cooling. THEN go to AP-RHR.1. LOSS OF RHR OR AP-RHR.2. LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

15 Evaluate MCB Annunciator Status (Refer to AR Procedures)

EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 12 of 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

16 Notify Higher Supervision 17 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 16 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 1 of 1 AP-CCW.3 APPENDIX LIST TITLE

1) ATTACHMENT NC (ATT-13.0)
2) ATTACHMENT EXCESS L/D (ATT-9.1)
3) ATTACHMENT NORMAL CCW FLOW (ATT-1.1)

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 1 of 14 GINNA STATION CONTROLLED COPY NUMBER _ _

RESPONSIBq MANAGER EF-3F-CTI-VED EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 2 of 14 A. PURPOSE - This procedure provides the guidance necessary to place and maintain the plant in a Hot Shutdown Condition in the event that a control room evacuation is necessary.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. ER-SC.9, SECURITY EVENT PLAN, if SS determines to evacuate the Control Room.
b. ER-FIRE.0, CR RESPONSE TO FIRE ALARMS AND REPORTS, if the fire is in the Control Complex and affects Control Room Habitability or continued safe plant operation.
2. SYMPTOMS - The symptoms of CONTROL ROOM INACCESSIBILITY are:
a. Fire in the Control Complex, or
b. Smoke in the Control Complex, or
c. Noxious Fumes in the Control Room.

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 3 of 14 o Verify Reactor Trip: Manually trip reactor.

o At least one train of reactor IF reactor trip breakers NOT open.

trip breakers - OPEN THEN perform the following:

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

o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM b. Verify rod drive MG sets tripped.

c. Close Bus 13 and Bus 15 normal feed breakers.
d. Reset lighting breakers.

IF the Rx can NOT be tripped from the Control Room. THEN dispatch personnel to locally open the reactor trip breakers.

O Verify Turbine Stop Valves -

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

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

3 Evaluate Control Complex IF fire is NOT controllable, THEN Conditions: perform the following:

o Verify no fire in progress a. Place BOTH ARVs in AUTO. set at 1005 psig.

b. Manually close both MSIVs.
c. Trip both RCPs AND place in PULL-STOP.
d. Place both PRZR PORV switches to CLOSE.
  • PCV-430

. PCV-431C

e. Stop all charging pumps AND place in PULL-STOP.
f. Operating shift personnel proceed to Appendix R locker immediately outside the Control Room.
g. Go to ER-FIRE.1. ALTERNATIVE SHUTDOWN FOR CONTROL COMPLEX FIRE. DO NOT continue in this procedure.

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 5 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: PPCS terminals may be used for monitoring and trending plant parameters.

4 Establish Local Operating Stations (Refer to ATT-7.0, ATTACHMENT CR EVAC) 5 Locally Verify Emergency AC Consider restoration of emergency Busses 14 And 18 - ENERGIZED AC power using ER-FIRE.1. ALTERNATE (STA in A D/G room at ELCP) SHUTDOWN FOR CONTROL COMPLEX FIRE.

. EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 6 of 14 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED I 6 Locally Establish AFW Flow To S/Gs (HCO):

a. Transfer MDAFW pump control to LOCAL
b. Start MDAFW pumps - ANY PUMPS b. Locally perform the following:

RUNNING

1) Open TDAFW pump steam supply valves at the steam header.
  • MOV-3504A
  • MOV-3505A
2) Insert pins in valve operators for TDAFW flow control valves to allow operation of valves.
  • AOV-4297
  • AOV-4298
3) Throttle TDAFW flow to each S/G to maintain approximately 350 inches wide range level.
4) Go to Step 7.
c. Verify MDAFW pump flow - LESS c. Locally throttle MDAFW flow THAN 230 GPM PER RUNNING PUMP control valves to maintain flow less than 230 gpm per running pump.
  • MOV-4007
  • MOV-4008
d. Throttle MDAFP flow to each S/G to maintain approximately 350 inches wide range level.
  • MDAFP A. MOV-4007
  • MDAFP B. MOV-4008

EOP: TITLE:

REV: 2 0 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 7 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 7 Energize IPELIP (Switch At Bottom Of IBELIP)

fEDP:

TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY I. .PAGE 8 of 14

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

THEN go to Step 9.

IF RCS temperature decreasing.

THEN perform the following:

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

. TDAFW Pump to S/G A.

AOV-4297

AOV-4298

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

(locked valve key required) o S/G A

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

- Close IA to MSIV. V-5409B

  • Open vent valves. V-5472 AND V-5474
3) IF MDAFW pump available to feed SIGs. THEN manually isolate steam supply to TDAFW pump.
  • V-3504
  • V-3505
b. Go to Step 10.

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 9 of 14 ACTION/EXPECTED RESPONSE SP RESPONSE NOT OBTAINEDl 9 Monitor RCS Temperature (IBELIP)

a. RCS temperature - INCREASING a. To to Step 10.
b. Locally throttle S/G ARVs to stabilize RCS temperature.
c. IF ARVs NOT adequate. THEN perform the following:
1) Check open MSIVs or open MSIV bypass valves as necessary.

. S/G A. V-3615

  • S/G B. V-3614
2) Open priming ejector steam supply root valve. V-3578
3) Throttle open selected priming ejector steam supply to 200 psig (PI-2019)
  • Priming ejector A. V-3581
  • Priming ejector B, V-3580 10 Locally Establish Charging Flow Control (CO):
a. Transfer charging pump control to LOCAL
b. Verify at least one charging b. Locally start one charging pump.

pump - RUNNING

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

THEN locally start a second charging pump.

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

EOP: TITLE: REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 10 of 14 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED 11 Locally Monitor PRZR Pressure IF pressure increasing. THEN ensure

- PRESSURE STABLE (AFW pump RCS temperature and PRZR level area, west wall) stable.

IF pressure decreasing. THEN perform the following:

a. Transfer PRZR heater backup group to local control (MDAFW pump area).
b. Verify PRZR level greater than 13%.
c. Energize PRZR heater backup group.

12 Check SW Pumps - AT LEAST ONE Locally close SW Pump breakers to RUNNING IN EACH LOOP (CRF, establish one SW pump running in Locally in the Screenhouse) each loop.

o Loop A

. Bus 18 Position 29C. SW Pump A

  • Bus 17 Position 27C. SW Pump B o Loop B
  • Bus 18 Position 29D. SW Pump C
  • Bus 17 Position 27D. SW Pump D

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Transfer CNMT Recirc Fan Establish two fans running.

Control To LOCAL And Check -

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

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

o Levels - APPROXIMATELY 350 INCHES

  • MDAFW pump A. MOV-4007 o Levels - STABLE
  • TDAFW pump to S/G A. AOV-4297
  • TDAFW pump to SIG B. AOV-4298

EOP: TITLE:

REV: 2 0 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 12 of 14 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 15 Establish CSD Xenon Free Boron Concentration:

a. Determine amount of boron required (Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)
b. Locally open emergency borate b. Perform the following:

valve. MOV-350 (Primary AO)

1) Locally open manual charging pump suction from RWST. V-358 (charging pump room between A and B pumps).
2) Go to Step 15e.
c. Transfer boric acid pump control to LOCAL (Primary AO)
d. Start one boric acid pump (Primary AO)
e. Check if required amount of e. Continue with Step 16. WHEN boric acid added required amount of boric acid added. THEN do Step 15f.
f. Stop boration as follows:
1) Stop all boric acid pumps
2) Locally close emergency borate valve. MOV-350

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 13 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Evaluate Control Room Return to Step 5.

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

EOP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 14 of 14 NOTE: When the control room is manned by NRC licensed personnel, then equipment control may be transferred back to the control room in an orderly manner. Consult plant staff for additional guidance.

18 Establish Normal Control Room Operation:

a. Restore normal control room operation of equipment
  • PRZR heaters

. Charging pumps

. SW pumps

. CNMT recirc fans

. TDAFW pump steam supplies

. TDAFW pump flow control valves

. Letdown orifice valves

  • MOV-350
  • BAST pumps

. Other equipment that was locally operated

b. Verify 431K in AUTO b. Place 431K in AUTO. if desired.
c. Verify PRZR spray valves in AUTO c. Place PRZR spray valves in AUTO, if desired.
d. Ensure PRZR heaters restored:

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

e. Verify one charging pump in AUTO e. Place one charging pump in AUTO.

if desired.

f. Consult Plant Staff to determine f. IF cooldown NOT required. THEN if cooldown is necessary go to 0-3. HOT SHUTDOWN WITH XENON PRESENT.
g. At least one RCP - RUNNING g. Perform the following:
1) Ensure 2 control rod shroud fans running.
2) Go to ES-0.2. NATURAL CIRCULATION COOLDOWN. Step 1.
h. Go to 0-2.2. PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN

-END-

EDP: TITLE:

REV: 20 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 1 of 1 AP-CR.1 APPENDIX LIST TITLE

1) ATTACHMENT CR EVAC (ATT-7.0)

GINNA STATION CONTROLLED COPY NUMBER a_3 RESPONSIBLO MANAGER EFF-3ECT-IE DA EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the necessary instructions to mitigate the consequences of a CVCS leak.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from;
a. AP-RCS.1, REACTOR COOLANT LEAK, when conditions indicate a CVCS leak.
b. AR-RMS-4, R4 CHARGING PUMP ROOM, when VCT level response warrants.
2. SYMPTOMS - The symptoms of CVCS leak are;
a. Charging line pressure low, or
b. Letdown line low pressure and/or low flow, or
c. Charging Pump Room area monitor R-4 on alarm, or
d. Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 3950F, lit, or
e. Annunciator B-9 (B-10), RCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or
f. Annunciator F-14, CHARGING PUMP SPEED, lit.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

o A local radiation emergency should be declared for any unexplained area radiation monitor alarm.

  • 1 Monitor PRZR Level - STABLE IF PRZR level decreasing. THEN AT PROGRAM LEVEL start additional charging pumps and increase speed to increase PRZR level to program.

IF PRZR level continues to decrease. THEN close letdown isolation AOV-427 AND excess letdown AOV-310.

IF available charging pumps are running at maximum speed with letdown isolated. AND PRZR level is decreasing. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

ACTION/EXPECTED RESPNOT OBTAINED NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may require a load reduction.

2 Check VCT Makeup System:

a. Verify VCT level - GREATER THAN a. Perform the following:

5%

1) Ensure charging pump suction aligned to RWST
  • LCV-112B - OPEN
  • LCV-112C - CLOSED
2) Go to Step 3.
b. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
c. Check VCT level: c. Perform the following:

o Level GREATER THAN 20% 1) Ensure letdown divert valve.

LCV-112A. aligned to VCT.

-OR-

2) Manually increase VCT makeup o Level - STABLE OR INCREASING flow as follows:

a) Ensure BA transfer pumps and RMW pumps running.

b) Adjust RMW flow control valve. HCV-111, to increase RMW flow.

c) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

NOTE: A load reduction may be required if charging pump suction is aligned to the RWST.

3 Check Charging Pump Suction Aligned To VCT:

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 4. WHEN VCT level greater than 20%.

THEN do Step 3b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed 4 Check If RCS Leakage In CNMT: IF leakage is indicated in CNMT.

THEN perform the following:

o Check CNMT radiation monitors -

NORMAL a. Direct RP to sample CNMT for entry.

  • R-2
  • R-7 b. Continue with Step 5. WHEN CNMT
  • R-1OA cleared for entry. THEN dispatch
  • R-11 personnel to investigate CNMT
  • R-12 for RCS leakage.

o CNMT sump A pump run frequency -

NORMAL (Refer to leakage surveillance sheet)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • * * . * . * * * * * *
  • 4 * * * * * * * . * . * * * * * * * * * * * * * *
  • 4 .

CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.

  • * * * * * * * * * *
  • 4 * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • 5 Check If RCS Leakage In AUX Dispatch AO To AUX BLDG To BLDG: Investigate For CVCS Leak (locked area keys required)
a. Check AUX BLDG radiation monitors - NORMAL
  • R-4
  • R-9
  • R-1OB

. R-13

  • R-14
b. AUX BLDG sump pump run frequency

- NORMAL (Refer to leakage surveillance sheet)

c. AUX BLDG sump tank leak rate -

NORMAL (Refer to leakage surveillance sheet)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check For Leak In Charging Perform the following to isolate Line To REGEN Hx: normal letdown:

o Annunciator A-4. REGEN HX a. Close letdown isolation. AOV-427.

LETDOWN OUT HI TEMP 3950F -

EXTINGUISHED b. Close letdown orifice valves (AOV-200A. AOV-200B. and o Regen Hx Ltdn Outlet Temp - LESS AOV-202).

THAN 3500 F AND STABLE (TI-127)

c. Close letdown isolation. AOV-371.
d. Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program

e. Close charging to loop B cold leg. AOV-294.
f. Go to Step 9.

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

. * * * * * . * *

  • 4 * * * * * *, * * * * * * * * * . *
  • 4 * * * * * . 4 4
  • 4 CAUTION o IF LEAK EXISTS IN THE LETDOWN LINE. H2 GASES FROM THE VCT MAY DIFFUSE OUT THE LEAK AND CAUSE A HAZARDOUS CONDITION.

o WHILE ON EXCESS LETDOWN. VCT LEVEL MAY BE DECREASED BY MANUALLY DIVERTING EXCESS LETDOWN FLOW TO THE RCDT USING AOV-312.

  • i 4 * * * . . * * . * *. * * . * * *
  • 4 .
  • 4 . * * * * * *
  • 4 4, *
  • 4 4 7 Check Normal Letdown:
a. Normal letdown - IN SERVICE a. Perform the following:
1) IF excess letdown in service.

THEN perform the following:

a) Close excess letdown flow control valve. HCV-123.

b) Close excess letdown isolation valve, AOV-310.

2) Go to Step 8.
b. Check Letdown Indications: b. Isolate Normal Letdown:

o Letdown flow - APPROXIMATELY 1) Close letdown isolation.

40 GPM (60 GPM IF AOV-202 AOV-427 OPEN)

2) Close letdown orifice valves o Low pressure LTDN pressure - (AOV-200A. AOV-200B. and APPROXIMATELY 250 PSIG AOV-202) o Pressure control valve. 3) Close letdown isolation PCV-135. demand - AOV-371 APPROXIMATELY 35% OPEN (40%

OPEN IF AOV-202 OPEN) 4) Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

  • RCP labyrinth seal D/P less than 80 inches
  • PRZR level at program
5) Close charging to loop B cold leg, AOV-294.
6) Go to Step 12.

I--

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINEDl 8 Check For Leakage To CCW IF leakage to the CCW system is System: indicated. THEN go to AP-CCW.1.

LEAKAGE INTO THE COMPONENT COOLING o CCW radiation monitor (R-17) - LOOP.

NORMAL o CCW surge tank level -

APPROXIMATELY 50% AND STABLE

  • 4
  • 4 i 4
  • 4 4 4 *
  • 4 4 *
  • 4 4
  • 4 4 4
  • 4 *
  • 4
  • 4
  • 4 4 4 4 4
  • 4 4 4 4 CAUTION RCP OPERATION WITHOUT SEAL INJECTION SHOULD BE MINIMIZED.

4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4

  • 4 4 4 4 4 4 4
  • 4 4 4 4 4 4 9 Check RCP Seal Injection IF RCP seal injection leak is Indications: suspected. THEN perform the following:

o Seal injection flows - GREATER THAN 6 GPM AND STABLE a. Verify charging flow control valve. HCV-142, open. IF no o RCP labyrinth seal D/Ps - charging path through REGEN Hx GREATER THAN 15 INCHES AND available. THEN go to Step 11.

APPROXIMATELY EQUAL

b. Verify CCW cooling to operating o RCP seal inlet temperatures - RCP thermal barriers. IF NOT.

STABLE THEN seal injection should be maintained.

c. Attempt to locate and isolate leak.
d. Go to Step 12.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 10 Check RCP Seal Leakoff Flows: Dispatch AO with a key to the RWST gate to check seal return line for o RCP seal leakoff flows - WITHIN leakage.

THE NORMAL OPERATING RANGE OF FIG-4.O. FIGURE RCP SEAL LEAKOFF IF a seal return line leak is indicated downstream of RCP seal o RCP seal leakoff flows - STABLE return isolation valve. MOV-313.

THEN perform the following:

a. Close RCP seal return isolation valve, MOV-313.
b. Monitor RCP indications.
c. Evaluate leak location. IF possible, THEN isolate the seal return line from the VCT.
d. Go to Step 12.

11 Evaluate Local Leak Isolate leak if possible (Refer to Investigation - CVCS SYSTEM CVCS piping diagrams as necessary).

INTACT IN AUX BLDG 12 Evaluate Plant Status:

a. Leak location identified a. IF CVCS leak NOT indicated. THEN go to AP-RCS.1. REACTOR COOLANT LEAK.
b. Check RCS leakage within limits b. Initiate plant shutdown (Refer (Refer to leakage surveillance to 0-2.1. NORMAL SHUTDOWN TO HOT sheet and ITS section 3.4.13) SHUTDOWN):
c. At least one charging flowpath - c. Go to AP-CVCS.3. LOSS OF ALL AVAILABLE FOR INVENTORY CONTROL CHARGING FLOW.
  • AOV-294
  • AOV-392A
  • Seal Injection

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 13 Check Normal Or Excess IF normal letdown desired. THEN Letdown - IN SERVICE establish normal letdown. (Refer to ATT-9.0. ATTACHMENT LETDOWN)

IF normal letdown NOT available, THEN establish excess letdown if desired (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D).

NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 14 Establish Stable Plant Conditions:

a. PRZR level - TRENDING TO PROGRAM a. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program
b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:

. 431K in MANUAL

. Manual control of PRZR heaters and sprays IF pressure can NOT be controlled. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.-

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish Control Systems In Auto

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

16 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

17 Notify Higher Supervision

-END-

AP-CVCS.1 APPENDIX LIST TITLES

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)
2) ATTACHMENT EXCESS L/D (ATT-9.1)
3) ATTACHMENT LETDOWN (ATT-9.0) I J0

EOP: TITLE:

REV: 27 P-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE I of 33 GINNA STATION 43 CONTROLLED COPY NUMBER _ _

RESPONSIBL NAGER EFE3 T VEooAf EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 27 PP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 2 of 33 A. PURPOSE - This procedure provides actions to respond to a loss of 12A and/or 12B Busses from HSD or at power conditions.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of loss of #12A or 12B SS Transformer are:
a. Annunciator L-7, BUS 16 UNDER VOLTAGE SAFEGUARDS, I lit, or I
b. Annunciator L-14, BUS 14 UNDER VOLTAGE SAFEGUARDS, I lit, or I
c. Annunciator L-15, BUS 17 UNDER VOLTAGE SAFEGUARDS, I lit, or
d. Annunciator L-20, 12A XFMR OR 12A BUS TROUBLE, lit, or
e. Annunciator L-23, BUS 18 UNDER VOLTAGE SAFEGUARDS, I lit, or I
f. Annunciator L-27, 34 KV BREAKER TRIP, lit, or I
g. Annunciator L-28, 12B XFMR OR 12B BUS TROUBLE, lit, or
h. Annunciator 12A-4, LOSS OF 4160V ON 12A TRANSFORMER I SECONDARY, lit, or I
i. Annunciator 12A-8, 12A BUS UNDERVOLTAGE, lit, or I
j. Annunciator 12B-4, LOSS OF 4160V ON 12B TRANSFORMER I SECONDARY, lit, or l
k. Annunciator 12B-8, 12B BUS UNDERVOLTAGE, lit. I

TITLE:

EOP

.EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 3 of 33

  • a a *
  • a * * * .* a a . *
  • a *
  • a . a a *
  • a
  • a a a
  • a a a * *
  • a a .
  • CAUTION o IF ANY RADIOACTIVE RELEASE IN PROGRESS. THEN IT SHOULD BE TERMINATED UNTIL SUPPORT CONDITIONS ARE EVALUATED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS.

AND 1950 KW FOR CONTINUOUS SERVICE.

  • * . * * * *
  • a * *
  • a*. * * *
  • a
  • a a
  • a a
  • a a a * * * * * * * * * *
  • NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check RCS Temperature - Go to AP-ELEC.3. LOSS OF 12A AND/OR GREATER THAN 3500F 12B TRANSFORMER (BELOW 3500F).

  • 2 Monitor Tavg
a. Place Rods in MANUAL
b. Manually move control rods to control Tavg 3 Verify RCPs - BOTH RUNNING IF reactor trip breakers closed.

THEN manually trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

4 Verify Emergency D/G Manually start D/G(s) associated Associated With Deenergized with affected bus.

Bus(es) - RUNNING o Bus 12A - D/G A o Bus 12B - D/G B

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED 5 Verify Both Trains Of AC IF Bus 14 AND Bus 16 are Emergency Busses Energized To deenergized, THEN go to ECA-0.0.

At Least 420 VOLTS: LOSS OF ALL AC POWER. Step 1.

o Bus 14 and bus 18 IF one train deenergized. THEN perform the following:

o Bus 16 and bus 17

a. Ensure D/G aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check D/G running.

IF NOT, THEN perform the following:

1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G will NOT start. THEN dispatch AO to locally start D/G. (Refer to ER/D/G.1.

RESTORING D/Gs)

c. Adjust D/G voltage to approximately 480V
d. Adjust D/G frequency to approximately 60 Hz.

IF only ONE safeguards bus is deenergized., THEN refer to AP-ELEC.14/16. LOSS OF SAFEGUARDS BUS 14/16 or AP-ELEC.17/18. LOSS OF SAFEGUARDS BUS 17/18.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAI 6 Verify Service Water System

.Operation:

a. Check at least one SW pump a. Perform the following:

running in each loop

1) Manually start pumps as
  • A or B Pump in Loop A necessary (257 kw each).
  • C or D Pump in Loop B
2) IF adequate cooling can NOT be supplied to a running D/G.

THEN perform the following:

a) Pull stop affected D/G(s) b) Immediately depress voltage shutdown pushbutton

3) IF no SW pumps can be operated. THEN perform the following:

a) Trip the reactor b) WHEN all E-0 Immediate Actions done. THEN trip BOTH RCPs c) Close letdown isol. AOV-427 d) Close excess letdown, HCV-123 e) Go to E-0. REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated. THEN refer to AP-SW.2. LOSS OF SERVICE WATER.
b. SW header pressure - GREATER b. Refer to AP-SW.1. SERVICE WATER THAN 40 PSIG IN EACH LOOP LEAK.

EOP: TITLE: 1 REV: 27 K

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES lPAGE 6 of 33 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 7 Check CCW Pump Status:

a. At least one CCW pump - RUNNING a. Start one CCW pump (122 kw).

IF neither CCW pump can be started. THEN perform the following:

o IF reactor trip breakers closed, THEN:

1) Trip the reactor
2) WHEN all E-0 Immediate Actions done. THEN trip both RCPs
3) Close letdown isol. AOV-427
4) Close excess letdown.

HCV-123

5) Pull stop BOTH CCW pumps
6) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

o IF reactor trip breakers open. THEN:

1) Trip both RCPs
2) Close letdown isol. AOV-427
3) Close excess letdown.

HCV-123

4) Pull stop BOTH CCW pumps
5) Go to step 8
b. Annunciator A-22. CCW PUMP b. Start second CCW pump (122 kw).

DISCHARGE LO PRESS 60 PSIG -

EXTINGUISHED

TITLE:

LOP EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 7 of 33 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I 8 Verify charging pump status - Isolate letdown flowpaths:

AT LEAST ONE RUNNING

a. Close letdown isol. AOV-427
b. Close excess letdown. HCV-123
c. Close Loop A cold leg to excess letdown Hx. AOV-310 9 Verify Annunciator H-16, Dispatch AO to locally reset and INSTRUMENT AIR COMP - start adequate air compressors. IF EXTINGUISHED electric air compressor(s) can NOT be restored. THEN start diesel air compressor. (Refer to ATT-11.2.

ATTACHMENT DIESEL AIR COMPRESSOR).

IF IA can NOT be established. THEN refer to AP-IA.1. LOSS OF INSTRUMENT AIR.

10 Verify Bus 11A And l1B Normal Go to Step 22.

Feed Breakers - CLOSED 11 Check MFW Regulating Valves - Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO a. Place affected S/Gs MFW regulating valves in MANUAL

b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.l.

ABNORMAL MAIN FEEDWATER FLOW.

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 8 of 33 ACTION/EXPECTED RESPONSE1 STEP RESPONSE NOT OBTAINEDI NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may require a load reduction.

12 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level: b. Check letdown divert valve.

LCV-112A. aligned to VCT.

o Level GREATER THAN 20%

Manually increase VCT makeup

-OR- flow as follows:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve. HCV-lll, to increase RMW flow.
3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary:

M EOP: TITLE:

I I -REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES lI PAGE 9 of 33 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 13 Check Charging Pump Suction Aligned to VCT:

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 14. WHEN VCT level greater than 20%.

THEN do Step 13b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINEDl NOTE: When restarting equipment for recovery. it is preferable to start equipment on busses being supplied from offsite power.

14 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. Perform the following:

RUNNING

1) IF all seal cooling has been lost to any RCP. THEN close seal injection to affected RCP(s)
2) Start one charging pump (75 kw).
3) IF no charging pumps can be operated. THEN refer to AP-CVCS.3, LOSS OF ALL CHARGING FLOW.

This Step continued on the next page.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 14 continued from previous page)

b. Check letdown indications: b. Perform the following:

o Check PRZR level - GREATER 1) Close letdown isolation.

THAN 13% AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 gpm (60 gpm if AOV-202 (AOV-200A. AOV-200B. and OPEN) AOV-202) o Letdown flow - STABLE 3) Close letdown isolation.

AOV-371

4) IF seal injection in service.

THEN close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

  • RCP labyrinth seal D/P between 15 inches and 80 inches

. PRZR level at program

5) IF PRZR level greater than 13%. THEN go to Step 15. IF NOT. THEN continue with Step 17. WHEN PRZR level greater than 13%. THEN do Steps 15 and 16.
c. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
d. Go to Step 16

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 12 of 33 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish Normal Letdown: IF normal letdown can NOT be (Refer to ATT-9.0, ATTACHMENT established. THEN establish excess LETDOWN) letdown. (Refer to ATT-9.1, ATTACHMENT EXCESS L/D) 16 Verify PRZR Heaters Restored: IF adequate D/G capacity available for PRZR heaters (400 kw each o PRZR proportional heater breaker bank), THEN perform the following:

- CLOSED

a. Reset and close PRZR o PRZR backup heater breaker - proportional heater breaker if RESET/IN AUTO necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available. THEN refer to ER-PRZR.1.

RESTORATION OF PRZR HEATERS DURING BLACKOUT.

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES P PAGE 13 of 33 STEP ACTION/EXPECTED RESPONSE _ 1RESPONSE NOT OBTAINED 17 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD a. IF alarm is due to a loss of SEQUENCE OR ROD DEVIATION - power to MRPI. THEN maintain EXTINGUISHED rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment. THEN refer to AP-RCC.2. RCC/RPI MALFUNCTION.

while continuing with this procedure.

b. Annunciator E-28, POWER RANGE b. Perform the following:

ROD DROP ROD STOP - EXTINGUISHED

1) Place rods in MANUAL.
2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.
c. Annunciator F-15. RCS TAVG DEV c. Go to step 18.

4 0F - EXTINGUISHED

d. Place rods in AUTO if desired

STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3).

18 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:
  • Reduce turbine load

. Dilution of RCS

b. Check PRZR pressure - TRENDING b. Control PRZR pressure by one of TO 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. Check PRZR level - TRENDING TO c. Perform the following:

PROGRAM IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

IiEOP: TITLE:

IT REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 15 of 33 ACTION/EXPECTED RESPONSE P lRESPONSE NOT OBTAINEDl
  • * * * * . * * * * *
  • 4 * * * * * . , * *
  • 4 * * * * * * * *
  • 4 * * * * * *
  • CAUTION ANYTIME EMERGENCY D/GS ARE THE ONLY SOURCE OF AC POWER TO THE PLANT.

PERSONNEL SHOULD BE ASSIGNED TO MAINTAIN SURVEILLANCE OF THE D/GS.

  • * * * * * * * * * * * * * * * * * * * * * * * * *
  • 4 * * * *
  • 4 4 * * * * *
  • 19 Restore Normal Electric System Alignment:
a. Verify circuit 767 and/or 751 - a. Continue with Step 20. WHEN AVAILABLE offsite power available. THEN do Steps 19b. c and d.
b. Restore power to non-faulted Buses 12A and/or 12B (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER)
c. Verify all AC bus normal feed c. Restore all AC busses and MCCs breakers - CLOSED to normal power supply (Refer to ER-ELEC.1. RESTORATION OF

. Bus 13 OFFSITE POWER)

  • Bus 14
  • Bus 15
  • Bus 16
  • Bus 17
  • Bus 18
d. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 16 of 33 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED 20 Check CNMT Recirc Fans - AT Establish 2 CNMT recirc fans running LEAST 2 RUNNING

EOP: TITLE: 27 1REV AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 17 of 33 ACTION/EXPECTED RESPONSENED 21 Establish Control Systems In Auto:

a. Verify 431K in AUTO a. Place 431K in AUTO. if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO, if desired.
c. Verify PRZR heaters restored: c. Restore PRZR heaters. if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

d. Verify charging pumps d. Perform the following:

o 2 charging pumps running 1) IF all seal cooling has been lost. THEN ensure seal o One charging pump in AUTO injection isolated to affected RCPs

. RCP B. V-300B

2) Establish 2 charging pumps running (75 kw each).
3) Place one charging pump in AUTO, if desired.
e. Verify MFW regulating valves in e. Place MFW regulating valves in AUTO AUTO. if desired.
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Select load rate to 10%/hour
3) Match setter and reference
g. Verify annunciator G-15. STEAM g. WHEN Tavg within 5 0F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
h. Verify Rods in AUTO h. Place Rods in AUTO, if desired.
i. Go to Step 38

EOP: TITLE:

REV: 27 K

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 18 of 33 ACTION/EXPECTED RESPONSEREONEOTBAID NOTE: o Temperatures in the loop with the stopped RCP will not be indicative of true Tavg and AT values.

o Attempts to restore offsite power should continue (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER.)

22 Check Secondary Heat Sink Status:

a. Any main feed pump - RUNNING a. Perform the following:
1) Verify MDAFW pumps running as necessary.
2) Verify TDAFW pump running if necessary.
3) Adjust AFW pump flow to restore S/G level to 52%.
4) Go to Step 23.
b. Verify MFW regulating valves - b. Perform the following:

RESTORING S/G LEVEL TO 52%

1) Place affected S/G(s) MFW regulating valve in MANUAL.
2) Restore S/G level to 52%.

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1. ABNORMAL MAIN FEEDWATER FLOW.

EOP: TITLE: REV: 27 F.

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 19 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check TDAFW Pump Status:

a. TDAFW pump - RUNNING a. Go to Step 24.
b. Check S/G status b. Go to Step 24.

o At least one S/G level -

GREATER THAN 17%

-OR-o Both MDAFW pumps - OPERABLE

c. Pull stop TDAFW pump steam supply valves
  • MOV-3504A a MOV-3505A NOTE: Use of ARV associated with the running RCP is preferred.

24 Establish RCS Temperature Control:

a. Verify condenser available: a. Perform the following:

o Any MSIV - OPEN 1) Adjust S/G ARV controllers to stabilize RCS temperature.

o Annunciator G-15. STEAM DUMP ARMED - LIT 2) Go to Step 25.

b. Adjust condenser steam dump controller HC-484 to stabilize RCS temperature
c. Place steam dump mode selector switch to MANUAL

EOP: TITLE: REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 20 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Restore Non-Safeguards Busses As Follows:

a. Verify Bus 13 and 15 - ENERGIZED a. IF offsite power available, THEN attempt to restore offsite power and normal feed to Bus 13/15 (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

IF offsite power is NOT available. THEN perform the following:

o Close Bus 13 to Bus 14 tie breaker o Close Bus 15 to Bus 16 tie breaker

b. Verify MCC A - ENERGIZED b. Perform the following:
1) Ensure the following pumps in PULL STOP:
  • EH pump A

. Turning gear oil pump

  • HP seal oil backup pump
2) Close MCC A supply breaker from bus 13.
3) Start HP seal oil backup pump.
c. Verify MCC B - ENERGIZED c. Perform the following:
1) Ensure EH pump B in PULL STOP.
2) Close MCC B supply breaker from bus 15.
d. Verify annunciator J-8. 480V MCC d. Restore power to other MCCs as SUPPLY BREAKER TRIP - D/G loading permits.

EXTINGUISHED

e. Reset control room lighting
f. Reset MAIN XFMR AUX PWR SUPPLY breakers
  • Bus 13
  • Bus 15

TITLE:

EOP

.EOP: TITLE:RE:2 REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

. . .PAGE 21 of 33 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED I NOTE: When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power, if possible.

26 Verify Instrument Bus D - Energize MCC B. IF MCC B NOT ENERGIZED available. THEN refer to ER-INST.3, INSTRUMENT BUS POWER RESTORATION.

27 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level: b. Check letdown divert valve.

LCV-112A, aligned to VCT.

o Level GREATER THAN 20%

Manually increase VCT makeup

-OR- flow as follows:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve. HCV-111. to increase RMW flow.
3) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES l .. . .PAGE 22 of 33 ACTION/EXPECTED RESPONSE SP [RESPONSE NOT OBTAINEDl 28 Check Charging Pump Suction Aligned to VCT:

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 29. WHEN VCT level greater than 20%.

THEN do Step 28b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

EDP: TITLE:1 REV: 27 V

AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 23 of 33 ACTION/EXPECTED RESPONSEOT OBTAI 29 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. Perform the following:

RUNNING

1) Close letdown isolation.

AOV-427.

2) Start one charging pump (75 kw).
3) Establish greater than 20 gpm charging line flow.
b. Check letdown indications: b. Perform the following:

o Check PRZR level - GREATER 1) Close letdown isolation.

THAN 13% AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 GPM (60 GPM IF AOV-202 (AOV-200A. AOV-200B. and OPEN) AOV-202) o Letdown flow - STABLE 3) Close letdown isolation, AOV-371

4) IF seal injection in service.

THEN close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

  • RCP labyrinth seal D/P between 15 inches and 80 inches

. PRZR level at program

5) IF PRZR level greater than 13%. THEN go to Step 30. IF NOT. THEN continue with Step 32. WHEN PRZR level greater than 13%. THEN do Steps 30 and 31.
c. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
d. Go to Step 31

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

._.PAGE 24 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Establish Normal Letdown IF normal letdown can NOT be (Refer to ATT-9.0, ATTACHMENT established, THEN establish excess LETDOWN) letdown. (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D) 31 Verify PRZR Heaters Restored: IF adequate D/G capacity available for PRZR heaters (400 kw each o PRZR proportional heater breaker bank). THEN perform the following:

- CLOSED

a. Reset and close PRZR o PRZR backup heater breaker - proportional heater breaker if RESET/IN AUTO necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available. THEN refer to ER-PRZR.1.

RESTORATION OF PRZR HEATERS DURING BLACKOUT.

MPEO: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

. .PAGE 25 of 33 ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINEDl 32 Verify TDAFW Pump Aligned For Auto Start:

a. Any MDAFW pump - AVAILABLE a. Verify TDAFW pump operating to maintain required S/G level and go to Step 34.
b. Verify AMSAC TRIPPED status b. Reset AMSAC.

light - EXTINGUISHED

c. Verify both S/G levels - GREATER c. Continue with Step 34. WHEN SIG THAN 17% level greater than 17%. THEN do Steps 32d. e and 33.
d. Verify Bus 11A and Bus 11B - AT d. Perform the following:

LEAST ONE ENERGIZED

1) IF TDAFW pump NOT required to maintain S/G level. THEN pull stop TDAFW pump steam supply valves:

. MOV-3504A

  • MOV-3505A
2) Go to Step 33.
e. Verify the following:
1) TDAFW pump - OFF 1) IF TDAFW pump NOT required to maintain S/G level. THEN stop pump if desired.
2) TDAFW pump steam supply valve 2) Place TDAFW pump steam supply switches in AUTO valve switches in AUTO.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl 33 Establish Normal AFW Pump Shutdown Alignment:

a. Verify the following: a. Continue with Step 34. WHEN conditions met, THEN do o Both S/G levels - GREATER Steps 33b through f.

THAN 17% AND STABLE OR INCREASING o Total AFW flow - LESS THAN 200 GPM

b. Close MDAFW pump discharge valves
  • MOV-4007
  • MOV-4008
c. Place AFW bypass switches to DEF
d. Stop all but one MDAFW pump
e. Open AFW discharge crossover valves

. MOV-4000A

  • MOV-4000B
f. Adjust AFW bypass valves to control S/G levels at 52%
  • AOV-4480
  • AOV-4481

l EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 27 of 33 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 34 Establish Stable Plant Conditions:

a. Check PRZR pressure - TRENDING a. Control PRZR pressure at the TO 2235 PSIG IN AUTO desired value by one of the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
b. Verify charging pumps b. Perform the following:

o 2 charging pumps running 1) IF all seal cooling has been lost to any RCP. THEN isolate o One charging pump in AUTO seal injection to affected RCP(s).

2) Establish 2 charging pumps running (75 kw each).
3) Place one charging pump in AUTO. if desired.
c. Check PRZR level - TRENDING TO c. Perform the following:

PROGRAM IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.
d. Check RCS Tavg - STABLE d. Control dumping steam to stabilize RCS Tavg.

EOP: TITLE:

REV: 2 7 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES P lPAGE 28 of 33.

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I

  • 4 4 4 4
  • 4 4
  • 4 * ,* .4 *4 * * .* 4 4 4 4 4 4
  • 4 4 4 4 *
  • 4 4 *
  • 4 4 4 CAUTION ANYTIME EMERGENCY D/GS ARE THE ONLY SOURCE OF AC POWER TO THE PLANT, PERSONNEL SHOULD BE ASSIGNED TO MAINTAIN SURVEILLANCE OF THE D/GS.
  • * * * *
  • 4 4
  • 4 *
  • 4 4 4 *
  • 4 4 4 4 4 4 4 4 4 4 *
  • 4 4 4
  • 4 4 4 * *
  • 4 35 Restore Normal Electric System Alignment:
a. Verify circuit 767 and/or 751 - a. Continue with Step 36. WHEN AVAILABLE offsite power available. THEN do Steps 35b. c and d.
b. Restore power to non-faulted Buses 12A and/or 12B if necessary (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER)

c. Verify all AC bus normal feed c. Restore all AC busses and MCCs breakers - CLOSED to normal power supply (Refer to ER-ELEC.1. RESTORATION OF
  • Bus 13 OFFSITE POWER)
  • Bus 14
  • Bus 15
  • Bus 16

. Bus 17

. Bus 18

d. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 29 of 33 ACTION/EXPECTED RESPONSEINED 36 Check CNMT Recirc Fans - AT Establish 2 CNMT recirc fans running LEAST 2 RUNNING NOTE: Evaluate conditions to determine if turbine should be placed on turning gear.

37 Verify Turning Gear Oil Pump Perform the following:

- RUNNING

a. Manually start turning gear oil pump (42 kw).
b. Break vacuum to accelerate turbine coastdown.
c. Continue with Step 38. WHEN shaft stops, THEN dispatch AO to place turbine on turning gear (36 KW).

38 Check Status Of DC System Loads:

a. Verify TURB emergency DC lube a. Manually stop emergency DC lube oil pump - OFF oil pump.
b. Verify TDAFW pump DC oil pump - b. Perform the following:

OFF IN AUTO

1) Direct AO to locally check TDAFW AC oil pump running.

IF not running. THEN start pump from MCB.

2) Stop TDAFW pump DC oil pump.
c. Verify both MFW pump DC oil c. Perform the following:

pumps - OFF

1) Ensure associated MFW pump AC oil pump running.
2) Stop MFW pump DC oil pump and place in AUTO

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

. .. PAGE 30 of 33

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Inst Bus C provides power to all MCB manual controllers.

39 Check Status of Battery Chargers:

a. Battery Chargers 1A OR lAl - a. IF BOTH battery chargers are ENERGIZED (Annunciator J-15. deenergized. THEN direct the BATTERY CHRGR FAILURE OR PA Electricians to crosstie TSC INVERTER TROUBLE. EXTINGUISHED) battery charger to main battery A (Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

b. Battery chargers 1B OR iBI - b. IF BOTH battery chargers are ENERGIZED (Annunciator J-15. deenergized. THEN direct the BATTERY CHRGR FAILURE OR PA Electricians to crosstie TSC INVERTER TROUBLE. EXTINGUISHED) battery charger to main battery B (Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC)

U

EOP: TITLE:

REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

. - .PAGE 31 of 33 ACTION/EXPECTED RESPONSEINED 40 Restore Equipment Alignment:

a. Check CCW pumps - ONLY ONE a. IF two CCW pumps running. THEN RUNNING manually stop one pump.
b. Check radiation monitoring b. Restore sample pumps and systems: radiation monitors.

o CNMT vent sample pump -

RUNNING o Plant vent sample pump -

RUNNING o All area and process monitors operating as required

c. Dispatch AO to verify proper operation of seal oil system
d. Verify motor fire pump breaker - d. Close motor fire pump breaker.

CLOSED

e. Verify annunciator L-1. AUX BLDG e. IF bus 11A or 11B energized.

VENT SYSTEM CONTROL PANEL - THEN dispatch AO to restore AUX EXTINGUISHED BLDG ventilation (Refer to T-35A. AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)

f. Verify MCC G - ENERGIZED f. Manually close breaker.
g. Verify control board valve g. Manually align valves as alignment - NORMAL (Refer to necessary.

0-6.13, DAILY SURVEILLANCE LOG)

h. Verify adequate Rx head cooling:
1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw).
2) Verify one Rx compartment 2) Manually start one fan as cooling fan - RUNNING power supply permits (23 kw).
i. Dispatch AO to ensure one waste gas compressor in service This Step continued on the next page.

EOP TITLE:

EOP: TITLE: REV: 27 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES

" . .PAGE 32 of 33 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED (Step 40 continued from previous page)

j. Dispatch AO to restore SFP cooling
k. Verify adequate electric driven k. Go to Step 41.

air compressors - RUNNING

1. IF diesel air compressor supplying instrument air, THEN secure diesel air compressors.

(Refer to T-2F. BACKUP AIR SUPPLY) 41 Reset UV Relay Targets On Undervoltage Cabinets

  • Bus 14
  • Bus 16
  • Bus 17

. Bus 18 42 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

43 Notify Higher Supervision

ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED 44 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 2 7 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES PAGE 1 of 1 AP-ELEC. 1 APPENDIX LIST TITLE

1) ATTACHMENT NC (ATT-13.0)
2) ATTACHMENT D/G STOP (ATT-8.1)
3) ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0)
4) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
5) ATTACHMENT EXCESS L/D (ATT-9.1)
6) ATTACHMENT LETDOWN (ATT-9.0)

GINNA STATION CONTROLLED COPY NUMBER d'2~

RESPONSIBt MANAGER 10-36-Z6L(-

EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 2 of 14 A. PURPOSE - This procedure provides actions to respond to a loss of Bus 13 or Bus 15.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit, I if power is lost to Bus 13 or 15. I
b. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, if I power is lost to Bus 13 or 15. 1
2. SYMPTOMS - The symptoms of a loss of Bus 13 or Bus 15 are;
a. Annunciator L-6, BUS 13 UNDERVOLTAGE NON-SAFEGUARD, lit, or,
b. Annunciator L-22, BUS 15 UNDERVOLTAGE NON-SAFEGUARD, lit.

WP: TITLE:

REV: I AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 3 of 14 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED

  • 1 Monitor Tavg
a. Place rods in MANUAL
b. Manually operate control rods to control Tavg NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 2 Check Instrument Buses - ALL IF any instrument bus deenergized.

ENERGIZED: THEN perform the following:

o Annunciator E-6, LOSS A INSTR a. Place controller 431K to MANUAL.

BUS - EXTINGUISHED

b. IF steam dump is armed. THEN o Annunciator E-14, LOSS B INSTR place STEAM DUMP MODE SELECTOR BUS - EXTINGUISHED Switch to MANUAL.

K-I o Annunciator E-22, LOSS C INSTR BUS - EXTINGUISHED

c. Transfer affected instrument bus to available supply.

o Annunciator E-30, LOSS D INSTR d. Place 431K to AUTO, if desired.

BUS - EXTINGUISHED

e. Return steam dump to AUTO, if desired.

EoP: TITLE:

REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 4 of 14 3 Check IA System

a. Verify adequate air a. Manually start adequate air compressor(s) - RUNNING compressor(75 kw).
b. Check IA supply b. Dispatch an AO to locally reset and start adequate air o Pressure - GREATER THAN compressors (75 kw).

60 PSIG IF electric air compressor(s) o Pressure - STABLE OR can NOT be restored. THEN use INCREASING diesel air compressor. (Refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

IF IA can NOT be established, THEN refer to AP-IA.1. LOSS OF INSTRUMENT AIR.

4 Start EH Pump On Redundant IF no EH pump can be operated. THEN Train perform the following:

o IF Bus 13 deenergized. THEN o IF greater than P-9. THEN trip start EH pump B the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

-OR-

-OR-o IF Bus 15 deenergized. THEN start EH pump A o IF less than P-9. THEN trip the turbine and go to AP-TURB.1.

TURBINE TRIP WITHOUT RX TRIP REQUIRED.

ACTION/EXPECTED RESPONSEED 5 Locally Ensure At Least One IF no fans running. THEN reduce Bus Duct Cooling Fan - RUNNING load per AR-J-4. GENERATOR ISO PHASE BUS COOLING SYSTEM.

6 Check Condensate Bypass Valve Perform the following:

- CLOSED

a. Close condensate bypass valve AND place in AUTO.
b. Verify MFW pump suction pressure remains greater than 200 psig.

IF NOT. THEN manually open condensate bypass valve.

EOP: TITLE: REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 6 of 14 ACTION/EXPECTED RESPONSE llRESPONSE SE NOT OBTAINED I NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may require a load reduction.

7 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level: b. Perform the following:

o Level - GREATER THAN 20% 1) Check letdown divert valve.

LCV-112A, aligned to VCT.

-OR-

2) Manually increase VCT makeup o Level - STABLE OR INCREASING flow as follows:

a) Ensure BA transfer pumps and RMW pumps running.

b) Adjust RMW flow control valve, HCV-lll. to increase RMW flow.

c) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

EOP: TITLE:

REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 7 of 14 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDe 8 Check Charging Pump Suction Aligned To VCT:

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 9. WHEN VCT level greater than 20%.

THEN do Step 8b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

9 Check If Generator Online:

a. Check generator output breakers a. Go to Step 10.

- AT LEAST ONE CLOSED

  • IG13A72
  • 9X13A72
b. Check Tavg - TRENDING TO TREF b. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:
  • Reduce turbine load
  • Dilution of RCS
c. Verify annunciator G-15. STEAM c. WHEN Tavg within 50 F of Tref, DUMP ARMED - EXITINGUISHED THEN perform the following:
1) Ensure steam dump valves closed.
2) Reset steam dump.

NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3)

  • 10 Monitor PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Control Systems In Auto:

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO

d. Verify annunciator G-15. STEAM d. WHEN Tavg within 50 F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed
2) Reset steam dump
e. Verify rods in AUTO e. Place rods in AUTO, if desired.

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REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15

.PAGE 10 of 14 ACTION/EXPECTED RESPONSE STEP +RESPONSE NOT OBTAINED 12 Restore Equipment Alignment:

a. Stop turbine emergency DC lube oil pump
b. Place switch for EH pump associated with deenergized bus to stop, then return to AUTO.

o Bus 13. EH Pump A

-OR-o Bus 15. EH Pump B

c. Align MFW pump oil pumps as follows:
1) Select MFW pump A AC oil pump to an energized supply:
  • lAl. IF Bus 13 energized
  • 1A2. IF Bus 15 energized
2) Stop MFW pump A DC oil pump.

then return to AUTO

3) Select MFW pump B AC oil pump switch to an energized supply:

. lB1. IF Bus 13 energized

. 1B2. IF Bus 15 energized

4) Stop MFW pump B DC oil pump.

then return to AUTO

d. Check turbine speed - AT LEAST d. Go to step 12h.

1800 RPM

e. IF turning gear oil pump has auto started. THEN stop turning gear oil pump
f. Locally verify DC air side seal f. IF DC air side seal oil backup oil backup pump running. pump is NOT running, THEN go to Step 12h.

This Step continued on the next page.

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REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 11 of 14 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED (Step 12 continued from previous page)

g. IF DC air side seal oil backup pump running AND the HP seal oil backup pump has auto started.

THEN stop HP seal oil backup pump

h. Locally verify at least one h. Locally start available vacuum vacuum priming pump running priming pump.
i. Locally check FW Pump Seal Water i. IF Inst Bus D is energized. THEN Panel FW PMP OUTBOARD SEAL WATER locally reset solenoids.

SOLENOID TRIP lights -

EXTINGUISHED 13 Notify Maintenance To Monitor Affected DG:

a. Monitor DG for proper operation:
  • Security D/G. IF Bus 13 deenergized

. TSC D/G. IF Bus 15 deenergized

b. Add fuel oil as needed

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 14 Check If The Deenergized Bus Can Be Restored:

a. Check relay targets to determine cause of trip
b. Annunciator L-8. 480V GROUND, b. IF ground is on affected bus.

EXTINGUISHED THEN continue with step 17.

WHEN ground is cleared. THEN do Steps 14c, 15 and 16.

c. Cause of loss of bus - KNOWN AND c. Perform the following:

CORRECTED

1) IF bus 13 deenergized, THEN place generator bearing drain vapor extractor backup eductor in service (Refer to T-17K).
2) Review P-12 load list for the deenergizedbus.
3) Continue with step 17. WHEN cause is known and corrected.

THEN do Steps 15 and 16.

15 Energize Affected Bus (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER)

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REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 13 of 14 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 16 Restore Equipment Alignment:

a. Locally check air side seal oil pumps:
1) Air side seal oil pump - 1) Locally start air side seal RUNNING oil pump.

IF air side seal oil 'pump can NOT be started. THEN go to step 16b.

2) DC air side seal oil backup 2) Locally stop DC air side seal pump - OFF oil backup pump.
b. Locally check H2 side seal oil b. Locally start H2 side seal oil pump - RUNNING pump.
c. Check Control Room ventilation c. Restore Control Room ventilation operating normally (Refer to to normal operation, if desired.

0-6.13)

d. Check fire water booster pump d. Place fire water booster pump switch in AUTO switch to AUTO, if desired.
e. Restore affected rod drive MG set (Refer to S-1A. STARTUP OF ROD DRIVE MOTOR GENERATOR SETS)
f. Locally ensure both bus duct cooling fans - RUNNING
g. Locally ensure at least one vacuum priming pump- RUNNING
h. Locally ensure relay room AC unit - RUNNING
i. Locally restore MFP room ventilation (Refer to T-4G)
j. Dispatch AO to ensure one waste gas compressor in service
k. Verify annunciator L-1. AUX BLDG k. IF bus 11A or l1B energized.

VENT SYSTEM CONTROL PANEL - THEN dispatch AO to restore AUX EXTINGUISHED BLDG ventilation (Refer to T-35A, AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN).

1. Restore generator bearing drain vapor extractor to normal operation

EOP: TITLE: REV: 1 AP-ELEC.13/15 LOSS OF BUS 13/15 PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify All Instrument Buses IF normal supply available, THEN On Normal Supply place affected instrument bus on normal supply, if desired (Refer to ER-INST.3. INSTRUMENT BUS POWER RESORATION).

18 Evaluate MCB Annunciator Status (Refer to AR procedures) 19 Notify Higher Supervision 20 Verify Bus 13 AND Bus 15 - Return to Step 14.

ENERGIZED 21 Return To Procedure Or Guidance In Effect

-END-

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REV: 8 I AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1

, I PAGE I of 21 GINNA STATION CONTROLLED COPY NUMBER 4 3 RESPONSIBLE MANAGER EE-3C-IEAT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EMP: TITLE: REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 2 of 21 A. PURPOSE - This procedure provides actions to respond to a loss of AC Emergency Bus 14 or Bus 16.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of a LOSS OF SAFEGUARDS BUS 14/16 are;
a. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit, or
b. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit, or
c. Annunciator L-7, BUS 16 UNDER VOLTAGE SAFEGUARDS, lit, or
d. Annunciator L-14, BUS 14 UNDER VOLTAGE SAFEGUARDS, lit.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDI

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  • CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED. THEN AP-ELEC.1. LOSS OF 12A AND/OR 12B BUSSES. SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS.

AND 1950 KW FOR CONTINUOUS SERVICE.

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  • NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
  • 1 Monitor Tavg
a. Place Rods in MANUAL
b. Manually move control rods to control Tavg 2 Verify Emergency D/G Manually start D/G(s) associated Associated With Affected Bus with affected bus. (Refer to

- RUNNING ER-D/G.1. RESTORING D/Gs) o Bus 14 - D/G A o Bus 16 - D/G B

EOP: TITLE: REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 4 of 21 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINEDl 3 Verify Both Trains Of AC IF Bus 14 AND Bus 16 are Emergency Busses Energized To deenergized. THEN go to ECA-0.0, At Least 420 VOLTS: LOSS OF ALL AC POWER.

o Bus 14 and Bus 18 IF one train deenergized. THEN perform the following:

o Bus 16 and Bus 17

a. Ensure D/G aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check D/G running.

IF NOT, THEN perform the following:

1) Depress D/G FIELD RESET pushbutton
2) Depress D/G RESET pushbutton
3) Start D/G
4) IF D/G will NOT start, THEN dispatch AO to locally start D/G. (Refer to ER-D/G.1.

RESTORING D/Gs)

c. Adjust D/G voltage to approximately 480V.
d. Adjust D/G frequency to approximately 60 Hz.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 5 of 21 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl

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  • a * * * *
  • a * * * * * * * *
  • a * * * * * * * * * * *
  • a
  • CAUTION IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.
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  • a 4 Verify CCW Pump Status
a. At least one CCW Pump - RUNNING a. Start one CCW pump (122 kw)

IF neither CCW pump can be started. THEN perform the following:

o IF reactor trip breakers closed. THEN:

1) Trip the reactor.
2) WHEN all E-0 Immediate Actions done, THEN trip BOTH RCP's.
3) Close letdown isolation.

AOV-427.

4) Close excess letdown.

HCV-123.

5) Pull stop BOTH CCW pumps.
6) Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

o IF reactor trip breakers open, THEN:

1) Trip both RCPs.
2) Close letdown isolation.

AOV-427.

3) Close excess letdown.

HCV-123.

4) Pull stop BOTH CCW pumps.
5) Go to Step 5.
b. Annunciator A-22. CCW PUMP b. Start second CCW pump (122 kw).

DISCHARGE LO PRESS 60 PSIG -

EXTINGUISHED

ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 5 Verify Charging Pump Status- Isolate letdown flowpaths AT LEAST ONE RUNNING

a. Close letdown isolation, AOV-427.
b. Close EXCESS LETDOWN HCV-123.
c. Close loop A cold leg to EXCESS LETDOWN Hx. AOV-310.

6 Check MFW Regulating Valves - Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO a. Place affected S/G MFW regulating valve in MANUAL.

b. Restore S/G level to 52%.

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 7 of 21 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 7 Verify Bus 14 - ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Close letdown isolation. AOV-427.
b. IF steam dump is armed, THEN place STEAM DUMP MODE SELECTOR Switch to MANUAL.
c. Ensure only one charging pump operating (75 kw).
d. Transfer Inst Bus B to maintenance supply.
e. Return steam dump to AUTO. if desired.
f. Ensure the following equipment operating as necessary:
  • PRZR Backup Heaters

. CNMT Recirc Fans B and C

  • RMW Pump B

. Reactor Compartment Cooling Fan B

. Penetration Cooling Fan B

g. IF Bus 14 can NOT be energized.

THEN:

o Provide alternate room cooling for D/G A.

o Cross-connect D/G B fuel oil transfer pump to D/G A (Refer to ER-D/G.1. RESTORING DIGs).

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 8 of 21 ACTION/EXPECTED RESPONSE IRESPONSE NOT OBTAINED 8 Verify Bus 16 - ENERGIZED TO Perform the following:

AT LEAST 420 VOLTS

a. Ensure the following equipment operating as necessary:
  • CCW Pump A v Charging Pump A

. PRZR Proportional Heaters

  • CNMT Recirc Fans A and D
  • RMW Pump A

. Reactor Compartment Cooling Fan A

  • Penetration Cooling Fan A
b. Direct AO to swap Aux Bldg lighting to MCC C (switch at MCC C. locked valve key required)
c. IF Bus 16 can NOT be energized.

THEN:

o Provide alternate room cooling for D/G B.

o Cross-connect D/G A fuel oil transfer pump to D/G B (Refer to ER-D/G.1. RESTORING DIGs).

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 9 of 21 NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may required a load reduction.

9 Check VCT Makeup System:

a. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
b. Check VCT level: b. Check letdown divert valve, LCV-112A. aligned to VCT.

o Level GREATER THAN 20%

Manually increase VCT makeup

-OR- flow as follows:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve. HCV-11l. to increase RMW flow.
3) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION, if necessary-.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 10 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Charging Pump Suction Aligned To VCT:

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 11. WHEN VCT level greater than 20%.

THEN do Step 10b.

b. Align charging pumps to VCT o LCV-112C open o LCV-112B closed

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 11 of 21 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED NOTE: When restarting equipment for recovery, it is preferable to start equipment on busses being supplied from offsite power.

11 Check CVCS Operation:

a. Charging pumps - AT LEAST ONE a. IF charging pump(s) available.

RUNNING THEN perform the following:

1) IF all seal cooling has been lost to any RCP. THEN isolate seal injection to affected RCP
2) Start one charging pump (75 kw).
3) Establish greater than 20 gpm charging line flow.

IF NO charging pumps available.

THEN perform the following:

1) WHILE continuing in this procedure. perform actions of AP-CVCS.3. LOSS OF ALL CHARGING FLOW.
2) Go to Step 13.
b. Charging line flow - GREATER b. Establish charging line flow to THAN 20 GPM REGEN Hx - GREATER THAN 20 GPM This Step continued on the next page.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 11 continued from previous page)

c. Check letdown indications: c. Perform the following:

o Check PRZR level - GREATER 1) Close letdown isolation.

THAN 13% AOV-427.

o Letdown flow - APPROXIMATELY 2) Close letdown orifice valves 40 GPM (60 GPM IF AOV-202 (AOV-200A. AOV-200B. and OPEN) AOV-202) o Letdown flow - STABLE 3) Close letdown isolation.

AOV-371.

4) IF seal injection in service.

THEN close charging flow control valve HCV-142 WHILE adjusting charging pump speed to maintain:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program

5) IF PRZR level greater than 13%. THEN go to Step 12. IF NOT. THEN continue with Step 14. WHEN PRZR level greater than 13%. THEN do Steps 12 and 13.
d. Adjust charging pump speed and HCV-142 to restore PRZR level and labyrinth seal D/P
e. Go to Step 13

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 13 of 21 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINEDl 12 Establish Normal Letdown IF normal letdown can NOT be (Refer to ATT-9.0, ATTACHMENT established, THEN establish excess LETDOWN) letdown. (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D) 13 Verify PRZR Heaters Restored: IF adequate D/G capacity available for PRZR heaters (400 kw each o PRZR proportional heater breaker bank). THEN perform the following:

- CLOSED

a. Reset and close PRZR o PRZR backup heater breaker - proportional heater breaker if RESET. IN AUTO necessary.
b. Reset PRZR backup heater breaker and return to AUTO if necessary.

IF adequate D/G capacity NOT available, THEN refer to ER-PRZR.1.

RESTORATION OF PRZR HEATERS DURING BLACKOUT.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 14 of 21 ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED 14 Verify Normal Rod Control Restored:

a. Annunciator C-5. PPCS ROD a. IF alarm is due to a loss of SEQUENCE OR ROD DEVIATION - power to MRPI. THEN maintain EXTINGUISHED rods in manual AND minimize rod motion.

IF alarm is due to actual rod misalignment. THEN refer to AP-RCC.2. RCC/RPI MALFUNCTION.

while continuing with this procedure.

b. Annunciator E-28. POWER RANGE b. Perform the following:

ROD DROP ROD STOP - EXTINGUISHED

1) Place rods in MANUAL.
2) Reset NIS rod drop rod stop signals (at NIS racks) as necessary.
c. Annunciator F-15. RCS TAVG DEV c. Go to step 15 4OF - EXTINGUISHED
d. Place rods in AUTO. if desired

EOP: TITLE: REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 15 of 21 NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 15 Establish Stable Plant Conditions:

a. Check Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

. Withdraw control rods

  • Reduce turbine load
  • Dilution of RCS
b. Check PRZR pressure - TRENDING b. Control PRZR pressure by one of TO 2235 PSIG IN AUTO the following:

. 431K in MANUAL

  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. Check PRZR level - TRENDING TO c. Perform the following:

PROGRAM IN AUTO CONTROL

1) Place affected charging pumps in MANUAL 2).Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Restore Normal Electric System Alignment:

a. Verify all AC bus normal feed a. Perform the following:

breakers - CLOSED

1) Refer to AR-L-5 to reset a
  • Bus 13 safeguards bus over current

. Bus 14 condition.

  • Bus 15

. Bus 16 2) Restore non-faulted AC busses

  • Bus 17 and MCCs to normal power
  • Bus 18 supply (Refer to ER-ELEC.1.

RESTORATION OF OFFSITE POWER)

3) IF normal power is restored to all AC emergency buses.

THEN return to step 9. IF NOT. THEN go to step 17.

b. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION)
c. Restore D/G Fuel Oil Transfer System to normal alignment.

(Refer to ER-D/G.1. RESTORING D/Gs)

17 Establish Normal Plant Conditions:

a. Verify 2 charging pumps - RUNNING a. Perform the following:
1) Manually start charging pumps as necessary.
2) Place one charging pump in AUTO, if desired.
b. Verify at least 2 CNMT recirc b. Establish 2 CNMT recirc fans fans - RUNNING running.
c. Check CCW pumps - ONLY ONE c. Locally verify two CCW pumps RUNNING running. THEN manually stop one pump.
d. Check radiation monitoring d. Restore sample pumps and systems: radiation monitors as necessary.

(Refer to the ODCM).

o CNMT vent sample pump -

RUNNING o Plant vent sample pump -

RUNNING o All area and process monitors operating as required 18 Check Status Of DC System Loads:

a. Verify TDAFW pump DC oil pump - a. Perform the following:

OFF IN AUTO

1) Direct AO to locally check TDAFW AC oil pump running.

IF not running. THEN start pump from MCB.

IF AC oil pump can NOT be started. THEN go to Step 19.

2) Stop TDAFW pump DC oil pump.

MeP: TITLE:

REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 18 of 21 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED NOTE: Inst Bus C provides power to all MCB manual controllers.

19 Check Status of Battery Chargers:

a. Battery Chargers 1A OR lAl - a. IF BOTH battery chargers are ENERGIZED (Annunciator J-15. deenergized. THEN direct the BATTERY CHRGR FAILURE OR PA Electricians to crosstie TSC INVERTER TROUBLE. EXTINGUISHED) battery charger to main battery A (Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

b. Battery Chargers 1B OR iBl - b. IF BOTH battery chargers are ENERGIZED (Annunciator J-15. deenergized. THEN direct the BATTERY CHRGR FAILURE OR PA Electricians to crosstie TSC INVERTER TROUBLE. EXTINGUISHED) battery charger to main battery B (Refer to ATT-24.0.

ATTACHMENT TRANSFER BATTERY TO TSC).

EOP: TITLE: REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 19 of 21 ACTION/EXPECTED RESPONSEED 20 Restore Equipment Alignment:

a. Verify annunciator L-1. AUX BLDG a. Dispatch AO to restore AUX BLDG VENT SYSTEM CONTROL PANEL - ventilation (Refer to T-35A.

EXTINGUISHED AUX AND INTERMEDIATE BUILDING VENTILATION STARTUP AND SHUTDOWN)

b. Restore affected bus equipment as power supply permits.

o SFP Cooling o Penetration cooling fans o Reactor compartment cooling fans o Hydrogen panel o PA system inverter (Battery Room A) o Auxiliary Bldg lighting (normal supply MCC D. manual throwover to MCC C)(switch at MCC C. locked valve key required) o Fire system (Refer to SC-3.16.2.3)

c. Evaluate MCB annunciator status (Refer to AR Procedures)
d. Verify control board valve d. Manually align valves as alignment - NORMAL (Refer to necessary.

0-6.13. DAILY SURVEILLANCE LOG)

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16

. PAGE 20 of 21 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 21 Establish Control System In Auto:

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO, if desired.
c. Verify PRZR heaters restored: c. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

e. Verify MFW regulating valves in e. Place MFW regulating valves in AUTO AUTO, if desired.
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
g. Verify annunciator G-15. STEAM g. WHEN Tavg within 51F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure-steam dump valves closed
2) Reset steam dump
h. Verify rods in AUTO h. Place rods in AUTO, if desired.

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REV: 8 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 2

. . PAGE 21 of 21 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINEDl 22 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

23 Verify emergency AC bus Return to Step 9 normal feed breakers closed o Bus 14 o Bus 16 24 Verify Inst Bus B on normal Place Inst Bus B on normal supply supply (Refer to ER-INST.3.INSTRUMENT BUS POWER RESTORATION).

K) 25 Reset UV relay targets on undervoltage cabinets o Bus 14 o Bus 16 26 Notify Higher Supervision 27 Return To Procedure Or Guidance In Effect

-END-

EDP: TITLE:

REV: 8 A ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 PAGE 1 of 1 AP-ELEC.14/16 APPENDIX LIST TITLE

1) ATTACHMENT TRANSFER BATTERY TO TSC (ATT-24.0)
2) ATTACHMENT EXCESS L/D (ATT-9.1)
3) ATTACHMENT LETDOWN (ATT-9.0)

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REV: 7

! AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 1 of 7 GINNA STATION CONTROLLED COPY NUMBER ___

RESPONSIBLY, MANAGER EFFECTIVE DAfE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 2 of 7 A. PURPOSE - This procedure provides actions to respond to a loss of AC Emergency Bus 17 or Bus 18.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of a LOSS OF SAFEGUARDS BUS 17/18 are;
a. Annunciator J-7, 480V MAIN OR TIE BREAKER TRIP, lit, or
b. Annunciator J-29, 480V TRANSFORMER BREAKER TRIP, lit, or
c. Annunciator L-15, BUS 17 UNDERVOLTAGE SAFEGUARDS, lit, or
d. Annunciator L-23, BUS 18 UNDERVOLTAGE SAFEGUARDS, lit.

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REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 3 of 7 SE ACTION/EXPECTED RESPONSE l lRESPONSE NOT OBTAINEDl

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  • a *
  • CAUTION o IF A LOSS OF BUS 12A OR 12B HAS OCCURRED. THEN AP-ELEC.1. LOSS OF 12A AND/OR 12B BUSSES, SHOULD BE PERFORMED.

o OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR. 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.

  • * * * * * * * * * * * *
  • a
  • a * *
  • a a
  • a
  • a a a a a a a a a a a a * * *
  • NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Verify Emergency D/G Manually start D/G(s) associated Associated With Affected Bus with affected Bus. (Refer to

- RUNNING ER-D/G.1. RESTORING D/Gs) o Bus 18 - D/G A o Bus 17 - D/G B

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REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 4 of 7 ACT ION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Verify Both Trains Of AC IF Bus 14 AND Bus 16 are Emergency Busses Energized To deenergized. THEN go to ECA-0.0.

At Least 420 VOLTS: LOSS OF ALL AC POWER.

o Bus 14 and Bus 18 IF one train deenergized. THEN perform the following:

o Bus 16 and Bus 17

a. Ensure DIG aligned for unit operation o Mode switch in UNIT o Voltage control selector in AUTO
b. Check DIG running.

IF NOT. THEN perform the following:

1) Depress DIG FIELD RESET pushbutton
2) Depress DIG RESET pushbutton
3) Start D/G
4) IF D/G will NOT start. THEN dispatch AO to locally start D/G. (Refer to ER-D/G.1.

RESTORING D/Gs)

c. Adjust D/G voltage to approximately 480V.
d. Adjust D/G frequency to approximately 60 Hz.

K-i

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REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 5 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify Service Water System Operation:

a. SW pumps - AT LEAST ONE RUNNING a. Perform the following:

IN EACH LOOP

1) Manually start SW pumps as o A or B pump in Loop A necessary (257 kw each).

o C or D pump in Loop B 2) IF adequate cooling can NOT be supplied to a running D7G THEN perform the following:

a) Pull stop affected D/G.

b) Immediately depress voltage shutdown pushbutton.

c) Refer to ER-D/G.2.

ALTERNATE COOLING FOR EMERGENCY DIGs.

3) IF no SW pumps can be operated. THEN perform the following:

a) Trip the reactor b) WHEN all E-0 Immediate Actions done. THEN trip BOTH RCPs c) Close letdown isol. AOV-427 d) Close excess letdown.

HCV-123.

e) Go to E-O, REACTOR TRIP OR SAFETY INJECTION

4) IF only one SW pump can be operated. THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
b. SW header pressure - GREATER b. Refer to AP-SW.l. SERVICE WATER THAN 40 PSIG IN EACH LOOP LEAK.

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REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18

. PAGE 6 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Restore Normal Electric System Alignment:

a. Verify all AC bus normal feed a. Perform the following:

breakers - CLOSED

1) Refer to AR-L-5 to reset
  • Bus 13 safeguards bus overcurrent
  • Bus 14 condition.
  • Bus 15
  • Bus 16 2) Restore all non-faulted AC
  • Bus 17 busses and MCCs to normal
  • Bus 18 power supply (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER)

IF normal power to all AC emergency buses can NOT be restored. THEN go to step 5.

b. Stop any unloaded emergency D/G and place in standby (Refer to T-27.4. DIESEL GENERATOR OPERATION) 5 Restore Equipment Alignment:
a. Check SW Pumps - AT LEAST ONE a. Start SW Pumps as necessary.

PUMP RUNNING IN EACH LOOP o Pump A or B in Loop A o Pump C or D in Loop B

b. Restore affected bus equipment as desired o MCC G o Intake Heaters o House Heating Boiler o Motor Fire Pump o Canal Sample Pump

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REV: 7 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 PAGE 7 of 7 ACTIN/EPECED ESPOSE l ESPNSENOT OBTAINED I 6 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

7 Verify Emergency AC Bus Return to Step 3 Normal Feed Breakers Closed

  • Bus 17
  • Bus 18 8 Reset UV relay targets on undervoltage cabinets

. Bus 17

  • Bus 18 9 Notify Higher Supervision 10 Return To Procedure Or Guidance In Effect

-END-

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 1 of 13 GINNA STATION CONTROLLED COPY NUMBER 43 RESPONSIBL MANAGER 4-3 -Rocq-EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 2 of 13 A. PURPOSE - This procedure provides the steps necessary to respond to a MFW system malfunction resulting in a decrease in or complete loss of main feedwater, or an uncontrolled increase in main feedwater.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. Other APs if feedwater flow can not be controlled.
b. AR-H-4, MAIN FEED PUMP OIL SYSTEM, if an MFP trips. I
c. AR-H-li, FEED PUMP SEAL WATER LO DIFF PRESS 15 PSI, I when an MFP trips. I
d. AR-G-8, 4 KV MOTOR OVERLOAD, if a MFP pump trips. I
2. SYMPTOMS - The symptoms of ABNORMAL MAIN FEEDWATER FLOW are;
a. Low indicated MFW pump suction flow on 1 pump, or
b. MFW pump indicates tripped, or
c. MFW pump discharge valve indicates shut, or
d. Annunciator G-3(5), S/G A(B) LEVEL DEVIATION +/- 7%,

lit, or

e. Annunciator G-19(21), S/G A(B) FLOW MISMATCH, lit, or
f. Annunciator H-17, FEED PUMP NET POSITIVE SUCTION I HEAD, lit, or I
g. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit.

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 3 of 13 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 1 Check MFW Flow - LESS THAN Perform the following:

STEAM FLOW

a. Place affected S/G(s) MFW regulating valve and bypass valve in MANUAL.
b. Restore S/G level to 52%.

IF SIG level greater than 52% AND can NOT be controlled manually.

THEN perform the following:

a. Trip the reactor.
b. WHEN all E-O Immediate Actions done. THEN stop all running MFW pumps.
c. Close both MFW pump discharge valves.
d. Go to E-O. REACTOR TRIP OR SAFETY INJECTION.

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1 REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW

. .PAGE 4 of 13 ACTIN/EXECTE REPONS l lRESPNSENOT OBTAINED NOTE: IF power reduction is required the thumb rule for initial boron addition is -2 gal/% load reduction.

2 Check MFW Requirements:

a. Power - GREATER THAN 50% a. IF power less than 50%. THEN go to Step 3.
b. Both MFW pumps - RUNNING b. IF power greater than 75%. THEN trip the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

IF only one MFW pump has tripped. THEN perform the following:

1) Start all 3 AFW pumps and verify flow.
2) Place turbine in manual.
3) Depress MANUAL CONTROL VALVE LOWER AND MANUAL CONTROL VALVE FAST pushbuttons.
4) Ensure control rods inserting to control Tavg at program.
5) IF S/G level drops to S 20%

AND feed flow less than steam flow. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

6) WHEN feed flow greater than steam flow. THEN stop load reduction.
7) IF a PORV opens during load reduction. THEN ensure PORV closes when PRZR pressure is below 2335 psig.
8) Go to Step 4.

IF both MFW pumps have tripped.

THEN ensure reactor trip and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

c. Go to Step 4

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 5 of 13 ACTION/EXPECTED RESPONSENED 3 Verify At Least One MFW Pump IF power greater than 35%, THEN

- RUNNING trip the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

IF NOT. THEN perform the following:

a. Start all 3 AFW pumps and verify flow.
b. IF turbine previously latched.

THEN ensure turbine trip and go to AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED OR E-0.

REACTOR TRIP or SAFETY INJECTION.

IF turbine NOT previously latched. THEN perform the following:

1) Reduce reactor power to less than 2%.
2) Go to Step 11.

4 Verify MFW Pump Suction Perform the following:

Pressure - GREATER THAN 185 PSIG a. Verify standby condensate pump running, if required.

b. Verify condensate bypass valve open.
c. Place Hotwell level controller in MANUAL-at 50%.
d. Place trim valve controller to manual and close trim valves.
e. If condensate booster pumps have tripped THEN reduce turbine load until MFW pump suction pressure greater than 200 psig AND stable.

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 6 of 13 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 5 Verify Adequate MFW Flow: Check MFW regulating valves controlling in AUTO. IF NOT, THEN o A MFW flow - GREATER THAN OR control MFW flow in MANUAL.

EQUAL TO A STEAM FLOW IF MFW flow can NOT be adjusted to o B MFW flow - GREATER THAN OR greater than steam flow. THEN trip EQUAL TO B STEAM FLOW the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

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E REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 7 of 13 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINED NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 6 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

. Reduce turbine load

. Dilution of RCS

b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in manual

. Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pump(s) in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.

This Step continued on the next page.

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 8 of 13 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl (Step 6 continued from previous page)

d. MFW regulating valves - d. Perform the following:

RESTORING SIG LEVEL TO 52% IN AUTO 1) Place affected S/G(s) MFW regulating valve in MANUAL.

2) 'Restore S/G level to .52%.
e. Rod insertion limit alarms - e. Borate and withdraw control rods EXTINGUISHED to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).

7 Check Status Of MFW System:

a. Check MFW pump suction pressure: a. Return to Step 4.

o Pressure - GREATER THAN 200 PSIG o Pressure - STABLE

b. Automatic feedwater control - b. Continue with Step 8. WHEN AVAILABLE malfunction identified. THEN do Step 7c.
c. Restore feedwater control system to AUTO if desired

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW

. .. ... PAGE 9 of 13 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 8 Check Status Of Condensate System:

a. Check.condensate bypass valve - a. Perform the following:

CLOSED. IN AUTO

1) Close condensate bypass valve AND place in AUTO.
2) Verify MFW pump suction pressure remains greater than 200 psig.

IF NOT. THEN manually open condensate bypass valve.

b. Verify hotwell level - AT b. Slowly restore hotwell level to SETPOINT setpoint.
c. Place hotwell level controller in AUTO
d. Check condensate pump - ONLY 2 d. Stop one condensate pump.

PUMPS RUNNING (Refer to T-5F. STARTING OR STOPPING THE CONDENSATE PUMPS)

e. Verify trim valves in AUTO e. Adjust trim valve controller to 300 to 375 psig (PI-2043) and place controller in AUTO.

W

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 10 of 13 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED 9 Establish Control Systems In Auto

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR Heaters restored: c. Restore PRZR heater. if desired.

o PRZR proportional heater breaker - CLOSED o PRZR backup heater breaker -

RESET/IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

e. Verify MFW regulating valves in e. Place MFW regulating valves in AUTO AUTO, if desired.
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
g. Verify steam dump controller.

HC-484. in AUTO at 1005 psig

h. Verify annunciator G-15. STEAM h. WHEN Tavg within 5 0F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
i. Verify Rods in AUTO i. Place Rods in AUTO. if desired.

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 11 of 13 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 10 Restore AFW System To Auto Standby:

a. Verify MFW regulating valves - a. IF level low. THEN return to RESTORING S/G LEVEL TO 52% IN Step 5. WHEN S/G levels return AUTO to 52%. THEN do Steps 10b through g.
b. Close TDAFW pump steam supply valves

. MOV-3504A

  • MOV-3505A
c. Direct AO to locally isolate S/G blowdowns. (Refer to T-14N.

BLOWDOWN SYSTEM FLOW CHANGES)

d. WHEN AO has locally isolated SIG blowdowns. THEN stop MDAFW pumps and place switches in AUTO
e. Open AFW pump discharge valves

. MOV-4007

  • MOV-4008

. MOV-3996

f. Open TDAFW pump flow control valves
  • AOV-4297
  • AOV-4298
g. Direct AO to locally restore S/G blowdowns to desired flow rate.

(Refer to T-14N. BLOWDOWN SYSTEM FLOW CHANGES)

h. Go to Step 12

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REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 12 of 13 ACTIN/EPECED ESPOSE 1 ESPNSENOT OBTAINEDl 11 Establish Stable Plant Conditions:

a. Verify reactor power - LESS THAN a. Adjust control rods to CONTROL 2% reactor power BETWEEN 1% AND 2%.
b. Adjust MDAFW pumps flow to restore S/G level to 52%.
c. PRZR pressure - TRENDING TO c. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in manual
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
d. PRZR level - TRENDING TO PROGRAM d. Perform the following:

IN AUTO CONTROL

1) Place affected charging pump(s) in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

e. Rod insertion limit alarms - e. IF the reactor is to remain EXTINGUISHED critical. THEN borate and withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
f. Tavg - STABLE AT APPROXIMATELY f. Verify proper operation of steam 5470F dump OR manually control steam dump as necessary.

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I REV: 16 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW

. . PAGE 13 of 13 ACTINIEXECTD REPONS 1 RESONSENOTOBTAINED 12 Evaluate MCB Annunciator Status (Refer to AR procedures) 13 Check If PRZR Boron Should Be Mixed

a. Boration performed for load a. Go to Step 14.

reduction

b. Place PRZR backup heaters switch to ON NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

14 Notify Higher Supervision 15 Return To Procedure Or Guidance In Effect

-END-

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 1 of 11 GINNA STATION CONTROLLED COPY NUMBER 1L RESPONSIBLE OANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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REV: 15 NP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 2 of 11 A. PURPOSE - This procedure provides the actions necessary to mitigate the consequences of abnormal PRZR pressure.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. Any of several APs, when PRZR pressure can not be controlled.
2. SYMPTOMS - The symptoms of ABNORMAL PRZR PRESSURE are;
a. Annunciator AA-13, PRESSURIZER SAFETY VALVE POSITION, lit, or
b. Annunciator C-27, PRESSURIZER LO PRESS SI CHANNEL I ALERT 1750 PSIG, or I
c. Annunciator C-28, PRESSURIZER LO PRESS SI CHANNEL I ALERT 1750 PSIG, or I
d. Annunciator F-1, PRT LIQUID HI TEMP 2200F, lit, or
e. Annunciator F-2, PRESSURIZER HI PRESS 2310 PSI, lit, or
f. Annunciator F-6, PRESSURIZER HEATER BREAKER TRIP, lit, or
g. Annunciator F-9, PRT HI PRESS 5 PSI, lit, or.
h. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or
i. Annunciator F-17, PRT LEVEL 60.8 % 84.5, lit, or
j. Annunciator F-18, PRZR SAFETY VLV OUTLET HI TEMP 1450F, lit, or
k. Annunciator F-19, PRZR PORV OUTLET HI TEMP 1450F, lit, or
1. Annunciator F-266, PRESSURIZER HI PRESS CHANNEL ALERT 2377 PSI.
m. Annunciator F-27, PRESSURIZER LO PRESS CHANNEL ALERT I 1873 PSI, or I
n. PPCS alarm PPCS-PPZR, PRESSURIZER AVERAGE PRESSURE. I

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 3 of 11 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: o Actual PRZR pressure should be verified by more than 1 indicator.

o Refer to ITS section 3.4.1.

1 Check PRZR Pressure: IF one pressure channel deviates significantly from the other 3.

o All 4 narrow range channels - THEN perform the following:

APPROXIMATELY EQUAL

a. IF the controlling PRZR pressure o All 4 narrow range channels - channel has failed. THEN place TRENDING TOGETHER controller. 431K. in MANUAL and adjust output to restore PRZR pressure.
b. Refer to ER-INST.1. REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

2 Check Reactor Power - STABLE IF the abnormal PRZR pressure is a result of a power transient. THEN evaluate conditions and go to the appropriate plant procedure.

3 Check PRZR Pressure:

a. Pressure - LESS THAN 2235 PSIG a. Go to Step 12.
b. Pressure - GREATER THAN 2000 PSIG b. IF pressure decreasing uncontrollably. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE

. PAGE 4 of 11 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 4 Check PRZR Heater Status:

a. PRZR proportional heater breaker a. Place PRZR proportional heaters

- CLOSED switch to TRIP to reset. then place switch to CLOSE and let return to AUTO.

b. PRZR heater backup group - ON b. IF PRZR pressure less than 2220 psig. THEN energize PRZR backup heaters.

IF PRZR backup heater breaker has tripped. THEN perform the following:

1) Place the breaker switch to OFF to reset breaker.
2) Place the breaker switch to ON to energize heaters.
3) Verify load increase on Bus 16.

5 Verify Normal PRZR Spray Place controllers in MANUAL at 0%

Valves - CLOSED demand. IF valves can NOT be closed. THEN perform the following:

. AOV-431A

  • AOV-431B a. Trip the reactor.
b. WHEN all E-0 Immediate Actions done. THEN trip the associated RCP.
  • AOV-431A. RCP A
  • AOV-431B. RCP B
c. Go to E-0. REACTOR TRIP OR SAFETY INJECTION.

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 5 of 11 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED I NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode (refer to TR 3.4.3).

6 Check PRZR Pressure Place 431K in MANUAL and decrease Controller, 431K, Demand - output to restore PRZR pressure to LESS THAN 50% 2235 psig.

7 Check PRZR PORVs:

a. PORVs - CLOSED a. Manually close PORVs.

IF any valve can NOT be closed.

THEN manually close the associated block valve.

  • MOV-516 for PCV-430
  • MOV-515 for PCV-431C
b. Annunciator F-19, PRZR PORV b. IF PORV leakage is indicated.

OUTLET HI TEMP 1450 F - THEN perform the following:

EXTINGUISHED

1) Close PORV block valves one at a time AND check if pressure stabilizes.
  • MOV-515
  • MOV-516
2) IF a leaking PRZR PORV is identified. THEN open any nonleaking PORV block valve AND go to Step 8.
c. Go to Step 9

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE

. ~PAGE 6 of 11i ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED I 8 Attempt To Reseat Any Leaking PORV:

a. Verify affected PORV block valve a. Close the affected PORV block

- CLOSED valve.

. MOV-516 for PCV-430

  • MOV-515 for PCV-431C
b. Cycle the leaking PORV open then closed
c. Open affected PORV block valve
d. Verify leakage has stopped d. IF leakage continues. THEN perform the following:
1) Reclose leaking PORV block valve.
2) Refer to ITS section 3.4.11 and TR 3.4.3 for required actions.
e. Go to Step 11 9 Check PRZR Safety Valves: IF safety valve leakage indicated.

THEN perform the following:

o Position indicator - LESS THAN 0.1 INCH a. Verify leakage within limits of ITS section 3.4.13.

o Annunciator F-18. PRZR SAFETY VLV OUTLET HI TEMP 1450F - b. Go to Step 16.

EXTINGUISHED o Annunciator AA-13. PRESSURIZER SAFETY VALVE POSITION -

EXTINGUISHED

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 10 Check AUX Spray Valve, Manually close valve. IF valve can AOV-296 - CLOSED NOT be closed. THEN perform the following:

a. Close letdown isolation. AOV-427.
b. Close letdown orifice valves (AOV-200A. AOV-200B and AOV-202).
c. Close letdown isolation. AOV-371.
d. Close charging flow control valve. HCV-142. WHILE adjusting charging pump speed to maintain:
  • RCP labyrinth seal D/P between 15 inches and 80 inches
  • PRZR level at program
e. Close charging to loop B cold leg, AOV-294.
f. Establish excess letdown.

(Refer to ATT-9.1, ATTACHMENT EXCESS L/D) 11 Check PRZR Pressure Control Restored:

a. Pressure - TRENDING TO 2235 PSIG a. IF pressure continues to decrease. THEN return to Step 1.
b. Go to Step 16

11 l EOP: TITLE:

l REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE l PAGE 8 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check PRZR Backup Heaters - Verify PRZR backup heater switch in OFF AUTO. AND ensure proper operation.

NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 13 Check PRZR Pressure Place 431K in MANUAL AND adjust Controller, 431K, Demand - output to reduce PRZR pressure to INCREASING 2235 psig.

.i<,

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REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 9 of 11 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED NOTE: The AT between the REGEN Hx charging outlet and the PRZR shall NOT exceed 320'F.

14 Establish PRZR Spray

a. Check RCPs - BOTH RUNNING a. Perform the following:
1) Place PRZR spray valve associated with any non-running RCP in MANUAL with demand at 0%.
  • PCV-431A. RCP A
  • PCV-431B. RCP B
2) IF any RCP running. THEN go to Step 14b.
3) IF NO RCP running. AND letdown in service. THEN perform the following as necessary to restore PRZR pressure to 2235 psig:

a) Open AUX spray valve, AOV-296.

b) Close normal charging valve. AOV-294.

c) Go to Step 15.

b. Check PRZR Spray Valves - b. Place PRZR spray valve OPENING AS REQUIRED controllers in MANUAL and open as required to restore pressure
  • AOV-431A to 2235 psig.

. AOV-431B IF PRZR spray valves will not open. AND letdown is in service, THEN perform the following as necessary to restore PRZR pressure to 2235 psig:

1) Open Aux spray valve. AOV-296.
2) Close normal charging valve.

AOV-294.

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l . REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE PAGE 10 of 11 ACTION/EXPECTED RESPONSE 15 Check PRZR Pressure - IF PRZR pressure continu es to TRENDING TO 2235 PSIG increase uncontrollably. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

16 Check PRT Indications:

a. Level - BETWEEN 61% AND 84% a. Drain PRT to RCDT using PRT drain valve. AOV-526 until PRT level is between 61% AND 84%.
b. Pressure - APPROXIMATELY b. Open PRT vent. AOV-527 until PRT 1.5 PSIG AND STABLE pressure is approximately 1.5 psig. IF PRT pressure will NOT decrease. THEN open PRT drain valve. AOV-526. to reduce pressure until PRT pressure is approximately 1.5 psig.
c. Temperature - AT CNMT AMBIENT c. To feed and bleed the PRT.

TEMPERATURE AND STABLE perform the following:

1) Start a RMW pump.
2) Verify RMW to CNMT isolation valve. AOV-508. open.
3) Feed and bleed the PRT using PRT fill valve from RMW.

AOV-548. and PRT drain valve.

AOV-526 to reduce PRT temperature to CNMT ambient temperature.

17 Establish PRZR Pressure Control In Auto:

a. Verify 431K in AUTO a. Place 431K in AUTO. if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valv e in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters. if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO 18 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

19 Notify Higher Supervision 20 Notify Reactor Engineer for Transient Monitoring Program

-END-

EOP: TITLE:

REV: 15 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE

. . PAGE I of I AP-PRZR.1 APPENDIX LIST TITLE

1) ATTACHMENT EXCESS L/D (ATT-9. 1)

GINNA STATION CONTROLLED COPY NUMBER -_ -

RESPONSIBL8;MNAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the steps necessary to mitigate a continuous control rod motion transient.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION are;
a. Unwarranted Control Rod motion, or
b. Annunciator C-22, ROD WITHDRAWAL BANK D HIGH 95%, lit, or
c. Annunciator F-16, TAVG - TREF DEVIATION +/- 5 0 F.
d. Annunciator C-7, INSERTION LIMIT BANK A LO, lit, or I
e. Annunciator C-8, INSERTION LIMIT BANK A LO-LO, lit, I or
f. Annunciator C-15, INSERTION LIMIT BANK B LO, lit, or I
g. Annunciator C-16, INSERTION LIMIT BANK B LO-LO, lit, I or I
h. Annunciator C-23, INSERTION LIMIT BANK C LO, lit, or I
i. Annunciator C-24, INSERTION LIMIT BANK C LO-LO, lit, I or I
j. Annunciator C-31, INSERTION LIMIT BANK D LO, lit, or I
k. Annunciator C-32, INSERTION LIMIT BANK D LO-LO, lit. I

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 1 Evaluate Rod Control System Operability:

a. Check turbine load - STABLE a. Go to Step 2.
b. Place Rods to MANUAL
c. Verify control rod motion stops c. Manually trip the reactor and go to E-O. REACTOR TRIP or SAFETY INJECTION.
  • * * * * . 4 * * ,
  • 4 4
  • 4 * * * * * * * * * * *
  • 4 4 * * * * * * . *. * *
  • CAUTION IF AN INSTRUMENT CHANNEL FAILURE IS INDICATED. ENSURE VALID INDICATIONS OF TAVG AND TREF ARE UTILIZED WHEN ADJUSTING CONTROL RODS AND/OR TURBINE LOAD.
  • * * * * * * * * * * *
  • a * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • 2 Monitor Tavg: Verify control rods responding in AUTO. IF NOT. THEN place rods to
  • Tavg - GREATER THAN 5450F MANUAL and adjust rods to restore
  • Tavg - LESS THAN 566 0F Tavg within limits.

IF Tavg is outside limits AND can NOT be controlled. THEN trip the reactor and go to E-Q. REACTOR TRIP OR SAFETY INJECTION.

3 Check Tavg - TRENDING TO Tref IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:

  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:
  • Reduce turbine load
  • Dilution of RCS

ACTION/EXPECTED RESPONSEINED 4 Check RCS Tavg Channel IF any Tavg channel malfunction is Indications: indicated. THEN refer to ER-INST.1.

REACTOR PROTECTION BISTABLE DEFEAT o All 4 channels indicate AFTER INSTRUMENTATION LOOP FAILURE.

approximately the same value o All 4 channels responding to the power change 5 Check Turbine 1st Stage IF PI-485 malfunction is indicated.

Pressure Channel, PI-485 - THEN refer to ER-INST.1. REACTOR APPROXIMATELY EQUAL TO PI-486 PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE.

6 Check NIS PR Indication: IF a NIS PR channel malfunction is indicated. THEN defeat affected o All PR total channel indicators channel (refer to ER-NIS.3, PR

- APPROXIMATELY EQUAL MALFUNCTION).

o All Al indicators -

APPROXIMATELY EQUAL

ACTION/EXPECTED RESPONSE P lRESPONSE NOT OBTAINEDI NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 7 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:
  • Reduce turbine load
  • Dilution of RCS
b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

This Step continued on the next page.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl (Step 7 continued from previous page)

d. Rod insertion limit alarms - d. Borate and withdraw control rods EXTINGUISHED to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
e. NIS PR AI - WITHIN +/- 5% OF e. Perform one or more of the TARGET VALUE following to restore Al to within limits:

. Borate RCS

a. Insert/withdraw control rods to MRPI transition
b. Verify MRPI indicates control b. Consult Plant Staff and ITS rod motion section 3.1 to determine operability of rod control system and go to Step 9.
c. Restore control rods to desired position

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 9 Establish Control Systems In Auto:

a. Verify rods in AUTO a. Place rods in AUTO, if desired.
b. Verify 431K in AUTO b. Place 431K in AUTO, if desired.
c. Verify PRZR spray valves in AUTO c. Place PRZR spray valves in AUTO.

if desired.

d. Verify PRZR heaters restored: d. Restore PRZR heaters. if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET IN AUTO

e. Verify one charging pump in AUTO e. Place one charging pump in AUTO.

if desired.

10 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to ITS section 3.1 for control rod operability requirements.

11 Notify Higher Supervision 12 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 1 of 10 GINNA STATION CONTROLLED COPY NUMBER C 3 co n RESPONSIBLd MANAGER EE-30-CI DAH-EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 2 of 10 A. PURPOSE - This procedure provides the steps necessary to continue plant operation while investigating an RCC/RPI malfunction.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of RCC/RPI MALFUNCTION are;
a. Power range NIS indicate a flux tilt, or
b. Group step counters for any individual bank are not within 1 step of each other, or
c. Incore flux map indicates abnormal flux tilt, or
d. Incore thermocouples indicate abnormal power tilt, or
e. Individual rods are not within +/- 12 steps of their respective step counters as indicated on MRPI, or
f. Annunciator C-5, PPCS ROD SEQUENCE OR ROD DEVIATION lit, or
g. Annunciator C-29, MRPI SYSTEM FAILURE, lit, or
h. Annunciator E-26, POWER RANGE CHANNEL DEV +/- 2%, lit, or
i. Annunciator F-29, PPCS AXIAL OR QUADRANT POWER TILT, lit.

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 3 of 10 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED 1 Place Rods To Manual

  • 4*. * * *- * * * * * * * * * * - -
  • 4 * * * * * * * - - * * -4 * -4 - * . 4 CAUTION o BANK ROD WITHDRAWAL SHOULD NOT BE PERFORMED UNTIL DIRECTED PER APPLICABLE RECOVERY PROCEDURE.

o UNTIL THE MRPI SYSTEM IS KNOWN TO BE AT FAULT. A ROD INDICATING GREATER THAN +/- 12 STEPS FROM ITS GROUP STEP COUNTER SHOULD BE CONSIDERED A MISALIGNED ROD.

  • * . * .* * .4 *
  • 4 * * *4 * * *4 .4 * *4 * * * * * * * * . 4* * * * . . 4 2 Check Dropped Rod Indication: IF the following conditions exist.

THEN go to AP-RCC.3. DROPPED ROD o Annunciator E-28. POWER RANGE RECOVERY.

ROD DROP ROD STOP 5%/5 SECONDS -

EXTINGUISHED o Reactor Power - decreasing o Annunciator C-14. ROD BOTTOM ROD o Tavg - decreasing STOP - EXTINGUISHED IF NOT. THEN go to Step 3.

3 Check Tavg - STABLE AT PROGRAM Perform the following:

a. Place EH control in MANUAL.
b. Manually adjust turbine load to match Tavg and Tref.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 4 Verify Annunciator G-15, Verify steam dump valves closed.

STEAM DUMP ARMED - IF NOT. THEN place STEAM DUMP MODE EXTINGUISHED SELECTOR switch to MANUAL and close valves.

5 Check Main Generator Load - IF load can NOT be stabilized above GREATER THAN 15 MW 15 MW. THEN trip the turbine and go to AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED.

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 5 of 10 ACTION/EXPECTED RESPONSE AINED NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 6 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref, THEN restore Tavg to Tref by RCS boration.

IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

  • Reduce turbine load
  • Dilution of RCS
b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and spray IF pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.
d. MFW Regulating Valves - d. Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected S/G(s) MFW regulating valve in MANUAL

2) Restore SIG level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

. EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 6 of 10 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 7 Check Control Rod Alignment:

a. Verify all rods in affected a. Refer to ITS Section 3.1.4.

group. - WITHIN +/- 12 STEPS OF ASSOCIATED GROUP STEP COUNTER NOTE: Step 8 is an attempt to determine whether a rod is misaligned or whether the MRPI System is malfunctioning.

8 Check QPTR - LESS THAN 1.02 IF QPTR greater than 1.02, THEN computer value should be verified using 0-6.4 to prevent action based on failed computer inputs.

NOTE: IF the MRPI CRT fails. THEN the PPCS can be used for rod position indication until the CRT is made operable. Rod position indication can be retrieved from the PPCS by selecting the "CBAW" display button.

9 Verify All Individual Rod Perform the following:

Position Indication Per Bank Operable: a. Refer to ITS section 3.1.7 for required action.

o MRPI system - NO MRPI SYSTEM ALARMS b. Consult Reactor Engineer and plant staff to evaluate MRPI.

o MRPI system - NO KNOWN PROBLEMS WITH MRPI SYSTEM THAT COULD c. Go to Step 11.

RENDER ROD POSITION INDICATION INOPERABLE

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 7 of 10 ACTION/EXPECTED RESPONSE I l RESPONSE NOT OBTAINED NOTE: The incore flux mapping system may aid in evaluating rod alignment depending on rod location.

10 Evaluate Control Rod Operability:

a. Verify less than two misaligned a. IF two or more rods are rods misaligned. THEN initiate plant shutdown. (Refer to 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN)

b. Direct I&C to locally investigate rod failure
c. Refer to ER-RCC.2. RESTORING A MISALIGNED RCC
d. Rod failure identified d. Perform the following:
1) Consult Reactor Engineer and ITS section 3.1.4 for operational concerns.
2) Return to step 2.
e. Rod failure corrected e. WHEN rod failure corrected. THEN continue with Step lOf.

IF rod failure can NOT be corrected at power. THEN go to ER-RCC.2, RESTORING A MISALIGNED RCC.

f. Restore misaligned rod (Refer to ER-RCC.2. RESTORING A MISALIGNED ROD)

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 8 of 10 ACTION/EXPECTED RESPONSEIREPNEOTBAND 11 Verify Affected Group Step Refer to ITS section 3.1.7 for Counters Operable: required actions.

a. Affected bank group step counter movement - CONSISTENT WITH MRPI TRANSITIONS (Evaluate affected bank using PT-1. ROD CONTROL SYSTEM)
b. Group step counters for affected bank - WITHIN 1 STEP OF EACH OTHER 12 Check Reactor Conditions:
a. Rod insertion limit alarms - a. Reduce load and borate and EXTINGUISHED withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
b. NIS PR AI - WITHIN +/- 5% OF b. Perform one or more of the TARGET VALUE following to restore AI to within limits:

. Restore control rods to desired position 13 Evaluate Plant Conditions:

a. Rod/MRPI malfunction - REPAIRED a. Return to Step 8.
b. Verify control rod operability - b. Refer to ITS section 3.1.4 and OPERABILITY RESTORED (Refer to consult plant staff for further PT-1, ROD CONTROL SYSTEM) guidance.

ESP:

AP-RCC.2 I

TITLE:

RCC/RPI MALFUNCTION REV: I1I

. .PAGE 9 of 10 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINEDl 14 Establish Control Systems In Auto

a. Verify 431K in AUTO a. Place 431K in AUTO. if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

e. Verify MFW regulating valves in e. Place MFW regulating valves in AUTO AUTO, if desired.
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
g. Verify annunciator G-15. STEAM g. WHEN Tavg within 5 0F of Tref, DUMP ARMED - EXTINGUISHED THEN perform the following:
1) Ensure-steam dump valves closed
2) Reset steam dump
h. Verify rods in AUTO h. Place rods in AUTO, if desired.

EOP: TITLE:

REV: 11 AP-RCC.2 RCC/RPI MALFUNCTION PAGE 10 of 10

_ STP _ CTIO/EXPCTE RESONSERESPNSENOT OBTAINED 15 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

16 Notify Higher Supervision 17 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 1 of 11 GINNA STATION CONTROLLED COPY NUMBER _ ___

RESPONSIBLE YANAGER 1 C DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOfP: TITLE:RE Ed~ilLE:REV:  : 117 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 2 of 11 A. PURPOSE - This procedure provides the instructions necessary to diagnose and to respond to a reactor coolant pump seal malfunction.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-3, STEAM GENERATOR TUBE RUPTURE, or
b. ES-1.1, SI TERMINATION, or
c. ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, or
d. ECA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, or
e. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or
f. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, or
g. ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED, or
h. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, or
i. FR-I.1, RESPONSE TO HIGH PRESSURIZER LEVEL, when RCP seal malfunction is indicated.
j. AR-A-7 (15), RCP A(B) CCW RETURN HIGH TEMP OR LOW FLOW, if other indications of seal malfunction exists.
2. SYMPTOMS - The symptoms of RCP SEAL MALFUNCTION are;
a. Annunciator A-8, RCP A SEAL WATER INLET HI TEMP 1500F, lit, or
b. Annunciator A-10, VCT PRESSURE 15 PSI 65, lit, or
c. Annunciator A-16, RCP B SEAL WATER INLET HI TEMP 1500F, lit, or Continued on next page

EOfP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 3 of 11

2. SYMPTOMS (cont)
d. Annunciator B-1(2), R('CP A(B) No. 1 SEAL OUT HI TEMP 2000F, lit, or,
e. Annunciator B-3(4), R(CP A(B) STAND PIPE HI LEVEL + 1 FT, lit, or
f. Annunciator B-9(10), ERCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or
g. Annunciator B-11(12), RCP A(B) STAND PIPE LO LEVEL -4 FT, lit, or
h. Annunciator B-17(18), RCP A(B) No.1 SEAL HI-LO FLOW 5.0 GPM 1.0 , lit, or
i. Annunciator B-21, RCP TEMP RECORDER, lit, or I
j. Annunciator B-25(26), RCP A(B) No. 1 SEAL LO DIFF PRESS 220 PSID, lit.

. EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 4 of 11 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl

  • * * *
  • 4 , * * * *
  • 4
  • 4 * * * . *
  • 4 * * *
  • 4 * * *
  • 4 4 4 * *
  • 4 * *
  • CAUTION IF ANY RCP IS SECURED BECAUSE OF A SEAL MALFUNCTION. IT SHOULD NOT BE RESTARTED UNTIL THE CAUSE OF THE MALFUNCTION HAS BEEN DETERMINED AND CORRECTED.

4 * *

  • 4
  • 4 4 4
  • 4 *
  • 4 * * *
  • 4
  • 4 * * * * * * * * * * * * * * *
  • 4 *
  • 4 NOTE: o If a Reactor trip is initiated while performing Step 1. transition to E-0 should occur while completing subsequent actions of the step.

o #2 Seal leak rate is total RCDT leak rate minus any known in-leakage to RCDT from another source.

o Total #1 Seal Flow is defined for each RCP as the sum of indicated

  1. 1 Seal Leakoff Flow and #2 seal leak rate to RCDT (PPCS Point ID L1003. 3.2 gal/% in the normal operating range).

1 Check Total #1 Seal Flow - IF a #1 Seal Failure is verified by LESS THAN 8.0 GPM FOR EACH RCP a decrease in Labyr Seal Diff Pressure OR increasing Seal Inlet/Outlet temps. THEN perform the following:

a. IF reactor trip breakers closed.

THEN trip the reactor.

b. WHEN all E-0 Immediate Actions done. THEN trip the affected RCP(s).
c. Allow 4 minutes for pump coast down. THEN close affected RCP(s) seal disch valve.
  • RCP A. AOV-270A
  • RCP B. AOV-270B
d. IF reactor trip was NOT required. THEN perform the following:
1) Initiate SDM verification per 0-3.1.
2) Go to step 4.

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 5 of 11 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 2 Check RCP Seal Return Valve Alignment:

a. RCP seal return isolation valve. a. Perform the following:

MOV-313 - OPEN

1) Ensure CI reset.
2) Ensure both trains of XY relays for RCP seal return isolation valve. MOV-313.

reset.

3) Open RCP seal return isolation valve. MOV-313.

IF MOV-313 can NOT be opened.

THEN dispatch AO to AUX BLDG with RWST area key to check valve and breaker locally (breaker MCC C position 13J).

b. Verify RCP seal disch valves - b. Manually open valves. IF valves OPEN can NOT be opened. THEN verify IA aligned to CNMT and go to
  • RCP A. AOV-270A Step 3.
  • RCP B. AOV-270B

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION

. PAGE 6 of 11 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 1 NOTE: o If a reactor trip is initiated while performing Step 3. transition to E-O should occur while completing subsequent actions of the step.

o The lower limit of 0.8 GPM limit for total #1 seal flow applies when the RCS is at normal operating pressure. Refer to FIG-4.0.

FIGURE RCP SEAL LEAKOFF and consult plant staff for guidance if the RCS is at reduced pressure.

3 Check RCP Seal Return Flow:

a. Total #1 Seal Flow - BETWEEN a. IF #1 Seal Inlet and Outlet 0.8 GPM AND 6.0 GPM FOR EACH RCP temperatures are increasing in an uncontrolled manner. THEN perform the following:
1) IF reactor trip breakers closed. THEN trip the reactor.
2) WHEN all E-0 Immediate Actions done, THEN trip the affected RCP(s).
3) Allow 4 minutes for pump coast down. THEN close affected RCP(s) seal disch valve.
  • RCP A. AOV-270A
  • RCP B. AOV-270B
4) IF reactor trip was NOT required. THEN initiate SDM verification per 0-3.1.

IF #1 Seal Inlet and Outlet temperatures are NOT increasing in an uncontrolled manner. THEN go to Step 4.

b. Go to Step 5.

rEOP: TITLE:

I REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 7 of 11 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Determine RCP Shutdown Requirements:

a. Each RCP Total #1 seal flow - a. Perform the following while

> 0.8 GPM continuing with this procedure:

1) IF Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner. THEN return to Step 1.
2) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

3) IF Total #1 seal flow increases to 2 0.8 GPM. THEN pump shutdown is NOT required. Stop the load reduction AND return to Step 1.
4) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b. Each RCP Total 1 1 seal flow - b. Perform the following while 6.0 gpm continuing with this procedure:
1) IF total #1 Seal flow from any RCP greater than 6.0 gpm.

THEN maintain seal injection flow rate of 9.0 GPM or greater to the affected RCP.

2) IF total #1 Seal flow from any RCP exceeds 8.0 GPM OR Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner'. THEN return to Step 1.
3) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

4) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

EDP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 8 of 11 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: ATT-15.1. ATTACHMENT RCP DIAGNOSTICS may be used to aid in diagnosis.

5 Check RCP Cooling: Perform the following:

o Annunciator A-7. RCP A CCW a. Verify RCP CCW supply and return RETURN HIGH TEMP OR LOW FLOW - valves open.

EXTINGUISHED a RCP A. MOV-749A and MOV-759A o Annunciator A-15. RCP B CCW

  • RCP B. MOV-749B and MOV-759B RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED b. Ensure open CCW outlet valves from RCP thermal barriers.

  • RCP A. AOV-754A
  • RCP B. AOV-754B 6 Check RCP #2 Seal Indications: IF affected RCP #1 seal leakoff flow decreasing. THEN failure of #2 o Annunciator B-3, RCP A STANDPIPE seal may be indicated.

HI LEVEL +1 FT - EXTINGUISHED Check RCP #2 seal leak rate to RCDT o Annunciator B-4. RCP B STANDPIPE (PPCS Point ID L1003. 3.2 gal/% in HI LEVEL +1 FT - EXTINGUISHED the normal operating range).

a. IF RCP #2 seal leak rate to RCDT is < 1.1 gpm, THEN continue plant operation while closely monitoring RCP seal indications.
b. IF RCP #2 seal leak rate to RCDT is greater than 1.1 gpm. THEN perform the following:
1) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

2) Secure the affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

EDP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 9 of 11

  • 4
  • 4 *
  • 4 4 *
  • 4 4 * * *
  • 4 4
  • 4
  • 4 * * * * * * * * * * * * * * * * * *
  • CAUTION REDUCING CHARGING FLOW WILL RESULT IN INCREASING REGEN HX OUTLET TEMPERATURE.
  • 4 4 4 4 4 4 4 4 4
  • 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4
  • 4
  • 4 4 4
  • 4 4
  • 4
  • 4
  • 4 7 Check RCP Labyrinth Seal D/Ps Perform the following:

- GREATER THAN 15 INCHES OF WATER a. Ensure open CCW outlet valves from RCP thermal barriers.

  • RCP A. AOV-754A
  • RCP B. AOV-754B
b. Verify seal injection flow greater than 5 GPM for affected RCP.
c. Adjust HCV-142 to obtain at least 15 inches labyrinth seal AP.
d. Dispatch AO to check seal injection filter D/P.
e. Check CCW surge tank level stable. IF level increasing.

THEN go to AP-CCW.1. LEAKAGE INTO THE COMPONENT COOLING LOOP.

8 Check RCP #3 Seal Indications: Check CNMT radiation monitors normal.

o Annunciator B-il. RCP A STAND PIPE LO LEVEL -4FT - EXTINGUISHED . R-l1

  • R-12 o Annunciator B-12. RCP B STAND PIPE LO LEVEL -4FT - EXTINGUISHED IF RCP standpipe level low and CNMT radiation increasing. THEN W 3 seal leakage increase is probable.

Continue plant operation while closely monitoring RCP seal indications.

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 10 of 11 NOTE: In the absence of other seal failure indications, an elevated #1 seal outlet temperature may indicate pump bearing damage.

  • 9 Monitor.RCP Seal Conditions:
a. RCP total #1 seal flow for each a. IF affected RCP running. THEN RCP return to Step 1. IF NOT. THEN perform the following:

o Total #1 seal flow - LESS THAN 6.0 GPM 1) Monitor affected RCP (Refer to ATT-15.1, ATTACHMENT RCP o Total #1 seal flow - GREATER DIAGNOSTICS).

THAN 0.8 GPM

2) Consult Plant Staff to determine if cooldown required.
b. RCP #1 Seal Leakoff Flow - b. Perform the following:

WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0. FIGURE RCP o Ensure seal injection flow SEAL LEAKOFF exceeds #1 seal leakoff flow.

o Refer to S-2.1. Reactor Coolant Pump Operation.

o Consult plant staff for further instructions.

c. RCP W1 seal outlet temperatures c. IF pump bearing damage is

- LESS THAN 2150 AND STABLE suspected. THEN notify plant staff and expedite shutdown of the affected RCP. IF NOT. THEN return to Step 1.

d. RCS leakage - NORMAL (Refer to d. Perform the following:

leakage surveillance sheet)

1) Calculate RCS leakrate.
2) Refer to ITS section 3.4.13.

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 11 of 11 ACTION/EXPECTED RESPONSENOT OBTAINED 10 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

11 Notify Higher Supervision

-END-

EOP: TITLE:

REV: 17 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 1 of 1 AP-RCP.1 APPENDIX LIST TITLE

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)
2) ATTACHMENT RCP DIAGNOSTICS (ATT-15.1)

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 1 of 13 GINNA STATION CONTROLLED COPY NUMBER ___

RESPONSIB W MANAGER EF-3ECTVoo E EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 2 of 13 A. PURPOSE - This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated.
b. AP-CVCS.1, CVCS LEAK, when leak cannot be isolated.
c. Any of several APs when PRZR level can not be controlled.
d. AR-RMS-2, R2 CONTAINMENT, if other CNMT rod monitors increasing, or I
e. AR-RMS-7, R7 INCORE DETECTION AREA, if other CNMT rod I monitors increasing, or
f. AR-RMS-1OA, R10A CNMT IODINE, if R-11, R-12 increasing, I or I
g. AR-RMS-11, R11 CNMT PARTICULATE MON, if RCS leak is I suspected, or
h. AR-RMS-12, R12 CNMT GAS, if RCS leak is suspected, or I
i. AR-C-18, CONTAINMENT SUMP A PUMP AUTO START, if RCS leak I is suspected, or I
j. AR-C-19, CONTAINMENT SUMP A HI LEVEL, if RCS leak is l suspected, or I
k. AR-C-20, CONTAINMENT SUMP B HI LEVEL, if RCS leak is I suspected. I
2. SYMPTOMS - The symptoms of REACTOR COOLANT LEAK are;
a. Annunciator A-2, VCT LEVEL 14% 86, lit, or
b. Annunciator B-27, RCS LOOP A LO FLOW CHANNEL ALERT, I lit, or I
c. Annunciator B-28, RCS LOOP B LO FLOW CHANNEL ALERT, l lit, or I

EOP: TITLE: REV: 17 AP-RCS.1 REACTOR COOLANT LEAK

. . .PAGE 3 of 13

d. Annunciator F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5, lit, or
e. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or
f. Annunciator F-l, PRESSURIZER LO LEVEL 13%, lit. or
g. Annunciator F-14, CHARGING PUMP SPEED, lit.

EOP: TITLE: REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 4 of 13 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED]

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

  • 1 Monitor.PRZR Level - STABLE IF PRZR level decreasing. THEN AT PROGRAM LEVEL start additional charging pumps and increase speed to increase PRZR level to program.

IF PRZR level continues to decrease. THEN close letdown isolation AOV-427 AND excess letdown AOV-310.

IF available charging pumps are running at maximum speed with letdown isolated. AND PRZR level is decreasing. THEN trip the reactor and go to E-0. REACTOR TRIP or SAFETY INJECTION.

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 5 of 13 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may require a load reduction.

2 Check VCT Makeup System:

a. Verify VCT level - GREATER THAN a. Perform the following:

5%

1) Ensure charging pump suction aligned to RWST.
  • LCV-112B - OPEN
  • LCV-112C - CLOSED
2) Go to Step 3.
b. Ensure the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
c. Check VCT level: c. Perform the following:

o Level GREATER THAN 20% 1) Ensure letdown divert valve.

LCV-112A. closed.

-OR-

2) Manually increase VCT makeup o Level - STABLE OR INCREASING flow as follows:

a) Ensure BA transfer pumps and RMW pumps running.

b) Adjust RMW flow control valve. HCV-111. to increase RMW flow.

c) Adjust boric acid flow to maintain required concentration.

IF VCT level can NOT be maintained. THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION, if necessary.

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 6 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: IF leakage is indicated in CNMT.

THEN perform the following:

o Check CNMT radiation monitors -

NORMAL a. Direct RP to sample CNMT for entry.

. R-2

  • R-7 b. Continue with Step 4. WHEN CNMT
  • R-1OA cleared for entry, THEN dispatch
  • R-l1 personnel to investigate CNMT
  • R-12 for RCS leakage.

o CNMT sump A pump run frequency -

NORMAL (Refer to RCS Daily Leakage Log)

  • * * * * * * * * * * * * * * * * * * * * * *
  • a* . a *
  • a * * * * * * * * *
  • CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.
  • * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * - * * * *
  • a *
  • 4 Dispatch AO To AUX BLDG To Investigate For CVCS Leak (locked area keys required) 5 Check For Leak To CCW System: Go to AP-CCW.1. LEAKAGE INTO THE COMPONENT COOLING LOOP.

o CCW surge tank level -

APPROXIMATELY 50% AND STABLE o CCW radiation monitor, R NORMAL Ix

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions:

a. Normal letdown - IN SERVICE a. Perform the following:
1) IF excess letdown in service, THEN check excess letdown heat exchanger outlet temperature and pressure -

NORMAL.

IF pressure and/or temperature abnormal. THEN isolate excess letdown:

a) Close excess letdown HCV-123.

b) Close excess letdown AOV-310.

2) Go to Step 6c.
b. Letdown indication: b. Go to AP-CVCS.1. CVCS LEAK.

o Letdown flow - APPROXIMATELY 40 GPM (60 GPM IF AOV-202 OPEN) o Low pressure LTDN pressure -

APPROXIMATELY 250 PSIG o Letdown pressure control valve. PCV-135. demand -

APPROXIMATELY 35% OPEN (40%

OPEN IF AOV-202 OPEN)

This Step continued on the next page.

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 8 of 13 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED (Step 6 continued from previous page)

c. Charging indication: c. Go to AP-CVCS.1. CVCS LEAK.

o Seal injection flows -

GREATER THAN 6 GPM AND STABLE o RCP Labyrinth seal D/Ps -

GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure - GREATER THAN RCS PRESSURE

d. AUX BLDG radiation levels - d. Go to AP-CVCS.1. CVCS LEAK and NORMAL refer to CVCS piping diagrams for further guidance.
  • R-4
  • R-9
  • R-1OB
  • R-13

. R-14 7 Check PRT Indications: Check tailpipe and valve leakoff temperatures for the PRZR safety

a. Level - BETWEEN 61% AND 84% valves and PORVs for indication of leakage.
b. Pressure - APPROXIMATELY 1.5 PSIG AND STABLE IF no PORV or safety valve leakage is indicated. THEN check other leak
c. Temperature - AT CNMT AMBIENT paths from the RCS to the PRT.

TEMPERATURE AND STABLE

  • Letdown relief valve. RV-203
  • Seal return relief valve. RV-314

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK

. PAGE 9 of 13 ACTION/EXPECTED RESPONSE SP lRESPONSE NOT OBTAINED I 8 Check SIGs For Leakage: IF SIG tube leak indicated, THEN go to AP-SG.1. STEAM GENERATOR TUBE o Air ejector radiation monitors - LEAK.

NORMAL

  • R-15
  • R-15A o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors -

NORMAL

  • R-31
  • R-32 o S/G sample activity - NORMAL (Check with RP Department for normal) 9 Check SI Accumulator Levels - Calculate inleakage to SI STABLE accumulators (Refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS).

10 Check RCP Seal Leakoff Flows: Go to AP-RCP.1. RCP SEAL MALFUNCTION.

o Leakoff flows - WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF o Leakoff flows - STABLE

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 10 of 13 STE P ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED 11 Check RCDT Leak Rate - NORMAL Check other sources of in leakage (Refer to RCS Daily Leakage to RCDT:

Log and PPCS point ID L1003)

a. IF Rx vessel flange leakoff temperature has increased. THEN close Rx VESS FLANGE SEAL LEAKOFF VLV. AOV-521.
b. Verify excess letdown isolated.

IF NOT, THEN ensure RCDT divert valve. AOV-312, in the VCT position.

c. IF source of leakage NOT determined. THEN suspect loop drains.

12 Check Valve Leakoff IF any valve leakoff temperature is Temperatures - NORMAL (Refer abnormally high. THEN initiate to Pressurizer Valve Leak-Off investigation of that leakage path.

Temperature Record Log) 13 Check Normal Or Excess IF normal letdown desired, THEN Letdown - IN SERVICE establish normal letdown (refer to ATT-9.O. ATTACHMENT LETDOWN)

IF normal letdown NOT available.

THEN establish excess letdown. if desired (refer to ATT-9.1.

ATTACHMENT EXCESS L/D).

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 11 of 13 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 14 Establish Stable Plant Conditions:

a. PRZR level - TRENDING TO PROGRAM a. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.
b. Check PRZR pressure - TRENDING b. Control PRZR pressure by one of TO 2235 PSIG IN AUTO the following:

. 431K in MANUAL

  • Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

15 Establish Control Systems In Auto

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters. if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

EOP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 12 of 13 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 16 Evaluate MCB Annunciator Status (Refer to AR Procedures) 17 Evaluate RCS Leakage:

a. Leakage within limits (Refer to a. IF leak NOT isolable. but PRZR leakage surveillance sheet and level and seal injection can be ITS section 3.4.13) maintained. THEN shut the plant down (Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5. RAPID LOAD REDUCTION).
b. Leak location identified b. Return to Step 1.

NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION. for reporting requirements.

18 Notify Higher Supervision

-END-

EoP: TITLE:

REV: 17 AP-RCS.1 REACTOR COOLANT LEAK PAGE 13 of 13 AP-RCS.1 APPENDIX LIST TITLE

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)
2) ATTACHMENT LETDOWN (ATT-9.0)
3) ATTACHMENT EXCESS L/D (ATT-9.1)

EOP: TITLE:

REV: 12 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW PAGE 1 of 3 GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLS MANAGER 6 _o24 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 12 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW PAGE 2 of 3 A. PURPOSE - This procedure provides actions required to stabilize plant conditions following a loss of reactor coolant flow.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of LOSS OF REACTOR COOLANT FLOW are;
a. Low RCS flow indicated on either or both loops and verified by more than one indication, or
b. Steam flow rapidly decreasing in one loop and rapidly increasing in the other loop.
c. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
d. Annunciator B-27, (28), RCS LOOP A(B) LO FLOW CHANNEL ALERT, lit, or
e. Annunciator B-29, RCP BREAKER CHANNEL ALERT, lit, or
f. Annunciator F-24, RCS AVG DT DEVIATION 30 F, lit I

EOP: TITLE:

REV: 12 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW

. PAGE 3 of 3 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED 1 Check RCS flows:

a. Verify two loops operating: a. Perform the following:

o Both RCPs running 1) IF reactor trip breakers closed, THEN trip the reactor o Flow greater than 91% in both and go to E-O. REACTOR TRIP loops OR SAFETY INJECTION.

2) IF reactor trip breakers open AND no RCPs running. THEN verify natural circulation per ATT-13.0. ATTACHMENT NC.

Go to Step 2.

b. Return to procedure and step in effect 2 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION. for reporting requirements.

3 Notify Higher Supervision 4 Return To Procedure Or Guidance In Effect

-END-

EOP: TITLE:

REV: 12 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW PAGE 1 of 1 AP-RCS.2 APPENDIX LIST TITLE

1) ATTACHMENT NC (ATT-13.0)

EOP: TITLE:. Ed: lREV: R V 11 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 1 of 4 GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLEt MANAGER EFC3I-20VDA EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 11 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 2 of 4 A. PURPOSE - This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. AR-RMS-9, R9 LETDOWN LINE MONITOR, at entry.
2. SYMPTOMS - The symptoms of HIGH REACTOR COOLANT ACTIVITY are;
a. Unexplained increase in letdown line monitor, R-9, or
b. Sampling indicates I-131 equivalent GREATER THAN

.64 pCi/gm at 40 gpm letdown or GREATER THAN

.46 pCi/gm at 60 gpm letdown or

c. Sampling indicates gross degassed activity GREATER THAN 20 pCi/gm, or
d. Sampling indicates that total specific activity exceeds 100/E.

EOP: TITLE:

REV: 1).

AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 3 of 4 NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

1 Verify RCS Activity:

a. Direct RP Tech to sample RCS for activity
b. RCS activity - GREATER THAN b. IF normal activity verified.

NORMAL THEN return to procedure or guidance in effect.

2 Increase Letdown Flow To 60 GPM (Refer to S-3.2P, SWAPPING CVCS LETDOWN ORIFICE VALVES) 3 Check Letdown Line Monitor, Evaluate conditions to determine R LESS THAN 200 MR/HR whether local radiation emergency ABOVE BACKGROUND exists (Refer to EPIP 1-13. LOCAL RADIATION EMERGENCY).

  • * * * * .
  • 4*. * * * * * * * * * * . * * * * * * * * * * * * * * * * * * * *
  • CAUTION PLACING A NEW DI IN SERVICE MAY RESULT IN A POSITIVE OR NEGATIVE REACTIVITY ADDITION DUE TO A BORON CHANGE.
  • * * *
  • 4 4 * * * * * *
  • 4 4 4 4 * *
  • 4 4 4
  • 4 4 4 *
  • 4 * * *
  • 4 *
  • 4 4
  • 4 Direct RP Tech To Sample IF DI efficiency is NOT acceptable.

Letdown DI Efficiency - THEN place a-new mixed bed in DECONTAMINATION FACTOR service (Refer to S-3.2B. PLACING A GREATER THAN 10 MIXED BED DEMINERALIZER IN SERVICE

- BORON CONCENTRATION DIFFERENT THAN RCS).

EOP: TITLE:

REV: 11 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 4 of 4 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 5 Evaluate AUX BLDG Radiation Levels:

a. Direct RP Tech to survey AUX BLDG
b. Check AUX BLDG radiation b. Perform the following:

monitors - NORMAL

1) Direct RP Tech to survey AUX v R-4 BLDG areas as necessary.
  • R-9
  • R-1OB 2) Evaluate conditions to

. R-13 determine whether local

  • R-14 radiation emergency exists (Refer to EPIP 1-13. LOCAL RADIATION EMERGENCY).

6 Evaluate MCB Annunciator Status (Refer to AR Procedures) 7 Determine If Plant Operation IF plant shutdown is required. THEN Can Continue (Consult Plant refer to 0-2.1. NORMAL SHUTDOWN TO staff if necessary) - HOT SHUTDOWN.

OPERATION CAN CONTINUE

. RP Supervision

. Chemistry Supervision

  • Reactor Engineer NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

8 Notify Higher Supervision

-END-

GINNA STATION CONTROLLED COPY NUMBER I'd RESPONSIBq MANAGER 6 6&66Y+

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, R1OA CNMT IODINE, if R-l1, R-12 increasing,l 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 RESPONSE STEP lRESPONSE NOT OBTAINED 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: Perform the following:

o RCS subcooling based on core a. Stop RHR pumps and place in PULL exit T/Cs - GREATER THAN 00F STOP.

FIG-1.0. FIGURE MIN SUBCOOLING

b. Close RHR discharge valves to SI o PRZR level - GREATER THAN 5% pump suction

[30% adverse CNMT]

  • 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.
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

ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED 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 00 F USING FIG-1.0. FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%

[30% adverse CNMT]

o PRZR level - STABLE OR INCREASING

b. Verify charging flow needed to b. Go to Step 7.

maintain PRZR level stable -

LESS THAN 75 gpm (PPCS point FCHG)

c. Go to AP-RCS.1. REACTOR COOLANT LEAK
  • *
  • 4 4 4 *
  • 4 4
  • 4 4 * * * * *
  • 4 * * * * * * * * * * * * * * * * * * * *
  • 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 14.

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

5 Verify SI Injection Capability:

a. Check RCS temperature - LESS a. Perform the following:

THAN 3500 F

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 b. Manually open valves. Dispatch

- OPEN AO to locally restore power to the following if necessary

  • SI pump A. MOV-878A and (locked valve key required):

MOV-878B

  • SI pump B. MOV-878C and
  • MOV-878A. MCC C position 8C MOV-878D
  • MOV-878B. MCC D position 8C
  • MOV-878C. MCC C position 8F
  • MOV-878D. MCC D position 8F
c. SI pumps - AT LEAST TWO PUMPS c. Dispatch AO to restore power to AVAILABLE 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

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

a. Verify the following valves - a. Manually open 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 b. Ensure at least one SI pump RWST: suction valve from RWST open.

. MOV-825A . MOV-825A

. MOV-825B

  • 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

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDI 8 Establish Required CNMT Conditions:

a. Depress MANUAL CNMT ISOLATION pushbutton
b. Verify CI/CVI valves - CLOSED b. Manually close CI and CVI valves. IF valves can NOT be verified closed by MCB indication. THEN dispatch AO to locally close valves (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 a. Go to Step 10.
b. Check RCP #1 seal D/P - GREATER b. Stop affected RCP(s) and go to THAN 220 PSID Step 9d.
c. Check RCP #1 seal leakoff - c. IF RCP #1 seal failure is WITHIN THE NORMAL OPERATING suspected, THEN stop affected RANGE OF FIG-4.0, FIGURE RCP RCP(s).

SEAL LEAKOFF

d. Ensure PRZR spray valves - CLOSED
  • PCV-431A
  • PCV-431B

ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 10 Check RHR Pump Status:

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

mode:.

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

ACTION/EXPECTED RESPONSE SP RESPONSE NOT 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: b. Ensure at least one suction valve and one discharge valve o RHR suction valves from loop closed.

A hot leg (MOV-700 and MOV-701) - 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 1) Close MOV-850A and MOV-850B.

(outside CNMT) - CLOSED Do NOT continue until valves closed.

2) MOV-851A and MOV-851B (inside 2) Open MOV-851A and MOV-851B.

CNMT) - OPEN

d. Verify open RHR pump suction d. Manually open valves.

valves (MOV-704A and MOV-704B)

e. Check RHR pump suction e. Go to Step 13.

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)

ACTIN/EPECED ESPOSE l ESPNSENOT OBTAINED I 12 Check If RHR Injection Flow Required:

a. RCS subcooling based on core a. Perform the following:

exit T/Cs - GREATER THAN 00F USING FIG-1.0. FIGURE MIN 1) Open RHR core deluge valves SUBCOOLING

  • MOV-852A
  • MOV-852B
2) Start one RHR pump.

13 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE a. IF PRZR level greater than 5%

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

IF NOT. THEN start to SI pumps to restore PRZR level to greater than 5% [30% adverse CNMT] and stable or increasing and go to Step 14.

b. Check RVLIS indication: b. Start SI pump(s) to restore RVLIS level (no RCPs) or fluid o Level (no RCPs) - GREATER fraction (any RCP running) and THAN 77% [82% adverse CNMTI go to Step 14.

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

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

STE P ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check RCS Hot Leg Control steam dump (or ARVs) and Temperatures - STABLE 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 b. Attempt to identify and isolate leakage to AUX BLDG (Refer to
  • Plant vent particulate (R-13)

. Plant vent gas (R-14)

. CCW liquid monitor (R-17)

  • CHG pump room (R-4)
c. Direct RP to obtain the following samples:
d. Evaluate and operate equipment as necessary:

. CCW pumps

  • SW pumps I
  • Charging pumps
  • Steam dump/ARVs
  • VCT makeup system

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 - a. Manually start pumps as power RUNNING supply permits (257 kw each).
b. SW header pressure - GREATER b. Manually align valves to restore THAN 40 PSIG IN EACH LOOP SW pressure greater than 40 psig in each loop. (Refer to AP-SW.2, LOSS OF SERVICE WATER)

ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED 19 Establish IA To CNMT:

a. Verify non-safeguards busses a. Restore IA supply as follows:

energized from offsite power

1) IF electric air compressor is o Bus 13 normal feed - CLOSED desired. THEN perform the following:

-OR-a) Close non-safeguards bus o Bus 15 normal feed - CLOSED tie breakers:

  • Bus 13 to Bus 14 tie e 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 b. Manually align valves.

isolation valves - OPEN

  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664 This Step continued on the next page.

EOP: TITLE: REV: 15 AP-RCS.4 SHUTDOWN LOCA PAGE 15 of 35 (Step 19SPONS cotNOT N/XPECTE OBTAINEDp (Step 19 continued from previous page)

c. Verify adequate air c. Manually start air compressors compressor(s) - RUNNING 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: d. Perform the following:

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

o Pressure - STABLE OR INCREASING 2) Continue with Step 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 - a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
  • MOV-515. MCC D position 6C
  • MOV-516. MCC C position 6C
b. Block valves - AT LEAST ONE OPEN b. Open one block valve unless it was closed to isolate an open PORV.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

  • * * *
  • A *
  • 4 4 4 * * * *
  • 4
  • 4 4 4
  • 4 4 4 4
  • 4 4 A 4 4
  • 4
  • 4 4
  • 4 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.
  • Monitor
  • RZR*ORV* * * * * * * * * * * * * * * * *
  • 4 * * * * * * * * *
  • 21 Monitor PRZR PORV Status:
a. Check Reactor Vessel a. Go to Step 21d.

overpressure protection system -

IN SERVICE

b. Check RCS pressure - LESS THAN b. Verify at least one PRZR PORV 410 PSIG 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 d. Verify at least one PRZR PORV 2335 PSIG open. Continue with Step 22.

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

e. Verify PRZR PORVs - CLOSED e. Manually close PORVs. IF any PORV can NOT be closed. THEN manually close its block valve.

ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 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.

  • * * * * , * * * *
  • a * * * * * * * * * * * * * * * . * * * * * * * * * * * * *
  • 22 Monitor If RHR Pumps Should Be Stopped:
a. RHR Pump running in injection a. Go to Step 23.

mode

b. Check RCS pressure: 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

ACTON/XPETED ESPNSEl l ESPNSENOT OBTAINED I 4 * * * * * * * * *

  • 4 *
  • 4 * * * * * * * * * * * *
  • 4 4 * * *
  • 4 * * *
  • 4
  • 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).

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

23 Monitor SIG Levels:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 17% [25%

adverse CNMT] in at least one S/G.

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

[25% adverse CNMT] and 50% feed to that S/G.

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

a. Check the following: a. Go to Step 25.

o RCS cold leg temperature -

LESS THAN 3500F o RCS pressure - LESS THAN 400 psig [300 psig adverse CNMT1

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

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 25 Check core exit T/Cs - Go to Step 27.

GREATER THAN 2000F 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 1001F/HR
b. Use RHR system if in service
c. Dump steam to condenser from S/Gs c. Manually or locally dump steam using S/G ARVs.

27 Check RCS Subcooling Based On Go to Step 46.

Core Exit T/Cs - GREATER THAN 0F USING FIG-1.0, FIGURE MIN SUBCOOLING 28 Check If SI In Service: Go to Step 38.

o SI pumps - ANY RUNNING

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

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 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 Go to Step 32.

13% [40% adverse CNMT]

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

. * *

  • i * * * * * * * - 4 *
  • 4 * *
  • 4* - - *
  • 4 * * * - - 4 * -* 4 * . *
  • 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 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. PRZR level - GREATER THAN 13% b. Continue with Step 32. WHEN

[40% adverse CNMT] level greater than 13% [40%

adverse CNMT], THEN do Step 31c.

c. Stop RCS depressurization

ACTION/EXPECTED RESPONSE llRESPONSE SP 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 b. Go to Step 46.

exit T/Cs - GREATER THAN 0F USING FIG-1.O. FIGURE MIN SUBCOOLING

c. PRZR level - GREATER THAN 13% c. Return to Step 30.

[40% adverse CNMT]

d. Try to start an RCP d. IF an RCP can NOT be started.

THEN perform the following:

1) Establish conditions for starting an RCP 1) Ensure at least one control rod shroud fan running a) Bus 11A or 11B energized (45 kw).

b) Refer to ATT-15.0. 2) Ensure one Rx compartment ATTACHMENT RCP START cooling fan running (23 kw).

2) Start one RCP

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Check RCS Cold Leg Go to Step 37.

Temperature - GREATER THAN 2850F

  • * *
  • 4* . 4 * * * * * * * *, *
  • 4
  • 4 * * * *
  • 4 * *
  • 4
  • 4 * * * * * *
  • CAUTION IF RHR PUMP SUCTION TEMPERATURE IS GREATER THAN 2500F (PPCS POINT ID T0684A OR T0684B). THEN CONSULT TSC BEFORE STARTING AN RHR PUMP.
  • C h *k 4 *P u * *
  • u * * * * * * * *
  • 4 * * * * * * * * * * * * * * * *
  • 34 Check SI Pump Status:
a. Three SI pumps - RUNNING a. Go to Step 35.
b. RCS subcooling Based on core b. IF RCS hot leg temperature exit T/Cs - GREATER THAN 350 F greater than 3201F [3101F

[900F adverse CNMT] using adverse CNMT] OR IF RHR normal FIG-1.0, FIGURE MIN SUBCOOLING cooling in service, THEN go to Step 46.

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

[3100F 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 34c. IF no RHR pump can be operated in injection mode.

THEN go to Step 46.

c. PRZR level - GREATER THAN 13% c. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

d. Stop one SI pump

35 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 36.
b. Determine required RCS subcooling from table Charging Pump RCS Subcooling Criteria Availability NONE 120'F [200'F adverse CNMT]

ONE 115'F [190lF adverse CNMT]

TWO 105'F [1801F adverse CNMT]

THREE 100'F [1750F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperature exit T/Cs - GREATER THAN VALUE greater than 320'F [310'F FROM TABLE ABOVE USING FIG-1.0. adverse CNMT] OR IF RHR normal FIGURE MIN SUBCOOLING cooling in service. THEN go to Step 46.

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

[3100F adverse CNMTJ. AND RHR pump suction temperature less than 2501F. 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 13% d. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

e. Stop one SI pump K

STEP ACTION/EXPECTED RESPONSEREPSENTOAID 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 255 0F [2950F adverse CNMT]

TWO 235 0F [2850F adverse CNMT]

THREE 210'F [2700F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperature exit T/Cs - GREATER THAN greater than 320'F [3100F REQUIRED SUBCOOLING USING adverse CNMTI OR IF RHR normal FIG-1.0. FIGURE MIN SUBCOOLING cooling in service, THEN go to Step 46.

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

[3100F adverse CNMT]. AND RHR pump suction temperature less than 250 0F. 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 13% d. DO NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

e. Stop SI pump
f. Go to Step 38

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

a. Any SI pump - RUNNING a. Go to Step 38.
b. RCS pressure - GREATER THAN b. Go to Step 46.

295 psig [510 psig adverse CNMT]

c. PRZR level - GREATER THAN 13% c. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 31.

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 a. Start charging pumps and control INJECTION MODE charging flow to maintain PRZR level and go to Step 39.
b. Go to Step 46.

EOP: TITLE: REV 15 AP-RCS.4 SHUTDOWN LOCA PAGE 26 of 35 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 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 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

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED CAUTION DEPRESSURIZING THE RCS MAY RESULT IN LOSING THE MINIMAL RCP #1 SEAL OPERATING CONDITIONS. THIS WILL REQUIRE THE RCPS TO BE TRIPPED.

  • 4 * - . * - - - * * - - * -4 * *4 4 * * * -* - - - - * - - * - * - - - .

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 100 F USING FIG-1.0. FIGURE MIN SUBCOOLING

d. Stop RCS depressurization

ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 41 Verify Adequate Shutdown Margin

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

GREATER THAN REQUIREMENTS OF FIG-2.0, FIGURE SDM 42 Check If Letdown Can Be Established:

a. PRZR level - GREATER THAN 13% a. Go to Step 46.

[40% adverse CNMT]

b. Charging flow - LESS THAN 20 GPM b. Go to Step 46.

43 Establish Normal Letdown IF RCP seal return has been (Refer to ATT-9.0, ATTACHMENT established. THEN establish excess LETDOWN) 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.

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: d. Manually increase VCT makeup flow as follows:

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running. IF NOT.

THEN reset MCC C and MCC D UV o Level - STABLE OR INCREASING lockouts.

2) Place RMW flow control valve HCV-111 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 Suction Aligned To VCT:

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: a. Perform the following:

o RCS subcooling based on core 1) Manually operate SI pumps to exit T/Cs - GREATER THAN 0F restore inventory and/or USING FIG-1.0. FIGURE MIN subcooling. DO NOT operate SUBCOOLING more than two SI pumps.

o PRZR level - GREATER THAN 5% 2) Go to Step 47.

[30% adverse CNMT]

b. Go to Step 48

ACTION/EXPECTED RESPONSEINED 47 Verify Adequate SI Flow:

a. Check RVLIS - AVAILABLE a. IF PRZR level greater than 5%

[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 5% [30% adverse CNMT] and stable or increasing and go to Step 48.

b. Check RVLIS indication: b. Start SI pumps as necessary to restore RVLIS level (no RCPs) or o Level (no RCPs) - GREATER fluid fraction (any RCP running)

THAN 77% [82% adverse CNMT] and go to Step 48.

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

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

48 Check If Emergency D/Gs Should Be Stopped:

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

o Emergency D/G output breakers

- OPEN o AC emergency bus voltage -

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

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

ACTIN/EPECTD RSPONE lRESPNSENOTOBTAINED 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

EOP~: TITLE: REV: 15 AP-RCS.4 -SHUTDOWN LOCA PAGE 33 of 35 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 50 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D - a. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).
b. Verify RCP #1 seal outlet b. Go to Step 51.

temperature - LESS THAN 2350F

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 e. Perform the following:

valve MOV-313

1) Place MOV-313 switch to open.
2) Dispatch AO to locally open MOV-313.
f. Verify RCP #1 seal leakoff flow f. Perform the following:

- LESS THAN 6.0 GPM

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 g. Refer to AP-RCP.l. RCP SEAL

- GREATER THAN 0.8 GPM MALFUNCTION.

SP ACTION/EXPECTED RESPONSE llRESPONSE 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 3500 F 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)
c. Consult plant staff to determine if RHR normal cooling should be established using ATT-14.1.

ATTACHMENT RHR COOL

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 TITLE

1) FIGURE MIN SUBCOOLING (FIG-1.0)
2) FIGURE SDM (FIG-2.0)
3) FIGURE RCP SEAL LEAKOFF (FIG-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)

TITLE:

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 1 of 17 GINNA STATION CONTROLLED COPY NUMBER _

RESPONSIBL NAGER

&-36 -A-c)

EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 2 of 17 A. PURPOSE - This procedure provides guidance necessary for maintaining core cooling and protecting the reactor core in the event that RHR cooling is lost during RCS reduced inventory operation, (i.e., at indicated Loop Levels of less than 64 inches with fuel in the vessel).

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The following symptoms are indicative of LOSS OF RHR AT RCS REDUCED INVENTORY CONDITIONS:
a. No RHR pumps running, or
b. Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode) lit, or
c. Unexpected increase in RCS temperature while on RHR cooling at low loop levels, or
d. Erratic or no flow on FI-626, or
e. Annunciator J-9, SAFEGUARD BREAKER TRIP, lit. I

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 3 of'17 ACTON/XPE TED RESONSAIE I

  • * * * * * * * * * * * * *
  • 4 * *
  • 4 4 * * * * *
  • 4 *
  • 4
  • 4 * *
  • 4 * * *
  • CAUTION o CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATIONS.

o SHOULD CORE BOILING OCCUR. 'SURGE LINE FLOODING" MAY RESULT IN RCS PRESSURIZATION AND ERRONEOUS HIGH LOOP LEVEL INDICATION.

o IA TO CNMT MAY BE REQUIRED FOR RCS MAKEUP AND SHOULD NOT BE ISOLATED UNTIL DIRECTED BY THIS PROCEDURE.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.O. GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

1 Check If RCS Draindown Should Be Stopped:

a. Check RCS draindown - IN PROGRESS a. Go to step 2.
b. Stop draining RCS (Refer to 0-2.3.1. DRAINING AND OPERATION AT REDUCED INVENTORY OF THE REACTOR COOLANT SYSTEM) 2 Check RHR Pumps - AT LEAST IF the running pump has tripped due ONE RUNNING to loss of NPSH, THEN go to step 3.

IF NOT. THEN go to step 17.

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 4 of 17 3 Initiate CNMT Closure (Refer to O-2.3.1A, CONTAINMENT CLOSURE CAPABILITY IN TWO HOURS DURING RCS REDUCED INVENTORY OPERATION) 4 Check If RHR Pumps Should Be Stopped:

a. RHR pump - ANY RUNNING a. Go to Step 5.
b. Check RCS level: b. Stop RHR pumps and go to Step 5.

o Level - GREATER THAN 6 INCHES o Level - STABLE

c. RHR flow - LESS THAN 500 GPM c. Perform the following:
1) IF BOTH RHR pumps running with discharge crossties open, THEN stop one RHR pump.
2) Reduce RHR flow to less than 500 gpm.
d. RHR pumps cavitating: d. Go to Step 20.

o RHR pump flow - OSCILLATING

-OR-o RHR pump NPSH - APPROXIMATELY ZERO (PPCS Group Display NPSH)

e. Stop RHR pumps

EOP: TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 AP-RHR.2 INVENTORY CONDITIONS PAGE 5 of 17 ACTION/EXPECTED RESPONSE SP [RESPONSE NOT OBTAINED 5 Isolate Letdown And Known Drain Paths

a. Verify the following valves - a. Manually close valves.

CLOSED

. RCDT pump suctions from sump B. MOV-1813A and MOV-1813B

. Letdown isolation. AOV-427

  • Low pressure letdown pressure control valve. PCV-135

. RHR letdown flow control valve. HCV-133

  • Excess letdown isolation valve. AOV-310
b. Evaluate normal drain lineups
c. Evaluate maintenance activities affecting RCS or RHR system 6 Start Available CNMT RECIRC Fans NOTE: Personnel remaining in CNMT to assist in event mitigation should consult Radiation Protection for changes in radiological concerns.

7 Initiate Actions To Protect Personnel In CNMT:

a. Evacuate non-essential personnel from CNMT
b. Periodically monitor CNMT radiation

ITLE:

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 6 of 17

. * * * * *

  • 0 *
  • 4*, *
  • 4 4 * * *
  • 4 * * * * * * *
  • 4 * * * *
  • 0 * *
  • 4
  • CAUTION o PERSONNEL WORKING IN CNMT SHOULD BE WARNED BEFORE REFILLING THE RCS TO AVOID INADVERTENT CONTAMINATION OF PERSONNEL WORKING NEAR RCS OPENINGS.

o THE S/G OFFICE SHOULD BE NOTIFIED BEFORE RAISING LOOP LEVEL.

o ONLY BORATED WATER SHOULD BE ADDED TO THE RCS TO MAINTAIN ADEQUATE SDM.

  • * * *
  • 0
  • 4 * * * * * * *
  • 4 * * *
  • 4
  • 4 * *
  • 4 *
  • 4 * * * * * *
  • 4
  • 4
  • 8 Check RCS Temp Go to Step 13.

o Core Exit TCs - LESS THAN 200'F o No visual steam at RCS vents 9 Check RCS Loop Level - LESS Go to Step 14.

THAN 30 INCHES

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 7 of 17 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED NOTE: o The next four steps are sequenced to indicate the preferred order of RCS refill methods if core boiling is not occurring.

o Gravity feed through MOV-856 is expected at approximately 12 turns open.

10 Refill The RCS By Gravity Feed From The RWST

a. Dispatch AO to locally throttle open RHR pump suction from RWST.

MOV-856

b. Close RHR pump discharge valve to loop B cold leg. MOV-720
c. Verify MOV-856 indicates c. Perform the following:

midposition

1) Open MOV-720.
2) Go to Step 11.
d. Verify RCS loop level - d. Perform the following:

INCREASING AS EXPECTED

1) Close MOV-856.
2) Open MOV-720.
3) IF RCS loop level greater than 6 inches. THEN go to Step 11. IF NOT. THEN go to Step 13.
e. Check RCS loop level - GREATER e. Continue filling RCS. WHEN RCS THAN 30 INCHES loop level greater than 30 inches. THEN do Steps 10f through h.
f. Manually close MOV-856 f. Direct AO to locally close valve.
g. Open RHR pump discharge valve to g. IF MOV-720 does NOT open. THEN B loop cold leg. MOV-720 open core deluge valves MOV-852A and MOV-852B.
h. Go to Step 14

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 8 of 17 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 11 Refill The RCS By Charging To B Loop Cold Leg:

a. Verify IA to CNMT, AOV-5392 - a. Manually open valve.

OPEN

b. Open and verify open charging b. Open alternate charging line to line valve to loop B cold leg. loop A cold leg. AOV-392B. and AOV-294 go to Step 1ld.
c. Ensure HCV-142 demand at 0%
d. Start operable charging pump and increase flow to maximum
e. Verify charging flow - GREATER e. Perform the following:

THAN ZERO

1) Stop operating charging pump.
2) Close AOV-294.
3) Go to Step 12.
f. Verify RCS loop level - f. Perform the following:

INCREASING AS EXPECTED

1) Open or verify open alternate charging line to loop A cold leg. AOV-392B.
2) Close AOV-294.
3) Verify loop level increasing as expected. IF NOT. THEN perform the following:

a) Stop operating charging pump.

b) Close AOV-392B.

c) Close IA to CNMT. AOV-5392.

d) Go to Step 12.

g. Check RCS loop level - GREATER g. Continue filling RCS. WHEN loop THAN 30 INCHES level greater than 30 inches.

THEN do Steps llh through j.

h. Stop running charging pump
i. Close or verify closed charging line valve to loop B cold leg.

AOV-294 and AOV-392B

j. Go to Step 14

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 9 of 17 12 Refill RCS Using SI Pumps To

.Cold Legs:

a. Open the appropriate SI pump a. Ensure at least one valve open.

discharge valves to loop cold legs IF valves can NOT be opened.

THEN dispatch AO to check

. A SI Pump - MOV-878B breakers.

. B SI Pump - MOV-878D

. C SI Pump - MOV-878B AND/OR

  • MOV-878B. MCC D position 8C MOV-878D
  • MOV-878D. MCC D position 8F
b. Open SI pump suction valves from b. Ensure at least one valve open.

RWST IF valves can NOT be opened.

. MOV-825A THEN dispatch AO to check

  • MOV-825B breakers.
  • MOV-825A. MCC C position 9J
  • MOV-825B. MCC D position 9J
c. Start operable SI pump
d. Verify the following: d. Perform the following:

o SI flow - GREATER THAN ZERO 1) Stop operating SI pump.

o RCS loop level - INCREASING 2) Close loop cold leg inlet AS EXPECTED valves.

. MOV-878B

  • MOV-878D
3) Go to step 13.
e. Check RCS loop level - GREATER e. Continue filling RCS. WHEN loop THAN 30 INCHES level greater than 30 inches.

THEN do steps 12f through h.

f. Stop running SI pump
g. Close SI discharge valves to loop cold legs. MOV-878B and MOV-878D
h. Go to Step 14

TLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 10 of 17 NOTE: SI Pump makeup should not be secured when core boiling is indicated.

13 Refill RCS Using SI Pumps To Hot Legs:

a. Open the appropriate SI pump a. Ensure at least one valve open.

discharge valves to loop hot legs IF valves can NOT be opened.

. A SI Pump - MOV-878A THEN dispatch AO to check

  • B SI Pump - MOV-878C breakers.
  • C SI Pump - MOV-878A AND/OR MOV-878C
  • MOV-878A. MCC C position 8C
  • MOV-878C. MCC C position 8F
b. Open SI pump suction valves from b. Ensure at least one valve open.

RWST IF valves can NOT be opened.

  • MOV-825A THEN dispatch AO to check

. MOV-825B breakers.

  • MOV-825A, MCC C position 9J
  • MOV-825B. MCC D position 9J
c. Start operable SI pump
d. Verify the following: d. Perform the following:

o SI flow - GREATER THAN ZERO 1) Stop operating SI pump.

o RCS loop level - INCREASING 2) Close loop hot leg inlet AS EXPECTED valves.

  • MOV-878A

. MOV-878C

3) Ensure makeup flow is initiated

. Gravity feed from RWST

  • Charging pumps
  • SI pumps to cold legs
  • VCT'overpressure
  • RWST purification pump
e. Operate SI Pump as necessary to e. IF core exit TC's continue to maintain the following increase. THEN return to Step 11 parameters: to establish additional charging or SI flow to the RCS cold legs.

o Core Exit TC's - LESS THAN 2000F o No visual steam at RCS vents o RCS loop level - GREATER THAN 30 INCHES

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 11 of 17 14 Identify And Isolate Any RCS Leakage NOTE: If adequate time to completely vent the RHR system is not available.

then air can be swept out of the RHR lines by running an RHR pump at a flowrate between 1200 gpm and 1400 gpm.

15 Vent RHR System As Necessary

a. Check RCS temperature - LESS a. Go to step 16.

THAN 2000 F

b. Maintain RCS level while venting RHR system
c. Direct AO to vent RHR suction line from loop A at valve V-2764 (in CNMT by loop A)

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 12 of 17 ACTION/EXPECTED RESPONSE SP LRESPONSE NOT OBTAINED I

  • * * * . * , * * * * * * * * * * * * * * * * * * * * * . * * * * *
  • 4 * * * *
  • CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.
  • 4 *
  • 4 4 4
  • 4 4 4 4
  • 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 *
  • 4 16 Check IA Available For RHR Reset and start adequate air Flow Control: compressors (75 kw each).

o Verify adequate air compressors IF electric air compressor not

- RUNNING available. THEN start diesel air compressor (Refer to ATT-11.2, o Verify IA pressure - GREATER ATTACHMENT DIESEL AIR COMPRESSOR)

THAN 60 PSIG IF IA pressure can NOT be restored.

o IA available to HCV-624 AND THEN perform the following:

HCV-625

a. Dispatch AO with locked valve key to locally close RHR Hx outlet valves
  • A RHR Hx. HCV-625 handwheel

. B RHR Hx. HCV-624 handwheel

b. WHEN conditions permit. THEN refer to AP-IA.1. LOSS OF INSTRUMENT AIR. to restore IA.

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 13 of 17 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 17 Establish Conditions To Start RHR Pump:

a. Check RHR cooling valve a. Manually or locally align valves alignment - NORMAL (Refer to as necessary.

ATT-14.0. ATTACHMENT NORMAL RHR COOLING)

b. Verify CCW cooling to RHR system b. Perform the following:

in service

1) Increase SW from CCW Hx
1) CCW pumps - ENSURE AT LEAST ONE RUNNING
  • CCW Hx A. V-4619
  • CCW Hx B. V-4620
2) CCW to RHR Hxs. MOV-738A AND MOV-738B - ADJUSTED TO OBTAIN 2) Adjust MOV-738A and MOV-738B DESIRED COOLING to obtain desired cooling.
3) Check CCW flow
  • 4900 gpm 3) IF > 4900 gpm CCW flow (FI-619) required for desired RHR cooling. THEN notify the Shift Supervisor.

IF CCW can NOT be restored. THEN continue with step 18 while attempting to restore CCW (Refer to AP-CCW.3. LOSS OF CCW - PLANT SHUTDOWN).

c. Verify the following RCS c. Perform the following:

conditions:

1) Start trending core exit TCs.

o Core exit TC's - LESS THAN 2000F 2) Return to Step 7.

o No visual steam at RCS vents o RCS loop level - GREATER THAN

-30 INCHES

d. RHR pump - AVAILABLE d. Perform the following:
1) Start trending core exit TCs.
2) Place RCDT pumps in service (Refer to ER-RHR.1. RCDT OPERATION FOR CORE COOLING).
3) Return to Step 7.

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 14 of 17 ACTON/XPE TED RESOBANSE I

  • * , * , . , , , , , , , , , * , , , ,, * , ,C * , * * , , , * * , . . . . . . .

CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL DECREASE DUE TO SHRINK OR VOID COLLAPSE.

  • *S , * * , ,* * * * * * * * * ,* , * , * * * * ,* * * * . , * * * ,* .*
  • 18 Restore RHR Flow:
a. Close RHR pump flow control a. IF IA NOT available. THEN ensure valves AO has locally closed RHR Hx outlet valves and go to step 18c.
  • HCV-624
  • HCV-625
b. Place RHR Hx bypass valve.

HCV-626. to MANUAL and close valve

c. Start one RHR pump
d. Ensure RHR flow - LESS THAN d. IF IA NOT available. THEN 1500 GPM dispatch AO with locked valve key to locally adjust flow using RHR Hx outlet valves.
  • A RHR Hx. HCV-625 handwheel

. B RHR Hx, HCV-624 handwheel

e. Check RCS loop level - GREATER e. Establish adequate makeup flow THAN 30 INCHES to stabilize RCS loop level at greater than 30 inches.
f. Gradually increase RHR bypass flow to desired flowrate
g. RHR flow - RESTORED g. Perform the following:
1) Start trending core exit T/Cs.
2) Place RCDT pumps in service (Refer to ER-RHR.l. RCDT OPERATION FOR CORE COOLING).
3) Return to Step 7.
h. Establish desired RCS cooldown rate

IUL:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Consult with Plant Staff to determine alternatives for long term cooling.

19 Establish Stable Plant Conditions:

a. Verify Core Exit TC's - LESS a. Continue cooling with RHR.

THAN 2000 F Return to Step 18d.

b. Check RCS loop level: b. IF RCS loop level increasing.

THEN reduce makeup rate to o Level - GREATER THAN 30 INCHES stabilize level. IF RCS loop level decreasing. THEN return to o Level - STABLE Step 10.

c. Stop any running SI pump
d. Stop any running charging pump
e. Maintain RCS level stable using e. Initiate makeup to the RCS using RWST gravity feed either of the following:

o One charging pump at maximum flow

-OR-o One SI pump

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE -IEPNENTOTIE 20 Check CCW System Operation: To restore CCW cooling to RHR Hxs.

perform the following:

o CCW pumps - AT LEAST ONE RUNNING

a. Ensure the standby CCW pump is o RCS temperature - STABLE OR running.

DECREASING

b. Increase SW from CCW Hx o Annunciator A-21. COMP COOLING HX OUT HI TEMP - EXTINGUISHED
  • CCW Hx A. V-4619
  • CCW Hx B. V-4620 o Annunciator A-22. CCW PUMP DISCHARGE LO PRESS - EXTINGUISHED c. Adjust MOV-738A and MOV-738B to maintain RCS temperature stable o Annunciator A-30. CCW PUMP INLET or decreasing.

HEADER HI TEMP - EXTINGUISHED IF > 4900 gpm CCW flow required for o Check CCW flow

  • 4900 gpm desired RHR cooling (FI-619). THEN (FI-619) notify the Shift Supervisor.

IF CCW can NOT be restored. THEN continue attempts to restore CCW (Refer to AP-CCW.3. LOSS OF CCW -

PLANT SHUTDOWN).

21 Check Core Exit TCs: Continue cooling with RHR. Return to Step 18d.

o Temperature - LESS THAN 140'F o Temperature - STABLE OR DECREASING

TITLE:

LOSS OF RHR WHILE OPERATING AT RCS REDUCED REV: 14 INVENTORY CONDITIONS PAGE 17 of 17 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 22 Initiate Monitoring of RCS Temperature 23 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

24 Notify Higher Supervision 25 Return To Procedure Or Guidance In Effect

-END-

.I HILE:

REV: 14 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS PAGE 1 of 1 AP-RHR.2 APPENDIX LIST TITLE

1) ATTACHMENT NORMAL RHR COOLING (ATT-14.0)
2) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

GINNA STATION CONTROLLED COPY NUMBER E_

RESPONSIBL MMANAGER EFFECTIVE ATE CATEGORY 1.0 REVIEWED BY:

A. PURPOSE - This procedure provides the necessary instructions to control the plant following a turbine trip without a reactor trip required.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. AR-G-32, EMERGENCY DC LUBE OIL PUMP, if turbine I tripped. I
b. AR-I-8, EH RESERVOIR HI-LO LEVEL, if level is I decreasing and cannot be stabilized.
c. AR-I-16, EH RESERVOIR LO LEVEL PUMP LOCKOUT, if level l is decreasing and cannot be stabilized. I
d. AR-J-2, GENERATOR STATOR WINDING HI TEMP, if I generator conditions warrant turbine trip. I
e. AR-VOLT-REG-3, LOSS OF BOTH FIRING CIRCUITS, if voltage regulator will not control voltage. I
f. AP-CW.1, LOSS OF A CIRC WATER PUMP, or,
g. AP-ELEC.1, LOSS OF 12A AND/OR 12B BUSSES, or,
h. AP-FW.1, ABNORMAL FEED FLOW, or,
i. AP-TURB.2, TURBINE LOAD REJECTION, or,
j. AP-TURB.3, TURBINE VIBRATION, or,
k. AP-TURB.4, LOSS OF CONDENSER VACUUM, when power is less than P-9 and the turbine trips without a Rx trip.
2. SYMPTOMS - The symptoms of TURBINE TRIP WITHOUT RX TRIP REQUIRED are:
a. Annunciator F-21, COND HI PRESS 20" HG OR LOSS OF BOTH CIRC WTR PMPS, lit, or
b. Annunciator G-15, STEAM DUMP ARMED, lit, or
c. Annunciator J-11, GENERATOR REVERSE POWER, lit, or I
d. Annunciator J-26, GENERATOR EXCITER FIELD BREAKER I TRIP, lit, or I
e. Annunciator K-1, THRUST BEARING FAILURE, lit, or
f. Annunciator K-3, AMSAC ACTUATED, lit.
g. Annunciator K-9, TURBINE BEARING OIL LO PRESS TRIP 6 psi, lit, or
h. Annunciator K-10, TURBINE HIGH VIBRATION TRIP, lit, or
i. Annunciator K-17, TURBINE LOW VACUUM TRIP 20" HG, lit, or
j. Annunciator K-25, TURBINE OVERSPEED ALERT 1980 RPM, lit, or
k. Annunciator K-26, GENERATOR LOCKOUT RELAY, lit, or
1. Annunciator L-12, CONDENSER PIT OR SCREENHOUSE HI LEVEL 6.5", lit, or
m. Annunciator VOLT-REG-12, LOSS OF BOTH PWR SUPPLY, lit.1

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Verify Turbine Stop Valves - Manually trip turbine.

CLOSED IF turbine stop valves can NOT be closed. THEN perform the following:

a. Trip the reactor
b. WHEN all E-O Immediate Actions done. THEN ensure both MSIVs closed
c. Go to E-O. REACTOR TRIP OR SAFETY INJECTION NOTE: o Automatic rod control is desired. if available.

o Transition to E-0 is NOT required if the reactor trip breakers are opened in the following step.

2 Check Reactor Power:

a. NIS power ranges - ABOVE 1% a. Perform the following:
1) IF the reactor is subcritical. THEN shut down the reactor using manual trip pushbutton.
2) Go to Step 3.
b. Verify control rods driving in b. Perform the following:

to reduce reactor power in AUTO

1) Place rods in MANUAL
2) Adjust rods to control reactor power between 1% and 2%.
c. Borate to maintain control rods above rod insertion limits

P ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED

  • 3 Monitor MFW Regulating Valves Perform the following:

- RESTORING S/G LEVEL TO 52%

IN AUTO a. Place affected S/G(s) MFW regulating valve in MANUAL

b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1.

ABNORMAL MAIN FEEDWATER FLOW.

4 Verify Proper Operation Of Steam Dump:

a. Verify annunciator G-15. STEAM a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
b. Condenser steam dump operating b. IF steam dump NOT available, in AUTO THEN perform the following:
1) Adjust S/G ARV setpoints to 1005 psig and verify ARV operating to control Tavg to approximately 547 0 F.
2) IF power is greater than 8%.

THEN ensure reactor trip and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

c. Check RCS Tavg: c. Verify control rods responding in AUTO. IF NOT. THEN place

. Tavg - GREATER THAN 5451F rods to MANUAL and adjust

  • Tavg - LESS THAN 5660 f control rods to restore Tavg within limits.

IF Tavg is outside limits and can NOT be controlled. THEN trip the reactor and go to E-0.

REACTOR TRIP OR SAFETY INJECTION.

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 5 Check PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:

  • 431K in MANUAL
  • Manual control of heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

K>'

STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check PRZR Level:

a. Level - GREATER THAN 13% a. Perform the following:
1) Place letdown isolation valve AOV-427 switch to CLOSE.
2) Place letdown orifice valve switches to CLOSE .(AOV-200A.

AOV-200B. and AOV-202).

3) Close excess letdown isolation valve, AOV-310.
4) Ensure PRZR heaters off.
5) Close letdown isolation AOV-371 WHILE adjusting charging pump speed to maintain:

o RCP labyrinth seal D/P between 15 inches and 80 inches o PRZR level at program

6) WHEN PRZR level greater than 13%. THEN restore letdown.

(Refer to ATT-9.0. ATTACHMENT LETDOWN)

b. Level - TRENDING TO PROGRAM IN b. Perform the following:

AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 7 Check MFW System:

a. MFW pumps - BOTH RUNNING a. Perform the following:
1) Verify one MFW pump running.

IF NOT. THEN establish sufficient AFW flow to maintain S/G levels

2) Go to Step 8.
b. Close one MFW pump discharge valve
c. Stop selected MFW pump

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED CAUTION IF AT ANY TIME IT IS SUSPECTED THAT THE REACTOR IS SUBCRITICAL, THEN MANUALLY TRIP THE REACTOR.

NOTE: o With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) o Transition to E-O is NOT required if the reactor trip breakers are opened in the following step.

8 Establish Stable Plant Conditions:

a. NIS power ranges - LESS THAN 2% a. Return to Step 2.
b. Place rods in MANUAL
c. Check reactor power - GREATER c. IF the reactor is subcritical.

THAN 1% THEN perform the following:

1) Shut down the reactor using manual trip pushbutton.
2) Go to Step 8e.
d. Maintain reactor power between 1% and 2%
e. PRZR pressure - BETWEEN e. Control PRZR pressure between 2220 PSIG AND 2260 PSIG 2220 psig and 2260 psig by one of the following:
  • 431K in AUTO
  • 431K in MANUAL
  • Manual control of heaters and spray
f. RCS Tavg - GREATER THAN 545 0 F f. Control dumping steam to control Tavg. IF cooldown continues.,

THEN close both MSIVs.

IF MSIVs closed AND Tavg still decreasing. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

ACTION/EXPECTED RESPONSNOT OBTAINE

, * * *

  • 4 * * * * * * * * * * * * . * *
  • 4 * * * * * * .
  • 4 * * . * * * * *.

CAUTION IF ANY S/G LEVEL ABOVE 52%. THEN AFW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT S/G ISOLATION.

  • * * * * * * * * * * * * * * * * * *
  • 4 * * * * * * * * * * * * * * * * * * *
  • NOTE: Maintaining reactor power less than 2% is within the capacity of MDAFW pumps.

9 Check S/G Feed Flow Status:

a. Manually start both MDAFW pumps
b. Verify AFW flow - SUFFICIENT b. Perform the following:

FLOW TO MAINTAIN S/G LEVELS

1) Establish MFW flow using MFW regulating valve bypass valves.

IF MFW NOT available. THEN manually start TDAFW pump and establish flow.

2) Adjust feed flow to restore S/G level to 52%.
3) Go to Step 10.
c. Verify MFW flow control valves - c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.

. MFW regulating valves

  • MFW bypass valves
d. Close MFW pump discharge valves
  • MOV-3977. A MFW pump
  • MOV-3976. B MFW pump
e. Stop any running MFW pump and place in PULL STOP
f. Place A and B MFW regulating and bypass valve controllers in manual at 0% demand.
g. Adjust AFW pump flow to restore S/G level to 52%.

STEP ACTION/EXPECTED RESPONSEREPNEOTBAID 10 Establish Normal AFW Pump Shutdown Alignment:

a. Place AFW bypass switches to DEF
b. Verify the following: b. Continue with Step 11. WHEN conditions met. THEN do Steps o Both S/G levels - STABLE OR 10c through d.

INCREASING o Total AFW flow - LESS THAN 200 GPM

c. Close MDAFW pump discharge valves
  • MOV-4007
  • MOV-4008
d. Adjust AFW bypass valves to control S/G levels at 52%
  • AOV-4480
  • AOV-4481

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1.

ATTACHMENT SD-2.

b. Perform the following:

o Open generator disconnects

  • 1G13A71
  • 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump (Refer to T-5F.

STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify Bus llA and Bus 1lB c. IF either bus NOT energized.

energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2.

THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/

BUS 12B.

d. Dispatch AO to perform ATT-17.0, ATTACHMENT SD-1

ACTION/EXPECTED RESPONSEREPNEOTBAID 12 Establish Control Systems In Auto:

a. Verify 431K in AUTO a. Place 431K in AUTO, if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valvesS in AUTO.

if desired.

c. Verify one charging pump in AUTO c. Place one charging pum]p in AUTO.

if desired.

d. Verify PRZR heaters restored: d. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO K> 13 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION. for reporting requirements.

14 Notify Higher Supervision 15 Establish Desired Plant Conditions:

a. Reactor shutdown - DESIRED a. IF turbine is to be reistored to service. THEN maintain reactor critical and refer to 0-1.2.

PLANT STARTUP FROM HOT SHUTDOWN TO FULL LOAD.

b. Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

AP-TURB.1 APPENDIX LIST TITLE

1) ATTACHMENT SD-1 (ATT-17.0)
2) ATTACHMENT SD-2 (ATT-17.1)
3) ATTACHMENT LETDOWN (ATT-9.0)

EOP: TITLE:

REV: 1 9 DP-TURB.2 TURBINE LOAD REJECTION PAGE 1 of 12 GINNA STATION CONTROLLED COPY NUMBER _ _ _

RESPONSIBLA MANAGER 4 tooq EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:l Ed:REV: RV 19 8P-TURB.2 TURBINE LOAD REJECTION PAGE 2 of 12 A. PURPOSE - This procedure provides the guidance necessary to control the plant during a transient resulting from an unanticipated turbine/secondary plant load decrease.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. AR-12A-4, LOSS OF 4160V ON 12A TRANSFORMER SECONDARY, I if a turbine load rejection has occurred. I
b. AR-12A-8, 12A BUS UNDERVOLTAGE, if a turbine load I rejection has occurred. I
c. AR-12B-4, LOSS OF 4160V ON 12B TRANSFORMER SECONDARY, I if a turbine load rejection has occurred. I
d. AR-12B-8, 12B BUS UNDERVOLTAGE, if a turbine load I rejection has occurred. I
2. SYMPTOMS - The symptoms of TURBINE LOAD REJECTION are;
a. Unexplained decrease in main generator output, lit, or
b. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, I or I
c. Annunciator F-15, RCS TAVG DEV 4 0 F, lit, or I
d. Annunciator F-30, OPAT TURBINE RUNBACK, lit, or
e. Annunciator F-31, OTAT TURBINE RUNBACK, lit, or
f. Annunciator G-15, STEAM DUMP ARMED, lit, or I
g. Annunciator I-30, TURBINE VALVES CHANNEL ALERT, lit, I or
h. Annunciator L-27, 34 KV BREAKER TRIP, lit. I

EOP: TITLE:

REV: 19 AP-TURB.2 TURBINE LOAD REJECTION PAGE 3 of 12 ACTION/XPECTE RESPONSE I

  • A * * * * * * * - A * ** - *-
  • *- *- *- *- 6 6 6- 6. 6 - *- A

-

  • A 6 CAUTION ANY AT RUNBACK SIGNAL WILL BLOCK AUTO AND MANUAL OUT MOTION OF ROD CONTROL SYSTEM.
  • * * * *
  • 6 * * *
  • f o r * * * * * * * * * *
  • i s * * * * *
  • r* e d* i *
  • NOTE: The thumb rule for initial boron addition is -2 gal/X load reduction.
  • 1 Monitor RCS Tavg Verify control rods responding in AUTO. IF NOT, THEN place rods to o Tavg - GREATER THAN 5450F MANUAL and adjust rods to restore Tavg within limits.

o Tavg - LESS THAN 5660 F IF Tavg is outside limits AND can NOT be controlled, THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

2 Check Steam Dump Status: IF steam dump required but NOT operating. THEN perform the o Annunciator G-15. STEAM DUMP following:

ARMED - LIT

a. Place STEAM DUMP MODE SELECTOR o Steam dump operating properly in Switch to MANUAL.

AUTO

b. Place steam dump controller, HC-484. to MANUAL.
c. Operate steam dump valves manually as necessary.

EOP: TITLE:

REV: 19 AP-TURB.2 TURBINE LOAD REJECTION PAGE 4 of 12 RESPONSE IACTION/EXPECTED 3 Verify Tavg - TRENDING TO TREF Place control rods to MANUAL and adjust control rods to restore Tavg to Tref.

NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3)

  • 4 Monitor PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
  • 5 Monitor MFW Regulating Valves Perform the following:

- RESTORING S/G LEVEL TO 52%

IN AUTO a. Place affected S/G(s) MFW regulating valve in MANUAL

b. Restore SIG level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.l.

ABNORMAL MAIN FEEDWATER FLOW.

EOP: TITLE: REV: 19 AP-TURB.2. TURBINE LOAD REJECTION PAGE 5 of 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 6 Monitor PRZR Level - TRENDING Perform the following:

.TO PROGRAM IN AUTO CONTROL

a. Place affected charging pumps in MANUAL
b. Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1.

REACTOR COOLANT LEAK.

7 Check Turbine Runback Criteria:

a. Any AT annunciator - LIT a. Go to Step 8.

. F-30. OPAT TURBINE RUNBACK

. F-31. OTAT TURBINE RUNBACK

b. AT runback occurring as required b. Place EH in MANUAL and reduce turbine load by 5% RTP every 30 seconds.

8 Check Turbine Power - STABLE Determine cause of continued power reduction and stabilize load if a Setter possible.

  • Control valve position
  • Generator load

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check Main Generator Load - IF load can NOT be stabilized above GREATER THAN 15 MW 15 MW. THEN trip turbine and go to AP-TURB.1. TURBINE TRIP WITHOUT RX TRIP REQUIRED, Step 1.

ACTION/EXPECTED RESPONSE INED NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 10 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref, THEN restore Tavg to Tref by one or more of the following:

. Withdraw control rods

  • Reduce Turbine Load

. Dilution of RCS

b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually, THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

This Step continued on the next page.

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED (Step 10 continued from previous page)

d. MFW regulating valves - d. Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected SIG(s) MFW regulating valve in MANUAL

2) Restore S/G level to 52%

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1. ABNORMAL MAIN FEEDWATER FLOW.

e. Steam dump valves - CLOSED e. Perform the following:
1) Ensure proper operation of steam dump control system.
2) If either of the following occurs. THEN refer to AP-TURB.4, LOSS OF CONDENSER VACUUM o Condensate Temperature greater than 100'F (PPCS Point ID T2053)

-OR-o Condenser vacuum degrading (PPCS top menu condenser backpressure)

EOP: . TITLE: 1 REV: 19 AP-TURB.2 TURBINE LOAD REJECTION PAGE 9 of 12 ACTION/EXPECTED RESPONSEINED 11 Verify Cause Of Turbine Load Attempt to determine and correct Rejection - IDENTIFIED cause of turbine load rejection.

EOP: TITLE:

REV: 19 AP-TURB.2 TURBINE LOAD REJECTION PAGE 10 of 12 STE ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 12 Establish Normal Plant Conditions:

a. Verify 431K in AUTO a. Place 431K in AUTO. if desired.
b. Verify PRZR spray valves in AUTO b. Place PRZR spray valves in AUTO.

if desired.

c. Verify PRZR heaters restored: c. Restore PRZR heaters. if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET, IN AUTO

d. Verify one charging pump in AUTO d. Place one charging pump in AUTO.

if desired.

e. Verify MFW regulating valves in e. Place MFW regulating valves in AUTO AUTO, if desired.
f. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hour
3) Match setter and reference
g. Verify steam dump controller.

HC-484. in AUTO at 1005 psig

h. Verify annunciator G-15. STEAM h. WHEN Tavg within 5 0F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
i. Verify Rods in AUTO i. Place Rods in AUTO. if desired.

This Step continued on the next page.

kEOP: TITLE:

REV: 19 AP-TURB.2 TURBINE LOAD REJECTION PAGE 11 of 12 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl (Step 12 continued from previous page)

j. Rod insertion limit alarms - j. IF any AT channel failed. THEN EXTINGUISHED determine actual RIL from the COLR. IF alarm valid. THEN borate as necessary and withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
k. NIS PR AI - WITHIN +/- 5% OF k. Perform one or more of the TARGET VALUE following to restore AI to within limits:

. Borate RCS

. Dilute RCS

a. Boration performed for load a. Go to Step 14.

injection

b. Place PRZR backup heaters switch to ON 14 Evaluate MCB Annunciator Status (Refer to AR Procedures)

EOP: TITLE:

REV: 19 lAP-TURB.2 ..

TURBINE LOAD REJECTION PAGE 12 of 12 ACTION/EXPECTED RESPONSERSOS OTOTIE NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

15 Notify Higher Supervision 16 Return To Procedure Or Guidance In Effect

-END-

IEDP: - - TITLE:

nP-TURB.2 I REV: 19 lTURBINE LOAD REJECTION lPAGE 1 of 1 AP-TURB.2 APPENDIX LIST TITLE

1) ATTACHMENT EXCESS L/D (ATT-9.1)

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 1 of 9 GINNA STATION CONTROLLED COPY NUMBER CZ1 RESPONSIBLE, ANAGER E-3 -TIE6DA C

EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 2 of 9 A. PURPOSE - This procedure provides the necessary actions to be taken in the event of increasing turbine vibrations.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. N/A
2. SYMPTOMS - The symptoms of TURBINE VIBRATION are;
a. Increasing or High Turbine Vibration detected, or
b. Annunciator I-27, Rotor Eccentricity or Vibration alarm is lit, or
c. Annunciator J-19, TURBINE HIGH VIBRATION TRIP BLOCKED, lit.

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED

  • 1 Verify Turbine Vibration - Perform the following:

ALL BEARINGS LESS THAN 14 MILS

a. Verify the Turbine tripped. IF Turbine is not tripped. THEN manually trip Turbine.
b. Go to AP-TURB.1. TURBINE TRIP WITHOUT RX TRIP REQUIRED OR E-0, REACTOR TRIP OR SAFETY INJECTION, as required.

STEP ACTION/EXPECTED RESPONSE {RESPONSE NOT OBTAINEDl NOTE: IF power reduction is required the thumb rule for initial boron addition is -2 gal/% load reduction.

2 Check Turbine Vibration:

a. Bearings No. 1 through No. 8 - a. Attempt to stabilize vibration LESS THAN 7 MILS as follows:

o IF increasing turbine speed.

THEN stop speed increase and evaluate. Evaluate reducing speed to a non-resonance region. (Refer to 0-1.2) o IF generator on line, THEN begin reducing load to stabilize vibrations. (Refer to AP-TURB.5. RAPID LOAD REDUCTION)

b. Bearing No. 9 - LESS THAN b. Attempt to stabilize vibrations 8.5 MILS as follows:

o Adjust generator hydrogen temperature.

-OR-o Adjust turbine lube oil temperature.

-OR-o Adjust exciter cooling.

-OR-o Adjust generator seal oil cooling.

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 5 of 9 3 Evaluate Plant Conditions:

a. Check turbine vibrations - a. Reduce turbine load until STABLE OR DECREASING turbine vibrations stabilize.

IF vibrations can NOT be stabilized with the plant at power. THEN take unit off line (refer to AP-TURB.5. RAPID LOAD REDUCTION)

b. Stop load reduction

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 6 of 9 ACT ION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Establish Stable Plant Conditions

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:
  • Reduce turbine load
  • Dilution of RCS
b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL
2) Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.
d. MFW Regulating valves - d. Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected SIG(s) MFW regulating valve in MANUAL.

2) Restore S/G level to 52%.

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION

. ... k- PAGE 7 of 9 .

ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED 5 Evaluate Turbine Operation:

a. Verify no unusual noises exist a. IF unusual noises detected. THEN locally at turbine generator notify the Maintenance Manager.
b. Monitor turbine supervisory instrumentation to ensure conditions stable o Turbine Vibration Recorder (Front of MCB) o Turbine Vibration Monitor (Back of MCB)

EOP TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 8 of 9 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINEDl 6 Establish Control Systems In Auto:

a. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hr
3) Match setter and reference
b. Verify annunciator G-15. STEAM b. WHEN Tavg within 51F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
c. Verify one charging pump in AUTO c. Place one charging pump to AUTO.

if desired.

d. Verify rods in AUTO d. Place rods in AUTO. if desired.
e. Verify 431K in AUTO e. Place 431K in AUTO. if desired.
f. Verify spray valves in AUTO f. Place spray valves in AUTO, if desired.
g. Verify PRZR heaters restored: g. Restore PRZR heaters, if desired.

o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -

RESET. IN AUTO

h. Verify MFW regulating valves in h. Place MFW regulating valves in AUTO AUTO. if desired.

EOP: TITLE:

REV: 12 AP-TURB.3 TURBINE VIBRATION PAGE 9 of 9 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 7 Evaluate MCB Annunciator Status (Refer to AR Procedures) 8 Notify Higher Supervision

-END-

EOP: TITLE:

REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 1 of 20 GINNA STATION CONTROLLED COPY NUMBER 0?

RESPONSIBLE NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 2 of 20 A. PURPOSE -

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from
a. The SS has determined that a load reduction rate 2 1%/min is desired.
b. AR-J-4, GENERATOR ISO PHASE BUS COOLING SYS, if fan I and SW conditions require a load reduction, or. I
c. AR-J-12, GENERATOR MAIN TRANSFORMER ANNUNCIATOR, if I top oil temperature is outside limits, or winding I temperature is outside limits, or cooler/fan I combination requires load reduction, or I
d. AR-L-21, MAIN FEEDWATER PUMP OIL SUMP HI-LO LEVEL, if I SW in-leakage to MFP oil sump is apparent, or I
e. AR-VOLT-REG-3, LOSS OF BOTH FIRING CIRCUITS, if I generator did not trip. I

EOP: TITLE:

I I REV: 7 AP-TURB.5 RAPID LOAD REDUCTION I.I PAGE 3 of 20

  • * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
  • 4
  • 4 * * *
  • CAUTION IF MAIN FEEDWATER FLOW SHOULD DECREASE TO 25% OF FULL POWER VALUE

(.825 E+6 LBM/HR) PRIOR TO THE AMSAC SYSTEM AUTOMATICALLY BLOCKING. THEN A TURBINE TRIP AND AUX FEED PUMPS START COULD RESULT.

4 4 4 . 4 . . . 4 . . 4 4 * .

  • 4 4 . .* * .
  • 4 . * . .
  • 4 4 . * . . .4 * .4 NOTE: o IF the turbine is to be taken offline. THEN transfer of 4160V loads may be performed at any time. Refer to ATT-23.0. ATTACHMENT TRANSFER 4160V LOADS.

o A maximum continuous load reduction rate of > 5%/min should not be used unless directed by the Shift Supervisor.

1 Initiate Load Reduction

a. Verify rods in AUTO a. Perform the following:
1) Place rods to MANUAL.
2) Adjust Rods to match Tavg and Tref.
b. Reduce turbine load in Auto as b. IF Auto Control is inoperable.

follows: THEN reduce turbine load in manual at the desired rate.

1) Place Turbine EH Control in OPER PAN.. IMP PRESS IN. if desired.
2) Select desired rate on thumbwheel
3) Reduce the setter to the desired load
4) Depress the GO button
c. Verify steam dump operating c. IF stem dump required but NOT properly in AUTO operating. THEN perform the following:

o Annunciator G-15. STEAM DUMP ARMED - LIT 1) Place STEAM DUMP MODE SELECTOR Switch to MANUAL.

o Steam dump operating properly in auto 2) Place steam dump controller.

HC-484. to MANUAL.

3) Operate steam dump valves as necessary.
d. Place PRZR backup heaters switch to ON

EOP: TIRE:

REV: 7 AP-TURB.5 RAPID LOAD REDUCTION P

. l PAGE 4 of 20 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl

  • 4 * *
  • 4
  • 4 * *
  • 4 * *
  • 4 4
  • 4 . * * *
  • 4 0 * * * *
  • 4 * *
  • 4 4 4 *
  • CAUTION EXTREME AND RAPID ROD MOTION TO MITIGATE TAVG SWINGS MAY RESULT IN LARGE POWER EXCURSIONS AND SHOULD BE AVOIDED.

0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4

  • 4
  • 4 4 4 4 4 4 4 4 4 4 4 4 4 4
  • 4
  • 4 4 4 4 4
  • 2 Monitor RCS Tavg Verify control rods responding in AUTO. IF NOT. THEN place rods to o Tavg - GREATER THAN 5450F MANUAL and adjust rods to restore Tavg within limits.

o Tavg - LESS THAN 566 0 F IF Tavg is outside limits AND can NOT be controlled. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

NOTE: The thumb rule for initial boron addition is -2 gal/% load reduction.

3 Add Boric Acid As Necessary To:

o Maintain or return A Flux to the target band o Maintain control rods above insertion limits o Match Tavg and Tref o Compensate for Xenon

EOP: TITLE:

REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 5 of 20 ACTIN/EXECTE REPONS 1 1RESPNSENOT OBTAINED I NOTE: It is permissible to operate RCPs for limited periods without seal injection. provided CCW is being supplied to the thermal barriers.

4 Check IA Available To CNMT Control PRZR level and pressure as follows:

o IA pressure - > 60 psig o Adjust load reduction rate o Instr Air to CNMT Isol Valve.

AOV-5392 - OPEN o Ensure control rods are moving to control Tavg o IF CCW supplied to BOTH RCP thermal barrier heat exchangers.

THEN start/stop charging pumps as necessary to control PRZR level o Operate proportional and backup heaters to control PRZR pressure NOTE: With PRZR pressure controller in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3)

  • 5 Monitor PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

ACTION/EXPECTED RESPONSEINED

  • 6 Monitor MFW Regulating Valves Perform the following:

- RESTORING S/G LEVEL TO 52%

IN AUTO a. Place affected S/G(s) MFW regulating valve in MANUAL

b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually. THEN refer to AP-FW.1.

ABNORMAL MAIN FEEDWATER FLOW.

  • 7 Monitor PRZR Level - TRENDING Perform the following:

TO PROGRAM IN AUTO CONTROL

a. Place affected charging pumps in MANUAL.
b. Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1, REACTOR COOLANT LEAK.

NOTE: The load reduction should not be delayed to perform the remaining steps.

8 Check If Condensate Booster Pumps Should Be Secured

a. Power < 65% OR Trim Valve a. Go to Step 15.

V-9508G indicates > 80% open

b. Place the auto condensate booster pump to the trip position
c. Stop one condensate booster pump
d. WHEN condensate system pressures stabilize. THEN stop the remaining condensate booster pump

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 7 of 20 ACTIN/EXECTE REPONS P lRESPNSENOT OBTAINED l 9 Check If One MFW Pump Should Be Secured

a. Power. < 50% a. Go to Step 15.
b. Verify at least one MFWP Seal b. Notify AO to start one MFWP Seal Booster pump in service Booster pump
c. Two MFW Pumps running c. Go to Step 10.
d. Close discharge valve for the pump to be secured
  • MFW Pump A - MOV-3977
  • MFW Pump B - MOV-3976
e. Stop the desired MFW Pump
f. Close the secured MFW pump recirc valve by placing the control switch in pull stop
g. Close the service water block valve to the secured MFW pump oil cooler
  • MFW Pump A - V-4701
  • MFW Pump B - V-4702 10 Verify Trim Valves Place controller in manual and Controlling Condensate System control pressure between Pressure in Auto 300-375 psig.

(300-375 PSIG)

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I I -REV: 7 AP-TURB.5 RAPID LOAD REDUCTION lI PAGE 8 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Check AMSAC System Status

a. Power < 35% (-150 psig first a. Go to Step 15.

stage pressure)

b. Verify AMSAC Auto Block Status b. Place AMSAC Manual Block switch Light is ON to the BLOCK position 12 Check Heater Drain Tank Pump Status
a. Generator load < 175 MWe a. Go to Step 15.
b. Stop one Heater Drain Tank Pump
c. WHEN Heater Drain Tank level control is stable. THEN stop the second Heater Drain Tank Pump 13 Check MFW Regulating Bypass Vlv Status
a. Power < 30% a. Go to Step 15.
b. MFW Regulating Bypass Vlvs in b. Perform the following:

AUTO

1) Slowly open the MFW
  • HCV-480 Regulating Bypass Vlvs while
  • HCV-481 verifying the associated MFW Regulating Vlv compensates by closing slightly
2) Place MEW Regulating Bypass Vlvs in AUTO

ACTION/EXPECTED RESPONSENOT OBTAINED 14 Align Systems For Low Power Operation

a. Power-at 30% a. Go to Step 15.
b. Place AOV-3959. CNDST Bypass Vlv to CLOSE
c. Place LC-107. Hotwell Level Control. to MANUAL at 50%
d. Generator load < 100 MWe d. Go to Step 15.
e. Open turbine drain valves 15 Evaluate Plant Status
a. IF load was reduced more than 15% RTP in one hour. THEN notify RP to obtain primary samples required by ITS LCO 3.4.16
b. Power stable at desired level b. IF power > 20% and further reduction is required. THEN continue load reduction and return to Step 8.

IF power < 20% and further reduction is required. THEN go to Step 22.

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REV: 7 V

AP-TURB.5

.PAGE RAPID LOAD REDUCTION 10 of 20 STEP ACTION/EXPECTED RESPONSE 1RESPONSE NOT OBTAINEDI NOTE: With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3) 16 Establish Stable Plant Conditions:

a. Tavg - TRENDING TO TREF a. IF Tavg greater than Tref. THEN restore Tavg to Tref by one or more of the following:
  • RCS boration IF Tavg less than Tref. THEN restore Tavg to Tref by one or more of the following:

. Dilution of RCS

b. PRZR pressure - TRENDING TO b. Control PRZR pressure by one of 2235 PSIG IN AUTO the following:
  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.
c. PRZR level - TRENDING TO PROGRAM c. Perform the following:

IN AUTO CONTROL

1) Place affected charging pumps in MANUAL.
2) Adjust charging pump speed to restore PRZR level to program.

IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1. REACTOR COOLANT LEAK.

This Step continued on the next page.

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I I REV: 7 AP-TURB.5 RAPID LOAD REDUCTION

. .. PAGE 11 of 20

( S1 t ec pT i e R omS P rN Ev ous pa (Step 16 continued from previous page)

d. Rod insertion limit alarms - d. Borate and withdraw control rods EXTINGUISHED to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
e. Check MFW regulating valves - e. Perform the following:

RESTORING S/G LEVEL TO 52% IN AUTO 1) Place affected S/G(s) MFW regulating valve in MANUAL

2) Restore S/G level to 52%

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

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REV: 7 V.

AP-TURB.5 RAPID LOAD REDUCTION

. ., PAGE 12 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Normal Plant Conditions:

a. Restore EH controls
1) Place in OP PAN. IMP OUT
2) Place load rate thumbwheel to 10%/hour
3) Match setter and reference
b. Verify steam dump controller.

HC-484, in AUTO at 1005 psig

c. Verify annunciator G-15. STEAM c. WHEN Tavg within 51F of Tref.

DUMP ARMED - EXTINGUISHED THEN perform the following:

1) Ensure steam dump valves closed.
2) Reset steam dump.
d. Verify Rods in AUTO d. Place Rods in AUTO if desired.
e. Verify 431K in AUTO e. Place 431K in AUTO, if desired.
f. Verify PRZR spray valves in AUTO f. Place PRZR spray valves in AUTO, if desired.
g. Ensure PRZR Heaters restored:

o PRZR proportional heater breaker - CLOSED o WHEN PRZR mixing complete.

THEN place PRZR backup heater breaker to RESET. THEN AUTO

h. Verify one charging pump in AUTO h. Place one charging pump in AUTO.

if desired.

1`1-1

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION

. . PAGE 13 of 20 ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINED 18 Evaluate MCB Annunciator Status (Refer to AR Procedures)

NOTE: Refer to 0-9.3. NRC IMMEDIATE NOTIFICATION, for reporting requirements.

19 Notify Higher Supervision 20 Refer to 0-5.1, LOAD REDUCTIONS, for additional guidance 21 Return To Procedure Or Guidance In Effect 22 Transfer 4160V Auxiliary load from #11 Transformer (Refer to ATT-23.0, ATTACHMENT TRANSFER 4160V LOADS) 23 Check If Turbine Should Be Tripped

a. Check turbine load -
  • 15 MW a. Return to Step 15. WHEN turbine load is < 15 MW. THEN continue with Step 23b.
b. Trip the turbine

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REV: 7 I AP-TURB.5 RAPID LOAD REDUCTION PAGE 14 of 20 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 24 Verify Proper Operation Of Steam Dump:

a. Verify annunciator G-15. STEAM a. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
b. Condenser steam dump operating b. IF steam dump NOT available.

in AUTO THEN perform the following:

1) IF power is greater than 8%.

THEN ensure reactor trip and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

2) Adjust S/G ARV setpoints to 1005 psig and verify proper operation.
c. Tavg - TRENDING TO PROGRAM c. IF temperature less than 547 0F and decreasing. THEN perform the following:
1) Stop dumping steam
2) IF cooldown continues. THEN close both MSIVs.

IF temperature greater than 547 0F and increasing. THEN dump steam to stabilize and slowly decrease temperature to 547 0F.

IF Tavg can NOT be controlled.

THEN manually trip the reactor and go to'E-0. REACTOR TRIP OR SAFETY INJECTION.

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION

. ~PAGE 15 of 20.

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Reactor Is To Be Shutdown IF reactor is to be maintained (Consult Plant Staff If critical. THEN go to AP-TURB.1.

Necessary) TURBINE TRIP WITHOUT RX TRIP REQUIRED.

NOTE: Transition to E-0 is NOT required when the reactor trip breakers are opened in the following step.

26 Shutdown the Reactor

a. Place rods in MANUAL
b. Drive control rods until S 1%

RTP.

c. Press reactor trip pushbutton.
d. Verify reactor trip breakers d. Dispatch AO to locally open open. reactor trip breakers.
e. Verify MRPI indicates all e. IF one or more control rods NOT control and shutdown rods on fully inserted, THEN perform the bottom following:
1) Place RMW mode selector switch to BORATE.
2) Adjust boric acid flow control valve. FCV-110A. for desired flowrate.
3) Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).
4) Place RMW control to start and verify flow. IF flow can NOT be established. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION.

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 16 of 20 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED

, .

  • 4 . , . . . . 4 . .
  • 4 . . . *
  • 4* .4 * . . * . . .4
  • 4
  • i4 . . *4 * .

CAUTION IF ANY S/G LEVEL ABOVE 52%. THEN AFW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT S/G ISOLATION.

  • . * . . * . . . . . . * . . * . . . . * * * . * * * * * * . . . . . . . 4 . .

27 Check S/G Feed Flow Status:

a. Manually start both MDAFW pumps
b. Verify AFW flow - SUFFICIENT b. Perform the following:

FLOW TO MAINTAIN S/G LEVELS

1) Establish MFW flow using MFW regulating valve bypass valves.

IF MFW NOT available, THEN manually start TDAFW pump and establish flow.

2) Adjust feed flow to restore S/G to 52%.
3) Go to Step 28.
c. Verify MFW flow control valves - c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.
  • MFW regulating valves

. MFW bypass valves

d. Close MFW pump discharge valves
  • MOV-3977. A MFW pump
  • MOV-3976. B MFW pump
e. Stop any running MFW pump and place in PULL STOP
f. Place A and B MFW regulating and bypass valve control ers in manual at 0% demand
g. Adjust MDAFW pump flow to restore S/G level to 52%

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION

. PAGE 17 of 20 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 28 Establish Normal AFW Pump Shutdown Alignment:

a. Place AFW bypass switches to DEF
b. Close MDAFW pump discharge valves

. MOV-4007

. MOV-4008

c. Adjust AFW bypass valves to control S/G levels at 52%

. AOV-4480

  • AOV-4481

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 18 of 20 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 29 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1.

ATTACHMENT SD-2.

b. Perform the following as necessary:

o Open generator disconnects

  • 1G13A71
  • 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump (Refer to T-5F.

STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify Bus 11A and Bus liB c. IF either bus NOT energized.

energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2.

THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/BUS 12B.

d. Dispatch AO to perform ATT-17.0.

ATTACHMENT SD-1

ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED NOTE: Loss of forced air cooling may result in failure of NIS detectors.

30 Check If Source Range Detectors Should Be Energized:

a. Source range channels - a. Go to Step 30e.

DEENERGIZED

b. Check intermediate range flux - b. Continue with Step 31. WHEN EITHER CHANNEL LESS THAN flux is less than 10-10 amps on 10-10 AMPS any operable channel, THEN do Steps 30c. d and e.
c. Check the following: c. Continue with Step 31. WHEN either condition met. THEN do o Both intermediate range Steps 30d and e.

channels - LESS THAN 10-10 AMPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors - d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored. THEN refer to ER-NIS.1. SR MALFUNCTION, and go to Step 31.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

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. PAGE 20 of 20 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 31 Go to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

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REV: 7 AP-TURB.5 RAPID LOAD REDUCTION PAGE 1 of 1 AP-TURB.5 APPENDIX LIST TITLE

1) ATTACHMENT TRANSFER 4160V LOADS (ATT-23.0)
2) ATTACHMENT SD-1 (ATT-17.0)
3) ATTACHMENT SD-2 (ATT-17.1)
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