ML051370238

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Emergency Operating Procedures
ML051370238
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/28/2005
From: Marlow T
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML051370238 (37)
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Text

1503 Lake Road Ontario, NewYork 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, L1C April 28, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

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

Very truly yours,

- le- A- 4 4a" Thomas A. Marlow TAM/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

AP Index AP-CCW.2, Rev 20 AP-CCW.3, Rev 17 AP-RCC.3, Rev 7

( C (

NPSP0200 Ginna Nuclear Power Plant Thu 4/2812005 11:16:24 am E66429 PROCEDURE INDE> Page 1 of 2 INPUT PARAMETERS: TYPE: PRAP STATUSVALUE(S): EFQU 5 YEARS ONLY:

PRAP - ABNORMAL PROCEDURE V 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 06/26/2002 06/26/2007 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 020 04/2812005 06126/2002 06/2612007 EF AP-CCW.3 LOSS OF CCW- PLANT SHUTDOWN 017 0412812005 06/26/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 021 04/2612005 0612612002 06/2612007 EF AP-CVCS.1 CVCS LEAK 014 06/30/2004 06/03/2002 06/0312007 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 005 0411012005 02127/2004 02/2712009 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 012 09/17/2004 04/1612003 04/16/2008 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 028 01/2112005 06/2612002 06/26/2007 EF AP-ELEC2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY O11 06/10/2004 06/26/2002 06/26/2007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 013 01/2112005 0612612002 0612612007 EF AP-ELEC.13115 LOSS OF BUS 13/15 001 06/30/2004 0912412003 09/24/2008 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 009 01/2112005 06/2612002 06/26n2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17118 008 01/2112005 06126/2002 06/2612007 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 016 06/3012004 06126/2002 0612612007 AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/2002 04/1612003 0411612008 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 015 06/3012004 06126/2002 0612612007 AP-RCC.1 CONTINUOUS CONTROL ROD VATHDRAWALANSERTION 009 06130/2004 04/1612003 04/16/2008 AP-RCC2 RCC/RPI MALFUNCTION 012 04/1012005 21/20151/2 01/22/2007 AP-RCC.3 DROPPED ROD RECOVERY 007 04/2812005 02/2512003 02/2512008 EF AP-RCP.1 RCP SEAL MALFUNCTION 017 06/3012004 0412412003 04/2412008 EF AP-RCS.1 REACTOR COOLANT LEAK 017 06/30/2004 04/1612003 04/1612008 EF AP-RCS2 LOSS OF REACTOR COOLANT FLOW 012 06/3012004 04/16/2003 04/1612008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY O11 06/30/2004 04/0112002 01/22/2007 EF AP-RCS.4 SHUTDOWN LOCA 017 03/1812005 0413012003 04/30/2008 EF AP-RHR.1 LOSS OF RHR 019 04/3012003 04/3012003 0413012008 E:

AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS 015 04/0512005 04/3012003 04/3012008 E:

AP-SG.1 STEAM GENERATOR TUBE LEAK 004 04/1012005 06/26/2002 06/26/2007 E:

AP-SW.1 SERVICE WATER LEAK 021 09/17/2004 04/21/2003 04/21/2008 E:

AP-SW.2 LOSS OF SERVICE WATER 007 01/21/2005 11/20/50/3 10131/2006 E:

AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 014 04/10/2005 06/26/2002 06/26/2007 E:

( c. (I

  • l

. -4i¢ NPSP0200 Ginna Nuclear Power Plant -Thu 4/28/2005 11:16:24 am E66429 PROCEDURE INDE) Page 2 of 2 INPUT PARAMETERS: TYPE: PRAP STATUSVALUE(S): EFQU 5YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 021 04/10/2005 06/2612002 06/26/2007 EF AP-TURB.3 TURBINEVIBRATION 012 06/30/2004 06/26/2002 06/2612007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 018 04110/2005 04/30/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 008 04110/2005 06/26/2002 06/26/2007 EF PRAP TOTAL 34 GRAND TOTAL 34

EOP: TITLE:

REV: 2 0 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 10 GINNA STATION CONTROLLED COPY NUMBER _2_3 RESPONSIBI4 MANAGER EFETg -ZoA5 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: -

EOP: TIUE:

REV: 20 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: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 3 of 10 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDI SP 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 150 0F. OR UNTIL CCW IS RESTORED.

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

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

EOP: TITLE:

REV: 2 0 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 10 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED 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-O Immediate Actions done. THEN trip BOTH RCPs.
5) Place both CCW pumps in pull stop.
6) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

EOP: TITLE:

REV: 2 0 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 5 of 10 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I 3 Check CCW To Both RCPs: IF CCW lost to RCP(s), THEN perform the following:

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

flow 165 gpm 1250F alarm -

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

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

recorder) -

  • 2001F
  • 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: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION F DPAGE 6 of 10 ACTION/EXPECTED RESPONSE STP lRESPONSE 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.l, 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 Locally Check Seal Water Hx IF VCT level increasing AND FI-605 CCW Outlet Flow - NORMAL abnormally low. THEN bypass and (FI-605) isolate Seal Water Hx and, if desired, isolate Seal Return.

a. To bypass and isolate Hx perform the following:
1) Open seal bypass V-394
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. THEN close MOV-313.
c. Notify RP to sample RCS for chromates.

EOP: TITLE:

REV: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 10 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINEDI 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.

EOP: TITLE:

REV: 20

[ IAP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 8 of 10 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED SP 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-9.0. 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: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 9 of 10 ACTION/EXPECTED RESPONSE llRESPONSE SP 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:

AP-CCW.2 LOSS OF CCW DURING POWER OPERATION

. OPAGE 10 of 10 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED l 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: 20 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- .0)
2) ATTACHMENT EXCESS L/D (ATT-9.1)
3) ATTACHMENT NORMAL CCW FLOW (ATT-. 1)
4) ATTACHMENT LETDOWN (ATT-9.0)

I EOP: TITLE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE I of 12 GINNA STATION CONTROLLED COPY NUMBER ___3 RESPONSIBL )MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 17 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: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 3 of 12 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 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 150 0F. OR UNTIL CCW IS RESTORED.

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:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 4 of 12 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED STP 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 200'F 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: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 5 of 12 ACTION/EXPECTED RESPONSE llRESPONSE 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 Temp1 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:

0

- LESS THAN 195 E.

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

EOP: TIRE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 6 of 12 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl -

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.

EOP: TITLE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 7 of 12 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl

  • 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

EOP: TITLE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN.

PAGE 8 of 12 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I NOTE: o IF Seal Water Hx will be bypassed, THEN an increase in VCT temperature is expected.

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

9 Locally Check Seal Water Hx IF VCT level increasing AND FI-605 CCW Outlet Flow - NORMAL abnormally low. THEN bypass and (FI-605) isolate Seal Water lx and, if desired, isolate Seal Return as follows.

a. To bypass and isolate Hx perform the following:
1) Open seal bypass V-394
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: TIE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 9 of 12 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 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: TITE:

REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 10 of 12 STE P ACTION/EXPECTED RESPONSE - lRESPONSE NOT OBTAINEDl 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: REV: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 11 of 12 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED 14 Evaluate Plant Conditions:

a. RHR normal cooling - IN SERVICE a. Adjust S/G ARVs to stabilize RCS temperature and go to Step i5.
b. Check RCS Cooling: b. Perform the following:

o RCS temperature - STABLE OR 1) Increase SW from CCW Hx 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: 17 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 12 of 12 ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I SP 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: RE :1 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)

.E: TITL: REV: 7

.AP-RCC.3 DROPPED ROD RECOVERY PAGE 1 of 9 GINNA STATION CONTROLLED COPY NUMBER .

M3&iQP RESPONSIBX MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

4

l EOP: TITLE: REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 2 of 9 A. PURPOSE - This procedure provides the guidance necessary to control the plant during a transient resulting from a dropped control rod.

B. ENTRY CONDITIONS/SYMPTOMS

1. SYMPTOMS - The symptoms of DROPPED CONTROL ROD are;
a. Annunciator E-28, POWER RANGE ROD DROP ROD STOP

-5%/5 SEC, lit, or

b. Annunciator C-14, ROD BOTTOM ROD STOP, lit, or
c. MRPI indicates control rod(s) on bottom.

rEOP:

IP TITLE:

REV: 7 l AP-RCC.3 DROPPED ROD RECOVERY PAGE 3 of 9 .

ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I SP NOTE: A NIS or MRPI dropped rod signal will block AUTO out rod motion.

1 Verify Only One Rod Has IF 2 or more rods dropped. THEN Dropped trip the reactor AND go to E-O, REACTOR TRIP OR SAFETY INJECTION.

2 Place Rods To MANUAL CAUTION BANK ROD WITHDRAWAL SHOULD NOT BE PERFORMED UNTIL THE DROPPED ROD IS RECOVERED.

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.

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: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 4 of 9 ACTION/EXPECTED RESPONSE llRESPONSE STP 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:.

. 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. MEW Regulating Valves - d. Perform the following:

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

2) Restore S/G level to 52%

IF S/G can NOT be controlled manually, THEN refer to AP-FW.1.

ABNORMAL MAIN FEEDWATER FLOW.

EOP: TITLE:

REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 5 of 9 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 7 Check QPTR - LESS THAN 1.02 Refer to ITS section 3.2.4. I

EOP: TITLE:

REV: 7 AP-RCC.3 DROPPED ROD RECOVERY

. .PAGE 6 of 9 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 8 Evaluate Control Rod Operability:

a. Verify MRPI indicates rod on a. Perform the following:

bottom

1) Verify all NIS power range channels approximately equal.

IF a NIS PR channel malfunction is indicated, THEN defeat failed channel (Refer to ER-NIS.3. PR MALFUNCTION).

2) IF RCS temperature and NIS power range response indicates potential dropped rodlets or RCCA spider disengagement, THEN request Reactor Engineer perform a flux map.
3) Go to Step 9.
b. Direct I&C to locally investigate rod failure
c. Refer to ER-RCC.1. RETRIEVAL OF A DROPPED RCC
d. Rod failure identified and d. Perform the following:

corrected - DROPPED ROD REPAIRED

1) Consult Reactor Engineer and ITS section 3.1.4 for operational concerns.
2) IF the dropped rod can NOT be repaired. THEN go to ER-RCC.1, RETRIEVAL OF A DROPPED RCC.
3) Return to step 3.
e. Retrieve dropped rod (Refer to ER-RCC.1. RETRIEVAL OF A DROPPED ROD)
f. Perform PT-1 for the affected bank

P' : TITLE:

el REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 7 of 9 ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINED l 9 Check Reactor Conditions:

a. Rod insertion limit alarms - a. Borate as necessary and withdraw EXTINGUISHED 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.

. Dilute RCS

EOP: TITLE: REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 8 of 9 ACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED I 10 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 MEW regulating valves in e. Place MEW 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.

EOP: TIRE:

REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 9 of 9 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 11 Evaluate MCB Annunciator Status (Refer to AR Procedures)

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

12 Notify Higher Supervision 13 Return To Procedure Or Guidance In Effect

-END-1,J

EOP: TITLE: REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 1 of 1 AP-RCC.3 APPENDIX PAGE TITLE

1) ATTACHMENT EXCESS L/D (ATT-9.1)
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