ML051370238
| ML051370238 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/28/2005 |
| From: | Marlow T Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051370238 (37) | |
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
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NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE>
Thu 4/2812005 11:16:24 am 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 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP-CW.1 AP-ELEC.1 AP-ELEC2 AP-ELEC.3 AP-ELEC.13115 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR.2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 LEAKAGE INTO THE COMPONENT COOUNG LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW-PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)
LOSS OF BUS 13/15 LOSS OF SAFEGUARDS BUS 14/16 LOSS OF SAFEGUARDS BUS 17118 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD VATHDRAWALANSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP WITHOUT RX TRIP REQUIRED 017 06/30/2004 06/26/2002 020 04/2812005 06126/2002 017 0412812005 06/26/2002 021 04/2612005 0612612002 014 06/30/2004 06/03/2002 005 0411012005 02127/2004 012 09/17/2004 04/1612003 028 01/2112005 06/2612002 O11 06/10/2004 06/26/2002 013 01/2112005 0612612002 001 06/30/2004 0912412003 009 01/2112005 06/2612002 008 01/2112005 06126/2002 016 06/3012004 06126/2002 018 06/26/2002 04/1612003 015 06/3012004 06126/2002 009 06130/2004 04/1612003 012 04/1012005 21/20151/2 007 04/2812005 02/2512003 017 06/3012004 0412412003 017 06/30/2004 04/1612003 012 06/3012004 04/16/2003 O11 06/30/2004 04/0112002 017 03/1812005 0413012003 019 04/3012003 04/3012003 015 04/0512005 04/3012003 004 04/1012005 06/26/2002 021 09/17/2004 04/21/2003 007 01/21/2005 11/20/50/3 014 04/10/2005 06/26/2002 06/26/2007 06/2612007 06/26/2007 EF EF EF 06/2612007 EF 06/0312007 EF 02/2712009 EF 04/16/2008 EF 06/26/2007 EF 06/26/2007 EF 0612612007 09/24/2008 06/26n2007 06/2612007 0612612007 0411612008 0612612007 04/16/2008 01/22/2007 EF EF EF 02/2512008 EF 04/2412008 EF 04/1612008 EF 04/1612008 EF 01/22/2007 EF 04/30/2008 EF 0413012008 04/3012008 06/26/2007 04/21/2008 10131/2006 06/26/2007 E:
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-4i¢ NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)
-Thu 4/28/2005 11:16:24 am Page 2 of 2 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 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
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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: 2 0 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 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDI 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 1500F. OR UNTIL CCW IS RESTORED.
1 Check CCW Pump Status:
o Both CCW pump breaker white lights - EXTINGUISHED o Annunciator A-17. MOTOR OFF RCP CCWP - EXTINGUISHED Perform the following:
- a. Ensure standby CCW pump running.
IF no CCW pump can be operated.
THEN perform the following:
- 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).
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TITLE:
REV: 2 0 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 10 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE: MCB CCW surge tank level indication AUX BLDG. if possible.
- 2 Monitor CCW Surge Tank Level APPROXIMATELY 50% AND STABLE should be verified locally in the Perform the following:
- 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 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I 3 Check CCW To Both RCPs:
o Annunciator A-7 (A-15), RCP 1A (1B) CCW return Hi temp or low flow 165 gpm 1250F alarm -
EXTINGUISHED o RCP motor bearings temperature (PPCS Group Display-RCPS OR RCP temperature monitor RK-30A recorder) -
- a. Trip the reactor.
- b. WHEN all E-O Immediate Actions done, THEN trip affected RCP(s).
- c. Go to E-O. REACTOR TRIP OR SAFETY INJECTION.
- 4 Monitor If Letdown Should Be Isolated:
- a. Check annunciator A-12, Non-Regen Hx Letdown Out Hi Temp 1450 - EXTINGUISHED
- a. Isolate Normal Letdown:
- 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
- LESS THAN 195 0F
- b. Isolate Excess Letdown:
- 1) Close excess letdown flow control valve, HCV-123.
- 2) Close excess letdown isolation valve. AOV-310.
[ EOP:
TITLE:
REV:
2 0 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION F
DPAGE 6 of 10 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 5 Check CCW Valve Alignment -
NORMAL
- a. Align CCW valves as necessary.
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 CCW Outlet Flow -
NORMAL (FI-605)
IF VCT level increasing AND FI-605 abnormally low. THEN bypass and 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.
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TITLE:
REV: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 10 SP ACTION/EXPECTED RESPONSE llRESPONSE 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:
o Level - STABLE o Sump A pumps - OFF
- 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).
. RCP A. MOV-749A and MOV-759A
- RCP B. MOV-749B and MOV-759B
- 4) Go to E-O. REACTOR TRIP OR SAFETY INJECTION.
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TITLE:
REV: 20 IAP-CCW.2 LOSS OF CCW DURING POWER OPERATION
[
PAGE 8 of 10 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 8 Check for CCW Leakage In AUX BLDG:
Dispatch AO to investigate AUX 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:
- 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 Letdown -
IN SERVICE IF normal letdown desired, THEN 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)
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REV: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 9 of 10 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 11 Check CCW System Leak Isolated
- a. Surge tank level - APPROXIMATELY 50%
- a. IF level less than 50%.
continue filling.
THEN 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 -
IDENTIFIED AND CORRECTED
- a. Return to Step 1.
- b. IF shutdown required. THEN refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN.
. EOP:
TITLE:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION OPAGE 10 of 10 SP ACTION/EXPECTED RESPONSE llRESPONSE 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-
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TITLE:
REV: 20 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 1 AP-CCW.2 APPENDIX LIST TITLE 1) 2)
3) 4)
ATTACHMENT AT POWER CCW ALIGNMENT ATTACHMENT EXCESS L/D ATTACHMENT NORMAL CCW FLOW ATTACHMENT LETDOWN (ATT-.0)
(ATT-9.1)
(ATT-. 1)
(ATT-9.0)
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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:
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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 SP ACTION/EXPECTED RESPONSE llRESPONSE 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 1500F. 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:
o Both CCW pump breaker white lights - EXTINGUISHED o Annunciator A-17, MOTOR OFF, RCP CCWP - EXTINGUISHED IF a CCW pump has tripped. THEN perform the following:
- a. Ensure standby CCW pump running.
- b. Attempt to reset and start the affected CCW pump if required for cooling.
NOTE:
MCB surge tank level indication Bldg, if possible.
2 Check CCW Surge Tank Level -
APPROXIMATELY 50% AND STABLE should be verified locally in the Aux IF CCW surge tank level is decreasing, THEN perform the following:
- a. Open RMW to CCW surge tank, MOV-823.
- b. Start RMW pump(s).
- d. Control CCW surge tank level at approximately 50% while continuing with Step 3.
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TITLE:
REV: 17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 4 of 12 STP ACTION/EXPECTED RESPONSE llRESPONSE 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:
o Annunciator A-7 (A-15), RCP A (B) CCW RETURN HI TEMP OR LOW FLOW 165 GPM 125 0F -
EXTINGUISHED o Verify RCP motor bearing temperatures (PPCS Group Display - RCPS or RK-30A recorder) - LESS THAN 200'F
- 1) Stop the affected RCP(s).
- 2) IF no RCPs running. THEN verify natural circulation (Refer to ATT-13.0.
ATTACHMENT NC).
- 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)
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TITLE:
REV: 17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 5 of 12 STP ACTION/EXPECTED RESPONSE llRESPONSE 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:
LESS THAN 1950E.
- 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
- b. Verify Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSIG
- EXTINGUISHED
- a. Go to Step 6.
- b. Dispatch AO to the AUX BLDG to perform the following:
- MOV-738A
- MOV-738B
- 2) Investigate for CCW leaks.
6 Check RCS Temperature -
STABLE OR DECREASING IF RHR cooling available, THEN 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 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl
- 7 Monitor CCW Surge Tank Level GREATER THAN 10%
Perform the following:
- 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 -
ANY LEAKAGE INDICATED Go to Step 13.
EOP:
TITLE:
REV: 17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN.
PAGE 8 of 12 SP ACTION/EXPECTED RESPONSE llRESPONSE 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 CCW Outlet Flow -
NORMAL (FI-605)
IF VCT level increasing AND FI-605 abnormally low. THEN bypass and 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.
EOP:
TIE:
REV:
17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 9 of 12 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 10 Check For CCW Leakage In CNMT:
o Level - STABLE o Sump A pumps - OFF
- b. RCP oil levels - STABLE
- b. IF any RCP oil level increasing uncontrollably. THEN perform the following:
- 1) Stop affected RCP.
. 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 BLDG:
Dispatch AO to investigate AUX 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:
- 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 Flow Rates -
AS REQUIRED FOR PLANT CONDITIONS (Refer to ATT-1.1, ATTACHMENT NORMAL CCW FLOW)
Realign valves to restore CCW to individual components.
EOP:
TITLE:
REV:
17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 11 of 12 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 14 Evaluate Plant Conditions:
- a. RHR normal cooling - IN SERVICE
- b. Check RCS Cooling:
o RCS temperature - STABLE OR DECREASING o CCW system status - ADEQUATE FOR RHR NORMAL COOLING
- b. Perform the following:
- CCW Hx A. V-4619
. CCW Hx B. V-4620
- 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)
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17 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 12 of 12 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 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-
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RE :1 AP-CCW.3 LOSS OF CCW -
PLANT SHUTDOWN PAGE 1 of 1 AP-CCW.3 APPENDIX LIST TITLE 1) 2)
3)
ATTACHMENT NC ATTACHMENT EXCESS L/D ATTACHMENT NORMAL CCW FLOW (ATT-13.0)
(ATT-9.1)
(ATT-1. 1)
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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:
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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.
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IP REV: 7 l AP-RCC.3 DROPPED ROD RECOVERY PAGE 3 of 9 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I NOTE: A NIS or MRPI dropped rod signal will block AUTO out rod motion.
1 Verify Only One Rod Has Dropped IF 2 or more rods dropped. THEN 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, STEAM DUMP ARMED -
EXTINGUISHED 5 Check Main Generator Load -
GREATER THAN 15 MW Verify steam dump valves closed.
IF NOT. THEN place STEAM DUMP MODE SELECTOR switch to MANUAL and close valves.
IF load can NOT be stabilized above 15 MW. THEN trip the turbine and go to AP-TURB.1. TURBINE TRIP WITHOUT RX TRIP REQUIRED.
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REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 4 of 9 STP ACTION/EXPECTED RESPONSE llRESPONSE 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 restore more of greater than Tref, THEN Tavg to Tref by one or the following:.
- Insert control rods
. Boration IF Tavg restore more of less than Tref, THEN Tavg to Tref by one or the following:
. Reduce turbine load
- Dilution of RCS
- b. PRZR pressure - TRENDING TO 2235 PSIG IN AUTO
- b. Control PRZR pressure by one of 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 IN AUTO CONTROL
- c. Perform the following:
- 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 -
RESTORING S/G LEVEL TO 52% IN AUTO
- d. Perform the following:
- 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.
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REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 5 of 9 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 7 Check QPTR -
LESS THAN 1.02 Refer to ITS section 3.2.4.
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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
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el REV: 7 AP-RCC.3 DROPPED ROD RECOVERY PAGE 7 of 9 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED l 9 Check Reactor Conditions:
- a. Rod insertion limit alarms -
EXTINGUISHED
- b. NIS PR AI - WITHIN +/- 5% OF TARGET VALUE
- a. Borate as necessary and withdraw control rods to clear insertion limit alarms (refer to affected rod bank alarm response procedures if necessary).
- b. Perform one or more of the following to restore AI to within limits.
- Borate RCS
. Dilute RCS
- Restore control rods to desired position
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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
- b. Verify PRZR spray valves in AUTO
- c. Verify PRZR heaters restored:
o PRZR proportional heaters breaker - CLOSED o PRZR backup heaters breaker -
RESET. IN AUTO
- d. Verify one charging pump in AUTO
- e. Verify MEW regulating valves in AUTO
- 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 DUMP ARMED - EXTINGUISHED
- a. Place 431K in AUTO, if desired.
- b. Place PRZR spray valves in AUTO, if desired.
- c. Restore PRZR heaters, if desired.
- d. Place one charging pump in AUTO, if desired.
- e. Place MEW regulating valves in AUTO, if desired.
- g. WHEN Tavg within 51F of Tref.
THEN perform the following:
- 1) Ensure steam dump valves closed.
- 2) Reset steam dump.
- h. Place rods in AUTO, if desired.
- h. Verify rods in AUTO
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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
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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)