ML022120502
| ML022120502 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/25/2002 |
| From: | Widay J Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, NRC/NRR/DLPM/LPD1 |
| References | |
| NPSP0200 | |
| Download: ML022120502 (189) | |
Text
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 07/25/02 PAGE: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAR PRAP PRE PRECA PRES ST)ATUS: EF QU S Y'EARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDUIRE TITLE REV DATE REVIEW REVIEW AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 06/26/02 06/26/02 06/26/07 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 016 06/26/02 06/26/02 06/26/07 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 014 06/26/02 06/26/02 06/26/07 AP-CR.1 CONTROL ROOM INACCESSIBILITY 018 06/26/02 06/26/02 06/26/07 AP-CVCS.1 CVCS LE] AK 013 06/26/02 06/03/02 06/03/07 AP-CVCS.3 LOSS OF ALL CHARGING FLOW 003 06/26/02 02/26/99 02/26/04 AP-CW.1 LOSS OF A CIRC WATER PUMP 011 06/26/02 05/01/98 05/01/03 AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 023 06/26/02 06/26/02 06/26/07 AP-ELEC.2 SAFEGUGARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 06/26/02 06/26/02 06/26/07 AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 011 06/26/02 06/26/02 06/26/07 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 004 06/26/02 06/26/02 06/26/07 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 004 06/26/02 06/26/02 06/26/07 AP-FW.1 ABNORMAl L MAIN FEEDWATER FLOW 014 07/25/02 06/26/02 06/26/07 AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/02 05/01/98 05/01/03 AP-PRZR.1 ABNORMAl U PRESSURIZER PRESSURE 013 06/26/02 06/26/02 06/26/07 AP-RCC.1 CONTINU( OUS CONTROL ROD WITHDRAWAL/INSERTION 008 06/26/02 05/14/98 05/14/03 AP-RCC.2 RCC/RPI MALFUNCTION 010 06/26/02 01/22/02 01/22/07 AP -RCC.3 DROPPED ROD RECOVERY 0O5 06/26/02 02/27/98 02/27/03 AP-RCP. 1 RCP SEAL MALFUNCTION 014 06/26/02 05/01/98 05/01/03 AP-RCS.I REACTOR COOLANT LEAK 016 06/26/02 05/01/98 05/01/03 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 011 06/26/02 05/01/98 05/01/03 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 010 06/26/02 04/01/02 01/22/07 AP-RCS.4 SHUTDOWN LOCA 012 06/26/02 05/01/98 05/01/03 AP -RHR.I LOSS OF RHR 018 07/25/02 05/01/98 05/01/03 EF
&3
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 07/25/02 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAR PRAP PRE PRECA PRES STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDIRE TITLE REV DATE REVIEW REVIEW ST AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 012 o5/30/02 03/31/00 03/31/05 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 002 06/26/02 06/26/02 06/26/07 EF AP-SW.1 SERVICE WATER LEAK 017 06/26/02 06/03/98 06/03/03 EF AP-SW.2 LOSS OF SERVICE WATER 002 06/26/02 10/31/01 10/31/06 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.2 TURBINE LOAD REJECTION 018 06/26/02 06/26/02 06/26/07 EF AP-TURB.3 TURBINE VIBRATION 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 016 07/25/02 05/01/98 05/01/03 EF AP-TURB.5 RAPID LOAD REDUCTION 006 06/26/02 06/26/02 06/26/07 EF TOTAL FOR PRAP 33
REPORT NO. 01 GTNNA NUCLEAR POWER PLANT 07/25/02 PAGE: 32 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRE EMERGENCY PROCEDURE PARAMETERS: DOC TYPES - PRAR PRAP PRE PRECA PRES STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDWIRE TITLE REV DATE REVIEW REVIEW ST E-0 REACTOR TRIP OR SAFETY INJECTION 031 05/30/02 05/01/98 05/01/03 EF E-l LOSS OF REACTOR OR SECONDARY COOLANT 025 07/25/02 05/01/98 05/01/03 EF E-2 FAULTED STEAM GENERATOR ISOLATION 010 07/25/02 05/01/98 05/01/03 EF E-3 STEAM GENERATOR TUBE RUPTURE 031 07/25/02 05/01/98 05/01/03 EF TOTAL FOR PRE
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 07/25/02 PAGE: 33 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRECA EMERGENCY CONTINGENCY ACTIONS PROC PARAMETERS: DOC TYPES - PRAR PRAP PRE PRECA PRES STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDUIRE TITLE REV DATE REVIEW REVIEW ST ECA- 0.0 LOSS OF ALL AC POWER 024 06/14/02 05/01/98 05/01/03 EF ECA- 0. 1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED 020 07/25/02 05/01/98 05/01/03 EF ECA- 0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 013 07/25/02 05/01/98 05/01/03 EF ECA- 1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 021 07/25/02 05/01/98 oS/01/03 EF ECA- 1 .2 LOCA OUTSIDE CONTAINMENT 005 05/01/98 o5/01/98 05/01/03 EF ECA-2. 1 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 023 05/02/02 05/01/98 05/01/03 EF ECA-3. 1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED 023 07/25/02 05/01/98 05/01/03 EF ECA- 3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED 026 07/25/02 05/01/98 05/01/03 EF ECA- 3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 027 07/25/02 05/01/98 05/01/03 EF TOTAL FOR PRECA
REPORT NO. 01 GINNA NUCLEAR POWER PLANT 07/25/02 PAGE: 34 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE! PRES EQUIPMENT SUB- PROCEDURE PARAMETERS: DOC TYPES PRAR PRAP PRE PRECA PRES STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMRER PROCED*JJ RE TITLE REV DATE REVIEW REVIEW ST ES 0.0 REDIAGN( OSIS 010 05/01/98 05/01/98 05/01/03 EF ES-0.1 REACTOR TRIP RESPONSE 020 07/25/02 05/01/98 05/01/03 EF ES-0.2 NATURAL CIRCULATION COOLDOWN 012 05/01/98 05/01/98 05/01/03 EF ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL 008 05/01/98 05/01/98 05/01/03 EF ES-1.I SI TERMINATION 022 07/25/02 05/01/98 05/01/03 EF ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 024 07/25/02 05/01/98 05/01/03 EF ES-I. 3 TRANSFER TO COLD LEG RECIRCULATION 033 07/25/02 05/01/98 05/01/03 EF ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 014 07/25/02 05/01/98 05/01/03 EF ES- 3.2 POST-SGTR COOLDOWN USING BLOWDOWN 015 07/25/02 05/01/98 05/01/03 EF ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 015 07/25/02 05/01/98 05/01/03 EF TOTAL FOR PRES 10
REPORT NO. 01 GINNA NUCI EAR POWER PLANT 07/25/02 PAGE: 3 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRFR FUNCTIONAr, RESTORATION GUIDELINE PROC PARAMETERS: DOC TYPES - PRFR PRER STATUS: EF QU 5 YYEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDPJRE TITLE REV DATE REVIEW REVIEW ST FR-C 1 RESPONSE TO INADEQUATE CORE COOLING 019 07/25/02 05/01/98 05/01/03 EF FR-C. 2 RESPONSE TO DEGRADED CORE COOLING 016 07/25/02 05/01/98 05/01/03 EF FR-C. 3 RESPONSE TO SATURATED CORE COOLING 008 05/01/98 05/01/98 05/01/03 EF FR-H. 1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 026 07/25/02 05/01/98 05/01/03 EF FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 004 05/01/98 05/01/98 05/01/03 EF FR-H. 3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 005 05/01/98 05/01/98 05/01/03 EF FR-H. 4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 004 05/01/98 05/01/98 05/01/03 EF FR-H 5 RESPONSE TO STEAM GENERATOR LOW LEVEL 008 05/02/02 05/01/98 05/01/03 EF FR-1. 1 RESPONSE TO HIGH PRESSURIZER LEVEL 014 10/31/01 05/01/98 05/01/03 EF FR-1.2 RESPONSE TO LOW PRESSURIZER LEVEL 009 10/31/01 05/01/98 05/01/03 EF FR- .3 RESPONSE TO VOIDS IN REACTOR VESSEL 016 10/31/01 05/01/98 05/01/03 EF FR-P. 1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 024 05/02/02 05/01/98 05/01/03 EF FR-P. 2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION 007 05/01/98 05/01/98 05/01/03 EF FR-S. I RESPONSE TO REACTOR RESTART/ATWS 014 07/25/02 05/01/98 05/01/03 EF FR-S. 2 RESPONSE TO LOSS OF CORE SHUTDOWN 008 05/01/98 05/01/98 05/01/03 EF FR- Z. 1 RESPONSE TO HIGH CONTAINMENT PRESSURE 005 12/14/98 05/01/98 05/01/03 EF FR-Z. 2 RESPONSE TO CONTAINMENT FLOODING 004 01/14/99 05/01/98 05/01/03 EF FR-Z. 3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 004 05/01/98 05/01/98 05/01/03 EF TOTAL FOR PRFR 18
EOP: TITLE:
REV: 14 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE I of 13 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE ATER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP: TITLE: REV: 14 AP-FW.I 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
- 2. SYMPTOMS - The symptoms of ABNORMAL MAIN FEEDWATER FLOW are;
- a. Annunciator G-3(5), S/G A(B) LEVEL DEVIATION +/- 7%, lit, or
- b. Annunciator G-19(21), S/G A(B) FLOW MISMATCH, lit, or
- c. Annunciator G-20, ADFCS SYSTEM SWITCH TO MANUAL, lit, or
- d. Annunciator K-18, MAIN FEEDWATER PUMPS TRIPPED, lit, or
- e. Low indicated MFW pump suction flow on 1 pump, or
- f. MFW pump indicates tripped, or
- g. MFW pump discharge valve indicates shut.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check MFW Flow - LESS THAN Perform the following:
STEAM FLOW
- a. Place affected SIG(s) MFW regulating valve and bypass valve in MANUAL.
- b. Restore S/G level to 52%.
IF S/G level greater than 52% AND can NOT be controlled manually, THEN perform the following:
- a. Trip the reactor.
- b. Stop all running MFW pumps.
- c. Close both MFW pump discharge valves.
- d. Go to E-0, REACTOR TRIP OR SAFETY INJECTION.
STEP ACTION /EXPECTED RESPONSE RESPONSE NOT 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 : 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
EOP: TITLE:
REV: 14 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 5 of 13 STEP ACTION/EXPECTED RESPONSE
] RESPONSE NOT OBTAINED 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.
STE ACTION/EXPECTED RESPONSEI RESPONSE 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-0. REACTOR TRIP OR SAFETY INJECTION.
STEP ACTION/EXPECTED RESPONSE RESPONS 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:
o Insert control rods
- 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:
e 431K in manual e 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.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 6 continued from previous page)
- 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 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
SSTEP ACTION/EXPECTED RESPONSEI
. RESPONSE 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.
STEP ACION /EXPECTED RESPONSE RESPONSE 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.
- 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°F 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.
EOP: TITLE:
REV: 14 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW PAGE 11 of 13 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 o MOV-3504A e MOV-3505A
- c. Direct AO to locally isolate S/G blowdowns. (Refer to T-14N, BLOWDOWN SYSTEM FLOW CHANGES)
- 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
I SACTION/EXPECTED RESPONSE - I-I RESPONSE NOT OBTAINED NOT OBTAINED l
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 TRIENDING 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 "547OF dump OR manually control steam dump as necessary.
STEP ACTION/EXPECTED RESPONSE 7 RESPONSE NOT OBTAINEDt 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
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONIlAMNAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A. PURPOSE - This procedure provides guidance in the event of a loss of RHR cooling at or above normal loop levels.
(i.e. RCS loop levels of 64 inches or greater)
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from;
- a. FR-C.3, RESPONSE TO SATURATED CORE COOLING, or
- b. AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F), when RHR flow can NOT be restored, or
- 2. SYMPTOMS - The following are symptoms of LOSS OF RHR;
- 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 temperature while on RHR cooling, or
- d. Erratic or no flow on FI-626, RHR Loop Flow, or
- e. Annunciator J-9, SAFEGUARD BREAKER TRIP, lit.
NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
1 Check PRZR Wide Range Level IF RCS loop level indicator in GREATER THAN 0 INCHES service and loop level less than 64 inches. THEN go to AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.
2 Check RHR Pumps - AT LEAST IF running pump tripped due to loss ONE RUNNING of NPSH, THEN go to step 4.
IF NOT. THEN go to step 11.
- *A* ** IO*. .*. . . . . *. . . *.. **.
- OAI*. .O. .
CAUTION IF BOTH RHR PUMPS RUNNING WITH DISCHARGE CROSSTIES OPEN, THEN TOTAL RHR FLOW SHOULD BE MAINTAINED GREATER THAN 1200 GPM.
3 Check If RHR Pump(s) Should Be Stopped:
- a. RHR pump ANY RUNNING a. Go to Step 4.
- b. Check RHR pump flow - LESS THAN b. Manually decrease RHR flow to 1500 GPM PER OPERATING PUMP less than 1500 gpm per operating pump. IF RHR flow can NOT be controlled from the MCB, THEN perform the following:
- 1) Stop running RHR pump.
"*A RHR Hx, HCV-625 handwheel
"*B RHR Hx, HCV-624 handwheel
- 3) Start an RHR pump.
- c. RHR pumps cavitating: c. Go to Step 19.
"o RHR pump flow - OSCILLATING
-OR "o RHR pump NPSH - APPROXIMATELY ZERO (PPCS Group Display NPSH)
- d. Stop RHR pumps
CAUTION 0 DO NOT INITIATE ANY ACTIONS WHICH MAY ADD POSITIVE REACTIVITY TO THE CORE.
"o NOTIFY S/G OFFICE THAT CNMT BREATHING AIR MAY BE LOST.
"o IF REFUELING IN PROGRESS, THEN STOP REFUELING OPERATIONS (NOTIFY REFUELING SRO).
NOTE: Personnel remaining in CNMT to assist in event mitigation should consult Health Physics for changes in radiological concerns.
4 Initiate Actions To Protect Personnel In CNMT:
- a. Evacuate non-essential personnel from CNMT
- c. Initiate monitoring of CNMT area c. Refer to appropriate alarm and process radiation monitors response procedures for required actions.
- d. Verify CNMT penetrations with d. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, close all CNMT direct access to outside penetrations to outside atmosphere - CLOSED (Refer to atmosphere.
ATT 3.1, ATTACHMENT CNMT CLOSURE)
- *EP* A **O O I *EXPECTED
- *
- I RESPONSE NOT OBTAINE*D CAUTION SYSTEM MAY BE PRESSURIZED. EXTRA CARE SHOULD BE EXERCISED WHEN OPERATING THE RHR VENT VALVE.
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.
5 Vent RHR System As Necessary
- a. Check vent hose at RHR suction a. Go to step 6.
V-2764 - INSTALLED
- b. Check RCS temperature LESS b. Go to step 6.
THAN 200OF
- d. Direct AO to vent RHR suction line from loop A at V-2764 (in CNMT by loop A) 6 Check RHR Cooling Valve Manually or locally align valves as Alignment - NORMAL (Refer to necessary.
ATT-14.O, ATTACHMENT NORMAL RHR COOLING)
AT *..*........
N XE E RS N*
- RSO ... E NOT 0BTANED *
- CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.
7 Check IA Available For RHR Perform the following:
Flow Control:
- a. Manually start adequate air o Verify adequate air compressors compressors (75 kw each). 1F RUNNING air compressors can NOT be started manually, THEN dispatch o Verify IA pressure GREATER AO to locally reset and start THAN 60 PSIG compressors (75 kw each).
o IA available to HCV-624 AND IF electric air compressor(s)
HCV-625 can NOT be restored. THEN start diesel air compressor. (Refer to ATT-I1.2, ATTACHMENT DIESEL AIR COMPRESSOR)
- b. IF IA pressure can NOT be restored, THEN perform the following:
e A RHR Hx, HCV-625 handwheel
- B RHR Hx, HCV-624 handwheel
- 2) WHEN conditions permit, THEN refer to AP-IA.1, LOSS OF INSTRUMENT AIR, to restore IA.
- 8 Monitor RCS Temperature Perform the following:
GREATER THAN 2000F
- b. Go to step 10.
CAUTION "o CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATION "o UNSTABLE OR FLUCTUATING LEVEL INSTRUMENTS SHOULD NOT BE RELIED ON FOR INDICATION OF RCS INVENTORY.
9 Verify RCS Intact: Perform the following:
o PRZR level GREATER THAN 5% AND a. Verify charging line flow STABLE control valve, HCV-142, open as necessary.
0 RCS pressure STABLE
- b. Ensure charging line valve to
" RCS subcooling based on core loop B cold leg, AOV-294, open.
exit T/Cs GREATER THAN 0°F USING FIG-1.0, FIGURE MIN c. Start charging pumps as SUBCOOLING necessary.
"o RCS vent paths - CLOSED d. Control charging pump speed and letdown flow to stabilize RCS conditions.
"* PRZR pressure
"* PRZR level
"* Loop level IF charging flow greater than 75 gpm with letdown isolated OR unable to verify RCS inventory, THEN go to AP-RCS.4, SHUTDOWN LOCA.
STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 10 Establish Conditions To Start RHR Pump:
- a. RHR pump AVAILABLE a. Perform the following:
- 1) Start trending core exit TCs.
in service
- CCW Hx A, V-4619 o CCW Hx B, V-4620 "o 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.
"o Check CCW flow
- 4900 gpm 3) IF > 4900 gpm CCW flow (Fl 619) required for desired RHR cooling, THEN notify the Shift Supervisor.
IF CCW can NOT be restored, THEN continue with Step 11 while attempting to restore CCW (Refer to AP-CCW.3, LOSS OF CCW PLANT SHUTDOWN).
- c. Close RHR pump flow control valves (controllers at 100%
demand)
- HCV-624 e HCV 625
- d. Place RHR Hx bypass valve, HCV-626, to MANUAL and close valve
CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL OR PRESSURE DECREASE DUE TO SHRINK OR VOID COLLAPSE.
11 Restore RHR Flow:
RUNNING
- b. Check RHR flow - LESS THAN b. Manually adjust RHR flow to less 1500 GPM PER PUMP than 1500 gpm per pump.
- c. Adjust RHR Hx bypass flow control valve, HCV-626, to desired flowrate
- d. Place RHR Hx bypass flow control valve, HCV-626, controller in AUTO
- e. RHR flow - RESTORED e. Perform the following:
- 1) Start trending core exit T/Cs.
SACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI 12 Monitor RCS Temperature:
- a. RCS temperature STABLE OR a. IF RCS closed. THEN go to DECREASING Step 13. IF RCS open to atmosphere, THEN go to Step 18.
- b. Go to Step 21 13 Check Any S/G Level - GREATER Verify at least 200 gpm AFW flow THAN 17% available. IF NOT, THEN go to Step 19.
14 Check RCS Pressure - GREATER Increase RCS pressure to greater THAN 300 PSIG than 300 psig. IF RCS pressure can NOT be increased, THEN go to Step 19.
15 Check RCP Status - ANY RCP Perform the following:
RUNNING
- a. Establish conditions for starting an RCP.
"o Verify bus 11A or 1lB energized.
"o Refer to ATT-15.0, ATTACHMENT RCP START.
- b. 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.
16 Establish Condenser Steam Dump Manual Control:
- a. Verify condenser available: a. Perform the following:
"o Any MSIV OPEN 1) Place S/G ARV controller in MANUAL and adjust ARVs to "o Annunciator G-15. STEAM DUMP stabilize RCS temperature.
ARMED - LIT
- 2) Go to Step 17.
- b. Place condenser steam dump controller HC-484 in MANUAL
- c. Place steam dump mode selector switch to MANUAL
- a. RCS temperature STABLE OR a. IF dumping steam does NOT DECREASING provide adequate cooling, THEN perform the following:
- 1) Initiate S/G blowdown from both S/Gs.
- 2) Maintain both S/G levels stable by controlling AFW flow.
- 3) Go to Step 19.
- b. Go to Step 20
18 Check RCS Conditions:
- a. Rx vessel head REMOVED a. Go to Step 19.
- b. Stop refueling operations if in progress
- c. Verify Refueling Cavity Level c. Increase refueling cavity level GREATER THAN 23 FEET ABOVE to greater than 23 feet (Refer VESSEL FLANGE to 0-15.3, FILLING REFUELING CANAL).
- d. Verify refueling cavity sweep d. Locally start refueling cavity fans - RUNNING sweep fans if available.
19 Check CCW System Operation: To restore CCW cooling to RHR Hxs, perform the following:
"o CCW pumps - AT LEAST ONE RUNNING
DECREASING
- b. Increase SW from CCW Hx "o Annunciator A-21, COMP COOLING HX OUT HI TEMP - EXTINGUISHED o CCW Hx A, V-4619 e 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
- d. IF > 4900 gpm CCW flow required "o CCW flow _<4900 gpm (Fl-619) for desired RHR cooling (FI-619), THEN 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).
NOTE: Consult with Plant Staff to determine alternatives for long term cooling.
20 Monitor RHR Cooling: Perform the following:
"o RHR cooling RESTORED a. Evaluate alternatives for long term cooling (Consult Plant "o RCS temperature - STABLE OR Staff)
DECREASING
"* Consider establishing secondary heat sink
"* Refer to ER-RHR.l. RCDT PUMP OPERATION FOR CORE COOLING
"* Consider RCS feed and bleed
- c. Return to Step 2.
21 Evaluate MCB Annunciator Status (Refer to AR Procedures)
NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
22 Notify Higher Supervision 23 Return to Procedure Or Guidance In Effect END
AP-RHR.l APPENDIX LIST TITLE
- 1) FIGURE MIN SUBCOOLING (FIG-1.0)
- 2) ATTACHMENT NORMAL RHR COOLING (ATT-14.0)
- 3) ATTACHMENT RCP START (ATT- 15. 0)
- 4) ATTACHMENT NC (ATT- 13. 0)
- 5) ATTACHMENT CNMT CLOSURE (ATT-3.1)
- 6) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
EOP: TITLE: REV: 16 P-TURB.4 LOSS OF CONDENSER VACUUM PAGE 1 of 11 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE AGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP: TITLE:
P-TURB.4 LOSS OF CONDENSER VACUUM PAGE 2 of 11 A. PURPOSE - This procedure provides the necessary actions to control the plant with decreasing condenser vacuum.
B. ENTRY CONDITIONS/SYMPTOMS
- 2. SYMPTOMS - The symptoms of LOSS OF CONDENSER VACUUM are;
- a. Low or decreasing condenser vacuum, or
- b. Annunciator H-7, CONDENSER HI PRESSURE 25.5" HG, lit, or
- c. PPCS high condenser backpressure alarm, or
- d. Unexplained decreasing generator output, or
- e. Annunciator 1-18, CONDENSER EXP JOINT A LO LEVEL, or
- f. Annunciator 1-19, CONDENSER EXP JOINT B LO LEVEL.
STEPH ACToN/ExPECTE RESoNS RESPoNSE NoT OBTAINED 1 Check Condenser Circulating IF a loss of circulating water has Water System occurred, THEN go to AP-CW.1, LOSS OF A CIRC WATER PUMP.
"o CW pump discharge valves - BOTH OPEN "o CW pumps BOTH RUNNING
EOP: TITLE:
REV: 16 AP-TURB.4 LOSS OF CONDENSER VACUUM PAGE 4 of 11
CAUTION o TURBINE LOAD DECREASE SHOULD BE COMPLETED AS QUICKLY AS POSSIBLE WHILE MINIMIZING THE AMOUNT OF STEAM DUMP OPERATION.
o EXCESSIVE BACK PRESSURE MAY RESULT IN SEVERE TURBINE BLADE VIBRATION.
MINIMIZE TIME OUTSIDE THE SATISFACTORY OPERATION REGION.
- 2 Check Condenser Indications:
- a. Turbine back pressure EACH a. IF back pressure is in the DO CONDENSER WITHIN THE NOT OPERATE region for SATISFACTORY OPERATING REGION OF > 5 minutes, THEN perform the FIG-13.0. FIGURE BACK PRESSURE following:
o IF power > P-9. THEN trip the reactor and go to E-0, REACTOR TRIP OR SAFETY INJECTION.
o IF power < P-9, THEN trip the turbine and go to AP-TURB.1.
TURBINE TRIP WITHOUT RX TRIP REQUIRED.
IF in the AVOID region, THEN adjust turbine load to return to the SATISFACTORY OPERATING REGION.
- b. Condenser vacuum - STABLE OR b. WHILE continuing with this IMPROVING procedure, decrease turbine load to stabilize condenser vacuum.
(Refer to AP-TURB.5. RAPID LOAD REDUCTION)
IF condenser vacuum can NOT be stabilized, THEN perform the following:
- 1) Decrease turbine load to less than 15 MW.
- 2) Trip turbine.
- 3) Go to AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED.
3 Dispatch AO To Perform Local Actions To Attempt To Restore Condenser Vacuum (Refer to ATT-6.0, ATTACHMENT COND VACUUM)
CAUTION "o D/P LIMITS ON THE GENERATOR HYDROGEN COOLER AND CONDENSATE COOLER SHOULD NOT BE EXCEEDED (DIP LIMITS INDICATED AT DIP METERS AT MCB REAR).
"o CLOSELY MONITOR FEED PUMP SUCTION PRESSURE WHEN ADJUSTING CONDENSATE COOLING VALVES.
4 Check Condensate Temperature Perform the following:
- LESS THAN 1000F (PPCS point ID T2053) a. Place S/G blowdown and sample valve master isolation switch to CLOSE.
- b. IF condensate cooler in service, THEN perform the following:
- 1) Place generator hydrogen temperature controller in MANUAL at 50%.
- 2) Dispatch AO to throttle close condensate cooler bypass valve to control condensate temperature.
- 3) Adjust hydrogen temperature controller and condensate cooler manual bypass valve to establish maximum condensate cooling.
STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 5 Dispatch AO To Check IF condenser inleakage is detected.
Condenser For Air Inleakage THEN isolate if possible.
NO INLEAKAGE DETECTED
"*Vacuum breaker
"*Condenser boot area
"*Condenser areas 6 Determine If Load Reduction Can Be Stopped:
- a. Monitor condenser indications: a. Return to Step 2.
" Condenser back pressure EACH CONDENSER WITHIN THE SATISFACTORY OPERATING REGION OF FIG-13.0. FIGURE BACK PRESSURE "o Vacuum - STABLE OR IMPROVING
- b. Stop the load reduction
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:
- Insert control rods o 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:
o 431K in MANUAL o 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.
(Step 7 continued from previous page)
- 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 S/G level to 52%
IF S/G level can NOT be controlled manually. THEN refer to AP-FW.l, ABNORMAL MAIN FEEDWATER FLOW.
STE 7ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE D 8 Establish Normal Plant Operation:
- a. Check condenser indications a. Return to Step 2.
"o Condenser pressure - EACH CONDENSER WITHIN THE SATISFACTORY OPERATING REGION OF FIG- 13.0, FIGURE BACK PRESSURE "o Vacuum - STABLE OR IMPROVING
- b. Restore EH controls
- 1) Place in OP PAN, IMP OUT
- 2) Place load rate thumbwheel to 10%/hour
- 3) Match setter and reference
- c. Verify annunciator G-15, STEAM c. WHEN Tavg within 5°F of Tref.
DUMP ARMED - EXTINGUISHED THEN perform the following:
- 1) Ensure steam dump valves closed.
- 2) Reset steam dump.
- d. Verify one charging pump in AUTO d. Place one charging pump in AUTO, if desired.
- e. Verify Rods in AUTO e. Place rods AUTO, if desired.
- f. Verify 431K in AUTO f. Place 431K in AUTO, if desired.
Verify PRZR spray valves in AUTO g. Place PRZR spray valves in AUTO, if desired.
This Step continued on the next page.
STP ACTION/EXPECTED RESPONSE i RESPONSE NOT OBTAINED (Step 8 continued from previous page)
- h. Verify PRZR heaters restored: h. Restore PRZR heaters, if desired.
o PRZR proportional heaters breaker CLOSED o PRZR backup heaters breaker RESET, IN AUTO
- j. Dispatch AO to remove priming ejector from service if desired
- k. Verify S/C blowdown and sample k. Perform the following:
valve master isolation switch in REMOTE 1) Dispatch AO to locally isolate blowdown.
- 2) WHEN blowdown locally isolated, THEN place blowdown and sample valve master switch to REMOTE.
- 3) Direct AO to restore blowdown flow (Refer to T-14N, BLOWDOWN SYSTEM FLOW CHANGES).
9 Evaluate MCB Annunciator Status (Refer to AR Procedures)
STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 10 Perform Notifications:
- a. Notify higher supervision
- b. Request Turbine System Engineer evaluate effect of back pressure transient on the turbine.
11 Return To Procedure Or Guidance In Effect
-END-
EOP: TITLE:
REV: 16 AP-TURB.4 LOSS OF CONDENSER VACUUM PAGE 1 of 1 AP-TURB.4 APPENDIX LIST TITLE
- 1) FIGURE BACK PRESSURE (FIG-13.0)
- 2) ATTACHMENT COND VACUUM (ATT-6.0)
EOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 22 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER d3 RESPONS I3E MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A. PURPOSE - This procedure provides actions to recover from a loss of reactor or secondary coolant.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-O, REACTOR TRIP OR SAFETY INJECTION, and FR-H.I, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
- b. E-0, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
- c. E-O, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.I, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.
- d. ES-I.I, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
- e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
- f. ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, after normal injection mode conditions are established.
- h. FR-C.I, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.
- i. FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.
STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[
CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP 1.
NOTE: o FOLDOUT page should be open AND monitored periodically.
"o Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.)
"o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP 1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
"o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
1 Monitor RCP Trip Criteria:
- b. ST pumps AT LEAST TWO RUNNING b. Go to Step 2.
- c. RCS pressure minus maximum S/G c. Go to Step 2.
pressure LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
EOF: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 4 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED5 2 Check If S/G Secondary Side IF any S/G pressure decreasing in Is Intact: an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:
o Pressure in both S/Gs - GREATER
- Steamlines THAN 110 PSIG o Feedlines IF NOT, THEN go to E 2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.
- 3 Monitor Intact S/G 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 5% [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 in an
[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
- 4 Monitor If Secondary IF steamline radiation monitors NOT Radiation Levels Are Normal available. THEN dispatch AO to locally check steamline radiation.
C Steamline radiation monitor (R 31 and R 32) IF abnormal radiation levels detected in any S/G, THEN go to o Request RP sample S/Gs for E-3, STEAM GENERATOR TUBE RUPTURE.
activity Step 1.
EOP: TITL: REV 2 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 22
.ACTON********************ONS NOT OBTANED*********
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
- 5 Monitor PRZR PORV Status:
- 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
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.
"*MOV-515, MCC D position 6C
"*MOV-516, MCC C position 6C
- c. Block valves AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
EOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 22 CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 6 Reset SI 7 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT b. Perform the following:
ISOLATION EXTINGUISHED
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
STEP ACTION/EXPECTED RESPONSE... RESPONSE NOT OBTAINED 1 8 Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps running, THEN perform the following:
- 1) Ensure SW isolation.
- 4) IF only one SW pump running, THEN refer to AP SW.2, LOSS OF SERVICE WATER.
- 5) Go to Step 10.
EOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 22 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized from offsite power
- 1) Close non-safeguards bus tie o Bus 13 normal feed CLOSED breakers:
OR "*Bus 13 to Bus 14 tie
"*Bus 15 to Bus 16 tie o Bus 15 normal feed CLOSED
- 2) 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 Attachment CNMT RECIRC FANS).
- 3) WHEN bus 15 restored, THEN reset control room lighting.
- b. Verify turbine building SW b. Manually align valves.
isolation valves OPEN
- MOV-4613 and MOV-4670 o MOV-4614 and MOV-4664
- c. Verify adequate air compressors c. Manually start air compressors RUNNING as power supply permits (75 kw each).. IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- 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 10. WHEN IA restored, THEN do Steps 9e and f.
Reset both trains of XY relays for IA to CNMT AOV-5392
ST - ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED 10 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).
"o Bus 14 normal feed breaker CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer "o Bus 16 normal feed breaker to Attachment CNMT RECIRC FANS).
CLOSED
[OP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 22 11 Check If Charging Flow Has Been Established:
- a. Charging pumps ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AG with key to RWST gate to close seal injection needle valve(s) to affected RCP:
a V-300A for RCP A
- V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.
o LCV-112B OPEN IF LCV-112B can NOT be opened, THEN dispatch AO to locally open o LCV 112C CLOSED manual charging pump suction from RWST (V 358 located in charging pump room).
IF LCV-112C can NOT be closed, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AG to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as "necessary and adjust charging flow to restore PRZR level
FOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 11 of 22 12 Check If SI Should Be Terminated:
o Pressure GREATER THAN 1625 psig [1825 psig adverse CNMT]
o Pressure - STABLE OR INCREASING
USING FIGURE MIN SUBCOOLING
- c. Secondary heat sink: c. IF neither condition satisfied, THEN do NOT stop SI pumps. Go "o Total feed flow to intact to Step 13.
S/Gs GREATER THAN 200 GPM
-OR
" Narrow range level in at least one intact S/G GREATER THAN 5% [25% adverse CNMT]
d1.PRZR level GREATER THAN 5% d. Do NOT stop SI pumps. Perform
[30% adverse CNMT] the following:
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
- 2) Go to Step 13.
- 13 Monitor If CNMT Spray Should Be Stopped:
- a. CNMT spray pumps - RUNNING a. Go to Step 14.
- b. Check the following: b. Continue with Step 14. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do Steps 13c through f.
4 PSIC o Sodium hydroxide tank level LESS THAN 55%
- c. Reset CNMT spray
- d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.
"* AOV-836A
"* AOV-836B
- e. Stop CNMT spray pumps and place in AUTO
CAUTION "o IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER)
"o RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIC [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
"*14 Monitor If RHR Pumps Should Be Stopped:
- a. Check RCS pressure:
- 1) Pressure GREATER THAN 1) Go to Step 16.
250 psig [465 psig adverse CNMT]
INCREASING t- Stop RHR pumps and place in AUTO 15 Check RCS And S/G Pressures
- a. Check pressures in both S/Cs a. Return to Step 1.
STABLE OR INCREASING
-. Check pressures in both S/Gs b. Monitor RCS pressure. IF RCS CRFIATER THAN 110 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.
. Check RCS pressure STABLE OR c. Return to Step 1.
D)ECREAS ING
SON/EXPECTED RE RESPONSE NOT OBTAINED 16 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Close non-safeguards bus tie "o Emergency D/G output breakers breakers as necessary:
OPEN e Bus 13 to Bus 14 tie "o AC emergency bus voltage e Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
- 2) Place the following pumps in "o AC emergency bus normal feed PULL STOP:
breakers CLOSED e EH pumps a Turning gear oil pump 9 HP seal oil backup pump
- 3) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
"* A from Bus 13
"* B from Bus 15
"* E from Bus 15
"* F from Bus 15
- 5) Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7) WHEN bus 15 restored, THEN reset control room lighting breaker.
- 8) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- 9) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
17 Check If RHR Should Be Throttled:
- a. Check RHR Pumps ANY RUNNING a. Go to step 18.
- b. Check RWST level LESS THAN 70% b. Continue with Step 18. WHEN RWST level less than 70%, THEN perform step 17b.
- c. RHR flow - LESS THAN 1500 GPM c. Manually adjust RHR Hx outlet PER OPERATING PUMP valves equally to reduce flow to less than 1500 gpm per operating pump
- RHR Hx A, HCV-625
- RHR Hx B, HCV-624 IF flow can NOT be reduced manually, THEN dispatch an AO with locked valve key to locally adjust RHR Hx outlet valve handwheels equally to reduce flow.
"* RHR Hx A, HCV 625 handwheel
"* RHR Hx B, HCV 624 handwheel
[OP: TITLE: REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 16 of 22 18 Verify CNMT Sump Recirculation Capability:
- 1) Power available to emergency IF at least one train of cold AC busses and MCCs required leg recirculation capability can for CNMT sump recirculation NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY o Bus 14 and bus 18 COOLANT RECIRCULATION, Step 1.
ENERGIZED o MCC C ENERGIZED o Bus 16 and bus 17 ENERGIZED o MCC D ENERGIZED
- b. Check SW pumps AT LEAST 2 b. Attempt to restore at least 2 SW PUMPS AVAILABLE pumps to operable. IF only 1 SW pump available, THEN refer to Attachment MIN SW for additional guidance.
- c. Dispatch AO to check AUX BLDG c. IF any RHR pump seal leakage sub basement for RHR system indicated, THEN leakage should leakage (AUX BLDG sub-basement be evaluated and isolated if key may be required) necessary.
v A TERESONSE NPOTOBaTAINEaD 19 Evaluate Plant Status:
- a. Check auxiliary building a. Notify RP and refer to radiation NORMAL appropriate AR RMS procedure.
S Plant vent iodine (R-10B) IF the cause is a loss of RCS 0 Plant vent particulate (R-13) inventory outside CNMT. THEN go S Plant vent gas (R-14) to ECA-1.2. LOCA OUTSIDE CONTAINMENT. Step 1.
S CCW liquid monitor (R-17)
S LTDN line monitor (R-9)
S CHG pump room (R-4)
- b. Direct RP to obtain following samples:
o RCS boron a RCS activity o CNMT hydrogen o CNMT sump boron
- c. Verify adequate Rx head cooling:
- 1) Verify at least one control I) Manually start one fan as rod shroud fan RUNNING power supply permits (45 kw)
- 2) Verify one Rx compartment 2) Perform the following:
cooling fan - RUNNING "o Dispatch AO to reset UV relays at MCC C and MCC D.
"o Manually start one fan as power supply permits (23 kw)
P: TIL:REv:
[O E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 25I 18 of 22 20 Check If RCS Cooldown And Depressurization Is Required:
- a. RCS pressure GREATER THAN a. IF RHR pump flow greater than 250 psig [465 psig adverse CNMT] 475 gpm. THEN go to Step 21.
lop: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 19 of 22 STE - ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF D/Gs supplying emergency AC busses, THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.
21 Establish Adequate SW Flow:
- a. Verify at least two SW pumps a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only I SW pump operable, THEN perform the following:
- 1) Ensure Attachment MIN SW is in progress.
- 2) Go to Step 22.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves OPEN
"*MOV-4615 and MOV-4734
"* MOV-4616 and MOV 4735 Dispatch AO to check BOTH CCW Dx c. Locally place BOTH CCW Hxs in IN SERVICE service Determine required SW flow to CCW HXs per table:
SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 6000 gpm to in service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX This Step continued on the next page.
FoP: TIT LEL: REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 20 of 22 (Step 21 continued from previous page)
- e. Direct AO to adjust SW flow to e. IF the required SW flow can NOT required value be obtained, THEN perform the following:
"o IF on normal SW discharge:
- 1) Isolate SW to screenhouse and
"*MOV-4609/MOV-4780 AT
-OR LEAST ONE CLOSED
"*MOV-4663/MOV-4733 AT "o IF on alternate SW discharge: LEAST ONE CLOSED
"* V 4619C, CCW HX A 2) Direct AO to locally adjust
"* V-4620B, CCW HX B SW flow to required value.
o SFP Hx A (V-4622) (for alternate SW discharge use V-4622A) o SFP Hx B (V-8689)
[OF: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 22 22 Establish CCW flow to RHR Hxs:
- a. Check both CCW pumps RUNNING a. Perform the following:
- 1) Start CCW pumps as power supply permits (122 kw each)
- 2) IF both CCW pumps are running, THEN go to step 22b.
- 3) IF only one CCW pump is running, THEN perform the following:
a) Direct AG to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR Loop "o Open MOV-738A
-OR "o Open MOV-738B c) Go to step 23.
"*MOV 738A
"*MOV /38B
FOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 22 of 22 ACION/EXPECTED RE01141S~ RESPONST N0T 0BTAIý'ýý t
23 Check If Transfer To Cold Leg Recirculation Is Required:
- a. RWST level LESS THAN 28% a. Return to Step 17.
- b. Go to ES 1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 END
E-1 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG 1.0)
- 3) ATTACHMENT CNMT RECIRC FANS (ATT -4.0)
- 4) ATTACHMENT D/G STOP (ATT 8. 1)
- 5) ATTACHMENT SD-I (ATT 17.0)
- 6) ATTACHMENT SI/UV (ATT 8.4)
- 7) ATTACHMENT MIN SW (ATT- 2. 1)
- 8) ATTACHMENT NO SW PUMPS (ATT 2.4)
- 9) ATTACHMENT LOSS OF OFFSITE POWER (ATT 8.5)
- 10) FOLDOUT
lOP: TITLE:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of I RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power greater than 5%
- b. CORE COOLING - Core exit T/Cs greater than 1200'F
-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%
adverse CNMT]
- c. HEAT SINK - Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
- e. CONTAINMENT - CNMT pressure greater than 60 psig
EOP: 1ITL:
REV: 25 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 FOLDOUT PAGE
- a. SI pumps - AT LEAST TWO RUNNING
- 2. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary:
"o RCS subcooling based on core exit T/Cs - LESS THAN 00 F USING FIGURE MIN SUBCOOLING
- OR "o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT]
- 3. SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
- a. RCS subcooling based on core exit T/Cs - GREATER THAN 00 F USING FIGURE MIN SUBCOOLING b- Total feed flow to intact S/Gs - GREATER THAN 200 GPM
- OR Narrow range level in at least one intact S/G - GREATER THAN 5% [25% adverse CNMT]
- c. RCS pressure:
"o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]
"o STABLE OR INCREASING
- d. PRZR level - GREATER THAN 5% [30% adverse CNMT]
- 4. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
5- E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation, THEN manually start SI pumps as necessary AND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
- 6. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
- 7. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW. 1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
EOL : TITLE:
REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 3 RESPONSIBLEý NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP: TITLE: REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 2 of 8 A. PURPOSE - This procedure provides actions to identify and isolate a faulted steam generator.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-0, REACTOR TRIP OR SAFETY INJECTION, with the following symptoms:
- 1) Any S/G pressure decreasing in an uncontrolled manner.
- 2) Any S/G completely depressurized.
- b. E-l, LOSS OF REACTOR OR SECONDARY COOLANT, E-3, STEAM GENERATOR TUBE RUPTURE, ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, and ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED, with the following symptoms and/or conditions:
- 1) Any S/G pressure decreasing in an uncontrolled manner.
- 2) Any S/G complete depressurized.
- 3) Faulted S/G isolation not verified.
- c. FR-H.5, RESPONSE TO STEAM GENERATOR LOW LEVEL, when the affected S/G is identified as faulted.
- d. Other procedures whenever a faulted S/G is identified.
LOP: T1LL: REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 3 of 8 CAUTION
- 0 0********
a AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
o ANY FAULTED S/G OR SECONDARY BREAK SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
NOTE: o Critical Safety Function Status Trees should be monitored.
0 Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
1 Check MSIV Of Faulted S/G(s) Manually close valve.
- CLOSED IF valve will NOT close from MCB, THEN dispatch AO with locked valve key to locally closed faulted S/G(s) MSIV as follows:
o S/G A
- open vent valves V 5471 AND V-5473 o S/G B
- open vent valves V 5472 AND V-5474
[OP: TITLE:R E : 1 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 4 of 8 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 2 Check If Any S/G Secondary IF both S/G pressures decreasing in Side Is Intact: an uncontrolled manner, THEN go to ECA-2.1, UNCONTROLLED o Check pressure in S/G A - STABLE DEPRESSURIZATION OF BOTH STEAM OR INCREASING GENERATORS, Step 1.
OR o Check pressure in S/G B STABLE OR INCREASING 3 Check Faulted S/G Status: IF both S/G pressures stable or increasing. THEN search for o Faulted S/G pressure initiating break and go to Step 6.
DECREASING IN AN UNCONTROLLED MANNER o Main steamlines o Main feedlines
-OR- o S/G blowdown system o Sample system o Faulted S/G COMPLETELY DEPRESSURIZED
EOP: TITLE: REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 5 of 8 STEF ACTION/EXPECTED RESPONSE NOT OBTAINEDI 4 Isolate Feed Flow To Faulted Manually close valves.
S/G:
IF valves can NOT be closed, THEN o Close faulted S/C MDAFW pump dispatch AO to locally isolate discharge valve flowpaths as necessary.
- S/G A, MOV-4007
- S/G A, AOV-4297
- S/G B, AOV-4298 "o Verify faulted S/G MFW regulating valve and bypass valve CLOSED
- S/C A, HCV-466 and HCV-480
- S/C B, HCV-476 and HCV-481 "o Verify MDAFW pump crosstie valves BOTH CLOSED
- MOV 4000A
- MOV 4000B
" Close faulted S/C SAFW pump discharge valve
- S/G A, MOV 9701A
- S/G B, MOV-9701B
LOP: TITLE:
REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 6 of 8
- STEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
5 Isolate Steam Flow From Manually close valves.
Faulted S/G:
IF valves can NOT be closed, THEN 0 Verify faulted S/G ARV CLOSED dispatch AO to locally isolate flowpaths as necessary.
"*S/G A, AOV-3411
"*S/G B, AOV-3410 o Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP
- S/G A, MOV-3505A e S/G B, MOV 3504A o Verify faulted S/G blowdown and sample valves CLOSED
- S/G A, AOV-5738 and AOV-5735
- S/G B, AOV-5737 and AOV-5736 Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)
[OP: TITLE: REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.
- 6 Monitor Intact S/G 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 5% [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 in an
[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
7 Check Secondary Radiation IF steamline radiation monitors NOT Levels - NORMAL available, THEN dispatch AO to locally check steamline radiation.
o Steamline radiation monitor (R 31 and R-32) IF abnormal radiation levels detected in any S/G, THEN go to o Air ejector radiation monitor E 3, STEAM GENERATOR TUBE RUPTURE, (R-15) Step 1.
o S/G blowdown radiation monitor (R-19)
O Request RP sample S/Cs for activity
FOP: TITLE: REV: 0 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 8 of 8 STEP' ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Adjust Steam Dump To Minimize RCS Heatup:
- a. Determine allowable intact S/G pressure using maximum hot leg temperature (Refer to Figure INTACT S/G PRESSURE) 1).Check condenser steam dump b. Perform the following:
available:
- 1) Adjust intact S/G ARV to o Verify intact S/G MSIV OPEN pressure determined from Figure INTACT S/G PRESSURE.
o Annunciator G-15, STEAM DUMP ARMED- LIT 2) Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.
- c. Verify steam dump mode selector switch in MANUAL
- d. Adjust condenser steam dump controller in AUTO to pressure determined from Figure INTACT S/G PRESSURE 9 Go To E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1 END
EOP: TITLE:
REV: 10 E-2 FAULTED STEAM GENERATOR ISOLATION PAGE 1 of 1 E-2 APPENDIX LIST TITLE I) FIGURE INTACT S/G PRESSURE (FIG 7.0)
- 2) ATTACHMENT FAULTED S/G (ATT 10.0)
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLOMANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: ___________
EOP TITLE: REV 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 42 A. PURPOSE - This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-0, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or
- b. E-0, REACTOR TRIP OR SAFETY INJECTION, E-l, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation is abnormal, or
- c. E-0, REACTOR TRIP OR SAFETY INJECTION, E-l, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, ES-I.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when an intact S/G narrow range level increases in an uncontrolled manner.
- d. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when pressurizer pressure control is restored.
- e. Any FOLDOUT page that has E-3 transition criteria whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
STEP ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDb NOTE: "o FOLDOUT page should be open AND monitored periodically.
"o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).
"o Personnel should be available for sampling during this procedure.
"o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
"o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
- 1 Monitor RCP Trip Criteria:
- b. St pumps AT LEAST TWO RUNNING b. Go to Step 2.
- c. RCS pressure minus maximum S/G c. Go to Step 2.
pressure LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
LOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 4 of 42
- A**O..*.
. ... R..*..X...*. R *O.
- O. .*OB*AINE.*
CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 2 Identify Ruptured S/G(s): Perform the following:
"o Unexpected increase in either a. Reset SI S/C narrow range level
- b. Continue with Steps 10
-OR through 16. WHEN ruptured S/G(s) identified, THEN do Steps "o High radiation indication on 3 through 9.
main steamline radiation monitor
"*R 31 for S/G A
"*R 32 for S/C B
-OR "o AG reports local indication of high steamline radiation
-OR RP reports high radiation from S/C activity sample
S -TEACTION/EXPECTED RESPONSE RESPONSE NOT OBTAIN"EI CAUTION o IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
3 Isolate Flow From Ruptured S/G(s):
- a. Adjust ruptured S/G ARV controller to 1050 psig in AUTO
- b. Check ruptured S/G ARV - CLOSED b. WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed. IF NOT closed, THEN place controller in MANUAL and close S/G ARV.
IF S/G ARV can NOT be closed, THEN dispatch AO to locally isolate.
Close ruptured S/G TDAFW pump c. Dispatch AO with locked valve steam supply valve and place in key to locally isolate steam PULL STOP from ruptured S/G to TDAFW pump.
- d. Verify ruptured S/G blowdown d. Place S/G blowdown and sample valve CLOSED valve isolation switch to CLOSE.
- S/G A, AOV-5738 IF blowdown can NOT be isolated
- S/G B, AOV-5737 manually, THEN dispatch AO to locally isolate blowdown.
- S/G A, V-5701
- S/G B, V-5702
FOP: TITLE:
REV: 31 STEAM GENERATOR TUBE RUPTURE E-3 PAGE 6 of 42 SACT*ON/ EXPECTED RESPNE RESPONSE NOT 0BTAINH1,1 4 Complete Ruptured S/G Isolation:
- a. Close ruptured S/G MSIV a. Perform the following:
RUPTURED S/G MSIV CLOSED
- 1) Close intact S/G MSIV.
- 2) Place intact S/G ARV controller at 1005 psig in AUTO.
- 3) Adjust condenser steam dump controller to 1050 psig in AUTO.
- 4) Place condenser steam dump mode selector switch to MANUAL.
- 5) Adjust reheat steam supply controller cam to close reheat steam supply valves.
- 6) Ensure turbine stop valves CLOSED.
- 7) Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).
- b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)
[OP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 42 SACTONIXPETEDRESONSI IRESPýONSE ýNOT 0ýBTAINýED ý ý CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
5 Check Ruptured S/G Level:
- a. Narrow range level GREATER a. IF ruptured S/G NOT faulted.
THAN 5% [25% adverse CNMT] THEN perform the following:
- 1) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT].
- 2) Continue with Step 6. WHEN ruptured S/G level greater than 5% [25% adverse CNMT],
THEN do Steps 5b through e.
- S/G A, MOV 4007
- S/G B, MOV-4008
- c. Pull stop MDAFW pump for ruptured S/G
- d. Close TDAFW pump flow control d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve
- S/G A, AOV-4297 to ruptured S/G.
s/G B, S AOV-4298
- S/G A, V-4005
- S/G B, V-4006
- e. Verify MDAFW pump crosstie e. Manually close valves.
valves - CLOSED
- MOV 4000A
- MOV-4000B
STE 4 ACTION/EXPECTED RESPONSE[ RESPONSE NOT OBTAINED[
6 Verify Ruptured S/G Isolated:
- a. Check ruptured MSIV CLOSED a. Ensure air ejector/gland steam supply and flange heating steam isolated. (Refer to ATTACHMENT RUPTURED S/G, part B).
- b. Check TDAFW pump steam supply b. Continue efforts to isolate from ruptured S/G - ISOLATED steam supply from ruptured S/G:
- S/G A, MOV-3505A OR V 3505
- S/G B, MOV-3504A OR V-3504
- c. Ruptured S/G pressure GREATER c. Go to ECA-3.1, SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
7 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available: a. Adjust S/G ARV controllers to maintain intact S/G pressure in o Intact S/G MSIV OPEN AUTO and go to Step 8.
o Annunciator G-15, STEAM DUMP ARMED - LIT
- b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
- c. Place steam dump mode selector switch to MANUAL
FOP: TITLE:RE : 3 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 8 Reset SI
EOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEI CAUTION RUPTURED S/G LEVEL SHALL BE MAINTAINED GREATER THAN 5% [25% ADVERSE CNMT]
DURING THE RCS COOLDOWN, UNLESS THE RUPTURED S/G IS ALSO FAULTED.
NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.
9 Initiate RCS Cooldown:
- a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE (OF) 1100 PSIG 525 [505 adverse CNMT]
1000 PSIG 510 [490 adverse CNMT]
900 PSIG 500 [475 adverse CNMT]
800 PSIG 485 [460 adverse CNMT]
700 PSIG 465 [440 adverse CNMT]
600 PSIG 450 [420 adverse CNMT]
500 PSIG 425 [395 adverse CNMT]
400 PSIG 405 [370 adverse CNMT]
300 PSIG 375 [330 adverse CNMT]
- b. IF ruptured S/G MSIV closed, b. Manually or locally initiate THEN initiate dumping steam to steam dump from intact S/G at condenser from intact S/G at maximum rate using S/G ARV.
maximum rate IF no intact S/G available, THEN perform the following:
"o Use faulted S/G.
" IF a ruptured S/G must be used, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
- c. Core exit T/Cs LESS THAN c. Continue with Step 10. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required, THEN do Step 9d.
- d. Stop RCS cooldown and stabilize core exit T/Cs less than required temperature
SACTION/EXPECTED RESPONSEI [ RESPONSE NOT OBTAINED NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.
10 Monitor Intact S/G Level:
- 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 5% [25%
adverse CNMT] in at least one S/G.
- h. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17% intact S/G continues to increase
[25% adverse CNMT] and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP I]B).
11 Monitor PRZR PORVs And 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
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed. THEN go to ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
- c. Block valves AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT b. Perform the following:
ISOLATION EXTINGUISHED
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses Perform the following:
BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.
volt busses - CLOSED
- b. Perform the following as o 480 volt bus voltage GREATER necessary:
THAN 420 VOLTS
- 1) Close non-safeguards bus tie o Emergency D/G output breakers breakers:
OPEN
"* Bus 13 to Bus 14 tie
"* Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
"* EH pumps
"* Turning gear oil pump
"* HP seal oil backup pump
- 3) Restore power to MCCs.
- A from Bus 13 o B from Bus 15 o E from Bus 15 o F from Bus 15
- 4) Start HP seal oil backup pump.
- 5) Start CNMT RECIRC fans as necessary.
- 6) Ensure D/C load within limits.
- 7) WHEN bus 15 restored, THEN reset control room lighting.
- c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).
EOP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 42 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[
14 Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps running, THEN:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- 4) IF only one SW pump running.
THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 5) Go to Step 16.
- b. Dispatch AG to establish normal shutdown alignment (Refer to Attachment SD-1)
EOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 16 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized
- 1) Close non-safeguards bus tie o Bus 13 normal feed CLOSED breakers:
-OR
- Bus 13 to Bus 14 tie o Bus 15 to Bus 16 tie 0 Bus 15 normal feed CLOSED
- 2) 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 Attachment CNMT RECIRC FANS).
- b. Verify turbine building SW b. Manually align valves.
isolation valves OPEN
- MOV-4613 and MOV-4670
- MOV-4614 and MOV-4664
- c. Verify adequate air compressors c. Manually start air compressors RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- 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 TNCREASING 2) Continue with Step 16. WHEN IA restored, THEN do Steps 15e and f.
STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDi 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.
16 Check If RHR Pumps Should Be Stopped:
- a. Check RCS pressure GREATER a. Go to Step 17.
THAN 250 psig [465 psig adverse CNMT]
- b. Stop RHR pumps and place both in AUTO
EOP: TIILE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 18 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 17 Establish Charging Flow:
- a. Charging pumps ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally close seal injection needle valves to affected RCP.
- 2) Ensure HCV 142 demand at 0%.
- b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN dispatch AG to locally open manual charging pump suction "o LCV 112B OPEN from RWST (V-358 located in charging pump room).
"o LCV- 112C CLOSED IF LCV 112C can NOT be closed, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AG to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as necessary and establish 75 gpm total charging flow
- Charging line flow
- Seal injection
EOP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 19 of 42 STEP -ACTION /EXPECTED RESPOS RESPONSE NOT OBTAINED 18 Check If RCS Cooldown Should Be Stopped:
- a. Core exit T/Cs LESS THAN a. Do NOT proceed until core exit REQUIRED TEMPERATURE T/Cs less than required temperature.
- b. Stop RCS cooldown
- c. Stabilize core exit T/Cs LESS THAN REQUIRED TEMPERATURE 19 Check Ruptured S/G Pressure IF pressure continues to decrease STABLE OR INCREASING to less than 250 psi above the pressure of the intact S/I. THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
20 Check RCS Subcooling Based On Go to ECA-3.1, SGTR WITH LOSS OF Core Exit T/Cs - GREATER THAN REACTOR COOLANT - SUBCOOLED 20OF USING FIGURE MIN RECOVERY DESIRED. Step I SUBCOOLING
EOP: TITLE: REV 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 20 of 42 SACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED!
NOTE: SI ACCUMs may inject during RCS depressurization.
21 Depressurize RCS To Minimize Break Flow And Refill PRZR:
- a. Check the following: a. Go to Step 22.
"o Ruptured S/G level - LESS THAN 90% [80% adverse CNMT]
"o Any RCP RUNNING o IA to CNMT - AVAILABLE
- b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
"o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
-OR "o RCS pressure LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
-OR "o BOTH of the following:
- 1) RCS pressure LESS THAN RUPTURED S/G PRESSURE
- 2) PRZR level GREATER THAN 5% [30% adverse CNMT]
- c. Close normal PRZR spray valves: c. Stop associated RCP(s).
- 1) Adjust normal spray valve controller to 0% DEMAND
- 2) Verify PRZR spray valves CLOSED
"* PCV-431A
"* PCV-431B
- d. Verify auxiliary spray valve d. Decrease charging speed to (AOV-296) CLOSED minimum and ensure charging valve to loop B cold leg open (AOV-294).
- e. Go to Step 24
S ACTION /EXPECTED RESPONSE RESPONSE NOT OBTAINED1 CAUTI ON o THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS. THIS MAY RESULT IN ABNORMAL CNMT CONDITIONS.
"o CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED.
"o THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING. THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o When using a PRZR PORV select one with an operable block valve.
22 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:
- b. PRZR PORVs AT LEAST ONE b. IF auxiliary spray available, AVAILABLE THEN return to Step 21b.
IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 1.
This Step continued on the next page.
STE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED' (Step 22 continued from previous page)
- c. Open one PRZR PORV until ANY of c. IF auxiliary spray available, the following conditions THEN return to step 21b.
satisfied:
- 1) IF auxiliary spray can NOT be "o PRZR level GREATER THAN 75% established, THEN go to
[65% adverse CNMT] ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, OR Step 1.
"o RCS pressure - LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
-OR "o BOTH of the following:
- 1) RCS pressure LESS THAN RUPTURED S/G PRESSURE
- 2) PRZR level GREATER THAN 5% [30% adverse CNMT]
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 23 Check RCS Pressure - Close block valve for the PRZR PORV INCREASING that was opened.
IF pressure continues to decrease, THEN perform the following:
- a. Monitor the following conditions for indication of leakage from PRZR PORV:
"o PORV outlet temp (TI-438) NOT decreasing.
"o PRT pressure, level or temperature continue to increase.
- b. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
STEP ACTION/EXPECTED RESPONSE, RESPONSE NOT OBTAINED CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED S/C.
24 Check If SI Flow Should Be Terminated:
- a. RCS subcooling based on core a. Do NOT stop SI pumps. Go to exit T/Cs GREATER THAN 0°F ECA-3.1. SGTR WITH LOSS OF USING FIGURE MIN SUBCOOLING REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
- b. Secondary heat sink: b. IF neither condition satisfied, THEN do NOT stop SI pumps. Go to "o Total feed flow to S/G(s) ECA-3.1, SGTR WITH LOSS OF GREATER THAN 200 GPM AVAILABLE REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
-OR "o Narrow range level in at least one intact S/C GREATER THAN 5% [25% adverse CNMT]
- c. RCS pressure - STABLE OR c. Do NOT stop SI pumps. Go to INCREASING ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
- d. PRZR level GREATER THAN 5% d. Do NOT stop SI pumps. Return to
[30% adverse CNMT] Step 6.
EOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 42 STEP ACTION/EXPECTED RESPONSEI 1 RESPONSE NOT OBTAINED 25 Stop SI Pumps And Place In AUTO 26 Establish Required Charging Line Flow:
- a. Charging pumps ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally isolate seal injection to affected RCP:
o RCP A, V-300A e RCP B. V-300B
- 2) Ensure HCV 142 open.
- 3) Start one charging pump.
- b. Establish 20 gpm charging line flow
- 27 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs GREATER THAN 0°F necessary and go to ECA-3.1, USING FIGURE MIN SUBCOOLING SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
- b. PRZR level GREATER THAN 5% b. Control charging flow to
[30% adverse CNMT] maintain PRZR level.
IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
eoP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 27 of 42 j~ ~ ~ o*I--- I*. o *** ý1i1~OX, 28 Check If SI ACCUMs Should Be Isolated:
- a. Check the following: a. Manually operate SI pumps as necessary and go to ECA-3.1, "o RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit T/Cs - GREATER THAN 0°F COOLANT - SUBCOOLED RECOVERY USING FIGURE MIN SUBCOOLING DESIRED, Step 1.
"o PRZR level GREATER THAN 5%
[30% adverse CNMT]
- b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves o MOV 841, MCC C position 12F
- MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
"* MOV 841 1) Open vent valves for
"* MOV 865 unisolated SI ACCUMs.
e ACCUM A, AOV-834A
- ACCUM B, AOV-834B
- 2) Open HCV-945.
STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 29 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least three SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps can be operated. THEN perform the following:
- 2) IF only one SW pump running, THEN refer to AP-SW.2. LOSS OF SERVICE WATER.
- 3) Go to Step 36.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves AT LEAST ONE SET OPEN e MOV-4615 and MOV-4734 e MOV-4616 and MOV-4735 This Step continued on the next page.
EOP: TITLE: REV: 3 1 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 42 (t ACTIONoEXPECTED R I E vBTAIN]'pg I RESPONSE NOp (Step 29 continued from previous page)
- c. Verify CNMT RECIRC fan c. Perform the following:
annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:
SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXs Normal 1 5000 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX
"o IF on normal SW discharge:
"* V-4619, CCW Hx A
"* V-4620, CCW Hx B
-OR "o IF on alternate SW discharge:
LOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 30 of 42 SSTEP
- ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED) 30 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored: a. Continue with Step 36. WHEN IA restored, THEN do Steps 30 o IA to CNMT (AOV-5392) OPEN through 35.
o IA pressure GREATER THAN 60 PSIG
- b. Verify instrument bus D b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:
- 1) Verify MCC A energized.
- 2) Place instrument bus D on maintenance supply.
- c. CCW pumps ANY RUNNING c. Perform the following:
- 1) IF any RCP #1 seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).
e RCP A, MOV-749A and MOV-759A a RCP B, MOV-749B and MOV-759B
- 2) Manually start one CCW pump.
- d. Charging pump ANY RUNNING d. Continue with Step 36. WHEN any charging pump running, THEN do Steps 31 through 35.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[
31 Check If Seal Return Flow Should Be Established:
- a. Verify RCP #1 seal outlet a. Go to Step 32.
temperature LESS THAN 235°F
- b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.
- AOV-270A
- AOV-270B
- c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
- d. Open RCP seal return isolation d. Perform the following:
valve MOV-313
- 1) Place MOV-313 switch to OPEN.
- e. Verify RCP #1 seal leakoff flow e. 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 discharge valves are shut, THEN go to Step 32.
lEOP: TITLE: REV 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Verify PRZR Level - GREATER Continue with Step 34. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Step 33.
33 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess
- a. Establish charging line flow to letdown as follows:
REGEN Hx GREATER THAN 20 GPM "o Place excess letdown divert
- b. Place the following switches to valve, AOV-312, to NORMAL.
CLOSE:
"o Ensure CCW from excess letdown
- Letdown orifice valves open, (AOV-745).
(AOV-200A. AOV-200B, and AOV 202) "o Open excess letdown isolation
- Letdown isolation valve AOV-371 valve AOV-310.
- Loop B cold leg to REGEN Hx AOV-427 " Slowly open HCV-123 to maintain excess letdown temperature less
- c. Place letdown controllers in than 195°F and pressure less MANUAL at 40% open than 100 psig.
- TCV 130 "o Adjust charging pump speed as
- PCV-135 necessary.
- d. Reset both trains of XY relays IF RCP seal return NOT established, for AOV-371 and AOV-427 THEN consult TSC to determine if excess letdown should be placed in
- e. Open AOV-371 and AOV-427 service.
F. Open letdown orifice valves as necessary
- g. Place TCV 130 in AUTO at 105'F
- h. Place PCV 135 in AUTO at 250 psig
- 1. Adjust charging pump speed and HCV 142 as necessary
EOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 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. Verify the following: c. Adjust controls as necessary.
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed RED LIGHT LIT
"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 as necessary.
- 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
EOP: TITLE:RE
- 3 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 34 of 42 STEP ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED 35 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 36. WHEN VCT level greater than 40%,
THEN do Step 35b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
"o LCV- 112C OPEN "o LCV- 112B CLOSED
lOP: TITLE: REV 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
- 36 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:
- a. Perform appropriate action(s) from table:
PRZR RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase Increase o Increase
[40% ADVERSE CNMT] charging flow charging charging flow flow o Depressurize RCS o Maintain RCS and using Step 36b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and
[40% ADVERSE CNMT] using Step 36b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and 165% ADVERSE CNMT] using Step 36b PRZR ruptured S/G heaters pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS and
[65% ADVERSE CNMT] charging flow PRZR ruptured S/G heaters pressure equal
- b. Control pressure using normal b. IF letdown is in service. THEN PRZR spray, if available, to use auxiliary spray (AOV-296).
obtain desired results for IF NOT, THEN use one PRZR PORV.
Step 36a
FOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 36 of 42 37 Monitor If CNMT Spray Should Be Stopped:
- a. CNMT spray pumps ANY RUNNING a. Go to Step 38.
- b. Verify CNMT pressure LESS THAN b. Continue with Step 38. WHEN 4 PSIG CNMT pressure less than 4 psig, THEN do Steps 37c through f.
- c. Reset CNMT spray
- d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.
- AOV-836A
- AOV 836B
- e. Stop CNMT spray pumps and place in AUTO
- f. Close CNMT spray pump discharge valves
"* MOV 860A
"* MOV-860B
"* MOV-860C
"* MOV 860D
.STEP.
ACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINEDI 38 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.I, RESTORATION OF OFFSITE POWER).
"o Emergency DIG 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 Attachment DIG STOP) 39 Minimize Secondary System Contamination:
- a. Isolate reject from hotwell to a. IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.
o Place hotwell level controller (LC-107) in MANUAL at 50%
o Verify hotwell level STABLE
- b. Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
LOP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of 42 ST ,, ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
"o Annunciator A-7, RCP IA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED "o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED
- b. Check RCP seal injection:
o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR o RCP seal injection flow to each RCP GREATER THAN 6 GPM
STEP
- ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
42 Check RCP Status:
- a. RCPs AT LEAST ONE RUNNING a. Perform the following:
- 1) Try to start one RCP:
a) Ensure conditions for starting an RCP.
"o Bus 11A or 11B energized.
"o Refer to Attachment RCP START.
b) IF RVLIS level (no RCPs) less than 95%. THEN perform the following:
"o Increase PRZR level to greater than 65% [82%
adverse CNMT].
" Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.
"o Energize PRZR heaters as necessary to saturate PRZR water c) Start one RCP.
- 2) IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT be verified. THEN increase dumping steam.
- b. Stop all but one RCP
E-3 0pITLREv:STEAM GENERATOR TUBE RUPTURE PAGE 31 j 40 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
43 Check If Source Range Detectors Should Be Energized:
- a. Source range channels a. Go to Step 43e.
DEENERGIZED
- b. Check intermediate range flux b. Perform the following:
EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.
- 2) Continue with Step 44. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 43c through e.
- c. Check the following: c. Continue with Step 44. WHEN either condition met, THEN do o Both intermediate range Steps 43d 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 44.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
EOP: TITLE:
REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 41 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:
- a. Check condenser AVAILABLE a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following:
"o Open generator disconnects
"* lG13A7l
"* 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
- c. 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) Perform the following:
cooling fan RUNNING "o Dispatch AG to reset UV relays at MCC C and MCC D.
"o Manually start one fan as power supply permits (23 kw)
- d. Verify Attachment SD 1 COMPLETE
STEP ACTION/EXPECTED RESPONSE1 RESPONSE NOT OBTAINED[
45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:
"o Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL. Step 1
-OR "a Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1
-OR "o Go to ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1
-END
Eop: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG- 1.0)
- 3) ATTACHMENT CNMT RECIRC FANS (ATT -4.0)
- 4) ATTACHMENT D/G STOP (ATT- 8.1)
- 5) ATTACHMENT N2 PORVS (ATT- 12.0)
- 6) ATTACHMENT NC (ATT- 13.0)
- 7) ATTACHMENT SEAL COOLING (ATT- 15.2)
- 8) ATTACHMENT RCP START (ATT- 15.0)
- 9) ATTACHMENT RUPTURED S/G (ATT- 16.0)
- 10) ATTACHMENT SD-I (ATT- 17.0)
- 11) ATTACHMENT SD-2 (ATT 17.1)
- 12) ATTACHMENT NO SW PUMPS (ATT-2.4)
- 13) ATTACHMENT LOSS OF OFFSITE POWER (ATT -8.5)
- 14) FOLDOUT
EOP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power greater than 5%
- b. CORE COOLING - Core exit T/Cs greater than 1200'F
-OR Core exit T/Cs greater than 7000F AND RVLIS level (no RCPs) less than 52% [55%
adverse CNMT]
- c. HEAT SINK - Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY - Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F
- e. CONTAINMENT - CNMT pressure greater than 60 psig
EOP: TITLE: REV: 31 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE
- 1. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
"o RCS subcooling based on core exit T/Cs - LESS THAN 0 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR "o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].
- 2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.
- 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
- 4. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
- 5. MULTIPLE S/G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
EOP: TITLE:
WITHOUT SI REV: 20 ECA-0.1 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 1 of 20 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLý MANAGER
/7-)ECIV DATE EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A. PURPOSE - This procedure provides actions to use normal operational systems to stabilize plant conditions following restoration of AC emergency power.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF AN SI SIGNAL IS ACTUATED PRIOR TO PERFORMING STEP 10 OF THIS PROCEDURE, THEN SI SHOULD BE RESET TO PERMIT MANUAL LOADING OF EQUIPMENT ON AN AC EMERGENCY BUS.
NOTE: o CSFSTs should be monitored for information only. FR procedures should not be implemented prior to completion of Step 10.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
1 Check RCP Seal Isolation Status:
- a. RCP seal injection needle valves a. Dispatch AO with key to RWST CLOSED gate to locally close valves before starting charging pump.
- V 300A
- V-300B
- MOV-759A status:
- MOV-759B
- 1) IF pump running, THEN go to Step 2.
- 2) IF pump NOT running, THEN manually close valves.
IF valve(s) can NOT be closed, THEN place switches for RCP thermal barrier CCW outlet valves to CLOSE.
e AOV-754A a AOV-754B
STEPH ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check CI Annunciator A-26, Perform the following:
CONTAINMENT ISOLATION EXTINGUISHED a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CONTAINMENT ISOLATION.
extinguished.
S A RESPONSE NOT OBTAINED 3 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized from offsite power
- 1) Close non-safeguards bus tie o Bus 13 normal feed CLOSED breakers:
-OR o Bus 13 to Bus 14 tie o Bus 15 to Bus 16 tie o Bus 15 normal feed CLOSED
- b. Check at least two SW pumps b. Manually start SW pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps running, THEN go to Step 4.
- c. Verify turbine building SW c. Manually align valves.
isolation valves OPEN
- MOV-4613 and MOV-4670
- MOV-4614 and MOV-4664
- d. Start adequate air compressor(s) d. IF air compressors can NOT be (75 kw each) started, THEN dispatch AD to locally reset compressors as necessary.
- e. Check IA supply: e. 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 6. WHEN IA restored, THEN do Steps 3f through 5.
STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.
4 Manually Load Following Equipment On AC Emergency Busses:
- a. Start one CCW pump (122 kw)
- b. Energize MCCs as power supply permits
"*MCC A from Bus 13
"*MCC B from Bus 15
"*MCC E from Bus 15
"*MCC F from Bus 15
- c. Verify instrument bus D c. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).
- d. WHEN bus 15 restored, THEN reset control room lighting
- e. Start at least one CNMT RECIRC fan
- f. Restore Rx head cooling as power supply permits:
- 1) Start one Rx compartment 1) Perform the following:
cooling fan (23 kw each)
"o Dispatch AO to reset UV relays at MCC C and MCC D.
"o Manually start one fan as power supply permits.
(23 kw)
- 2) Start both control rod shroud 2) Manually start at least one fans (45 kw each) fan (45 kw)
- g. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
EOP: TITLE:
WITHOUT SI REV: 20 LOSS OF ALL AC POWER RECOVERY ECA-O.1 REQUIRED PAGE 7 of 20 5 Check If Charging Flow Has Been Established:
- a. Charging pumps ANY RUNNING a. Perform the following:
- 1) Ensure seal injection needle valves to both RCPs isolated:
"* RCP A, V-300A
"* RCP B, V-300B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.
"o LCV- 112B OPEN IF LCV-112B can NOT be opened, THEN dispatch AO to locally open "o LCV- 112C CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).
IF LCV-112C can NOT be closed, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AG to close V 268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps (75 kw each) as necessary and adjust charging flow to restore PRZR level
FOP: TITLE:
WITHOUT SI REV: 20 ECA-O.l LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 8 of 20 SACTI~ON /EXPECTED RESOSE RESPONSE NOT 0BTAINEý
- 6 Monitor SI Initiation Criteria:
- a. RCS subcooling based on core a. Go to ECA-0.2, LOSS OF ALL AC exit T/Cs GREATER THAN 0°F POWER RECOVERY WITH SI REQUIRED, USING FIGURE MIN SUBCOOLING Step 1.
- b. PRZR level GREATER THAN 5% b. Control charging flow to
[30% adverse CNMT] maintain PRZR level.
IF PRZR level can NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 1.
7 Check PRZR Level - GREATER Control charging flow as necessary.
THAN 13% [40% FOR ADVERSE CONTAINMENT]
- . .O A. .. *. .. *. . . ..*.**.
. . X*O*. .*0*A **. .
CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).
o IF S/G NR LEVEL DECREASES TO LESS THAN 5% [25% ADVERSE CNMT] AND FEED FLOW IS LESS THAN 200 GPM. THEN THE MDAFW PUMPS SHOULD BE MANUALLY LOADED ON AC EMERGENCY BUS TO SUPPLY WATER TO THE S/G(S).
NOTE: o If MDAFW pump operation is not required, pump switches should be maintained in PULL-STOP to prevent automatic start.
o TDAFW pump flow control AOVs may drift open on loss of IA.
- 8 Monitor Intact S/G 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 5% [25%
adverse CNMT] in at least one S/G.
IF feed flow less than 200 gpm.
THEN perform the following:
- 1) Verify MDAFW pump discharge valves open.
o MOV-4007
- MOV-4008
- 2) Manually start MDAFW pumps as necessary (223 kw each).
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT] and 52%
STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish S/G Pressure Control:
- a. Adjust SIG ARV controllers to maintain existing S/C pressure
- b. Verify S/G ARV controllers in AUTO
- c. Dispatch AO to perform Attachment SD-2 CAUTION IF AN SI SIGNAL IS ACTUATED AFTER THE SI PUMP SWITCHES ARE PLACED IN AUTO, THEN ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, SHOULD BE PERFORMED.
NOTE: Safeguards pump switches should be placed in AUTO only if associated bus is energized.
10 Place Following Pump Switches In AUTO:
"* SI pumps
"* RHR pumps
"* CNMT spray pumps
NOTE: FR procedures may now be implemented as necessary.
11 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least two SW pumps - a. Manually start pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps can be operated, THEN perform the following:
- 2) IF ony one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 3) Go to Step 17.
- b. Verify AUX BLDG SW isolation b. Manually align valves. IF valves OPEN valves must be locally operated, THEN continue with Step 17.
"*MOV-4615 and MOV-4734 WHEN SW restored to AUX BLDG,
"*MOV-4616 and MOV-4735 THEN do Steps lic through 16.
This Step continued on the next page.
(Step ON c /EXP T fOrREI iONSd i OprAeI (Step 11 continued from previous page)
- c. Verify CNMT RECIRC fan c. Perform the following:
annunciator C-2. HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:
SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 6000 gpm equally divided to both HXs Normal 1 5000 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX
-OR "o IF on alternate SW discharge:
EOP: TITLE:
WITHOUT SI REV: 20 ECA-0.1 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 13 of 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored: a. Continue with Step 17. WHEN IA restored, THEN do Steps 12 o IA to CNMT (AOV-5392) OPEN through 16.
o IA pressure GREATER THAN 60 PSIG
- b. Charging pump ANY RUNNING b. Continue with Step 17. WHEN any charging pump running, THEN do Steps 13 through 16.
13 Verify PRZR Level - GREATER Continue with Step 17. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Steps 14 through 16.
SACTION/EXPECTED RESPONSEI I RESPONSE NOT OBTAINED!
14 Establish Normal Letdown: Consult TSC to determine if excess letdown should be placed in service.
- a. Establish charging line flow to REGEN Hx - GREATER THAN 20 GPM
- b. Place the following switches to CLOSE:
"* Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)
"*AOV-371, letdown isolation valve
"*AOV-427, loop B cold leg to REGEN Hx
- c. Place letdown controllers in MANUAL at 40% open
- TCV-130
- PCV-135
- d. Reset both trains of XY relays for AOV-371 and AOV-427 if necessary
- e. Open AOV-371 and AOV-427
- f. Open letdown orifice valves as necessary
- g. Place TCV 130 in AUTO at 105°F
- h. Place PCV 135 in AUTO at 250 psig
- i. Adjust charging pump speed and HCV-142 as necessary
TACTION/EXPECTED RESPONSE[ [RESPONSE NOT OBTAINED[
15 Check VCT Makeup System:
- a. Verify the following: a. IF VCT auto makeup can NOT be established, THEN manually
- 1) Boric acid and RMW flow control VCT level (Refer to control valves SET FOR ER-CVCS.1. REACTOR MAKEUP REQUIRED CSD CONCENTRATION CONTROL MALFUNCTION).
(Refer to Figure SDM)
- 2) At least one BA and RMW pump in AUTO
- 3) RMW mode selector switch in AUTO
- 4) RMW control armed - RED LIGHT LIT
"o Level GREATER THAN 20%
- 1) Ensure BA transfer pumps and
-OR RMW pumps running. IF NOT.
THEN dispatch AO to reset "o Level STABLE OR INCREASING MCC C and MCC D UV lockouts as necessary.
- 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
IF VCT level can NOT be restored, THEN go to Step 17.
EOP: TITLE:
WITHOUT SI REV: 20 ECA-0.1 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 16 of 20 16 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 17. WHEN VCT level greater than 40%,
THEN do Step 16b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
"o LCV- 112C OPEN "o LCV- 112B CLOSED 17 Control PRZR Level:
- a. Check letdown IN SERVICE a. Stop and start charging pumps as necessary to control PRZR level.
- b. Maintain PRZR level between 13%
[40% adverse CNMT] and 50%
SE ACTION/EXPECTED RESPONSE- I RESPONSE NOT OBTAINED 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 select one with an operable block valve.
18 Establish PRZR Pressure Control:
- a. Check letdown - IN SERVICE a. Perform the following:
IF IA NOT available, THEN Refer to Attachment N2 PORVS to operate PORV.
- 2) Go to Step 19.
- b. Use PRZR heaters and auxiliary spray valve (AOV-296) to maintain RCS pressure 19 Verify Natural Circulation: Increase dumping steam from intact S/Gs.
"o RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o S/G pressures - STABLE OR DECREASING "o RCS hot leg temperatures STABLE OR DECREASING "o Core exit T/Cs STABLE OR DECREASING "o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR S/G PRESSURE
EOP: TITLE:
WITHOUT SI REV: 20 ECA-0.1 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 18 of 20 STEP ACTION/EXPECTED RRESPONSE NOT OBTAINEDI NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
20 Check If Source Range Detectors Should Be Energized:
- a. Source range channels a. Go to Step 20e.
DEENERGIZED
- b. Check intermediate range flux b. Perform the following:
EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing THEN initiate boration.
- 2) Continue with Step 21. WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 20c through e.
- c. Check the following: c. Continue with Step 21. WHEN either condition met, THEN do "o Both intermediate range Steps 20d 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 21.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Verify Adequate Shutdown Margin:
- b. Verify boron concentration b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM 22 Maintain Stable Plant Conditions
- a. RCS pressure - STABLE a. Control PRZR heaters and auxiliary spray if available.
- b. RCS temperature STABLE b. Control dumping steam as necessary.
- c. PRZR level BETWEEN 13% [40% c. Control charging as necessary.
adverse CNMT] and 50%
- d. Intact S/G level BETWEEN 17% d. Control S/G feed flow as
[25% adverse CNMT] and 52% necessary.
- 23 Monitor SI Initiation Criteria:
- a. RCS subcooling based on core a. Go to ECA-0.2, LOSS OF ALL AC exit T/Cs GREATER THAN 0°F POWER RECOVERY WITH SI REQUIRED, USING FIGURE MIN SUBCOOLING Step 1.
- b. PRZR level GREATER THAN 5% b. Control charging flow to
[30% adverse CNMT] maintain PRZR level.
IF PRZR level can NOT be maintained, THEN go to ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 1.
SE ACTION/EXPECTED RESPONSE.
. RESPONSE NOT OBTAINEDI 24 Try To Restore Offsite Power Maintain plant condition stable To All AC Busses (Refer to using AC emergency power.
ER-ELEC.l, RESTORATION OF OFFSITE POWER) 25 Implement Plant Recovery Procedures:
- a. Review plant systems for realignment to normal conditions (Refer to ATT-26.0. ATTACHMENT RETURN TO NORMAL OPERATIONS)
- b. Consult plant staff to determine b. IF cooldown NOT required, THEN if RCS cooldown is necessary go to 0-3, HOT SHUTDOWN WITH XENON PRESENT.
- d. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN
.END
ECA-0.1 APPENDIX LIST TITLE
- 1) FIGURE MIN SUBCOOLING (FIG- 1. 0)
- 2) FIGURE SDM (FIG 2.0)
- 3) ATTACHMENT SD-I (ATT- 17.0)
- 4) ATTACHMENT SD-2 (ATT 17.1)
- 5) ATTACHMENT N2 PORVS (ATT 12.0)
- 6) ATTACHMENT NO SW PUMPS (ATT-2.4)
- 7) ATTACHMENT RETURN TO NORMAL OPERATIONS (ATT -26.0)
EOP: TITLE:
WITH SI REV: 13 ECA-0.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER ___-_
RESPONSIBLý MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: ___________
EOP: TITLE:
WITH SI REV: 13 ECA-O.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 2 of 9 A. PURPOSE - This procedure provides actions to use engineered safeguards systems to recover plant conditions following restoration of AC emergency power.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
LOP: TITLE:
WITH SI REV: 13 ECA-O.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 3 of 9 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o CSFSTs should be monitored for information only. FR procedures should not be implemented prior to completion of Step 10.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
1 Reset SI 2 Check RCP CCW Isolation Status:
- a. CCW pumps BOTH PUMPS OFF a. Go to Step 3.
- MOV-759A
- AOV-754A
- AOV-754B
-OR
"* MOV-749A
"*MOV-749B 3 Check RWST Level - GREATER Go to ES-1.3, TRANSFER TO COLD LEG THAN 28% RECIRCULATION, Step 1.
EOP: TITLE:
WITH SI REV: 13 ECA-0.2 LOSS OF ALL AC POWER RECOVERY "REQUIRED PAGE 4 of 9 P Aio x T R oS RESPONSE NOT OBTAINED NOTE: SI actuation to establish safeguards valve alignment is not recommended.
4 Manually Align SI And RHR Pumps To Establish SI Injection:
- a. SI pump suction valves from RWST a. Ensure at least one SI pump OPEN suction valve from RWST open.
o MOV-825A "* MOV-825A
- MOV-825B "* MOV-825B
- b. Verify SI pump C discharge b. Manually open valves as valves OPEN necessary.
o MOV-871A o MOV-871B
- c. RHR pump discharge to Rx vessel c. Ensure at least one deluge valve deluge OPEN open.
- MOV-852A a MOV-852A
- MOV 852B e MOV-852B
E°P: TITLE:
WITH SI REV: 13 ECA-0.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[
CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.
5 Manually Load Following Safeguards Equipment On AC Emergency Bus:
- a. Start all SI pumps a. Perform the following:
- 1) Start available SI pumps.
"o IF SI pump A NOT available, THEN ensure MOV-871B closed.
" IF SI pump B NOT available, THEN ensure MOV-871A closed.
o Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
o Pressure - STABLE OR INCREASING
- c. Place RHR pump switches in AUTO
- d. Start all available CNMT RECIRC fans
EOP: TITLE:
WITH SI REV: 13 ECA-O.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 6 of 9 STEP ACTION/EXPECTED REPNERESPONSE NOT OBTAINED CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET. THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.l. ALTERNATE WATER SUPPLY TO AFW PUMPS).
o IF SIG NR LEVEL DECREASES TO LESS THAN 5% [25% ADVERSE CNMT] AND FEED FLOW IS LESS THAN 200 GPM, THEN THE MDAFW PUMPS SHOULD BE MANUALLY LOADED ON AC EMERGENCY BUS TO SUPPLY WATER TO THE S/G(S).
NOTE: o If MDAFW pump operation is not required, pump switches should be maintained in PULL-STOP to prevent automatic start.
o TDAFW pump flow control AOVs may drift open on loss of IA.
- 6 Monitor Intact S/G 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 5% [25%
adverse CNMT] in at least one S/G.
IF feed flow less than 200 gpm, THEN perform the following:
- 1) Verify MDAFW pump discharge valve to intact S/G(s) open.
"* S/G A, MOV-4007
"* S/G B, MOV-4008
- 2) Manually start MDAFW pumps as necessary (223 kw).
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT] and 50%
EOP: TITLE:
WITH SI REV: 13 ECA-O.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 7 of 9 7 Verify CI And CVI:
- a. CI and CVI annunciators LIT a. Depress manual CI pushbutton.
"*Annunciator A-26, CNMT ISOLATION
"*Annunciator A-25, CONTAINMENT VENTILATION ISOLATION
- b. Verify CI and CVI valve status b. Manually close CI and CVI lights BRIGHT valves. IF valves can NOT be verified closed by MCB indication, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI).
- c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights valves.
BRIGHT
- AOV-4561
- AOV-4562
ECA-O 2 LOSS OF ALL AC POWER RECOVERY WITH SI REV: 13 OP:
L[ TITLE:
" REQUIRED PAGE 8 of 9 STEPH ACTON/EXPETE RESoNSE RESPoNS NoT OBTAINED 8 Verify CNMT Spray Not IF CNMT pressure is less than 28 Required: psig, THEN perform the following:
"o Annunciator A-27, CNMT SPRAY a. Reset CNMT spray.
EXTINGUISHED
- b. Place CNMT spray pump discharge "o CNMT pressure LESS THAN 28 PSIG valve switches to CLOSE to deenergize open contactor.
IF NOT, THEN perform the following:
- a. Depress manual CNMT spray pushbuttons (2 of 2).
- b. Ensure CNMT spray pump discharge valves open.
"o CNMT spray pump A:
"*MOV-860A
"*MOV-860B "o CNMT spray pump B:
"*MOV-860C
"*MOV-860D
- c. Ensure NaOH tank outlet valves open.
"*AOV-836A
"*AOV-836B
- d. Start both CNMT spray pumps.
- e. Go to step 10.
EOP: TITLE:
SI REV: 13 ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH REQUIRED PAGE 9 of 9 9 Place CNMT Spray Pumps In AUTO 10 Check RCP Seal Injection Locally close valves before Needle Valves - CLOSED starting charging pump.
- V-300A o V-300B NOTE: FR procedures may now be implemented as necessary.
11 Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1
-END
EOP: TITLE:
WITH SI REV: 13 ECA-O.2 LOSS OF ALL AC POWER RECOVERY REQUIRED PAGE 1 of 1 ECA-0.2 APPENDIX LIST TITLE
- 1) ATTACHMENT CI/CVI (ATT -3.0)
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 3 RESPONSIBL;NAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 2 of 32 A. PURPOSE - This procedure provides actions to restore emergency coolant recirculation capability, to delay depletion of the RWST by adding makeup and reducing outflow, and to depressurize the RCS to minimize break flow.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a. E-1, LOSS OF REACTOR OR SECONDARY COOLANT, when cold leg recirculation capability cannot be verified.
- b. ES-l.3, TRANSFER TO COLD LEG RECIRCULATION, when recirculation cannot be established or maintained OR when RWST level is < 15% and recirculation has not been established.
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REV: 21 ECA-I.I LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 3 of 32 CAUTION o IF EMERGENCY COOLANT RECIRCULATION IS ESTABLISHED DURING THIS PROCEDURE, FURTHER RECOVERY ACTIONS SHOULD CONTINUE BY RETURNING TO ES-1.3. TRANSFER TO COLD LEG RECIRCULATION.
o IF SUCTION SOURCE IS LOST TO ANY SI OR CNMT SPRAY PUMP, THE PUMP SHOULD BE STOPPED.
NOTE: Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.
- a. Check CNMT Sump B level AT a. IF Sump B level less than LEAST 113 INCHES 113 inches due to a loss of RCS inventory outside CNMT. THEN go to Step 2.
- b. Check RHR system: b. Perform the following:
"o RHR pumps OPERABLE 1) Manually or locally try to restore at least one train "o RHR suction valves from sump (Refer to ATT-14.5, B OPERABLE ATTACHMENT RHR SYSTEM to identify minimum components
"*MOV-850A for one train).
"*MOV-850B
- 2) Continue with step 2. WHEN "o RHR pump discharge to Rx at least one train is vessel deluge valves restored, THEN do steps Ic, d OPERABLE and e.
o MOV-852A
"* MOV-738A
"* MOV-738B This Step continued on the next page.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 4 of 32
( ACTION/EXP CTED RESPONSEm RSPONSE NT OTAINED)
(Step 1 continued from previous page)
- c. Check at least two SW pumps c. Manually start SW pumps as power RUNNING supply permits (257 kw each).
- d. Check RWST level - GREATER THAN d. Go to ES-1.3, TRANSFER TO COLD 28% LEG RECIRCULATION, Step 2 AND continue with step 2 of this procedure until such time as Emergency Coolant Recirculation is established.
- e. Return to procedure and step in effect.
2 Verify CNMT RECIRC Fans Running:
- a. All fans RUNNING a. Manually start fans. I
- b. Charcoal filter dampers green b. Dispatch personnel with relay status lights EXTINGUISHED rack key to locally open dampers using trip relay pushbuttons in relay room racks.
"*AUX RELAY RACK RA-2 for fan A
"*AUX RELAY RACK RA-3 for fan C
- 3 Monitor RWST Level - GREATER Go to Step 27.
THAN 15%
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 5 of 32 I
OBTAINEDI OBTAINED
- ACTION/EXPECTED RESPONSE I RESPONSE NOT l 4 Determine CNMT Spray Requirements:
- a. Determine number of CNMT spray pumps required from table:
CNMT CNMT RWST CNMT RECIRC FANS SPRAY PUMPS LEVEL PRESSURE RUNNING REQUIRED GREATER THAN 60 PSIG 2 GREATER 0 OR 1 2 THAN BETWEEN 28% 28 PSIG AND 60 PSIG 2 OR 3 1 ALL 0 LESS THAN 28 PSIC 0 GREATER THAN 60 PSIG 2 BETWEEN 15% 0, 1, 2, OR 3 1 AND BETWEEN 28% 28 PSIG AND 60 PSIG ALL 0 LESS THAN 28 PSIG 0 LESS THAN 0 15%
This Step continued on the next page.
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REV: 21 ECA-1.l LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 6 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI (Step 4 continued from previous page)
- b. CNMT spray pumps running EQUAL b. Manually operate CNMT spray TO MINIMUM NUMBER REQUIRED I pumps as necessary.
IF CNMT spray pump(s) must be stopped, THEN perform the following:
- 1) Reset CNMT spray.
- 2) Place CNMT spray pump in PULL STOP.
"o Pump A
"*MOV-860A
"*MOV-860B "o Pump B
"*MOV-860C
"* MOV-860D
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Add Makeup To RWST As Necessary "o Refer to ATT-18.0, ATTACHMENT SFP-RWST ( 400 gpm can be expected)
-OR
" Refer to S-3.2D, TRANSFERRING WATER FROM CVCS HUT(S) TO RWST OR SFP (- 60 gpm can be expected)
-OR-o Refer to S-9J, BLENDING TO RWST
(- 50 gpm can be expected)
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.
- 6 Monitor Intact S/G 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 5% [25%
adverse CNMT] in at least one SIC.
- 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 flow to that S/G.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 8 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to FIG-2.0, FIGURE SDM).
7 Initiate RCS Cooldown To Cold Shutdown:
- a. Establish and maintain cooldown rate in RCS cold legs LESS THAN 100°F/HR
- b. Dump steam to condenser from b. Manually or locally dump steam intact S/G(s) from intact SIG(s):
"o Use S/G ARVs
-OR "o Open TDAFW pump steam supply valves.
-OR
" Dispatch AO to perform the following:
- 1) Open S/G MSIV bypass valves.
- 2) Open priming air ejector steam supply root valve, V-3578.
- 3) Open 1A and 1B priming air ejector isolation valves.
- V-3580
- V-3581 IF no intact S/G available, THEN use faulted S/G.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 9 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED[
8 Check ECCS Pump Status: Go to step 19.
"o SI Pumps - ANY RUNNING
-OR "o RHR Pumps - ANY RUNNING IN INJECTION MODE CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN MANUAL ACTION MAY BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5, ATTACHMENT LOSS OF OFFSITE POWER) 9 Reset SI If Necessary 10 Establish One Train Of SI Flow
- a. St pumps - LESS THAN THREE a. Stop one SI pump.
RUNNING
250 psig [465 psig adverse CNMT]
IF no RHR pumps running, THEN start one RHR pump.
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REV: 21 ECA-1.I LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 10 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Verify No Backflow From RWST To Sump:
- a. Any RHR suction valve from a. IF both RHR suction valves from sump B OPEN sump B closed, THEN go to Step 12.
e MOV-850A a MOV-850B
suction (MOV-856) CLOSED
- 1) Place MOV-856 key switch to ON
- 2) Manually close valve IF valve can NOT be closed manually, THEN direct AO to locally close valve.
12 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT b. Perform the following:
ISOLATION - EXTINGUISHED
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 11 of 32 STEP ATiO/x R oNS RESPNS NOT OBTAINED 13 Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps running, THEN perform the following:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0, ATTACHMENT SD-1)
- 4) IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 5) Go to Step 16.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 12 of 32 STE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 14 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized from offsite power
- 1) Close non-safeguards bus tie o Bus 13 normal feed CLOSED breakers:
-OR e Bus 13 to Bus 14 tie
- Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED
- 2) 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).
- 3) WHEN bus 15 restored, THEN reset control room lighting.
- b. Verify SW isolation valves to b. Manually align valves.
turbine building OPEN
- MOV-4613 and MOV-4670
- MOV-4614 and MOV-4664
- 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 AG to locally reset compressors as necessary.
- d. Check IA supply: d. Perform the following:
"o Pressure GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.I, LOSS OF INSTRUMENT AIR).
"o Pressure STABLE OR INCREASING 2) Continue with Step 15. WHEN IA restored, THEN do Steps 14e and f.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 13 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDi 15 Establish Required Charging Line Flow:
- a. Charging pumps ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high, THEN dispatch AO with RWST area key to locally close seal injection needle valves to affected RCP:
e RCP A, V-300A e RCP B, V-300B
- 2) Ensure HCV-142 demand at 0%.
- 3) Start one charging pump.
- b. Establish 20 gpm total charging flow
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 14 of 32 CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP(S) SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
16 Check If An RCP Should Be Started:
- b. RCS subcooling based on core b. Go to Step 17.
exit T/Cs - GREATER THAN 0°F USING FIG-1.0, FIGURE MIN SUBCOOLING
- c. Try to start an RCP:
- 1) Establish conditions for starting an RCP "o Bus 11A or liB energized "o Refer to ATT-15.0, ATTACHMENT RCP START
- 2) Start one RCP.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 15 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED]
"*17 Monitor SI Termination Criteria:
- a. Check RVLIS indication: a. Go to step 19.
"o Level (no RCPs) GREATER THAN 77% [82% adverse CNMT]
-OR "o Fluid fraction (any RCP running) GREATER THAN 84%
- b. RCS subcooling based on core b. Limit RCS injection flow (SI, exit T/Cs - GREATER THAN 50'F RHR and charging) to that USING FIG-1.0, FIGURE MIN required to remove decay heat:
SUBCOOLING "o Determine required injection flow using FIG-6.0, FIGURE MIN RCS INJECTION
" Stop SI and/or RHR pumps as necessary to establish and maintain minimum required injection flow.
" IF required injection flow is less than 100 gpm, THEN establish charging at required flow and go to Step 18.
IF required injection flow is greater than 100 gpm, THEN perform the following:
- 1) Establish minimum charging flow for RCP seal injection.
- 2) Establish sufficient SI pumps and adjust charging flow to satisfy minimum required injection flow.
- 3) Consult TSC to determine if SI pump discharge valves should be locally throttled. (Locked valve key required.)
- 4) Go to Step 19.
STEP ACTION/EXPECTED RESPO.SEI RESPONSE NOT OBTAINED 18 Stop SI And RHR Pumps And Place In Auto
"*19 Verify Adequate RCS Makeup Flow:
- a. Check RVLIS indication: a. Increase RCS injection flow as necessary to maintain RVLIS "o Level (no RCPs) GREATER indication stable.
THAN 77% [82% adverse CNMT]
-OR "o Fluid fraction (any RCP running) GREATER THAN 84%
- b. Core exit T/Cs STABLE OR b. Increase RCS injection flow to DECREASING maintain core exit T/Cs stable or decreasing.
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 17 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Close non-safeguards bus tie "o Emergency D/G output breakers i breakers as necessary:
OPEN i e Bus 13 to Bus 14 tie "o AC emergency bus voltage e Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
- 2) Place the following pumps in "o AC emergency bus normal feed i PULL STOP:
breakers CLOSED i
"* EH pumps
"*Turning gear oil pump
"* HP seal oil backup pump
- 3) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
"* A from Bus 13
"* B from Bus 15
"* E from Bus 15
"* F from Bus 15
- 5) Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7) WHEN bus 15 restored. THEN reset control room lighting breaker.
- 8) Refer to ATT-8.4, ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
- 9) Try to restore offsite power.
(Refer to ER-ELEC.1.
RESTORATION OF OFFSITE POWER)
- b. Stop any unloaded emergency D/G and place in standby (Refer to ATT-8.1, ATTACHMENT D/G STOP)
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 18 of 32 STP CTION/EXPECTE REPOS RESONS 0NT OBTAINED CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE: If normal RCP support conditions can NOT be satisfied, then any running RCP(s) should be stopped.
21 Depressurize RCS To Decrease RCS Subcooling:
- a. Check RCS subcooling based on a. Go to Step 22.
core exit T/Cs GREATER THAN 10°F USING FIG-1.0, FIGURE MIN SUBCOOLING
- b. Normal PRZR spray -AVAILABLE b. Use one PRZR PORV. IF IA NOT available, THEN refer to ATT-12.0, ATTACHMENT N2 PORVS.
IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).
- c. Depressurize RCS until either of the following conditions satisfied:
o RCS subcooling based on core exit T/Cs - LESS THAN 10°F USING FIG-1.0, FIGURE MIN SUBCOOLING
-OR o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
- d. WHEN either condition met, THEN stop RCS depressurization
- e. Check RCS subcooling GREATER e. Increase RCS makeup flow as THAN 0°F USING FIG-1.0, FIGURE necessary to restore subcooling.
MIN SUBCOOLING
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REV: 21 ECA-I.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 19 of 32 SACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check If RHR Normal Cooling Can Be Established:
- a. RCS cold leg temperature - LESS a. Go to Step 23.
THAN 350°F
- b. RCS pressure - LESS THAN b. Go to Step 23.
400 psig [300 psig adverse CNMT]
- c. Place letdown pressure controller (PCV-135) in MANUAL CLOSED
- d. Check following valves - OPEN d. Perform the following:
o AOV-371, letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and o AOV-427, loop B cold leg to AOV-427.
REGEN Hx o At least one letdown orifice 2) Open AOV 371.
valve (AOV-200A, AOV-200B, or AOV 202) 3) Place AOV-427 switch to OPEN.
- 4) Open one letdown orifice valve.
- e. Verify pressure on PI-135 LESS e. Go to Step 23.
THAN 400 PSIG
- f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
- g. Consult TSC to determine if RHR normal cooling should be established using ATT-14.1, ATTACHMENT RHR COOL
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REV: 21 ECA-l.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 20 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If SI ACCUMs Should Be Isolated:
- a. Both RCS hot leg temperatures a. Continue with Step 24. WHEN LESS THAN 400°F both RCS hot leg temperatures less than 400'F, THEN do Steps 23b, c and d.
- MOV-841. MCC C position 12F
- MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
- MOV-841 1) Open vent valves for
- MOV-865 unisolated SI ACCUMs.
"*ACCUM A, AOV-834A
"*ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865
- 24 Monitor RCP Operation:
- a. RCPs ANY RUNNING a. Go to Step 25.
- b. Check the following: b. Stop affected RCP(s).
"o RCP #1 seal D/P GREATER THAN 220 PSID
" Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 21 of 32 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 25 Check Core Exit T/Cs Go to Step 40.
GREATER THAN 2000F 26 Check RWST Level - LESS THAN Return to Step 1.
15%
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 22 of 32 ACTION/EXPECTED RESPONSE
] RESPONSE NOT OBTAINED[
27 Minimize RWST Outflow:
- 2) Start one SI pump and verify flow.
- 3) Stop running charging pumps.
- 4) Go to Step 27d.
- b. Stop all but one SI pump
- c. Check charging pump suction from I c. Stop all charging pumps RWST (AOV-112B) - CLOSED
- d. Stop both RHR pumps
- e. Pull Stop both CNMT spray pumps
- f. Check CNMT pressure LESS THAN f. Go to Step 28.
- h. Close discharge valves for idle CNMT spray pump o Pump A
- MOV-860A o MOV-860B o Pump B
"* MOV 860C
"* MOV-860D
- i. Determine required injection flow using FIG-6.0, FIGURE MIN RCS INJECTION
- j. Consult TSC to determine if SI pump discharge valve should be locally throttled (locked valve key required)
EOP: TITLE: REV: 21 ECA-1i- LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 23 of 32 TACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED[
29 Try To Add Makeup To RCS From VCT:
- a. Check VCT level GREATER THAN 5% a. Stop charging pumps taking suction from VCT and continue with Step 30. WHEN VCT level greater than 5%. THEN do Steps 29b and c.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
"o LCV- 112C OPEN "o LCV-112B CLOSED
- c. Establish two charging pumps running
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REV: 21 ECA-1.I LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 24 of 32 30 Establish Maximum VCT Makeup:
- a. Check RMW contr ol armed RED a. Place RMW mode switch in AUTO LIGHT LIT and place RMW control switch to START.
- b. Check VCT level LESS THAN 20% b. Continue with Step 31. WHEN VCT level less than 20%, THEN do Steps 30c, d and e.
- c. Check VCT makeup system c. Perform the following:
OPERATING IN AUTO
- 1) Open makeup system valves.
"* AOV-I1OB
"* AOV-11OC
"* AOV-111
- 2) Start BA transfer pumps and RMW pumps.
- 3) Open boric acid flow control valve (AOV- 1OA).
- d. Increase VCT makeup flow
- 1) Start both RMW pumps
- 2) Start both boric acid pumps
- 3) Adjust RMW controller (HC-111) to maximum flow from table BAST MAX RMW CONC (PPM) FLOW (GPM) 8750 (5%) 40 10500 (6%) 50 12250 (7%) 60 14000 (8%) 70 15750 (9%) 80 17500 (10%) 90
- 4) Adjust boric acid flow controller (HC-GlOA) in MANUAL to 9.5 gpm e."Adjust charging pump speed to stabilize VCT level
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 25 of 32 STP ACTION/EXPECTED RESPONSE [ RESPONSE NOT OBTAINED I-31 Add Makeup To RWST As Necessary "o Refer to ATT-18.0, ATTACHMENT SFP-RWST ( 400 gpm can be expected)
_OR
" Refer to S-3.2D, TRANSFERRING WATER FROM CVCS HUT(S) TO RWST OR SFP (- 60 gpm can be expected)
_OR "o Refer to S- 9J, BLENDING TO RWST
(- 50 gpm can be expected) 32 Try To Add Makeup To RCS From Alternate Source:
- b. Consult TSC to determine other means of makeup 33 Verify SI ACCUM Isolation IF valves were closed to prevent SI Valves - OPEN ACCUM nitrogen injection, THEN go to Step 37.
- b. Open SI ACCUM discharge valves.
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REV: 21 ECA-1.l LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 26 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 34 Depressurize All Intact S/Gs To 785 PSIG:
- a. Check S/G pressures GREATER a. Go to Step 35.
THAN 785 PSIG
- b. Dump steam to condenser at b. Manually or locally dump steam maximum rate at maximum rate from intact S/G(s):
"o Use S/G ARVs
-OR "o Open steam supply valves to TDAFW pump
-OR "o Dispatch AO to perform the following:
- 1) Open S/G MSIV bypass valves.
- 2) Open priming air ejector steam isolation valves a V-3580 e V-3581
- c. Check S/G pressures LESS THAN c. Return to Step 34b.
785 PSIG
- d. Stop S/G depressurization
SACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI NOTE: The intent of the next step is to depressurize S/Gs more slowly, but at a rate that will maintain required RVLIS level.
35 Depressurize Intact S/Gs To 200 PSIG Slowly To Inject SI ACCUMs:
- a. Dump steam to condenser as a. Manually or locally dump steam necessary to maintain from intact S/G(s) to maintain appropriate RVLIS indication: appropriate RVLIS indication:
"o Level (no RCPs) - BETWEEN 77% "o Use S/G ARVs AND 82% [82% AND 85% adverse CNMT] -OR OR "o Open steam supply valves to TDAFW pump "o Fluid fraction (any RCP running) BETWEEN 84% AND 90% -OR "o Dispatch AO to perform the following:
- 1) Open affected S/G MSIV bypass valve.
- 2) Open priming air ejector steam isolation valves e V-3580 e V-3581
- b. Check S/G pressures LESS THAN b. Return to Step 35a.
200 PSIC
- c. Stop S/G depressurization
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 28 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 36 Check If SI ACCUMs Should Be Isolated:
- a. Both RCS hot leg temperatures a. Continue with Step 37. WHEN LESS THAN 400°F both RCS hot leg temperatures less than 400°F, THEN do Steps 36b. c and d.
- MOV-841, MCC C position 12F
- MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
- MOV-841 1) Open vent valves for
- MOV-865 unisolated SI ACCUMs.
"* ACCUM A, AOV-834A
"*ACCUM B, AOV-834B
- 2) Open HCV-945.
- 6. Locally reopen breakers for MOV 841 and MOV-865
- 37 Monitor RCP Operation:
- a. RCPs ANY RUNNING a. Go to Step 38.
- b. Check the following: b. Stop affected RCP(s).
"o RCP #1 seal D/P GREATER THAN 220 PSID
" Check RCP seal leakage WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF
SE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEt 38 Depressurize All Intact S/Gs To Atmospheric Pressure:
- a. Maintain cooldown rate in RCS cold legs LESS THAN 1000F/HR
- b. Dump steam to condenser b. Manually or locally dump steam from intact SIG(s):
"o Use S/G ARVs
-OR "o Open steam supply valves to TDAFW pump
-OR-o Dispatch AO to perform the following:
- 1) Open S/G MSIV bypass valves.
- 2) Open priming air ejector steam isolation valves
"* V-3580
"* V-3581
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REV: 21 ECA-1.l LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 30 of 32 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED" 39 Check If RHR Normal Cooling Can Be Established:
- a. RCS cold leg temperature LESS a. Return to Step 38.
THAN 350°F
- b. RCS pressure - LESS THAN b. Return to Step 38.
400 psig [300 psig adverse CNMT]
- c. Place letdown pressure controller in MANUAL CLOSED
- d. Check following valves OPEN d. Perform the following:
o AOV-371, letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and
- AOV-427, loop B cold leg to AOV-427.
REGEN Hx
- At least one letdown orifice 2) Open AOV-371 and AOV-427.
valve (AOV-200A, AOV-200B, or AOV-202) 3) Open one letdown orifice valve.
- e. Verify pressure on PI-135 LESS e. Return to Step 38.
THAN 400 PSIG
- f. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
- g. Consult TSC to determine if RHR normal cooling should be established using ATT-14.1, ATTACHMENT RHR COOL
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 31 of 32 STON/EXPECTED REO RESPONSE NOT OBTAINED 40 Maintain RCS Heat Removal:
- a. Use RHR system if in service
- b. Dump steam to condenser from b. Manually or locally dump steam intact S/Gs from intact S/C(s):
"o Use S/G ARVs
-OR "o Open steam supply valves to TDAFW pump
-OR "o Dispatch AO to perform the following:
- 1) Open S/G MSIV bypass valves.
- 2) Open priming air ejector steam isolation valves
"*V-3580
"*V-3581 IF no intact S/G available and RHR system NOT in service, THEN use faulted S/G.
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REV: 21 ECA-l.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 32 of 32 NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in the next step.
41 Check CNMT Hydrogen Concentration:
- b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.
42 Consult TSC
- END
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REV: 21 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE 1 of 1 ECA-1.1 APPENDIX LIST TITLE
- 1) FIGURE MIN SUBCOOLING (FIG -1.0)
- 2) FIGURE SDM (FIG -2.0)
- 3) FIGURE MIN RCS INJECTION (FIG -6.0)
- 4) FIGURE RCP SEAL LEAKOFF (FIG-4.0)
- 5) ATTACHMENT RHR COOL (ATT- 14. 1)
- 6) ATTACHMENT SFP-RWST (ATT -18.0)
- 7) ATTACHMENT RCP START (ATT- 15.0)
- 8) ATTACHMENT SD-I (ATT- 17.0)
- 9) ATTACHMENT CNMT RECIRC FANS (ATT -4.0)
- 10) ATTACHMENT RHR SYSTEM (ATT- 14.5)
- 11) ATTACHMENT N2 PORVS (ATT 12.0)
- 12) ATTACHMENT NO SW PUMPS (ATT 2.4)
- 13) ATTACHMENT LOSS OF OFFSITE POWER (ATT- 8.5)
- 14) ATTACHMENT SI/UV (ATT -8.4)