ML021410065
| ML021410065 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/02/2002 |
| From: | Widay J Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, NRC/NRR/DLPM/LPD1 |
| References | |
| Download: ML021410065 (187) | |
Text
IV F A Subsidiary of RGS Energy Group, Inc.
ROCHESTER GAS AND ELECTRIC CORPORATION
- 89 EAST AVENUE, ROCHESTER, N.Y 14649-0007
- 716-771-3250 JOSEPH A. WIDAY VICE PRESIDENT & PLANT MANAGER GINNA STATION May 2, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Robert Clark Project Directorate I Washington, D.C. 20555
Subject:
Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Clark:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Widay JAW/jdw xc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
ATT Index E Index ECA Index ES Index FR Index ATT-1.0, Rev 2 ATT-8.5, Rev 0 ATT-22.0, Rev 3 E-0, Rev 30 E-1, Rev 24 E-3, Rev 30 ES-0.1, Rev 19 ES-1.1, Rev 21 ES-1.3, Rev 32 ECA-1.1, Rev 20 ECA-2.1, Rev 23 ECA-3.1, Rev 22 ECA-3.2, Rev 25 FR-C. 1, Rev 18 FR-H. 1, Rev 25 FR-H.5, Rev 8 FR-P. 1, Rev 24 5
www.rge.com
REPORT NO. 01 REPORT: NPSP0200 DOC TYPE:
PRATT PARAMETERS:
DOC TYPES PRATT PROCEDURE NUMBER PROCEDURE ATT-1.0 ATTACNMEN ATT-1.1 ATTACHMEr ATT-2.1 ATTACHMEN ATT-2.2 ATTACHMEI ATT-2.3 ATTACH1MEN ATT-2.4 ATTACHME5 ATT-3.0 ATTACHMEN ATT-3.1 ATTACHMEN ATT-4.0 ATTACHMEN ATT-5.0 ATTACHMEN ATT-5.1 ATTACHMEI ATT-5.2 ATTACHMEN ATT-6.0 ATTACHMEN ATT-7.0 ATTACHMED (INNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS PRE PRECA PRES TITLE "IT AT POWER CCW ALIGNMENT "IT NORMAL CCW FLOW lT MIN SW FT SW ISOLATION IT SW LOADS IN CNMT IT NO SW PUMPS IT CI/CVI IT CNMT CLOSURE IT CNMT RECIRC FANS IT COND TO S/G IT SAFW IT FIRE WATER COOLING TO TDAFW PUMP IT COND VACUUM iT CR EVAC ATTACHMENT DC LOADS ATTACHMENT D/G STOP ATTACHMENT GEN DEGAS ATTACHMENT NONVITAL ATTACHMENT SI/UV ATT-8. 0 ATT-8.1 ATT-8.2 ATT-8.3 ATT-8.4 ATT-8.5 ATT-9.0 ATT-9.1 ATT-10.0 ATT-11.0 ATTACHMENT LOSS OF OFFSITE POWER ATTACHMENT LETDOWN ATTACHMENT EXCESS L/D ATTACHMENT FAULTED S/G ATTACHMENT IA CONCERNS PRFR STATUS:
EF QU 5
YEARS REV 002 000 005 008 004 001 006 004 003 005 007 003 003 006 006 005 007 004 005 000 008 005 006 002 ONLY:
EFFECT DATE 05/02/02 05/18/00 02/01/01 03/06/02 03/06/02 01/08/02 03/06/02 03/06/02 07/26/94 03/06/02 09/20/01 01/14/99 12/18/96 03/06/02 03/22/99 03/06/02 03/06/02 03/06/02 03/06/02 05/02/02 03/06/02 03/06/02 03/06/02 04/07/97 05/02/02 PAGE:
1 LAST REVIEW 02/10/98 05/18/00 02/10/98 08/11/98 12/31/99 10/31/01 01/06/99 01/25/99 05/13/98 12/31/99 12/31/99 01/14/99 02/10/98 02/10/98 01/14/99 02/10/98 08/17/99 02/10/98 02/10/98 05/02/02 03/06/02 10/31/01 05/13/98 08/11/998 NEXT REVIEW 02/10/ 03 05/18/05 02/10/03 08/11/03 12/31/04 10/31/06 01/06/04 01/25/04 05/13/03 12/31/04 12/31/04 01/14/04 02/10/03 02/10/03 01/14/04 02/10/03 08/17/04 02/10/03 02/10/03 05/02/07 03/06/07 10/31/06 05/13/03 08/11/03 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EFD EF EF EF EF EF EF EF
&.i
REPORT NO.
01 REPORT: NPSP0200 DOC TYPE:
PRATT PARAMETERS:
DOC PROCEDURE NUMBER ATT-11.1 ATT-11.2 ATT-12.0 ATT-13.0 ATT-14.0 ATT-14.1 ATT-14.2 ATT-14.3 ATT-14.5 ATT-14.6 ATT-15.0 ATT-15.1 ATT-15.2 ATT-16.0 ATT-16.1 ATT-16.2 ATT-17.0 ATT-17.1 ATT-18.0 ATT-20.0 ATT-21.0 ATT-22.0 ATT-23.0 ATT-24.0 TYPES PRATT 05/02/02 PAGE:
2
ýI NNA NUCLEAR POWER PIANT PROCEPURES INDEX EOP ATTACHMENTS PRE PRECA PRES PROCEDURE TITLE ATTACHMENT IA SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR ATTACHMENT N2 PORVS ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING ATTACHMENT RHR COOL ATTACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATTACHMENT RCP START ATTACHMENT RCP DIAGNOSTICS ATTACHMENT SEAL COOLING ATTACHMENT RUPTURED S/G ATTACHMENT SGTL ATTACHMENT RCS BORON FOR SGTL ATTACHMENT SD-I ATTACHMENT SD-2 ATTACHMENT SFP -
RWST ATTACHMENT VENT TIME ATTACHMENT RCS ISOLATION ATTACHMENT RESTORING FEED FLOW ATTACHMENT TRANSFER 4160V LOADS ATTACHMENT TRANSFER BATTERY TO TSC PRFR STATUS:
EF QU 5 YEARS ONLY:
EFFECT REV DATE 003 03/06/02 002 05/11/01 004 03/06/02 002 07/26/94 003 03/06/02 005 01/08/02 002 03/06/02 003 03/06/02 002 07/26/94 002 03/06/02 009 03/06/02 003 04/24/97 005 03/06/02 011 07/18/01 002 03/06/02 002 04/09/02 012 03/06/02 006 03/06/02 005 03/06/02 003 07/26/94 002.
03/06/07 003 05/02/02 000 02/26/99 000 09/08/00 LAST REVIEW 08/11/98 04/03/98 02/10/98 02/10/98 09/23/99 01/08/02 02/10/98 01/o*/99 02/10/98 01/14/99 03/17/00 02/10/98 02/10/98 01/11/00 09/08/00 09/08/00 02/29/00 01/30/01 02/10/98 02/10/98 02/10/98 01/22/02 02/26/99 09/08/00 NEXT REVIEW 08/11/03 04/03/03 02/10/03 02/10/03 09/23/04 01/08/07 02/10/03 01/06/04 02/10/03 01/14/04 03/17/05 02/10/03 02/10/03 01/11/05 09/08/05 09/08/05 02/28/05 01/30/06 02/10/03 02/10/03 02/10/03 01/22/07 02/26/04 09/08/05 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF
REPORT NO.
01 REPORT: NPSP0200 DOC TYPE: PRATT PARAMETERS:
DOC TYPES PRATT PROCEDURE NUMBER PROCEDURi ATT-26.0 ATTACHMEI (3INNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS PRE PRECA PRES E TITLE NT RETURN TO NORMAL OPERATIONS 05/02/02 PAGE:
3 PRFR STATUS: EF QU 5 YEARS ONLY:
EFFECT LAST NEXT REV DATE REVIEW REVIEW ST 000 10/31/01 10/31/01 10/31/06 EF TOTAL FOR PRATT 49 11
REPORT NO.
01 REPORT: NPSP0200 DOC TYPE:
PRE PARAMETERS:
DOC TYPES PRATT PROCEDURE NUMBER PROCEDURE E-0 REACTOR T E-1 LOSS OF R E-2 E-3 FAULTED STEAM GEN GINNA NU]CLEAR POWER PL PROCEDURES INDEX EMERGENCY PROCEDURE PRE PRECA PRES PRFR TITLE
'RIP OR SAFETY INJECTION REACTOR OR SECONDARY COOLANT TEAM GENERATOR ISOLATION IERATOR TUBE RUPTURE 05/02/02 PAGE:
4
ýNT STATUS:
EF QU 5 YEARS ONLY:
EFFECT REV DATE 030 05/02/02 024 05/02/02 009 12/20/00 030 05/02/02 TOTAL FOR PRE LAST REVIEW 05/01/98 05/01/98 05/01/98 05/01/98 NEXT REVIEW ST 05/01/03 EF 05/01/03 EF 05/01/03 EF 05/01/03 EF
REPORT NO.
01 REPORT: NPSP0200 DOC TYPE: PRECA PARAMETERS:
DOC TYPES -
PRATT PROCEDURE NUMBER ECA- 0.0 ECA- 0.1 ECA- 0.2 ECA-1.I ECA-1.2 ECA-2.1 ECA-3.1 ECA-3.2 ECA-3.3 OINNA NUCEIAR POWER PLANT PROCEDURES INDEX EMERGENCY CONTINGENCY ACTIONS PROC PRE PRECA PRES PRFR STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE TITLE LOSS OF ALL AC POWER LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED LOSS OF EMERGENCY COOLANT RECIRCULATION LOCA OUTSIDE CONTAINMENT UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 05/02/02 PAGE:
5 EFFECT LAST REV DATE REVIEW 023 10/31/01 05/01/98 019 10/31/01 05/01/98 012 10/18/99 05/01/98 020 005 023 022 025 026 05/02/02 05/01/98 05/02/02 05/02/02 05/02/02 10/31/01 05/01/98 05/01/98 05/01/98 05/01/98 05/01/98 NEXT REVIEW 05/01/03 05/01/03 05/01/03 05/01/03 05/01/03 05/01/03 05/01/03 05/01/03 05/01/98 05/01/03 EF TOTAL FOR PRECA ST EF EF EF EF EF EF EF EF 9
I I
REPORT NO.
01 GINNA NUCLEAR POWER PLANT 05/02/02 PAGE:
6 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE:
PRES EQUIPMENT SUB PROCEDURE PARAMETERS:
DOC TYPES -
PRATT PRE PRECA PRES PRFR STATUS:
EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ES-0.0 REDIAGNOSIS 010 05/01/98 05/01/98 05/01/03 EF ES-0.1 REACTOR TRIP RESPONSE 019 05/02/02 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-1.1 SI TERMINATION 021 05/02/02 05/01/98 05/01/03 EF ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 023 10/31/01 05/01/98 05/01/03 EF ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 032 05/02/02 05/01/98 05/01/03 EF ES-3.1 POST-SGTR COOLDOWN USING BACKFILL 013 05/01/98 05/01/98 05/01/03 EF ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN 014 05/01/98 05/01/98 05/01/03 EF ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 014 05/01/98 05/01/98 05/01/03 EF TOTAL FOR PRES 10 11
REPORT NO.
01 GINNA NUCLEAR POWER PLANT 05/02/02 PAGE:
7 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRFR FUNCTIONAL RESTORATION GUIDELINE PROC PARAMETERS:
DOC TYPES -
PRATT PRE PRECA PRES PRFR STATUS: EF QU 5 YEARS ONLY:
PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST FR-C.1 RESPONSE TO INADEQUATE CORE COOLING 018 05/02/02 05/01/98 05/01/03 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 015 12/02/99 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 025 05/02/02 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-Il.
RESPONSE TO HIGH PRESSURIZER LEVEL 014 10/31/01 05/01/98 05/01/03 EF FR-I.2 RESPONSE TO LOW PRESSURIZER LEVEL 009 10/31/01 05/01/98 05/01/03 EF FR-I.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.1 RESPONSE TO REACTOR RESTART/ATWS 013 12/14/98 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
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TITLE:
R V ATT-1.O ATTACHMENT AT POWER CCW ALIGNMENT PAGE 1 of 1 r
Responsible Manager Date This attachment provides the normal at power valve alignment for control board operated valves:
NOTE:
IF any valve position differs from that indicated below, THEN the reason should be determined and the valve restored to normal if desired.
"o CCW to RHR Hx A MOV-738A Closed "o CCW to RHR Hx B MOV-738B Closed "o CCW from RCP 1A Thermal Barrier AOV-754A Open "o
CCW from RCP lB Thermal Barrier AOV-754B Open "o
CCW from Ex Ltdn Hx Isol Vlv AOV-745 Open "o
CCW Surge Tk Vent RCV-017 Open "o
CCW to CNMT Isol Vlv MOV-817 Open "o
CCW to Rx Supp Clrs Isol Vlv MOV-813 Open "o
CCW from Rx Supp Clrs Isol Vlv MOV-814 Open "o
CCW to RCP 1A Isol Vlv MOV-749A Open "o CCW to RCP lB Isol Vlv MOV-749B Open "o CCW from RCP 1A Isol Vlv MOV-759A Open "o
CCW from RCP 1B Isol Vlv MOV-759B Open "o NRHX Ltdn Outlet Temp (Controller)
TCV-130 In Auto at approximately 1000 F
Responsible Manager_____________
Date ef 26c;
- 1.
IF offsite power is lost after SI has been reset, THEN the following equipment will auto start on the Emergency D/G, if available:
o One CCW pump, due to low header pressure (122 kw) o Selected SW pumps, on 40 sec timer (257 kw each) o
- MDAFPs, due to both MFP breakers open (223 kw each)
(discharge MOVs also open) o TDAFW pump, if both IIA AND lIB deenergized o
CS pumps, if previously running CAUTION OBSERVE D/G LOAD LIMITS WHEN MANUALLY STARTING EQUIPMENT SUPPLIED BY THE D/G.
- 2.
Manual start is required for the following equipment:
- SI pumps RHR pumps CNMT recirc fans (205 kw each) 0 Charging pumps (75 kw each) 0 PRZR heaters (400 kw each)
- SAFW pumps
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TITLE:
REV:
3 ATT-22.0 ATTACHMENT RESTORING FEED FLOW PAGE 1 of 3 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL6 MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
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TITLE:
REV:
3 ATT-22.0 ATTACHMENT RESTORING FEED FLOW PAGE 2 of 3 CAUTION FEED FLOW RATES SHOULD BE CONTROLLED TO PREVENT EXCESSIVE RCS COOLDOWN AND ASSOCIATED RCS PRESSURE AND INVENTORY REDUCTION.
NOTE:
o This attachment provides the desired feed flow rate when restoring feed flow to a SIG during FR-H.I.
o IF feedwater is restored via main feedwater or condensate the following may be used to indicate flow to the S/G:
o S/G feedwater flow meters (MCB) o SIG feedwater flow recorders (MCB) o SIG feedwater flow (PPCS Point ID F0466, F0467,
- F0476, F0477) o SIG feedwater RTD temperature decrease (PPCS Point ID T2096, T2097) 1 Initiate Feed flow as follows:
- a. Bleed and Feed initiated or required
- b.
Check RCS temp decreasing stable or
- a. IF feedwater flow to affected S-G greater than 50 gpm OR affected SG level greater than 50 inches (100 inches adverse CNMT),
THEN fill as desired to restore narrow range greater than 5% (25% adverse CNMT) and go to step 2 of this attachment.
IF NOT, THEN establish less than or equal to 100 gpm feed flow to affected SIG.
WHEN SIG level reater than 50 inches 100 inches adverse CNMT),
THEN fill as desired to restore narrow range greater than 5%
(25% adverse CNMT) and go to step 2 of this attachment.
- b. Fill ONE SIG at the highest possible flow rate and go to step 2 of this attachment.
- c. Establish less than or equal to 100 gpm feed flow to affected SIG.
WHEN SIG level greater than 50 inches (100 inches adverse CNMT),
THEN fill as desired to restore narrow range greater than 5% (25% adverse CNMT)
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3 ATT-22.0 ATTACHMENT RESTORING FEED FLOW PAGE 3 of 3 STE ACTioN/EXPETE RESoNSE RESPONSE NOT oBTAINE 2 Check RCS Loop Hot Legs BOTH HOT LEG TEMPERATURES DECREASING 3 Verify affected S/G is not faulted or ruptured.
Return to step 1 of this attachment.
Return to step 1 of this attachment and attempt to establish the intact S/G as heat sink.
Isolate feedwater and steam flow path to/from affected S/G.
IF neither S/G is intact, THEN establish a heat sink using the best available S/G.
-END -
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TITLE:
REV:
30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 28 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLýJMANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:___________
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TITLE:
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 2 of 28 A.
PURPOSE -
This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.
B.
ENTRY CONDITIONS/SYMPTOMS
- 1. The following are symptoms that require a reactor trip, if one has not occurred:
o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-i, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discretion.
- 2.
The following are symptoms of a reactor trip:
"o Any First Out reactor trip annunciator lit.
"o A rapid decrease in core neutron level as indicated by nuclear instrumentation.
"o MRPI indicates all control and shutdown rods on bottom.
"o Reactor trip breakers indicate open.
- 3.
The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
"o Any plant parameter reaches the Safety Injection setpoint and logic listed in procedure P-1, REACTOR CONTROL AND PROTECTION SYSTEM.
"o Operator discretion.
- 4.
The following are symptoms of a reactor trip and safety injection:
o Any SI annunciator lit.
o Safeguards sequencing started.
STE ACTIoN/xPETE RESoNSE RESPONS NoT OBTAINE Verify Reactor Trip:
"o At least one train of reactor trip breakers OPEN "o Neutron flux.- DECREASING "o MRPI indicates ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Verify Turbine Stop Valves CLOSED 0
Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS:
o Bus 14 and Bus 18
- Bus 16 and Bus 17 Attempt to start emergency D/G to all AC emergency IF power can NOT least one train, ECA-0.0, LOSS OF Step 1.
any failed restore power busses.
to be restored to at THEN go to ALL AC POWER, Manually trip reactor.
IF reactor trip breakers NOT open, THEN perform the following:
- a. Open Bus 13 and Bus 15 normal feed breakers.
- b. Verify rod drive MG sets tripped.
- c. Close Bus 13 and Bus 15 normal feed breakers.
- d. Reset lighting breakers.
IF the reactor will NOT trip OR IF power range NIS indicates greater than 5%,
THEN go to FR-S.l, RESPONSE TO REACTOR RESTART/ATWS, Step 1 Manually trip turbine.
IF turbine trip can NOT be verified, THEN close both MSIVs.
0
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 28 SEP H ACTION/EXPECTED RESPONSEI Check if SI is Actuated:
- a. Any SI Annunciator - LIT
- b.
SI sequencing -
BOTH TRAINS STARTED.
SRESPONSE NOT OBTAINED
- a. IF any of the following conditions are met, THEN manually actuate SI and CI:
"o PRZR pressure less than 1750 psig
- OR "o Steamline pressure less than 514 psig
- OR "o CNMT pressure greasier than 4 psig
-OR "o Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP
- RESPONSE, Step 1.
- b. Manually actuate SI and CI.
0
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 28 NOTE:
o FOLDOUT page should be open and monit-ored periodically.
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.
5 Verify SI and RHR Pumps Running:
- a. All SI pumps RUNNING
- a. Perform the following:
- 2) Manually start pumps.
- b. Both RHR pumps -
RUNNING 6 Verify CNMT RECIRC Fans Running:
- a. All fans - RUNNING
- b. Charcoal filter dampers green status lights EXTINGUISHED
- b. Manually start pumps.
- a. Manually start fans.
- b. Dispatch personnel to relay room with relay rack key to locally open dampers by pushing in trip relay plungers.
e AUX RELAY RACK RA-2 for fan A
- AUX RELAY RACK RA-3 for fan C
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 28 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 7 Verify CNMT Spray Not Required:
"o Annunciator A-27, CNMT SPRAY EXTINGUI SHED "o CNMT pressure LESS THAN 28 PSIG Verify CNMT spray initiated.
IF CNMT spray NOT initiated, THEN perform the following:
- a. Depress manual CNMT spray pushbuttons (2 of 2).
- b. Ensure CNMT spray pumps running.
IF no CNMT spray pump available, THEN go to Step 8.
- c. Ensure CNMT spray pump discharge valves open for operating pump(s).
"o CNMT spray pump A:
e MOV-860A
- MOV-860B "o CNMT spray pump B:
"* MOV-860C
"* MOV-860D
- d.
Ensure NaOH tank outlet valves open.
o AOV-836A e AOV-836B
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TITLE:
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 28 8 Check If Main Steamlines Should Be Isolated:
- a.
Any MSIV -
OPEN
- c.
Check if ANY main steamlines should be isolated:
"o Low Tavg (545°F) AND high steam flow (0.4x10 6 lb/hr) from either SIG
-OR "o High-High steam flow (3.6xi0 6 lb/hr) from either SIG
- d.
Verify MSIV closed on the affected SIG(s) 9 Verify MFW Isolation:
- a.
MFW pumps -
TRIPPED
- a. Go to Step 9.
- b. Ensure BOTH MSIVs closed and go to Step 9.
- c.
Go to Step 9.
- d. Manually close valves.
- a. Perform the following:.
- 1) Manually close MFW pump discharge valves and trip pumps.
- 2)
Continue with Step 9c.
WHEN both MFPs are tripped, THEN perform Step 9b.
- b.
Place A and B S/G MFW regulating valve and bypass valve controllers in MANUAL at 0%
demand.
- c.
S/G blowdown and sample valves CLOSED
- c. Place SIG blowdown and sample valve isolation switch to CLOSE.
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 28 SE ACTION/EXPECTED R o
E RESPONSE NOT OBTAINE 10 Verify Both MDAFW Pumps Running Manually start both MDAFW pumps.
IF less than 2 MDAFW pumps are running, THEN manually open TDAFW pump steam supply valves.
"* MOV-3505A
"* MOV-3504A 11 Verify At Least Two SW Pumps RUNNING Perform the following:
e Bus 17 e Bus 18
- b. IF offsite power NOT available, THEN ensure SW isolation.
12 Verify CI And CVI:
- a. CI and CVI annunciators - LIT
- a. Depress manual CI pushbutton.
"* Annunciator A-26, CNMT ISOLATION
"* Annunciator A-25, CNMT VENTILATION ISOLATION
- b. Verify CI and CVI valve status lights BRIGHT
- c.
CNMT RECIRC fan coolers SW outlet valve status lights BRIGHT
- b. Manually close CI and CVI valves as required.
IF valves can NOT be verified closed by MCB indication, THEN dispatch AO to locally close valves (Refer to ATT-3.0, ATTACHMENT CI/CVI for alternate isolation valves).
- c. Dispatch AO to locally fail open valves.
e FCV-4561 e FCV-4562 CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY.
13 Check CCW System Status:
- a. Verify CCW pump AT LEAST ONE RUNNING
- b.
Place switch for excess letdown AOV-310 to CLOSE
- c.
Place switch for CCW from excess letdown, AOV-745 to CLOSE
- a.
IF offsite power available, THEN manually start one CCW pump.
14 Verify SI And RHR Pump Flow:
- a. SI flow indicators -
CHECK FOR FLOW
- b.
RHR flow indicator -
CHECK FOR FLOW
- a. IF RCS pressure less than 1400 psig, THEN manually start pumps and align valves.
IF-NOT, THEN go to Step 15.
- b. IF RCS pressure less than 140 psig, THEN manually start pumps and align valves.
IF NOT, THEN go to Step 15.
15 Verify AFW Valve Alignment:
- a.
AFW flow - INDICATED TO BOTH S/G(s)
SE ACTION/EXPECTED RESPONSEI RESPONSE NTOBTAINEDI
"*16 Monitor Heat Sink:
- a. Check SIG narrow range level GREATER THAN 5% [25% adverse CNMT] in any S/G
- b.
Check S/G narrow range level BOTH S/G LESS THAN 50%
- c. Control feed flow to maintain S/G narrow range level between 5% and 50%.
- a. Perform the following:
- 1) Verify total AFW flow GREATER THAN 200 GPM IF total AFW is less than 200 gpm, THEN manually start pumps and align valves to establish greater than 200 gpm AFW flow.
IF AFW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.
- 2)
Go to Step 17.
- b.
Secure AFW flow to any S/G with level above 50%.
I
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 28 17 Verify SI Pump And RHR Pump Emergency Alignment:
- a.
RHR pump discharge to Rx vessel deluge OPEN o MOV-852A o MOV-852B
- b. Verify SI pump C - RUNNING
- c. Verify SI pump A - RUNNING
- d.
Verify SI pump B RUNNING
- e. Verify SI pump C discharge valves -
OPEN
- a. Ensure at least one valve open.
- b. Manually start pump on available bus.
- c.
Perform the following:
- 1) Ensure SI pumps B and C running.
IF either pump NOT, running, THEN go to Step 17e.
- 2) Ensure SI pump C aligned to discharge line A:
"o MOV-871A open "o MOV-871B closed
- 3)
Go to Step 18.
- d. Perform the following:
- 1) Ensure SI pumps A and C running.
IF either pump NOT, running, THEN go to Step 17e.
- 2) Ensure SI pump C aligned to discharge line B:
o MOV-871B open o
MOV-871A closed
- 3) Go to Step 18.
- e. Manually open valves as necessary.
"* MOV-871A
"* MOV-871B
A O X*
- * * *O O.
- 0 A*
- CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, TO RESTART SAFEGUARDS EQUIPMENT.
(REFER OFFSITE POWER)
THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5, ATTACHMENT LOSS OF 18 Check CCW Flow to RCP Thermal Barriers:
o Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW EXT INGUI SHED o
Annunciator A-15, RETURN HI TEMP OR EXTINGUISHED RCP 1B CCW LO FLOW -
IF CCW to a RCP is lost, THEN perform the following:
- a. Stop affected RCPs.
- b. Reset SI.
- c. Verify adequate power available to run one charging pump (75 kw).
- d. Start one charging pump at minimum speed for seal injection.
- e. Adjust HCV-142 to establish either of the following:
"o Labyrinth seal D/P to each RCP greater than 15 inches of water.
-OR "o RCP seal injection flow to each RCP greater than 6 gpm.
- f.
IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-300B.
19 Check If TDAFW Pump Can Be Stopped:
- a. Both MDAFW pumps RUNNING
- a.
Go to Step 20.
- b.
PULL STOP TDAFW pump steam supply valves
"* MOV-3504A
"* MOV-3505A
- 20 Monitor RCS Tavg -
STABLE AT IF temperature less than 5470F and OR TRENDING TO 5470 F decreasing, THEN perform the following:
- a. Stop dumping steam.
- b. Ensure reheater steam supply valves are closed.
- c.
IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT]
in at least one SIG.
- d.
WHEN S/G level greater than 5%
[25% adverse CNMT] in one S/G, THEN limit feed flow to that required to maintain level in at least one S/G.
- e.
IF cooldown continues, THEN close both MSIVs.
IF temperature greater than 547°F and increasing, THEN dump steam to stabilize and slowly decrease temperature to 547 0 F.
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 28 21 Check PRZR PORVs And Spray Valves:
- a.
- CLOSED
- b. Auxiliary spray valve (AOV-296)
CLOSED
- c.
Check PRZR pressure 2260 PSIG LESS THAN
- d.
Normal PRZR spray valves -
CLOSED
- PCV-431A e PCV-431B
- a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
IF any valve can NOT be closed, THEN manually close its block valve.
"* MOV-516 for PCV-430
"* MOV-515 for PCV-431C IF block valve can NOT be closed, THEN go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. Manually close auxiliary spray valve.
IF valve can NOT be closed, THEN perform the following:
- 1) Decrease charging pump flow to minimum.
- 2)
Ensure charging valve to loop B cold leg open (AOV-294).
- c.
Continue with Step 22.
pressure less than 2260 THEN do Step 21d.
WHEN
- psig,
- d. Place controllers in MANUAL at 0% demand.
IF valves can NOT be closed, THEN stop associated RCP(s).
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 28 STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 22 Monitor RCP Trip Criteria:
- a.
- b. SI pumps - AT LEAST TWO RUNNING
- c.
RCS pressure minus maximum S/G pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs 23 Check If S/G Secondary Side Is Intact:
"o Pressure in both S/Gs -
STABLE OR INCREASING "o Pressure in both S/Gs - GREATER THAN 110 PSIG 24 Check If S/G Tubes Are Intact:
"o Air ejector radiation monitors (R-15 or R-15A)
NORMAL "o S/G blowdown radiation monitor (R-19)
NORMAL "o Steamline radiation monitors (R-31 and R-32)
NORMAL
- a.
Go to Step 23.
- b.
Go to Step 23.
- c.
Go to Step 23.
IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
Go to E-3, STEAM GENERATOI{ TUBE
- RUPTURE, Step 1.
I
SSTEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 25 Check If RCS Is Intact:
- a.
CNMT area radiation monitors NORMAL Go to E-l.
LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
"* R-2
"* R-7
"* R-29
"* R-30
- b.
CNMT pressure LESS THAN 0.5 PSIG
- c.
LESS THAN 8 INCHES
- d.
Level STABLE o
Annunciator C-19, CONTAINMENT SUMP A HI LEVEL -
EXTINGUISHED
26 Check If SI Should Be Terminated:
- a.
RCS pressure:
"o Pressure -
GREATER THAN 1625 PSIG "o Pressure -
STABLE OR INCREASING
- b.
RCS subcooling based on core exit T/Cs -
GREATER THAN 0°F USING FIG-1.0, FIGURE MIN SUBCOOLING
- c.
Secondary heat sink:
"o Total feed flow to S/Gs GREATER THAN 200 GPM
-OR "o Narrow range level in at least one S/G GREATER THAN 5%
- d.
PRZR level GREATER THAN 5%
- a. Do NOT stop SI pumps.
Step 27.
- b.
Do NOT stop Step 27.
Go to SI pumps.
Go to
- c.
IF neither condition met, THEN do NOT stop SI pumps.
Go to Step 27.
- d.
Do NOT stop SI pumps.
the following:
Perform
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
- 2)
Go to Step 27.
- e.
Go to ES-1.1, SI TERMINATION, Step 1.
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REV 30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 19 of 28 NOTE:
o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o The Critical Safety Function Red Path Summary is available in APPENDIX 1.
27 Initiate Monitoring of Critical Safety Function Status Trees
- 28 Monitor S/G Levels:
- a. Narrow range level -
GREATER THAN 5%
- b. Control feed flow to maintain narrow range level between 17%
and 50%
29 Check Secondary Radiation Levels NORMAL "o Steamline radiation monitor (R-31 and R-32)
"o Dispatch AO to locally check steamline radiation "o Request RP sample S/Gs for activity
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one SIG.
- b. IF narrow range level in any SIG continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE.
Step 1.
Go to E-3.
STEAM GENERATOR TUBE RUPTURE.
Step 1.
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 28 STEP ACTION/EXPECTED RESPONSE
RESPONSE
CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET.
TO RESTART SAFEGUARDS EQUIPMENT.
(REFER OFFSITE POWER)
THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5, ATTACHMENT LOSS OF 30 Reset SI 31 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION
- EXTINGUISHED 32 Verify Adequate SW Flow:
- a. At least three SW pumps RUNNING
- b.
Perform the following:
- 1) Reset SI.
- 2)
Depress CI reset pushbutton.
- a. Manually start SW pumps as power supply permits (257 kw each).
IF less than three pumps running, THEN ensure SW isolation.
IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-I)
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 21 of 28 33 Establish IA to CNMT:
- a. Verify non-safeguards busses energized from offsite power "o Bus 13 normal feed -
CLOSED
-OR "o Bus 15 normal feed -
CLOSED
- b. Verify SW isolation valves to turbine building -
OPEN
- a. Restore IA supply as follows:
- 1) IF electric air compressor(s) is desired, THEN perform the following:
a) Close non-safeguards bus tie breakers:
e Bus 13 to Bus 14 tie e Bus 15 to Bus 16 tie b) Verify adequate emergency D/G capacity to run air compressor(s)
(75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped.
(Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS) c)
WHEN bus 15 restored, THEN reset control room lighting.
d)
Go to Step 33b.
- 2)
IF diesel air compressor is desired, THEN restore IA supply using the diesel air compressor.
(Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)
- b. Manually align valves.
e MOV-4613 and MOV-4670 e MOV-4614 and MOV-4664 This Step continued on the next page.
I1 I
I
(Step 33 continued from previous page)
- c. Verify adequate air compressor(s) -
RUNNING
- d.
Check IA supply:
o Pressure -
GREATER THAN 60 PSIG o
Pressure STABLE OR INCREASING
- f.
Verify IA to CNMT AOV-5392 OPEN 34 Check Auxiliary Building Radiation NORMAL 0
0 0
6 S
S Plant vent iodine (R-10B)
Plant vent particulate (R-13)
Plant vent gas (R-14)
CCW liquid monitor (R-17)
LTD line monitor (R-9)
CHG pump room (R-4)
- c.
Manually start air compressor(s) as power supply permits (75 kw each).
IF air compressor(s) can NOT be started, THEN dispatch AO to locally reset compressor(s) as necessary.
IF electric air compressor can NOT be started, THEN use diesel air compressor.
(Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)
- d. Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 34.
WHEN IA restored, THEN do Steps 33e and f.
Evaluate cause of abnormal conditions.
IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-I.2, LOCA OUTSIDE CONTAINMENT, Step 1.
SE ACTION/EXPECTED RSPNS RESPONSE NTOBTAINEDI 35 Check PRT Conditions "o PRT level (LI-442)
- LESS THAN 84%
"o PRT temperature (TI-439)
LESS THAN 120°F "o PRT pressure (PI-440A)
LESS THAN 3 PSIG Evaluate the following flowpaths for cause of abnormal conditions:
"* RCP seal return relief
"* PRZR PORVs
"* PRZR safeties
"* Letdown line relief IF excess letdown previously in service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
CAUTION RCS PRESSURE SHOULD BE MONITORED.
IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG, THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
36 Check If RHR Pumps Should Be Stopped:
- a.
Check RCS pressure:
- 1) Pressure GREATER THAN 250 PSIG
- 2)
Pressure STABLE OR INCREASING
- 1) Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- 2)
Go to Step 37.
- b.
Stop both RHR pumps and place in AUTO
SE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 37 Check Normal Power Available To Charging Pumps:
"o Bus 14 normal feed breaker CLOSED "o Bus 16 normal feed breaker CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to ATT-4.0, ATTACHMENT CNMT RECIRC FANS).
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 28 38 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 AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:
"* 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.
RWST:
IF LCV-112B can NOT be opened, "o LCV-112B -
OPEN THEN dispatch AO to locally open V-358, manual charging pump "o LCV-112C -
CLOSED suction from RWST (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.
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 28 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG "o Reset PRZR heaters "o Use normal PRZR spray
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 27 of 28 STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 40 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite power:
"o Emergency D/G output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED
- a. Perform the following:
- 1) Verify non-safeguards bus tie breakers closed:
- Bus 13 to Bus 14 tie a 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)
Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
- A from Bus 13 e B from Bus 15 e E from Bus 15
- F from Bus 15
- 5)
Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7)
Refer to ATT-8.4, ATTACHMENT SI/UV for other equipment lost with loss of offsite power.
- 8)
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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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 28 of 28 41 Return to Step 20
- END -
E-0 APPENDIX LIST TITLE
- 1)
RED PATH
SUMMARY
- 2)
FIGURE MIN SUBCOOLING (FIG-1.0)
- 3)
ATTACHMENT CI/CVI (ATT-3.0)
- 4)
ATTACHMENT SD-I (ATT-17.0)
- 5)
ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
- 6)
ATTACHMENT D/G STOP (ATT-8.1)
- 7)
ATTACHMENT SI/UV (ATT-8.4)
- 8)
ATTACHMENT NO SW PUMPS (ATT-2.4)
- 9)
ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)
- 10)
ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
- 10)
FOLDOUT
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 RED PATH
SUMMARY
- a.
SUBCRITICA-LITY -
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
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30 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE
- 1.
RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
- a.
SI pumps -
AT LEAST TWO RUNNING
- b.
RCS pressure minus maximum S/G pressure -
LESS THAN 175 PSIG
[400 psig adverse CNMT]
- 2.
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).
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB4 MANAGER 5-W -
o o EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:___________
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24 E-l LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 22 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-0, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, 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-0, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, 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-l.l, 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.
- g.
ECA-I.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.
- h.
FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been reestablished.
- i.
FR-H.I, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.
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REV: 24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3 of 22
- * * * * *O S O..
- O.
O
- A 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:
- a.
- b.
SI pumps AT LEAST TWO RUNNING
- c.
RCS pressure minus maximum S/G pressure LESS THAN 175 psig
[400 psig adverse CNMT]
- a.
Go to Step 2.
- b.
Go to Step 2.
- c.
Go to Step 2.
- d.
Stop both RCPs
2 Check If S/G Secondary Side IF any SIG pressure decreasing in Is Intact:
an uncontrolled manner OR "o Pressure in both S/Gs -
STABLE OR INCREASING "o Pressure in both S/Gs -
GREATER THAN 110 PSIG completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown:
e Steamlines e Feedlines IF NOT.
THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
- 3 Monitor Intact S/G Levels:
- a. Narrow range level -
GREATER THAN 5% [25% adverse CNMT]
- b. Control feed narrow range
[25% adverse flow to maintain level between 17%
CNMT]
and 50%
- 4 Monitor If Secondary Radiation Levels Are Normal "o Steamline radiation monitor (R-31 and R-32)
"o Request RP sample S/Gs for activity
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT]
in at least one S/G.
- b. IF narrow range levellin any S/G continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR ",UBE
- RUPTURE, Step 1.
i IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.
IF abnormal radiation levels detected in any S/G, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
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 AVAILABLE
- b.
PORVs -
CLOSED
- c.
Block valves AT LEAST ONE OPEN
- a. Restore power to block valves unless block valve was closed to isolate an open PORV:
"* MOV-515, MCC D position 6C
"* MOV-516, MCC C position 6C
- b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
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.
Open one block valve unless it was closed to isolate an open PORV.
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24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 22 A.....................................
O O 0A*
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 ISOLATION EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2)
Depress CI reset pushbutton.
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24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 22 8 Verify Adequate SW Flow:
- a.
Check at least two SW pumps RUNNING
- a. Manually start SW pumps as power 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 Attachment SD-1)
- 3)
IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
- 4)
IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 5) Go to Step 10.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
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24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 22 9 Establish IA to CNMT:
- a. Verify non-safeguards busses energized from offsite power o
Bus 13 normal feed -
CLOSED
-OR o
Bus 15 normal feed -
CLOSED
- b. Verify turbine building SW isolation valves OPEN
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers:
- Bus 13 to Bus 14 tie e Bus 15 to Bus 16 tie
- 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. Manually align valves.
"* MOV-4613 and MOV-4670
"* MOV-4614 and MOV-4664
- c.
Verify adequate air compressors RUNNING
- d.
Check IA supply:
"o Pressure -
GREATER THAN 60 PSIG "o Pressure -
STABLE OR INCREASING
- c. Manually start air compressors as power supply permits (75 kw each).
IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- d.
Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 10.
WHEN IA restored, THEN do Steps 9e and f.
EOP:
TITLE:
REV:
24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 22 STP ACTION/EXPE.CTEDO RESPONSEI RE.SPONSE NOT OBTAINEDI 10 Check Normal Power Available To Charging Pumps:
"o Bus 14 normal feed breaker CLOSED "o Bus 16 normal feed breaker CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).
IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
EOP:
TITLE:
REV: 24 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:
- b. Charging pump RWST:
o LCV-112B o
LCV-112C suction aligned to OPEN CLOSED
- 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 close seal injection needle valve(s) to affected RCP:
"* V-300A for RCP A
"* V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Manually align valves as necessary.
IF LCV-112B can NOT bel opened, THEN dispatch AO to locally open 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 AO 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
EOP:
TITLE:
REV:
24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 11 of 22 12 Check If SI Should Be Terminated:
- a.
RCS pressure:
o Pressure -
GREATER THAN 1625 psig [1825 psig adverse CNMT]
- a.
Do NOT stop SI pumps.
Step 13.
o Pressure STABLE OR INCREASING
- b.
RCS subcooling based on core exit T/Cs -
GREATER THAN 0°F USING FIGURE MIN SUBCOOLING
- c.
Secondary heat sink:
o Total feed flow to intact S/Gs -
GREATER THAN 200 GPM
-OR o
Narrow range level in at least one intact S/G GREATER THAN 5% [25% adverse CNMT]
- d.
PRZR level GREATER THAN 5%
[30% adverse CNMT]
- b.
Do NOT stop SI pumps.
Step 13.
Go to
- c.
IF neither condition satisfied, THEN do NOT stop SI pumps.
Go to Step 13.
- d.
Do NOT stop SI pumps.
the following:
Perform
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
- 2)
Go to Step 13.
- e.
Go to ES-1.1, SI TERMINATION, Step 1.
Go to
EOP:
TITLE:
REV:
24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 22
- 13 Monitor If CNMT Spray Should Be Stopped:
- a.
CNMT spray pumps RUNNING
- b.
Check the following:
o CNMT pressure LESS THAN 4 PSIG o
Sodium hydroxide tank level LESS THAN 55%
- c.
Reset CNMT spray
- d.
Check NaOH tank outlet valves CLOSED
"* AOV-836A
"* AOV-836B
- e.
Stop CNMT spray pumps and place in AUTO
- f.
Close CNMT spray pump discharge valves e MOV-860A e MOV-860B o MOV-860C o MOV-860D
- a.
Go to Step 14.
- b. Continue with Step 14.
WHEN BOTH conditions satisfied, THEN do Steps 13c through f.
- d. Place NaOH tank outlet valve controllers to MANUAL and close valves.
EOP:
TITLE:
REV: 24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 22 A
....X........
.s O
- O 0
- A * ** *
- 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 PSIG [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 250 psig [465 psig adverse CNMT]
- 2)
RCS pressure STABLE OR INCREASING
- a.
Check pressures in both S/Gs STABLE OR INCREASING
- b.
Check pressures in both S/Gs GREATER THAN 110 PSIG
- c.
Check RCS pressure -
STABLE OR DECREASING
- 1) Go to Step 16.
- 2)
Go to Step 15.
- a. Return to Step 1.
- b. Monitor RCS pressure.
IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.
- c.
Return to Step 1.
16 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses energized by offsite power:
"o Emergency D/G output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers as necessary:
9 Bus 13 to Bus 14 tie o Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
o 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 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)
EOP:
TITLE:
REV:
24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15 of 22 17 Check If RHR Should Be Throttled:
- a. Check RHR Pumps ANY RUNNING
- b. Check RWST level -- LESS THAN 70%
- c.
RHR flow -
LESS THAN 1500 GPM PER OPERATING PUMP
- a.
Go to step 18.
- b.
Continue with Step 18.
WHEN RWST level less than 70%,
THEN perform step 17b.
- c. Manually adjust RHR Hx outlet 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.
o RHR Hx A, HCV-625 handwheel
- RHR Hx B, HCV-624 handwheel
18 Verify CNMT Sump Recirculation Capability:
- 1) Power available to emergency AC busses and MCCs required for CNMT sump recirculation "o Bus 14 and bus 18 ENERGIZED "o MCC C -
ENERGIZED "o Bus 16 and bus 17 ENERGIZED "o MCC D -
ENERGIZED
- 2)
- 3)
CCW pumps and Hx -
- b.
Check SW pumps - AT LEAST 2 PUMPS AVAILABLE
- c. Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)
- a. Restore power to at least one train of emergency AC busses.
IF at least one train of cold leg recirculation capability can NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
IF only 1 SW pump available, THEN r:fer to Attachment MIN SW for *Edditional guidance.
- c.
IF any RHR pump seal leakage indicated, THEN leakage should be evaluated and isolated if necessary.
19 Evaluate Plant Status:
- a. Check auxiliary building radiation -
NORMAL 0
0 0
0 0
0 Plant vent iodine (R-10B)
Plant vent particulate (R-13)
Plant vent gas (R-14)
CCW liquid monitor (R-17)
LTDN line monitor (R-9)
CHG pump room (R-4)
- b. Direct RP to obtain following samples:
"* RCS activity
- c. Verify adequate Rx head cooling:
- 1) Verify at least one control rod shroud fan - RUNNING
- 2) Verify one Rx compartment cooling fan RUNNING
- a. Notify RP and refer to appropriate AR-RMS procedure.
IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
- 1) Manually start one fan as power supply permits (45 kw)
- 2)
Perform the following:
"o Dispatch AO to reset UV relays at MCC C and MCC D.
"o Manually start one fan as power supply permits (23 kw)
20 Check If RCS Cooldown And Depressurization Is Required:
- a.
RCS pressure -
GREATER THAN 250 psig [465 psig adverse CNMT]
- b.
Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1
- a.
IF RHR pump flow greater than 475 gpm, THEN go to Step 21.
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 RUNNING
- b. Verify AUX BLDG SW isolation valves OPEN
- a. Start additional SW pumps as power supply permits (257 kw each).
IF only 1 SW pump
- operable, THEN perform the following:
- 1) Ensure Attachment MIN SW is in progress.
- 2)
Go to Step 22.
- b. Manually align valves.
- MOV-4615 and MOV-4734 o MOV-4616 and MOV-4735
- d.
Determine required 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
EOP:
TITLE:
REV: 2 4 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 20 of 22
(
ACTION/EXPCTED fREm 4
SPONSE NOT OpTAINrag (Step 21 continued from previous page)
IF on normal SW discharge:
- OR o
IF on alternate SW discharge:
- e.
IF the required SW flow can NOT be obtained, THEN perform the following:
"* MOV-4609/MOV-4780 LEAST ONE CLOSED
"* MOV-4663/MOV-4733 LEAST ONE CLOSED AT AT
"* SFP Hx A (V-4622)
(for alternate SW discharge use V-4622A)
"* SFP Hx B (V-8689)
- 4) Verify SW portions of Attachment SD-1 are complete.
EOP:
TITLE:
REV 24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 22 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 22 Establish CCW flow to RHR Hxs:
- a. Check both CCW pumps -
RUNNING
- b.
Manually open CCW valves to RHR Hxs
"* MOV-738A
"* MOV-738B
- 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 AO 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.
- b. Dispatch AO to locally open valves.
EOP:
TITLE:
REV: 24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 22 of 22 STEP ACTION/EXPECTED RSPONSE RESPONSE NOT OBTAINIDJ 23 Check If Transfer To Cold Leg Recirculation Is Required:
- a.
RWST level -
LESS THAN 28%
- b.
Go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1
- a. Return to Step 17.
-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
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TITLE:
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24 E-1 LOSS OF REACTOR OR SECONDARY COOLANT 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:
24 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 TICs - LESS THAN 00 F USING FIGURE MIN SUBCOOLING
-OR o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT]
- 3. Sl TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
- 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 SIG 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).
EOP:
TITLE:
REV:
30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 42 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER 43 RESPONSIB6 MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:___________
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-1.2, 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 j ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI "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-l.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:
- a.
RCP status -
ANY RCP RUNNING
- b.
SI pumps AT LEAST TWO RUNNING
- c.
RCS pressure minus maximum SIG pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d.
Stop both RCPs
- a.
Go to Step 2.
- b.
Go to Step 2.
- c.
Go to Step 2.
NOTE:
CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, TO RESTART SAFEGUARDS EQUIPMENT.
(REFER OFFSITE POWER)
THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5, ATTACHMENT LOSS OF 2 Identify Ruptured S/G(s):
"o Unexpected increase in either S/G narrow range level
-OR "o High radiation indication on main steamline radiation monitor
"* R-31 for S/G A
"* R-32 for S/G B
-OR "o AC reports local indication of high steamline radiation
-OR "o RP reports high radiation from S/G activity sample Perform the following:
- a. Reset SI
- b. Continue with Steps 10 through 16.
WHEN ruptured SIG(s) identified, THEN do Steps 3 through 9.
S* *............
- O O O 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 SIG.
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
- c.
Close ruptured SIG TDAFW pump steam supply valve and place in PULL STOP
- SIG A, MOV-3505A
- S/G B, MOV-3504A
- d. Verify ruptured SIG blowdown valve CLOSED
- SIG A. AOV-5738
- SIG B, AOV-5737
- b.
WHEN ruptured S/G pressure less than 1050 psig, THEN verify SIG ARV closed.
IF NOT closed, THEN place controller in MANUAL and close SIG ARV.
IF SIG ARV can NOT be closed, THEN dispatch AO to locally isolate.
"* S/G A, V-3505
"* S/G B, V-3504
- d. Place SIG blowdown and sample valve isolation switch to CLOSE.
IF blowdown can NOT be isolated
- manually, THEN dispatch AO to locally isolate blowdown.
"* SIG A. V-5701
"* S/G B. V-5702
EOP:
TITLE:
REV:
30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 42 4 Complete Ruptured S/G Isolation:
- a. Close ruptured SIG MSIV
- a. Perform the following:
RUPTURED SIG MSIV CLOSED
- 1) Close intact SIG MSIV.
- 2)
Place intact SIG ARV controller at 1005 psig in AUTO.
- 3) Adjust condenser steam dump controller to 105C psig in AUTO.
- 4) Place condenser steam dump mode selector swit.:h to MANUAL.
- 5) Adjust reheat steam supply controller cam to close reheat steam supply valves.
- 6)
Ensure turbine stop kvalves CLOSED.
- 7) Dispatch AO to complete ruptured S/G isolaj-Jon (Refer to Attachment RUPTURED SIG, parts A and B).
- b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)
EOP:
TITLE:
REV:
30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 42 ACT*ON/EXPECTED NOT OBTAINED*
CAUTION IF ANY RUPTURED S/G IS FAULTED.
FEED FLOW TO THAT SIG SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
5 Check Ruptured S/G Level:
- a. Narrow range level -
GREATER THAN 5%
[25% adverse CNMT]
- b.
Close MDAFW pump discharge valve to ruptured S/G
- 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 valve to ruptured S/G
- S/G A, AOV-4297
- S/G B, AOV-4298
- e. Verify MDAFW pump crosstie valves -
CLOSED
- a. IF ruptured S/G NOT faulted, 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.
- b. Dispatch AO to locally close valve.
- d.
Dispatch AO with locked valve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.
"* S/G A, V-4005
"* S/G B, V-4006
- e. Manually close valves.
- MOV-4000A
- MOV-4000B
6 Verify Ruptured S/G Isolated:
- a. Check ruptured MSIV -
CLOSED
- b. Check TDAFW pump steam supply from ruptured SIG - ISOLATED
- c.
Ruptured S/G pressure -
GREATER THAN 300 PSIG 7 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available:
o Intact S/G MSIV -
OPEN o
Annunciator G-15, STEAM DUMP ARMED LIT
- b. Adjust condenser steam dump controller HC-484 to maintain intact SIG pressure and verify in AUTO
- c.
Place steam dump mode selector switch to MANUAL
- a. Ensure air ejector/gland steam supply and flange heating steam isolated.
(Refer to ATTACHMENT RUPTURED SIG, part B).
- b. Continue efforts to isolate steam supply from ruptured S/G:
- S/G A, MOV-3505A OR V-3505
- SIG B, MOV-3504A OR V-3504
- c.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
- a. Adjust SIG ARV controllers to maintain intact S/G pressure in AUTO and go to Step 8.
A O X
- *O*
- i.* *.O 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
ACTIONEXPECTED RESPONE...
REPO.
NOT OTAINED..
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
- b.
IF ruptured S/G MSIV closed, THEN initiate dumping steam to condenser from intact SIG at maximum rate
- c.
Core exit T/Cs -
LESS THAN REQUIRED TEMPERATURE
- d.
Stop RCS cooldown and stabilize core exit T/Cs less than required temperature
- b. Manually or locally initiate steam dump from intact S/G at maximum rate using S/G ARV.
IF no intact SIG available, THEN perform the following:
"o Use faulted S/G.
-OR 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.
Continue with Step 10.
WHEN core exit T/Cs less than
- required, THEN do Step 9d.
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]
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
10 Monitor Intact S/G Level:
- a. Narrow range level -
GREATER THAN 5% [25%. adverse CNMT]
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT] and 50%
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT]
in at least one SIG.
- b. IF narrow range level in the intact SIG continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
EOP:
TITLE:
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 42 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 liB).
11 Monitor PRZR PORVs And Block Valves:
- a. Power to PORV block valves AVAILABLE
- b.
PORVs CLOSED
- c. Block valves -
AT LEAST ONE OPEN
- a. Restore power to block valves unless block valve we. closed to isolate an open PORV:
"* MOV-515, MCC D position 6C
"* MOV-516, MCC C posi ion 6C
- b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
IF any PORV can NOT be&closed, THEN manually close iti* block valve.
IF block valve can NOT be closed, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RE(X0VERY
- DESIRED, Step 1.
- c.
Open one block valve unless it was closed to isolate an open PORV.
12 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED[
13 Monitor All AC Busses BUSSES ENERGIZED BY OFFSITE POWER o
Normal feed breakers to all 480 volt busses CLOSED o
480 volt bus voltage -
GREATER THAN 420 VOLTS o
Emergency D/G output breakers OPEN Perform the following:
- a.
IF any AC emergency bus normal feed breaker open. THEN ensure associated D/G breaker closed.
- b. Perform the following as necessary:
- 1) Close non-safeguards bus tie breakers:
"* Bus 13 to Bus 14 tie
"* Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
e EH pumps e Turning gear oil pump e HP seal oil backup pump
- 3) Restore power to MCCs.
"* A from Bus 13
"* B from Bus 15
"* E from Bus 15
"* F from Bus 15
- 4) Start HP seal oil backup pump.
- 5) Start CNMT RECIRC fans as necessary.
- 6) Ensure D/G 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).
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 42 14 Verify Adequate SW Flow:
- a.
Check at least two RUNNING SW pumps -
- a. Manually start SW pumps as power 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)
- 3)
IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
- 4)
IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 5)
Go to Step 16.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT:
- a. Verify non-safeguards busses energized "o Bus 13 normal feed -
CLOSED
-OR "o Bus 15 normal feed CLOSED
- b. Verify turbine building SW isolation valves - OPEN
- MOV-4613 and MOV-4670 o MOV-4614 and MOV-4664
- c. Verify adequate air compressors RUNNING
- d.
Check IA supply:
"o Pressure GREATER THAN 60 PSIG "o Pressure STABLE OR INCREASING
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers:
e Bus 13 to Bus 14 tie e Bus 15 to Bus 16 tie
- 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. Manually align valves.
- c. Manually start air compressors as power supply permits (75 kw each).
IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- d.
Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 16.
WHEN IA restored, THEN do Steps 15e and f.
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED" 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 THAN 250 psig [465 psig adverse CNMT]
- b.
Stop RHR pumps and place both in AUTO
- a.
Go to Step 17.
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 18 of 42 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.
e V-300A for RCP A
- V-300B for RCP B
- 2) Ensure HCV-142 demand at 0%.
- b.
Align charging pump suction to
- b.
IF LCV-112B can NOT be opened, RWST:
THEN dispatch AO 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 pu*i6 A NOT running and place in PULL STOP.
- 2) Direct AO 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
SATON/ EXPECTED 1EPOSE 1 RESPONSE NOT OBTAINED[)
18 Check If RCS Cooldown Should Be Stopped:
- a. Core exit 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 STABLE OR INCREASING 20 Check RCS Subcooling Based On Core Exit T/Cs -
GREATER THAN 20OF USING FIGURE MIN SUBCOOLING
- a. Do NOT proceed until core exit T/Cs less than required temperature.
IF pressure continues to decrease to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1
SE ACTION/EXPECTED RESPONS IRIESPONSE NOT OBTAINEDI NOTE:
SI ACCUMs may inject during RCS depressnrization.
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
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 21 of 42 STE ACTION/EXPECTED RESPONSE*
- E
- RESPONSE NOT OBTAINED CAUTION 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, closing normal charging valve spray flow may be increased by 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:
AVAILABLE
- b.
PRZR PORVs AVAILABLE AT LEAST ONE
- a. Refer to Attachment N2 PORVS to operate PORVs.
- b.
IF auxiliary spray 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.
(Step 22 continued from previous page)
- c.
Open one PRZR PORV 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]
- d. Close PRZR PORVs
- c. IF auxiliary spray available, THEN return to step 21b.
- 1) IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 1.
- d.
IF either PRZR PORV can NOT be closed, THEN close associated block valve.
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.
CAUTI ON SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED S/G.
- 1
- 24 Check If SI Flow Should Be Terminated:
- a.
RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING
- b. Secondary heat sink:
"o Total feed flow to S/G(s)
GREATER THAN 200 GPM AVAILABLE
-OR "o Narrow range level in at least one intact S/G GREATER THAN 5% [25% adverse CNMT]
- c.
RCS pressure STABLE OR INCREASING
- d.
PRZR level GREATER THAN 5%
[30% adverse CNMT]
- a. Do NOT stop SI pumps.
Go to ECA-3.1, SGTR WITH LOS)S OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- b. IF neither condition satisfied, THEN do NOT stop SI pumps.
Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- c.
Do NOT stop SI pumps.
Go to ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
- d.
Do NOT stop SI pumps. Return to Step 6.
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REV: 30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 42 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:
"* RCP A, V-300A
"* RCP B, V-300B
- 2) Ensure HCV-142 open.
- 3) Start one charging pump.
- b. Establish 20 gpm charging line flow
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 26 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27 Monitor SI Reinitiation Criteria:
- a.
RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING
- b.
PRZR level -
GREATER THAN 5%
[30% adverse CNMT]
- a. Manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY
- DESIRED, Step 1.
- b. Control charging flow to 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.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check If SI ACCUMs Should Be Isolated:
- a.
Check the following:
"o RCS subcooling based on core exit T/Cs -
GREATER THAN 0°F USING FIGURE MIN SUBCOOLING "o PRZR level -
GREATER THAN 5%
[30% adverse CNMT]
"* MOV-841, MCC C position 12F
"* MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves
- MOV-841 o MOV-865
- a. Manually operate SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY
- DESIRED, Step 1.
- c.
Vent any unisolated ACCUMs:
- 1) Open vent valves for unisolated SI ACCUMs.
o ACCUM A, AOV-834A o ACCUM B, AOV-834B
- 2)
Open HCV-945.
- d.
Locally reopen breakers for MOV-841 and MOV-865
SE ACTION/EXPECTED RESPONSEi RESPONSE NOT OBTAINEDt 29 Verify Adequate CCW Hx:
- a. Manually start pumps as power 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 valves AT LEAST ONE SET OPEN
- b. Manually align valves.
"* MOV-4615 and MOV-4734
"* MOV-4616 and MOV-4735 This Step continued on the next page.
STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 29 continued from previous page)
- c. Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED
- c. Perform the following:
"o IF on normal SW discharge:
"* V-4619, CCW Hx A
"* V-4620, CCW Hx B
-OR "o IF on alternate SW discharge:
e V-4619C, CCW Hx A
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
STEP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 30 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored:
OPEN "o IA pressure GREATER THAN 60 PSIG
- b. Verify instrument bus D ENERGIZED
- c.
CCW pumps ANY RUNNING
- d.
Charging pump ANY RUNNING
- a.
Continue with Step 36.
WHEN IA restored, THEN do Steps 30 through 35.
- b. Energize MCC B.
IF MCC B NOT available, THEN perform the following:
- 1) Verify MCC A energized.
- 2)
Place instrument bus D on maintenance supply.
- c. Perform the following.
- 1) IF any RCP #1 seal outlet temperature offscale high, THEN isolate CCW td thermal barrier of affected RCP(s).
"* RCP A, MOV-749A end MOV-759A
"* RCP B, MOV-749B Thid MOV-759B
- 2) Manually start one CCW pump.
- d.
Continue with Step 36.
WHEN any charging pump running, THEN do Steps 31 through 35.
31 Check If Seal Return Flow Should Be Established:
- a. Verify RCP #1 seal outlet temperature - LESS THAN 235°F
- b. Verify RCP seal outlet valves OPEN e AOV-270A e AOV-270B
- c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
- d.
Open RCP seal return isolation valve MOV-313
- e.
Verify RCP #1 seal leakoff flow LESS THAN 6.0 GPM
- f. Verify RCP #1 seal leakoff flow GREATER THAN 0.8 GPM
- a.
Go to Step 32.
- b. Manually open valves as necessary.
- d.
Perform the following:
- 1) Place MOV-313 switch to OPEN.
- e.
Perform the following:
- 1) Trip the affected RCP
- 2)
Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve o RCP A, AOV-270A o RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 32.
- f.
Refer to AP-RCP.1, RCP SEAL MALFUNCTION.
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REV :
30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 42 SE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDI 32 Verify PRZR Level -
GREATER THAN 13% [40% adverse CNMT]
33 Establish Normal Letdown:
- 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)
"* Letdown isolation valve AOV-371
"* Loop B cold leg to REGEN Hx AOV-427
- 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
- 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 Continue with Step 34.
WHEN PRZR level increases to greater than 13%
[40% adverse CNMT],
THEN do Step 33.
IF RCP seal return has been established, THEN establish excess letdown as follows:
"o Place excess letdown divert
- valve, AOV-312, to NORMAL.
"o Ensure CCW from excess letdown
- open, (AOV-745).
"o Open excess letdown isolation valve AOV-310.
Slowly open HCV-123 to maintain excess letdown temperature less than 195°F and pressure less than 100 psig.
"o Adjust charging pump speed as necessary.
IF RCP seal return NOT established, THEN consult TSC to determine if excess letdown should be placed in service.
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 42 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:
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed RED LIGHT LIT
- d.
Check VCT level:
"o Level GREATER THAN 20%
-OR "o Level STABLE OR INCREASING
- c.
Adjust controls as necessary.
- d. Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMW pumps running.
IF NOT, THEN reset MCC C and MCC D UV lockouts as necessary.
- 2)
Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
35 Check Charging Pump Suction Aligned To VCT:
- a.
VCT level -
GREATER THAN 20%
- b. Verify charging pumps aligned to VCT
- 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-l12B open "o LCV-112C closed
- 2)
Continue with Step 36.
WHEN VCT level greater than 40%,
THEN do Step 35b.
- b. Manually align valves as necessary.
"o LCV-112C -
OPEN "o LCV-112B -
CLOSED
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TITLE:
REV 3 0 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 42
- STEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 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
[65% 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 PRZR spray, if available, to obtain desired results for Step 36a
- b.
IF letdown is in service, THEN use auxiliary spray (AOV-296).
IF NOT, THEN use one PRZR PORV.
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 36 of 42 37 Monitor If CNMT Spray Should Be Stopped:
- a.
CNMT spray pumps -
ANY RUNNING
- b. Verify CNMT pressure
- LESS THAN 4 PSIG
- c.
Reset CNMT spray
- d.
Check NaOH tank outlet valves CLOSED
"* AOV-836A
"* AOV-836B
- e.
Stop CNMT spray pumps and place in AUTO
- f.
Close CNMT spray pump discharge valves
- MOV-860A
- MOV-860B o MOV-860C o MOV-860D
- a.
Go to Step 38.
- b. Continue with Step 38.
WHEN CNMT pressure less than 4 psig, THEN do Steps 37c through f.
- d. Place NaOH tank outlet valve controllers to MANUAL and close valves.
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 D/G and place in standby (Refer to Attachment D/G 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)
SE ACTION/EXPECTED RESPONSEI RESPONST NOT OBTAINEE 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).
- a.
"o Annunciator A-7, RCP 1A 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
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TITLE:
E-3 STEAM GENERATOR TUBE RUPTURE PAGE 39 of 42 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 1iB 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].
o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 201F 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
EOP:
TITLE:
REV 30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 40 of 42 SE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI NOTE:
Adverse CNMT conditions or loss of forc-ed air cooling may result in failure of NIS detectors.
43 Check If Source Range Detectors Should Be Energized:
- a. Source range channels DEENERGIZED
- b.
Check intermediate range flux EITHER CHANNEL LESS THAN 10-10 AMPS
- c.
Check the following:
"o Both intermediate range channels - LESS THAN 10-10 AMPS
-OR "o Greater than 20 minutes since reactor trip
- d.
Verify source range detectors ENERGIZED
- a.
Go to Step 43e.
- b.
Perform the following:
- 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.
Continue with Step 44.
WHEN either condition met, THEN do Steps 43d and e.
- d. Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can NOT be
- restored, THEN refer to ER-NIS.I, SR MALFUNCTION and go to Step 44.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
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30 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 41 of 42 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 44 Establish Normal Shutdown Alignment:
- a.
Check condenser - AVAILABLE
- b. Perform the following:
"o Open generator disconnects e IG13A71
- 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 rod shroud fan RUNNING
- 2) Verify one Rx compartment cooling fan -
RUNNING
- a. Dispatch AO to perform Attachment SD-2.
- 1) Manually start one fan as power supply permits (45 kw)
- 2)
Perform the following:
"o Dispatch AO 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-I COMPLETE
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RV E-3 STEAM GENERATOR TUBE RUPTURE PAGE 42 of 42 STEP ACTION/EXPECTED RESPONSE771 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 "o Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step I
-OR "o Go to ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1 END -
E-3 APPENDIX LIST TITLE
- 1)
RED PATH
SUMMARY
FIGURE MIN SUBCOOLING (FIG-1.0)
ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT CNMT RECIRC FANS (ATT-4.0)
D/G STOP (ATT -8. 1)
N2 PORVS (ATT-12.0)
NC (ATT-13.0)
SEAL COOLING (ATT-15.2)
RCP START (ATT-15.0)
RUPTURED S/G (ATT-16.0)
SD-i (ATT 17.0)
SD-2 (ATT-17. 1)
NO SW PUMPS (ATT-2.4)
LOSS OF OFFSITE POWER (ATT-8.5)
- 2)
- 3)
- 4)
- 5)
- 6)
- 7)
- 8)
- 9)
- 10)
- 11)
- 12)
- 13) 14)
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REV 30 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 12000F
-OR Core exit T/Cs greater than 700°F 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
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30 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 00 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.I, 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.
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBIý MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 2 of 19 A.
PURPOSE - This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.
B.
ENTRY CONDITIONS/SYMPTOMS
- 1.
ENTRY CONDITIONS -
This procedure is entered from:
- a.
E-0, REACTOR TRIP OR SAFETY INJECTION, when SI is neither actuated nor required.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 3 of 19 CAUTION IF SI ACTUATION OCCURS DURING THIS PROCEDURE, THEN E-0, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.
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.)
- 1 Monitor RCS Tavg -
STABLE AT IF temperature less than 5470F and OR TRENDING TO 5470F decreasing, THEN perform the following:
- a. Stop dumping steam.
- b. Ensure SIG blowdown and sample valves closed.
- c.
Ensure reheater steam supply valves are closed.
- d.
IF MDAFW pumps supplying greater than 200 gpm, THEN ensure TDAFW pump steam supply valves in PULL STOP.
- e. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one S/G.
WHEN S/G level greater than 5% in one SIG, THEN limit feed flow to that required to maintain S/G level.
- f.
IF cooldown continues, THEN close both MSIVs.
IF temperature greater than 5470F and increasing, THEN dump steam to stabilize and slowly decrease temperature to 5470F.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 4 of 19
~* **
CAUTION IF A MFW PUMP IS LEFT RUNNING ON RECIRC FOR EXTENDED PERIODS OF TIME, OVERHEATING MAY OCCUR.
2 Check S/G Feed Flow Status:
- a. Check RCS Tavg - LESS THAN 554°F
- b. Verify MFW flow control valves CLOSED
& MFW regulating valves e MFW bypass valves
- c. Verify total AFW flow -
GREATER THAN 200 GPM
- d.
Close MFW pump discharge valves e MOV-3977, A MFW pump
- MOV-3976, B MFW pump
- e.
Stop MFW pumps
- f.
WHEN both MFP pumps are stopped, THEN place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0% demand.
- a. Continue with Step 3.
WHEN temperature less than 554°F, THEN do Steps 2b through f.
- b. Place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0%
demand.
- c. Manually start both MDAFW pumps.
IF total AFW flow greater than 200 gpm can NOT be established, THEN perform the following:
o Manually start TDAFW pump.
-OR o
Perform the following:
- 1) Establish MFW on bypass valves.
- 2)
Go to step 3.
- d.
Manually stop MFW pumps.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 5 of 19 3 Monitor S/G Levels:
I
- a. Narrow range level GREATER THAN 5%
- b. Control feed flow to maintain narrow range level between 17%
and 52%.
4 Verify MRPI CONTROL AND BOTTOM Indicates -
ALL SHUTDOWN RODS ON
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one SIG.
- b.
IF narrow range level in any S/G continues to increase, THEN stop feed to that SIG.
IF one or more control rods NOT fully inserted, THEN perform the following:
- a. Place RMW mode selector switch to BORATE.
- b. Adjust boric acid flow control valve, FCV-11OA, for desired flowrate.
- c.
Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).
- d. Place RMW control to start and verify flow.
IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 6 of 19 5 Verify All AC Busses ENERGIZED BY OFFSITE POWER o
Normal feed breakers to all 480 volt busses CLOSED o
480 volt bus voltage -
GREATER THAN 420 VOLTS o
Emergency D/G output breakers OPEN Perform the following:
- a.
IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.
- b.
Perform the following as necessary:
- 1) Ensure one CCW pump running.
- 2)
Close non-safeguards bus tie breakers:
- Bus 13 to Bus 14 tie e Bus 15 to Bus 16 tie
- 3) Reset Bus 13 and Bus 15 lighting breakers.
- 4) Dispatch AO to locally reset and start adequate air compressors.
- 5)
Place the following pumps in PULL STOP:
"* EH pumps
"* Turning gear oil Pump
"* HP seal oil backup pump
- 6)
Restore power to MCCs.
o A from Bus 13 e B from Bus 15 e E from Bus 15 e F from Bus 15
- 7)
Start HP seal oil backup pump
- 8) Establish 2 CNMT RECIRC fans in service (205 kw each).
- 9) Ensure D/G load within limits.
- c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.I, RESTORATION OF OFFSITE POWER).
S STEPH ACTION/EXPECTED RESPONSE RESPONS NO OTAINED 6 Verify At Least Two SW Pumps RUNNING 7 Verify IA Available:
"o Adequate air compressor(s)
RUNNING "o IA pressure GREATER THAN 60 PSIG Manually start SW pumps as necessary.
IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
Dispatch AO to locally reset and start adequate air compressors.
IF adequate electric air compressor(s) can NOT be operated, THEN use diesel air compressor.
(Refer to ATT-11.2, ATTACHMENT DIESEL AIR COMPRESSOR)
IF IA pressure can NOT be maintained, THEN perform the following:
- a. Refer to AP-IA.l.
LOSS OF INSTRUMENT AIR.
- b. Verify charging pump A NOT running and place in PULL STOP.
pump
- d.
WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).
STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDt 8 Check PRZR Level Control:
- a. Verify charging pumps -
ANY RUNNING
- b.
PRZR level -
GREATER THAN 13%
- c. Verify letdown -
IN SERVICE
- d.
PRZR level - TRENDING TO 35%
- e.
Check PRZR heaters
- ENERGIZED o
PRZR proportional heaters o
PRZR heater backup group
- a. Perform the following:
- 1) Close letdown isolation, AOV-427.
- 2) Manually start one charging pump.
- b. Perform the following:
- 1) Place letdown isolation AOV-427 switch to close.
- 2) Verify excess letdown isolation valve AOV-310 closed.
- 3) Ensure PRZR heaters off.
- 4) Control charging to restore PRZR level greater than 13%.
- 5) Continue with Step 9.
WHEN PRZR level greater than 13%,
THEN do Steps 8c through e.
- c. Verify excess letdown in service.
IF NOT, THEN manually place letdown in service (Refer to ATT-9.0, ATTACHMENT LETDOWN).
- d.
Control charging and letdown to maintain PRZR level at 35%.
- e. Reset PRZR heaters and energize to restore PRZR pressure.
I I
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TITLE:
ES-0.1 REACTOR TRIP RESPONSE PAGE 9 of 19 STP ACTION/EXPECTED RESPONSE[
RESPONSE NOT OBTAINEDI 9 Check PRZR Pressure Control:
- a.
PRZR pressure -
GREATER THAN 1750 PSIG
- b.
PRZR pressure -
GREATER THAN 2210 PSIG
- a. Perform the following:
- 2)
Go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1.
- b. IF pressure less than 2210 PSIG and decreasing, THEN perform the following:
- 1) Ensure PRZR PORVs closed.
IF any valve can NOT be closed, THEN manually close its block valve.
e PCV-430, MOV-516
- PCV-431C, MOV-515
- 2) Ensure normal PRZR spray valves closed.
e PCV-431A e PCV-431B IF valves can NOT be closed, THEN stop associated RCP(s).
- 3)
Ensure PRZR heaters energized.1 This Step continued on the next page.
I
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 10 of 19 (Step 9 continued from previous page)
- c.
PRZR pressure
- LESS THAN
- c. IF pressure greater than 2260 PSIG 2260 psig and increasing, THEN perform the following:
- 1) Verify demand on PRZR pressure controller 431K greater than 50%.
IF NOT, THEN place controller in MANUAL and adjust to restore PRZR pressure to approximately 2235 psig.
- 2) Ensure PRZR heaters off.
- 3) Control pressure using normal PRZR spray.
IF normal PRZR spray NOT available and letdown is in service, THEN perform the following:
a) Verify spray line fluid to PRZR AT less than 320'F.
IF NOT, THEN use one PORV.
b) Use auxiliary spray.
IF PRZR spray NOT available, THEN use one PRZR PORV.
10 Check If TDAFW Pump Can Be Stopped:
- a. Both MDAFW pumps -
RUNNING
- b.
PULL STOP TDAFW pump steam supply valves
"* MOV-3504A
"* MOV-3505A 11 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available:
o Any MSIV -
OPEN o
Annunciator G-15, STEAM DUMP ARMED LIT
- a.
Go to Step 11.
- a. Perform the following:
- 1) Place SIG ARV controller in AUTO at 1005 psig and verify proper operation.
IF S/G ARV NOT controlling in
- AUTO, THEN control S/G ARV manually.
- 2)
Go to Step lid.
- b. Adjust condenser steam dump controller HC-484 to 1005 psig in AUTO
- c.
Place steam dump mode selector switch to MANUAL
- d. Adjust steam dump to restore Tavg.
IF steam dumps not available, THEN use ARVs.
12 Check RCP Status -
AT LEAST Perform the following:
ONE RUNNING
- a. Establish conditions for starting an RCP:
"o Verify bus 11A or 1iB 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.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 13 of 19 NOTE:
Loss of forced air cooling may result in failure of NIS detectors.
13 Check If Source Range Detectors Should Be Energized:
- a. Source range channels DEENERGIZED
- b.
Check intermediate range flux EITHER CHANNEL LESS THAN 10-10 AMPS
- c.
Check the following:
o Both intermediate range channels -
LESS THAN 10-10 AMPS
-OR o
Greater than 20 minutes since reactor trip
- d. Verify source range detectors ENERGIZED
- a.
Go to Step 13e.
- b. Perform the following:
- 1) IF neither intermediate range channel is decreasing THEN initiate boration.
- 2) Continue with Step 14.
WHEN flux is less than 10-10 amps on any operable channel, THEN do Steps 13c, d and e.
- c.
Continue with Step 14.
When either condition met, THEN do Steps 13d and e.
- d.
Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION, and go to Step 14.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
STP ACTION/EXPECTED RESPONSE[
RESPONSE NOT OBTAINED[
14 Establish Normal Shutdown Alignment:
- a. Check condenser
- AVAILABLE
- b. Perform the following:
"o Open generator disconnects e 1G13A71 o 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 Stop all but one condensate pump (Refer to T-5F, STARTING OR STOPPING THE CONDENSATE PUMPS)
- c. Verify adequate Rx head cooling:
- 1) Verify at least one control rod shroud fan -
RUNNING
- 2)
Verify one Rx compartment cooling fan -
RUNNING
- d.
Dispatch AO to perform ATT-17.0,.
ATTACHMENT SD-i
- a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.
- 1) Manually start one fan as power supply permits (45 kw).
- 2) Manually start one fan as power supply permits (23 kw).
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 15 of 19 STP ATO/XETDEPNERSOS NOTOBT INE 15 Maintain Stable Plant Conditions:
- a.
PRZR pressure BETWEEN 1800 PSIG AND 2260 PSIG
- b.
PRZR level -
BETWEEN 35% AND 40%
- c.
S/G narrow range levels BETWEEN 17% AND 52%
- d.
RCS Tavg -
GREATER THAN 540'F 16 Check VCT Makeup System:
- a. Verify the following:
- 1) Adjust boric acid flow control valve to 9.5 gpm
- 2) Adjust RMW flow control valve to 40 gpm
- 3)
RMW mode selector switch in AUTO
- 4)
RMW control armed -
RED LIGHT LIT
- b.
Check VCT level "o Level GREATER THAN 20%
-OR "o Level STABLE OR INCREASING
- a. Control PRZR heaters and spray as necessary.
- b. Control charging as necessary.
- c. Control S/G feed flow as necessary.
- d. Control dumping steam as necessary.
IF cooldown continues, THEN close both MSIVs.
- b. Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMW pumps running.
- 2) Place RMW flow control valve HCV-I11 in MANUAL and increase RMW flow.
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ES-0.1 REACTOR TRIP RESPONSE PAGE 16 of 19 17 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 18.
WHEN VCT level greater than 40%,
THEN do Step 17b.
- b. Align charging pumps to VCT o
LCV-112C OPEN o
LCV-112B CLOSED
18 Verify TDAFW Pump Aligned For AUTO Start:
- a.
Any MDAFW pump AVAILABLE
- b. Verify AMSAC TRIPPED status light EXTINGUISHED
- c. Verify both S/G levels THAN 17%
GREATER
- d. Verify Bus 11A and Bus 1lB - AT LEAST ONE ENERGIZED
- a. Verify TDAFW pump operating to maintain required S/G level and go to Step 20.
- b. Reset AMSAC.
- c.
Continue with Step 20.
level greater than 17%,
Steps 18d, e and 19.
WHEN S/G THEN do
- d. Perform the following:
o MOV-3504A o MOV-3505A
- 2)
Go to Step 19.
- e. Verify the following:
- 1) TDAFW pump OFF
- 2)
TDAFW pump steam supply valve switches in AUTO
- 1) IF TDAFW pump NOT required to maintain S/G level, THEN stop pump if desired.
- 2)
Place TDAFW pump steam supply valve switches in AUTO.
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ES-0.1 REACTOR TRIP RESPONSE PAGE 18 of 19 STP ACTION/EXPECTED RESPONSE[
RESPONSE NOT OBTAINEDI 19 Establish Normal AFW Pump Shutdown Alignment:
- a. Verify the following:
"o Both S/G levels GREATER THAN 17% AND STABLE OR INCREASING "o Total AFW flow - LESS THAN 200 GPM
- b.
Close MDAFW pump discharge valves
"* MOV-4007
"* MOV-4008
- d.
Stop all but one MDAFW pump
- e.
Open AFW discharge crossover valves e MOV-4000A e MOV-4000B
- f. Adjust AFW bypass valves to control S/G levels o AOV-4480
- AOV-4481
- a.
Continue with Step 20.
WHEN conditions met, THEN do Steps 19b through f.
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 19 of 19 20 Determine If Cooldown Is Required:
- a. Consult Plant Staff -
COOLDOWN REQUIRED
- b. At least one RCP -
RUNNING
- a.
Go to 0-3.
HOT SHUTDOWN WITH XENON PRESENT.
- b.
Perform the following:
- 1) Ensure 2 control rod shroud fans running.
- 2)
Go to ES-0.2, NATURAL CIRCULATION COOLDOWN, Step 1.
- c.
Go to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN
-END-
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 ES-O.1 APPENDIX LIST TITLE
- 1)
RED PATH
SUMMARY
- 2)
FIGURE MIN SUBCOOLING (FIG-1.0)
- 3)
ATTACHMENT LETDOWN (ATT-9.0)
- 4)
ATTACHMENT RCP START (ATT-15.0)
- 5)
ATTACHMENT NC (ATT-13.0)
- 6)
ATTACHMENT SD-I (ATT-17.0)
- 7)
ATTACHMENT SD-2 (ATT-17.1)
- 8)
ATTACHMENT NO SW PUMPS (ATT-2.4)
- 9)
ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)
- 10)
FOLDOUT
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19 ES-0.1 REACTOR TRIP RESPONSE 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
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19 ES-0.1 REACTOR TRIP RESPONSE PAGE 1 of 1 FOLDOUT PAGE
- 1.
SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and CI and go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:
"o RCS subcooling based on core exit T/Cs -
LESS THAN 0°F USING FIG-l.0, FIGURE MIN SUBCOOLING OR "o
PRZR level -
LESS THAN 5% [30% adverse CNMT]
AND RCS subcooling based on core exit T/Cs -
LESS THAN 20OF USING FIG-1.0, FIGURE MIN SUBCOOLING OR -
o Any automatic SI setpoint is reached
- 2.
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).
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED C OPY NUMBER
,RESPONSIB E MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A.
PURPOSE - This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions.
B.
ENTRY CONDITIONS/SYMPTOMS
- 1. ENTRY CONDITIONS - This procedure is entered from:
- a.
E-0, REACTOR TRIP OR SAFETY INJECTION, and E-l, LOSS OF REACTOR OR SECONDARY COOLANT, when specified termination criteria are satisfied.
- b.
FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and SI has been terminated.
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21 ES-I.1 SI TERMINATION PAGE 3 of 24 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)
NOTE:
o FOLDOUT page should be open AND monitored periodically.
"o Critical Safety Function Status Trees should be monitored (Refer to Appendix I for Red Path Summary).
"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 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION -
EXTINGUISHED
- b. Perform the following:
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
3 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG "o Reset PRZR heaters "o Use normal PRZR spray
4 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 Attachment SD-i).
- 3)
IF NO SW pumps running, THEN refer to ATT-2.4, ATTACHMENT NO SW PUMPS.
- 4)
IF only one SW pump running, THEN refer to AP-SW.2, LOSS OF SERVICE WATER.
- 5)
Go to Step 7.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-I)
5 Establish IA to CNMT:
- a. Verify non-safeguards busses energized from offsite power o
Bus 13 normal feed -
CLOSED
-OR o
Bus 15 normal feed -
CLOSED
- b. Verify SW isolation valves to turbine building -
OPEN "a MOV-4613 and MOV-4670
"* MOV-4614 and MOV-4664
- c. Verify adequate air compressor(s)
- RUNNING
- d.
Check IA supply:
"o Pressure -
GREATER THAN 60 PSIG "o Pressure -
STABLE OR INCREASING
- e.
Reset both trains of XY relays for IA to CNMT AOV-5392
- f.
Verify IA to CNMT AOV-5392 OPEN
- a. Perform the following:
- 1) Close non-safeguards bus tie breakers:
"* Bus 13 to Bus 14 tie
"* Bus 15 to Bus 16 tie
- 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. Manually align valves.
- c. Manually start air compressors as power supply permits (75 kw each).
IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
- d.
Perform the following:
- 1) Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step 6.
WHEN IA restored, THEN do Steps 5e and f.
EOP:
TITLE:
REV21 ES-I.1 SI TERMINATION PAGE 6 of 24 6 Check If Charging Flow Has Been Established:
- a. Charging pumps ANY RUNNING
- a. Perform the following:
- b. Charging pump RWST:
suction aligned to o
LCV-112B -
OPEN o
LCV-112C -
CLOSED
- 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 close seal injection needle valve(s) to affected RCP:
o RCP A, V-300A e RCP B, V-300B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Manually align valves as necessary.
IF LCV-112B can NOT be opened, THEN dispatch AO to locally open 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 AO 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
7 Stop SI And RHR Pumps And Place In AUTO
- 8 Monitor SI Reinitiation Criteria:
- a.
RCS subcooling based on core exit T/Cs GREATER THAN 0°F USING FIGURE MIN SUBCOOLING
- b.
PRZR level GREATER THAN 5%
[30% adverse CNMT]
- a. Manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. Control charging flow to maintain PRZR level.
IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
S~~ACTION/EXPECTED EPNE RESPONSE NOT OBTAIM!ýý]
- 9 Monitor If CNMT Spray Should Be Stopped:
- a.
CNMT spray pumps RUNNING
- a.
Go to Step 10.
LESS THAN
- b. Continue with Step 10.
WHEN CNMT pressure less than 4 psig, THEN do Steps 9c through f.
- c.
Reset CNMT spray
- d.
Check NaOH CLOSED tank outlet valves
- d. Place NaOH tank outlet valve 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
SSTEP ACTION/EXPECTED RESPONSE[
RESPONSE NOT OBTAINED[
10 Verify MRPI CONTROL AND BOTTOM Indicates -
ALL SHUTDOWN RODS ON IF one or more control rods NOT fully inserted, THEN perform the following:
- a.
Place RMW mode selector switch to BORATE.
- b. Adjust boric acid flow control valve, FCV-1IOA, for desired flowrate.
- c.
Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).
- d.
Place RMW control to start and verify flow.
IF flow can NOT be established, THEN refer to ER-CVCS.1, REACTOR MAKEUP CONTROL MALFUNCTION.
11 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available:
"o Any MSIV -
OPEN "o Annunciator G-15, STEAM DUMP ARMED
- LIT
- b. Adjust condenser steam dump controller HC-484 to desired pressure and verify in AUTO.
- c.
Place steam dump mode selector switch to MANUAL.
- a. Place SIG ARV controllers in AUTO at desired pressure and go to Step 12.
12 Verify Adequate CCW Hx:
- a. Manually start pumps as power 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 18.
- b. Verify AUX BLDG SW isolation valves -
OPEN
- b. Manually align valves.
o MOV-4615 and MOV-4734 e MOV-4616 and MOV-4735
- c.
Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED
- c.
Manually start an additional SW pump as power supply Termits (257 kw each).
SE ACTION/EXPECTED RESPONSE RESPONS NOCOTAND
13 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored:
OPEN "o IA pressure -
GREATER THAN 60 PSIG
- b. Verify instrument bus D ENERGIZED
- c.
CCW pumps ANY RUNNING
- d.
Charging pump -
ANY RUNNING
- a. Continue with Step 18.
WHEN IA can be restored,THEN do Steps 13 through 17.
- b. Energize MCC B.
IF MCC B NOT available, THEN perform the following:
- 1) Verify MCC A energized.
- 2)
Place instrument bus D on maintenance supply.
- 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.
Continue with Step 18.
WHEN any charging pump running, THEN do Steps 14 through 17.
STP ACTION/EXPECTE REPOS RESPONSE NO0BTAINEDI 14 Verify PRZR Level -
GREATER THAN 13% [40% adverse CNMT]
15 Establish Normal Letdown:
- a. Establish charging line flow to REGEN Hx GREATER THAN 20 GPM
- b. Place the following switches to CLOSE:
e Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)
- AOV-371, letdown isolation valve o AOV-427, loop B cold leg to REGEN Hx
- c.
Place letdown controllers in MANUAL at 40% open
- TCV-130 e PCV-135
- d. Reset both trains of XY relays for AOV-371 and AOV-427
- 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 to control PRZR level Continue with Step 16.
WHEN PRZR level increases to greater than 13%
[40% adverse CNMT],
THEN do Step 15.
IF RCP seal return has been established, THEN establish excess letdown as follows:
o Place excess letdown divert valve, AOV-312, to NORMAL.
o Ensure CCW from excess letdown
- open, (AOV-745).
o Open excess letdown isolation valve AOV-310.
o Slowly open HCV-123 to maintain excess letdown temperature less than 195°F and pressure less than 100 psig.
o Adjust charging pump speed as necessary.
IF RCP seal return NOT established, THEN consult Plant Staff to determine if excess letdown should be placed in service.
16 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:
- 1) RMW mode selector switch in AUTO
- 2)
RMW control armed -
RED LIGHT LIT
- d.
Check VCT level:
"o Level GREATER THAN 20%
-OR "o Level STABLE OR INCREASING
- c. Adjust controls as necessary.
- d. Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMW pumps running.
IF NOT, THEN dispatch AO to locally reset 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.
17 Check Charging Pump Suction Aligned To VCT:
- a.
VCT level -
GREATER THAN 20%
- b. Verify charging pumps aligned to VCT
- 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 18.
WHEN VCT level greater than 40%,
THEN do Step 17b.
- b. Manually align valves as necessary.
o LCV-112C -
OPEN o
LCV-112B -
CLOSED 18 Check RCS Hot Leg Temperatures -
STABLE Control steam dump and total feed flow as necessary to stabilize RCS temperature.
NOTE:
o WHEN using a PRZR PORV, THEN select one with an operable block valve.
o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
19 Control PRZR Heaters And Operate Normal Spray To Stabilize RCS Pressure IF normal spray NOT available and letdown is in service, THEN perform the following:
- a. Verify Regen Hx Chg outlet temp to PRZR Vapor temp AT less than 320°F.
IF NOT, THEN control pressure using one PRZR PORV and go to Step 20.
- b. Control pressure using auxiliary spray.
IF auxiliary spray NOT available, THEN use one PRZR PORV.
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
- 20 Monitor Intact S/G Levels,:
- a.
Narrow range level GREATER THAN 5% [25% adverse CNMT]
- b.
Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT] and 50%
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT]
in at least one S/G.
- b.
IF narrow range level in any SIG continues to increase, THEN stop feed flow to that S/G.
NOTE:
SW should be aligned to CCW Hxs before restoring RCP seal cooling.
21 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 WATER
-OR "o RCP seal injection flow to each RCP GREATER THAN 6 GPM
22 Check If Seal Return Flow Should Be Established:
- a. Verify RCP #1 seal outlet temperature LESS THAN 2350F
- b. Verify RCP seal outlet valves OPEN
- 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 valve MOV-313
- a.
Go to Step 23.
- b. Manually open valves as necessary.
- d.
Perform the following:
- 1) Place MOV-313 switch to OPEN.
- e. Verify RCP #1 seal leakoff flow LESS THAN 6.0 GPM
- f.
Verify RCP #1 seal leakoff flow GREATER THAN 0.8 GPM
- e. Perform the following:
- 1) Trip the affected RCP
- 2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve.
o RCP A, AOV-270A o RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 23.
- f.
Refer to AP-RCP.1, RCP SEAL MALFUNCTION.
STP ATONEPCE REPOS IEPNENTOT INE 23 Verify All AC Busses ENERGIZED BY OFFSITE POWER o
Normal feed breakers to all 480 volt busses -
CLOSED o
480 volt bus voltage GREATER THAN 420 VOLTS o
Emergency D/G output breakers OPEN Perform the following:
- a. IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.
- b. Perform the following as necessary:
- 1) Close non-safeguards bus tie breakers:
"* Bus 13 to Bus 14 tie
"* Bus 15 to Bus 16 tie
- 2) Reset Bus 13 and Bus 15 lighting breakers.
- 3)
Dispatch AO to locally reset and start two IA compressors.
- 4) Place the following pumps in PULL STOP:
S S
EH pumps Turning gear oil pump HP seal oil backup pump
- 5) Restore power to MCCs.
0 0
0 0
A from Bus 13 B from Bus 15 E from Bus 15 F from Bus 15
- 6)
- 7)
- 8) 9)
Start HP seal oil backup pump.
Start CNMT RECIRC fans as necessary.
Ensure D/G load within limits.
Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- c.
Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
NOTE:
Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
24 Check If Source Range Channels Should Be Energized:
- a. Source range channels DEENERGIZED
- b.
Check intermediate range flux EITHER CHANNEL LESS THAN 10-10 AMPS
- c.
Check the following:
"o Both intermediate range channels LESS THAN 10-10 AMPS
-OR "o Greater than 20 minutes since reactor trip
- d. Verify source range detectors ENERGIZED
- a.
Go to Step 24e.
- b. Perform the following:
- 1) IF neither intermediate range channel is decreasing, THEN initiate boration.
- 2)
Continue with Step 25.
WHEN flux is LESS THAN 10-10 amps on any operable channel, THEN do Steps 24c, d and e.
- c.
Continue with step 25.
WHEN either condition met, THEN do Steps 24d and e.
- d.
Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can NOT be
- restored, THEN refer to ER-NIS.I, SR MALFUNCTION, and go to Step 25.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
25 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses
- a. Try to restore offsite power energized by offsite power:
(Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
"o Emergency D/G output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED
- b.
Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
A S
- O*TA
- DI CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
26 Check RCP Status AT LEAST Perform the following:
ONE RUNNING
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 20OF using Figure MIN SUBCOOLING.
"o Energize PRZR heaters as necessary to saturate PRZR water.
- b. Establish conditions for starting an RCP:
"o Verify bus 11A or 1iB energized.
"o Refer to Attachment RCP START.
- c. Start one RCP.
IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation NOT verified, THEN increase dumping steam from intact S/Gs.
STP ACTION/EXPECTED RESPONSEI RESPONSE NO 0BTAINEDI 27 Establish Normal Shutdown Alignment:
- a. Check condenser
- AVAILABLE
- b.
Perform the following:
"o Open generator disconnects
"* IG13A71
"* 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 rod shroud fan -
RUNNING
- 2) Verify one Rx compartment cooling fan -
RUNNING
- a. Dispatch AO to perform Attachment SD-2.
- 1) Manually start one fan as power supply permits (45 kw)
- 2)
Perform the following:
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
28 Maintain Plant Conditions Stable:
- a.
RCS pressure - BETWEEN 1800 PSIG AND 2235 PSIG
- b.
PRZR level BETWEEN 35% AND 40%
- c. Intact SIG narrow range levels BETWEEN 17% AND 52%
- d.
RCS cold leg temperature -
STABLE
- 29 Monitor SI Reinitiation Criteria:
- a.
RCS subcooling based on core exit T/Cs -
GREATER THAN 0°F USING FIGURE MIN SUBCOOLING
- b.
PRZR level -
GREATER THAN 5%
[30% adverse CNMT]
- a. Control PRZR heaters and spray as necessary.
- b. Control charging as necessary.
- c. Control SIG feed flow as necessary.
- d. Control dumping steam as necessary.
IF cooldown continues, THEN close both MSIVs.
- a. Manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. Control charging flow to maintain PRZR level.
IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
-JSTEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 30 Implement Plant Recovery Procedures:
- a. Review plant systems for realignment to normal conditions (Refer to ATT-26.0.
ATTACHMENT RETURN TO NORMAL OPERATIONS)
- b.
Go to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN END
ES-1.1 APPENDIX LIST TITLE
- 1)
RED PATH
SUMMARY
FIGURE MIN SUBCOOLING (FIG-1.0)
ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT CNMT RECIRC FANS (ATT-4.0)
D/G STOP (ATT-8. 1)
NC (ATT-13.0)
SEAL COOLING (ATT-15.2)
RCP START (ATT-15.0)
SD-I (ATT-17.0)
SD-2 (ATT-17.1)
SI/UV (ATT -8.4)
NO SW PUMPS (ATT-2.4)
RETURN TO NORMAL OPERATIONS (ATT-26.0)
LOSS OF OFFSITE POWER (ATT-8.5)
- 2)
- 3)
- 4)
- 5)
- 6)
- 7)
- 8)
- 9)
- 10)
- 11)
- 12)
- 13) 14)
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 700°F 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
FOLDOUT PAGE
- 1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY
- COOLANT, Step 1:
"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]
- 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.
- 3.
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).
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 21 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE.YNAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
A.
PURPOSE -
This procedure provides the necessary instructions for transferring the Safety Injection system and Containment Spray system to recirculation modes of operation.
B.
ENTRY CONDITIONS/SYMPTOMS
- 1.
ENTRY CONDITIONS -
This procedure may be entered from:
- a.
E-1, LOSS OF REACTOR OR SECONDARY COOLANT, or,
- b.
ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI
- REQUIRED, or,
- c.
ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or,
- d.
FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, or,
- e.
FR-C.2, RESPONSE TO DEGRADED CORE COOLING, or,
- f.
FR-C.3, RESPONSE TO SATURATED CORE COOLING, or,
- g.
FR-H.I, RESPONSE TO LOSS OF SECONDARY HEAT SINK, or,
- h.
FR-Z.1, RESPONSE TO HIGH CONTAINMENT PRESSURE, on low RWST level.
- i.
Other procedures whenever RWST level reaches the switchover setpoint (28%).
EOP:
TITLE:
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 3 of 21
- I* *
- I *
- 0 0 0
- I* **
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 CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING.
SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.
NOTE:
o FOLDOUT page should be open and monitored periodically.
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 Verify RWST level GREATER THAN 15%
AT LEAST 113 INCHES IF sump recirculation NOT in
- progress, THEN pull-stop all pumps taking suction from RWST, EXCEPT one SI pump AND go to ECA-I.I, LOSS OF EMERGENCY COOLANT RECIRCULATION.
Step 1.
IF RWST level is less than 28% AND CNMT sump B level is less than 113 inches.
THEN go to ECA-I.2, LOCA OUTSIDE CONTAINMENT, Step 1.
NOTE:
Steps 3 through 13 should be performed without delay.
FR procedures should not be implemented prior to completion of these steps.
3 Reset SI
EOP:
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 4 of 21 NOTE:
IF D/Gs supplying emergency AC busses, THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.
4 Establish Adequate SW Flow:
- a. Verify at least two SW pumps RUNNING
- b. Verify AUX BLDG SW isolation valves -
OPEN
- a. Start additional SW pumps as power supply permits (257 kw each).
IF only 1 SW pump
- operable, THEN perform the following:
- 2)
Go to Step 5.
- b. Manually align valves.
"* MOV-4615 and MOV-4734
"* MOV-4616 and MOV-4735
- c.
Dispatch AO to Check BOTH CCW Hxs IN SERVICE
- d.
Determine required CCW HXs per table:
- c.
Locally place BOTH CCW! Hxs in service SW flow to This Step continued on the next page.
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
(Step 4 continued from previous page)
-OR "o IF on alternate SW discharge:
- V-4619C.
- e. IF the required SW flow can NOT be obtained, THEN perform the following:
"* MOV-4609/MOV-4780 LEAST ONE CLOSED
"* MOV-4663/MOV-4733 LEAST ONE CLOSED AT AT
"* SFP Hx A (V-4622)
(for alternate SW discharge use V-4622A)
"* SFP Hx B (V-8689)
- 4) Verify SW portions of Attachment SD-1 are complete.
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 6 of 21 STP ACTION/EXPECTED RESPONSE[
RESPONSE NOT OBTAINED[
5 Establish CCW flow to RHR Hxs:
- a. Check both CCW pumps - RUNNING
- b.
- MOV-738A o MOV-738B
- 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 5b.
- 3)
IF only one CCW pump is running, THEN perform the following:
a) Direct AO 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 6.
- b. Dispatch AO to locally open valves.
SE ACTION/EXPECTED RESPONSEI
RESPONSE
NOT OBTAINED CAUTION o
THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625)
WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.
o CONSULT WITH RADIATION PROTECTION BEFORE DISPATCHING PERSONNEL TO AUXILIARY BUILDING.
SWITCHOVER TO RECIRCULATION MAY CAUSE HIGH RADIATION LEVELS.
6 Check RHR Flow:
o RHR flow - LESS THAN 1500 GPM PER OPERATING PUMP Manually adjust RHR Hx outlet 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
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 8 of 21 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI 7 Check IF Unnecessary Pumps Can Be Stopped:
- a. Three SI pumps -
RUNNING
- b. Stop SI pump C and place both switches in PULL STOP
- c.
Stop both RHR pumps and place in PULL STOP
- d.
Both CNMT spray pumps -
RUNNING
- e. Pull stop one CNMT spray pump
- f.
Check CNMT pressure - LESS THAN 28 PSIG.
- g.
Place NaOH Tank outlet valve controllers in manual, full open.
e AOV-836A
- AOV-836B
- h. Reset CNMT spray
- i.
Close discharge valves for idle CNMT spray pump(s) o Pump A
- MOV-860A
- MOV-860B o
Pump B
- MOV-860C 9 MOV-860D
- a.
Go to Step 7c.
- d. Pull stop any idle CNMT spray pump and go to Step 7f.
- f.
Go to Step 8.
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 9 of 21 8 Verify RHR System Alignment:
- a. Verify the following valves CLOSED "o RHR suction valves from loop A hot leg e MOV-700 e MOV-701 "o RHR discharge valves to loop B cold leg o MOV-720
- MOV-721
- b. Verify RHR pump suction crosstie valves OPEN
"* MOV-704A
"* MOV-704B
- c. Verify the following valves OPEN
- a. Ensure at least one suction valve and one discharge valve closed.
- b. Manually open valves.
If valves can NOT be opened, THEN dispatch AO to locally open valves.
- c. Ensure at least one valve in each set open.
"o RHR pump discharge to Rx vessel deluge valves
"* MOV-852A
"* MOV-852B "o RHR suction from sump B (inside CNMT) o MOV-851A e MOV-851B
CLOSED
- d.
Manually close valves.
MOV-1813A
"* MOV-1813B
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 10 of 21 STP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDA CAUTI ON RHR FLOW INDICATED ON FI-626 SHOULD BE TO ENSURE OPTIMUM PUMP PERFORMANCE.
LIMITED TO 1500 GPM PER OPERATING PUMP 9 Initiate RHR Sump Recirculation:
"o MOV-850A OPEN "o MOV-850B OPEN
- c.
Check MOV-738A AND MOV-738B BOTH OPEN
- a. Dispatch AO to locally close valve and continue wi.h Step 9b.
- b.
IF only one valve will open, THEN perform the following:
- 1) Initiate only one train of RHR recirculation (Refer to Attachment RHR NPSH for further guidance).
- 2)
Go to 9e.
IF neither valve will open, THEN refer to Attachment RHPl PRESS REDUCTION for further 2luidance.
- c.
Perform the following:
- 1) IF MOV-738A open, THEN start RHR Pump A and go to step 9e.
- 2) IF MOV-738B open, THEN start RHR Pump B and go to step 9e.
- d. Start both RHR pumps
- e. Verify at least one RHR pump RUNNING
- e. IF no RHR pump can be started, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 11 of 21 SE ACTION/EXPECTED RESPONSEI RESPONSE NOT 0 TAINEDI CAUTION SUMP RECIRCULATION FLOW TO RCS MUST BE MAINTAINED AT ALL TIMES, EXCEPT DURING ALIGNMENT FOR HIGH HEAD RECIRCULATION.
NOTE:
The TSC should be requested to establish periodic monitoring of the AUX BLDG sub-basement, as radiological conditions permit, to monitor RHR pump operation.
10 Check RWST Level -
LESS THAN 15%
11 Stop All Pumps Supplied From RWST:
- a. Stop all SI pumps and place in PULL STOP
- b. Stop all charging pumps
- c.
Stop operating CNMT spray pump and place in PULL STOP
- d.
Check CNMT pressure -
LESS THAN 28 PSIG
- e.
Reset CNMT spray if necessary
- f. Close CNMT spray pump discharge valves 0
0 0
0 DO NOT continue with this procedure until RWST level is less than 15%.
- d.
Go to Step 12.
MOV-860A MOV-860B MOV-860C MOV-860D
.A.......X
.O..
- OT O
- A*
CAUTION RHR FLOW MUST BE MAINTAINED LESS THAN 1500 GPM PER OPERATING RHR PUMP AS DETERMINED BY THE TOTAL OF FI-931A, FI-931B AND FI-626 INDICATIONS.
12 Align SI And CNMT Spray For Sump Recirculation:
- a. Verify SI pump suction valves from BASTs CLOSED
- a. Ensure at least one valve in each flowpath closed.
"* MOV-826A and MOV-826B
"* MOV-826C and MOV-826D
- b. Ensure at least one valve closed.
"* MOV-896A
"* MOV-896B
- c.
Close SI pump RECIRC valves
- c.
Ensure at least one valve closed.
- MOV-898 o MOV-897
OPEN
- d. Ensure at least one valve open.
- MOV-825A o MOV-825B
"o IF RHR Pump A operating, THEN open MOV-857A and MOV-857C "o IF RHR Pump B operating, THEN open MOV-857B
- e. Ensure at least one flowpath aligned from RHR pump(s) to SI and CS pump suction header (Refer to Attachment RHR SYSTEM).
IF neither flow path can be aligned, THEN refer to Attachment RHR PRESS REDUCTION for further guidance.
A
- ** O*
- *X
- 4.ON
- O*
A CAUTION SI PUMPS SHOULD BE STOPPED IF RCS PRESSURE IS GREATER THAN THEIR SHUTOFF HEAD PRESSURE.
NOTE:
Operation of SI pump C is preferred since it delivers to both RCS loops.
13 Verify Adequate RCS Makeup Flow:
- a.
RCS pressure -
LESS THAN 225 psig [425 psig adverse CNMT]
- b. RHR injection flow adequate:
o Core exit T/Cs REQUIREMENTS OF INJECTION
- a.
Perform the following:
- 1) Check RCS conditions:
"o RCS subcooling based on core exit T/Cs greater than Figure MIN SUBCOOLING.
"o PRZR level greater than 5%
[30% adverse CNMT].
IF either condition NOT met.
THEN start one SI pump.
- 2)
Go to Step 14.
- b. Start one SI pump.
LESS THAN FIGURE RHR o
Check RVLIS level (no RCPS)
GREATER THAN 52% [55% adverse CNMT]
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REV: 32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 14 of 21 t_
CAUTION IF A CNMT SPRAY PUMP IS STARTED, THEN CNMT PRESSURE SHOULD BE CLOSELY MONITORED.
CNMT PRESSURE SHOULD NOT BE REDUCED TO LESS THAN 32 PSIG.
14 Check If CNMT Spray Is Required:
- a.
CNMT pressure -
GREATER THAN 37 PSIG
- a. Perform the following:
- 1) IF CNMT spray previously actuated and NaOH tank level greater than 55%,
THEN consult TSC to determine if CNMT spray should be restarted.
- 2)
Go to Step 15.
- b. Verify CNMT spray pump discharge valves -
OPEN
- MOV-860A o MOV-860B o MOV-860C e MOV-860D
- c. Start selected CNMT spray pump
- b. Manually open valve(s) for selected pump.
"* CS pump A, MOV-860A or MOV-860B
"* CS pump B, MOV-860C or MOV-860D
- c.
IF the selected CNMT spray pump will not start, THEN align and start the other CNMT spray pump.
IF neither pump will start, THEN continue with Step 15.
WHEN a CNMT spray pump can be started, THEN do steps 14d, e and f.
- d. Adjust RHR flow to maintain less than 1500 gpm per operating RHR pump as indicated by the total of FI-931A, FI-931B and FI-626 indications.
- e.
Open NaOH tank outlet valves
- AOV-836A e AOV-836B
- f.
WHEN CNMT pressure decreases to 32 psig, THEN pull stop CNMT spray pump
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32 ES-l.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 15 of 21 SE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINED 15 Verify Adequate Core Cooling:
"o Core exit T/Cs - STABLE OR DECREASING "o RVLIS level (no RCPs)
STABLE OR INCREASING "o RVLIS level (no RCPs)
GREATER THAN 52% [55% adverse CNMT]
IF both RHR pumps running, THEN ensure two SI pumps running.
IF only one RHR pump running, THEN perform the following:
- a. Ensure one SI pump running.
- b.
WHEN CNMT spray pumps stopped, THEN start one additional SI pump.
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
"*16 Monitor Intact S/G Levels:
- a. Narrow range level GREATER THAN 5% [25% adverse CNMT]
- a. Maintain total feed flow greater 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 narrow range level between 17%
[25% adverse CNMT]
and 50%
SE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDt 17 Establish Normal Shutdown Alignment:
- a. Check condenser
- AVAILABLE
- b.
Perform the following:
"o Open generator disconnects
- 1G13A71
- 9X13A73 "o Place voltage regulator to OFF "o Open turbine drain valves "o Rotate reheater steam supply controller cam to close valves "o Place reheater dump valve switches to HAND "o Stop all but one condensate pump
- c.
Verify adequate Rx head cooling:
- 1) Verify at least one control rod shroud fan -
RUNNING
- 2) Verify one Rx compartment cooling fan -
RUNNING
- a. Dispatch AO to perform Attachment SD-2.
- 1) Manually start one fan as power supply permits (45 kw)
- 2)
Perform the following:
"o Dispatch AO 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-I -
COMPLETE
18 Check If Emergency D/Gs Should Be Stopped:
- a. Verify AC emergency busses
- a. Try to restore offsite power energized by offsite power:
(Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
"o Emergency D/G output breakers OPEN "o AC emergency bus voltage GREATER THAN 420 VOLTS "o AC emergency bus normal feed breakers CLOSED
- b.
Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
19 Check If SI ACCUMs Should Be Isolated:
- a. Both RCS hot leg temperatures LESS THAN 400°F
"* MOV-841, MCC C position 12F
"* MOV-865, MCC D position 12C
- c.
Close SI ACCUM discharge valves
"* ACCUM A, MOV-841
"* ACCUM B. MOV-865
- a. Continue with Step 20.
WHEN both RCS hot leg temperatures less than 400 0 F, THEN do Steps 19b through d.
- c. Vent any unisolated ACCUMs:
- 1) Open vent valves for 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
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 19 of 21 STEP ACTTON** XPECTED RES**0*
S*
- 1 RESPONSE NOT 0*TAI CAUTION TT' 1'TT'IT ThAIXTA/"T*
TC f'lT1C('
m1)'[*'fTh*T ~IAT)T ATa r
ffl*^CT1T('
r' r
-C'*-II TT-cr TC"'T~qT'TT 1*T
'Am1)"n
'flTT*K]
Tlr'C' PRESSURE.
20 Check If Intact S/Gs Should Be Depressurized To RCS Pressure:
- a.
RCS pressure LESS THAN INTACT SIG PRESSURES
- b. Direct RP to sample S/Gs for activity
- c. Request TSC perform a dose projection on steaming S/Gs
- d.
Dose projection for each S/G ACCEPTABLE
- e.
Dump steam to condenser from intact S/G(s) until SIG pressure less than RCS pressure
- a.
Go to Step 21.
- d.
Do NOT dump steam from a S/G with an unacceptable dose projection.
- e.
IF steam dump to condenser NOT available, THEN dump steam using intact S/G ARVs until S/G pressure less than RCS pressure.
21 Consult TSC to Determine If Rx Vessel Head Should Be Vented
SE ACTION/EXPECTED RESPONSE IRIESPONSE NOT OBTAINEDI NOTE:
This procedure should be continued whil6 obtaining CNMT hydrogen sample in Step 22.
22 Check CNMT Hydrogen Concentration:
- b. Hydrogen concentration - LESS THAN 0.5%
NOTE:
The TSC should be consulted before changing recirculation lineups.
23 Check Event Duration GREATER THAN 19 HOURS AFTER EVENT INITIATION 24 Secure CNMT Spray
- a. Reset CNMT spray
- b. Place NaOH Tank outlet valve controllers in AUTO
- AOV-836A
- AOV-836B
- c.
Place CNMT spray pumps in PULL STOP
- d. Close discharge valves for idle CNMT spray pumps "o Pump A o MOV-860A o MOV-860B "o Pump B o MOV-860C
- MOV-860D Consult TSC to evaluate long term plant status.
STP ACTION/EXPECTED RESPONSEI R
ESPONSE NOT OBTAINED 25 Verify Two SI Pumps RUNNING 26 Check Core Exit T/Cs LESS THAN REQUIREMENTS OF FIGURE RHR INJECTION.
Manually start pumps.
Perform the following:
- a. Manually open both PRZR PORVs and block valves.
- b. Verify core exit T/Cs decreasing to less than requirements of Figure RHR INJECTION.
IF NOT, THEN dump steam from intact S/Gs until core exit T/Cs less than required.
27 Consult TSC To Evaluate Long Term Plant Status
.END
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 ES-1.3 APPENDIX LIST TITLE
- 1)
RED PATH
SUMMARY
FIGURE RHR FIGURE MIN ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT INJECTION (FIG -5.0)
SUBCOOLING (FIG-1.0)
D/G STOP (ATT-8.1)
SD-I (ATT-17.0)
SD-2 (ATT-17. 1)
RHR SYSTEM (ATT-14.5)
MIN SW (ATT -2.1)
RHR PRESS REDUCTION (ATT -14.6)
LOSS OF OFFSITE POWER (ATT-8.5)
- 2)
- 3)
- 4)
- 5)
- 6)
- 7)
- 8)
- 9)
- 10)
- 11) 12)
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32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 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
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REV 32 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION PAGE 1 of 1 FOLDOUT PAGE
- 1. ECA-1.1 TRANSITION CRITERIA IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-l.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
- 2.
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).