ML17309A490
| ML17309A490 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/26/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| PROC-920626, NUDOCS 9207090120 | |
| Download: ML17309A490 (60) | |
Text
ACCELERATED DISTMBUTION DEMONSTPA,TION SYSTEM REGULATOR ZNFORMATZON DZSTRZBUTZON STEM (RZDS)
ACCESSION NBR:9207090120 DOC.DATE: 92/06/26 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A. Project Directorate I-3
SUBJECT:
Revised EOPs,including Rev 1 to ATT,Rev 2 to ATT,Rev 8 to AP-SW.1,Rev 6 to FR-S.1 6 Rev ll to FR-H.l.W/920626 1tr.
DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82- 3)
NOTES:License Exp date in a d nce with 10CFR2,2.109(9/19/72). - 05000244
/~i+g I/N/gE'ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 . PD1-3 PD, 1 1 JOHNSON,A 2 2 INTERNAL: NRR/DLPQ/LHFB11 1 1 OC/LFMB 1 0 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1
/Yo p7~~e~ ~g 8 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
pP TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9
ZIIIIIIIZ t ZZZZZIZ ZZZ ZI ZZIZZZZ ROCHESTER GAS AND ELECTRIC CORPORATION 4 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY TELEPHONE Vice Prerldent AAEACOOE716 546 2700 Ginna Nudear Production June 26, 1992
'.S.
Nuclear Regulatory Commission Document Control Desk Mr. Allen Johnson
'ttn:
Project Directorate I-3 Washington, D.C. 20555
Subject:
Emergency Operating Procedures R. E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecredy Enclosures c: Mr. Lee Bettenhausen, USNRC, Region 1 Resident Inspector, Ginna Station o )rAi(
emergency. pro yoS 92@7090120<0 0>ppp24+
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Abnormal Procedures Index - issued 6/23 EOP/AP Attachment Index - 6/23/92 ATT EOP/AP Attachments - Rev. 1 - 5/1 3/92 - SW Isolation ATT EOP/AP Attachments - SW Loads in CNMT ATT EOP/AP Attachments - Rev. 2 - 5/1 4/92-Flow Through MFW Pump B AP-SW.1 Service Water Leak - Rev. 8 AP-TURB.1 Turbine Trip Without RX Trip Required, Rev. 5 FR-S.1 Response to Reactor Restart/ATWS - Rev. 6 FR-H.1 Response to Loss of Secondary Heat Sink - Rev. 11
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P4 b/P4o/FM FM~F&l~ SSS0 9 SOCEOVEES XSS ISSUED: 03/20/92 EFFECTIVE RROCED TITLE REV DATE AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 90/02/28 V
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 8 89/12/19 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN 7 89/12/19 AP-CR.1 CONTRO ROOM INACCESSIBILITY 11 91/05/10 AP-CVCS.1 CVCS LEAK 5 89/12/19 AP-CVCS.2 IMMEDIATE BORATIO 7 , 90/02/23 AP-CW.1 LOSS OF A CIRC WATER PUMP 4 90/02/23 AP-ELEC.1 LOSS OF jg12A OR 12B TRANSFORMER 8 91/06/17 AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 5 90/02/23
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ABNORMAL PROCEDURES INDEX XSSDED: D3/2S/92 EFFECTIVE PRDCEDDRE TITLE REV DATE AP-FW.1 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER 8 91/05/10 AP-IA.1 LOSS OF INSTRUMENT AIR 6 92/03/19 AP-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE 5 91/11/01 AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 4 90/02/23 AP-RCC.2 RCC/RPI MALFUNCTION 4 90/04/09 AP-RCP.1 RCP SEAL MALFUNCTION 6 89/11/17
'AP-RCS.1 REACTOR COOLANT LEAK 7 91/11/01 AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 5 90/02/23 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 5 90/11/20
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ABNORMAL PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE PROCEDURE T XTLE REV DATE AP-RHR.1 LOSS OF RHR 8 90/06/01 AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 4 92/03/27
'1 AP-SW.1 SERVICE WATER LEAK 7 90/02/23 AP-TURB.1 TURBINE TRIP WITHOUT gX TRIP REQUIRED 4 90/02/23 AP-TURB.2 AUTOMATIC TURBINE RUNBACK 10 91/10/11 AP-TURB.3 TURBINE VIBRATIONS 5 90/02/23 AP-TURB.4 LOSS OF CONDENSER VACUUM 6 90/02/23
EMERGENCY PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE PROCEDURE TITLE REV DATE E-0 REACTOR TRIP OR SAFETY INJECTION 16 91/05/03 E-1 LOSS OF REACTOR OR SECONDARY COOLANT 10 91/05/03 E-2 FAULTED STEAM GENERATOR ISOLATION 4 90/04/09 E-3 STEAM GENERATOR TUBE RUPTURE 12 91/07/26
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ENERGENCY CON'NGENCY ACTIONS PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE TITLE REV DATE ~
ECA-O.O LOSS OF ALL AC POWER 12 91/08/05 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED 5 91/05/03 ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 6 90/04/09 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 6 91/05/03 ECA-1.2 LOCA OUTSIDE CONTAINMENT 2 90/04/09 ECA-2. 1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS 6 91/05/03 ECA-3. 1 SGTR WITH LOSS OF REACTOR
., COOLANT-SUBCOOLED RECOVERY DESIRED 7 91/05/03 ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED 9 91/05/03
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EMERGENCY CONTINGENCY ACTIONS PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE PROCEDVRE pZ~ REV DATE ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 6 91/05/03
EQUIPMENT. SUB-PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE PROCED REV DATE ES-O.O REDIAGNOSIS 7 90/04/09 ES-F 1 REACTOR TRIP RESPONSE 7 90/12/19 ES-0.2 NATURAL CIRCULATION COOLDOWN 2 91/05/03 ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS) 1 90/04/30 ES-1.1 SI TERMINATION 7 91/05/03 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 8 91/06/24 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 13 91/10/28 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 4 91/05/03 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN 5 91/05/03
it E UIPMENT SUB-PROCEDURES INDEX ISSUED. 03/28/92 EFFECTIVE PROCED REV DATE I
ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 5 91/05/03
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CRITICAL SAFETY FUNCTION STATUS TREES INDEX ISSUED: 03/28/92 EFFECTIVE
~TTLE REV DATE F-0. 1 SUBCRITICALITY CSFST 1 89/07/21 F-0.2 CORE'COOLING CSFST 3 89/07/21 F-0.3 HEAT SINK CSFST 2 "'0/01/12
~ F-0.4 INTEGRITY CSFST 1 89/07/21 F-0.5 CONTAINMENT CSFST 2 90/01/12 F-0.6 INVENTORY CSFST 3 90/01/12
p3 FUNCTIONAL RESTORAT PN GUIDELIZNES PROCEDURES INDEX ISSUED- 03/28/92 EFFECT?VE TITLE REV DATE FR-C.1 RESPONSE TO INADEQUATE CORE COOLING 6 90/04/09 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 5 90/04/09 FR-C.3 RESPONSE TO SATURATED CORE COOLING 4 90/04/09 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 10 91/06/14 FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 2'0/04/09 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 2 90/04/09 FR-H.4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 1 90/04/09 FR-H.5 'RESPONSE TO STEAM GENERATOR LOW LEVEL 2 90/04/09 FR-I.1 RESPONSE TO HIGH PRESSURIZER
I' FUNCTIONAL RESTORATXON GUIDELILNES PROCEDURES INDEX ZSSUED: 03/28/92 EFFECTIVE TITLE REV DATE LEVEL 3 91/05/03 FR-X.2 RESPONSE TO LOW PRESSURIZER LEVEL 4 91/05/03 FR-I.3 RESPONSE TO VOIDS IN REACTOR VESSEL 5 91/05/03 FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITXON 6 91/05/03 FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITXON 2 90/04/09 CI FR-S.1 RESPONSE TO NUCLEAR POWER GENERATION/ATWS 4 90/04/09 FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN 2 90/04/09
,FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE 2 90/04/09 FR-Z 2
~ RESPONSE TO CONTAINMENT FLOODING 2 90/04/09
FUNCTIONAL RESTORATION GUIDELILNES PROCEDURES INDEX ISSUED: 03/28/92 EFFECTIVE PROCEDURE 'ITLE REV DATE FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 90/04/09
If EOP AP ATTAMBG~NT INDEX X<SURD: 03/28/92 EFFECTIVE TITLE REV DATE ATT AUX BLDG SW 0 90/04/09 ATT CI/CVI 1 90/04/09 ATT CNMT RECIRC FANS 1 90/04/30 ATT COND TO S/G 1 90/04/09 ATT DC LOADS 2 91/05/10 ATT D/G STOP 1 90/04/09 ATT EXCESS L/D 1 90/04/30 ATT FAULTED S/G 2 90/09/17 ATT GEN DEGAS 91/05/10 ATT LETDOWN 91/01/17
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EOP AP ATTA&969FI'NDEX ISSUED: 03/28/92 EFFECTIVE PROCED REV DATE ATT N2 PORVS 1 90/04/09 ATT NC 1 90/04/30 ATT NONVITAL" 1 90/04/09 ATT RCP START 1 90/04/09 ATT RCS ISOLATION 0 90/04/09 ATT RHR COOL 1 90/04/09 ATT RHR NPSH 0 91/05/10 ATT RHR SYSTEM 1 90/04/30 ATT RUPTURED S/G 3 91/09/05 k
ATT SAFW 2 91/10/11
0 EOP AP ATTACf969lT INDEX ISSUED: 03/28/92 EFFECTIVE PROCEDURE TITLE REV DATE ATT SD-1 2 90/06/27 ATT SD-2 2 90/06/27 ATT SEAL COOLING 1 90/04/09 ATT SFP-RWST 1 90/04/30 ATT SI FLUSH 2 91/09/05 ATT SI/UV 1 90/04/09 ATT VENT TIME 1 90/04/30 ATT NORMAL RHR COOLING 0 92/03/27
EMEEMENCY CONTINGENCY CTIO S PROCEDURES INDEX ISSUED: 01/08/92 EFFECTIVE PROCED REV DATE ECA-O.O LOSS OF ALL AC POWER 12 91/08/05 ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED 5 91/05/03 ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 90/04/09 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 6 91/05/03 ECA-1.2 LOCA OUTSIDE CONTAINMENT 2 90/04/09 ECA-2. 1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS 6 91/05/03
'CA-3
' SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED 7 91/05/03 ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED 9 91/05/03
4 EMERGENCY CONTINGENCY ACTIONS PROCEDURES INDEX ISSUED: 01/08/92 TITLE ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 6 91/05/03
~ f CRITICAL SAFETY FUNCTION STATUS TREES INDEX ISSUED: 01/08/92 EFFECTIVE TITLE REV DATE F-0. 1 SUBCRITICALITY CSFST 1 89/07/21 F-0.2 CORE COOLING CSFST 3 89/07/21 F-0.3 HEAT SINK CSFST 2 90/01/12 F-0.4 INTEGRITY CSFST 1 89/07/21 F-0.5 CONTAINMENT CSFST 2 90/01/12 F-0.6 INVENTORY CSFST 3 90/01/12
FUNCTIONAL RESTORATION GUIDELINES PROCEDURES INDEX IS~: 01/08/92 EFFECTIVE TITLE REV DATE FR-C.1 RESPONSE TO INADEQUATE CORE COOLING 6 90/04/09 FR-C.2 RESPONSE TO DEGRADED CORE COOLING 5 90/04/09 FR-C.3 RESPONSE TO SATURATED CORE COOLING 4 90/04/09 FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK 10 91/06/14 FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 2 90/04/09 FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 2 90/04/09 FR-H.4 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 1 90/04/09 FR-H.5 RESPONSE TO STEAM GENERATOR LOW LEVEL 2 90/04/09 FR-I' RESPONSE TO HIGH PRESSURIZER
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FUNCTIONAL RESTORATION GUIDELINES PROCEDURES INDEX ISSUED: 01/08/92 EFFECTIVE PROCEDURE TITLE REV DATE LEVEL 3 91/05/03 FR-I' RESPONSE TO LOW PRESSURIZER LEVEL 91/05/03 FR-I.3 RESPONSE TO VOIDS IN REACTOR VESSEL 5 91/05/03 FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 6 91/05/03 FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION 2 90/04/09 FR-ST 1 RESPONSE TO NUCLEAR POWER GENERATION/ATWS 4 90/04/09 FR-S.2 RESPONSE TO LOSS OF CORE SHUTDOWN 2 90/04/09 FR-Z.1 RESPONSE TO HIGH CONTAINMENT PRESSURE 2 90/04/09 FR-Z.2 RESPONSE TO CONTAINMENT FLOODING 2 90/04/09
FUNCTIONAL RESTORATION GUIDELINES PROCEDURES INDEX ISSUED: OX/08/92 EFFECTIVE PROCEDURE TITLE REV DATE FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 2 90/04/09
EOP AP ATTACE969iT EX ISSUED: Ol./08/92 EFFECTIVE PROCED TITLE REV DATE ATT AUX BLDG SW ~
0 90/04/09 ATT CI/CVI 1 90/04/09 ATT CNMT RECIRC FANS 1 90/04/30 ATT COND TO S/G 1 90/04/09 ATT DC LOADS 2 91/05/10 ATT D/G STOP 90/04/09 ATT EXCESS L/D 1 90/04/30 ATT FAULTED S/G 90/09/17 ATT GEN DEGAS 91/05/10 ATT LETDOWN 91/01/17
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EOP AP ATTAC596~NT INDEX ISSUED: 01/08/92 PROCEDURE TITLE REV DATE ATT N2 PORVS 1 90/04/09 ATT NC 1 90/04/30 ATT NONVITAL 1 90/04/09 ATT RCP START 1 90/04/09 ATT RCS ISOLATION 0 90/04/09 ATT RHR COOL 1 90/04/09 ATT RHR NPSH 0 91/05/10 ATT RHR SYSTEM 1 90/04/30 ATT RUPTURED S/G 3 91/09/05 ATT SAFW 2 91/10/11
EOP AP ATTACEDCENT INDEX ISSUED: 01/08/92 EFFECTIVE REV DATE ATT SD-1 2 90/06/27 ATT SD-2 2 90/06/27 ATT SEAL COOLING 1 90/04/09 ATT SFP-RWST 1 90/04/30 ATT SI FLUSH 2 91/09/05 ATT SI/UV 1 90/04/09 ATT VENT TIME 1 90/04/30
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EOP: TITLE: REV: 1 ATT EOP/AP ATTACHMENTS PAGE 1 of 2 ATTACHMENT SD-1 Supt. Date
'Perform the following local a I','hutdown:
tions to - piete normal secondary system o Close Reheater 4th pass temperature control valves:
o V-2432 (SW corner 1A MSR) o V-2433 (SW corner 1B MSR) o V-2434 (SW corner 2A MSR) o V-2435 (SW corner 2B MSR) o Close reheater steam chain valves:
o V-3550 o V-3551 o V-3552 o V-3553 o Open Reheater steamline vents (SW corner of condenser, middle floor) o V-8500 o V-8501 o,. V-8502 o V-8504 o V-8505 o Close flange heating isolation valves:
o MOV-3601A o MOV-3602A o Open the following valves to align for condensate feed system cooldown RECIRC:
o V-3982B (at N5 heater outlet header) o V-3983B (at N5 heater outlet header) o V-4363 (at g5 heater outlet header) o V-4365 (by MFW regulating valves) o V-4361 (southwest corner of condenser, middle floor) o V-3976A A MFP discharge valve bypass valve o V-3977 B MFP discharge valve bypass valve o Secure all 5 secondary chemical addition pumps on TURB BLDG middle floor by N5 heaters.
o Secure all 3 ammonia pumps, TUB BLDG basement by MCC A.
o Isolate SW from the following coolers:
o Main Feed Pump Oil Coolers:
o V-4703 o V-4704 o Exciter Air Cooler:
o V-4679 (chain valve next to condensate transfer pump) o Bus Duct Air Cooler o V-4674 o V-4674C (mini bypass around V-4674)
I REV: 1 ATT EOP/AP ATTACHMENTS PAGE 2 of 2 ATTACHMENT SD-1 (Cont'd) o Throttle SW as necessary from following coolers:
o Generator Seal Oil Unit Coolers (H2 side and air side):
o V-4676A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o V-4677A (mini bypass disch valve inside seal oil enclosure Bldg. NW corner) o Main Lube Oil Coolers (SW corner of Turb Oil Reservoir) o V-4691 o V-4692 o Notify Control Room when turbine shaft stops. Control Room person-nel will determine gear.
if adequate power available to start turning o Transfer house heating steam to house heating boiler if necessary (refer to T-35H, NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE).
o Perform T-14G, STEAM GENERATOR BLOWDOWN HEAT RECOVERY SYSTEM SHUTDOWN.
o Restore MAKEUP to CSTs as directed by Control Room.
e EOP:
REV 1 ATT EOP/AP ATTACHMENTS PAGE 1 of 1 ATTACHMENT LETDOWN Supt. Date The 'following .conditions must be met to place either normal or excess letdown in service:
o IA to CNMT ESTABLISHED o CCW IN SERVICE o PRZR level GREATER THAN 13:.
B) Establish Normal Letdown:
- l. Establish charging line flow to REGEN Hx GREATER THAN 20 gpm.
- 2. Place the following switches to CLOSE:
o Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202) o AOV-427, loop B cold leg to REGEN Hx
- 3. Place letdown controllers TCV-130 and PCV-135 in MANUAL at 254 open.
- 4. Verify AOV-371, letdown isolation valve OPEN.
S. Open loop B cold leg to REGEN Hx, AOV-427.
- 6. Open one 40 gpm letdown orifice valve (AOV-200A or AOV-200B) .
- 7. Place TCV-130 in AUTO at, 105'F.
- 8. Place PCV-135 in AUTO at 250 psig.
- 9. Adjust charging pump speed and HCV-142 as necessary.
C) IF normal letdown can NOT be established, THEN establish excess letdown:
- 1. Place AOV-312 to NORMAL.
- 2. Ensure CCW from excess letdown Hx, (AOV-745) OPEN
- 3. Open excess letdown isolation valve AOV-310.
- 4. Slowly open HCV-123 to maintain excess letdown temperature less than 195'F and pressure less than 100 psig.
- 5. Adjust charging pump speed as necessary.
EOP: TITLE:
REV: 1 ATT ATTACHMENTS PAGE 22 of 32 ATTACHMENT RUPTURED S G CONT CAUTION PART B OF THIS ATTACHMENT SHOULD ONLY BE PERFORMED IF RUPTURED S/G MSIV CANNOT BE CLOSED.
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PART B. Dispatch AO to locally perform the following when a ruptured S/G MSIV cannot be closed, if areas are accessible:
Close Air Ejector/Gland steam root valve, V-3540 (Main steam header TURB BLDG).
- 2) Close flange heating isolation valves, MOV-3601A and MOV-3602A.
- 3) Verify MSIV bypass valves shut.
- 4) Notify Control Room that main flowpaths are isolated, THEN complete isolation by closing the following valves:
o Support heating steam valves, V-3669 and V-3668, (INT BLDG steam header area) o Steam to sampling system valves, V-3413A and V-3412A, (INT BLDG steam header area) o Upstream traps isolation valves, V-3520 and V-3521, (TURB BLDG east of MFW regulating valves) o MFW regulating valve and bypass valve manual isolation valves for both S/Gs:
S/G A, V-3985 and V-3989 S/G B, V-3984 and V-3988 o Steam to trap header isolation valves o V-8513 (Main steam header TURB BLDG) o V-8529 (south side EH skid) o V-8510 (south side EH skid) o Steam dump header isolation and bypass valves (Main steam header TURB BLDG on platform overhead) o V-3532 and V-3658 o V-3533 and V-3659 o Reheat steam chain valves and reheat. steamline warmup valves (warmup vlvs located east end of 1A and 2A MSRs TURB BLDG middle floor) o 1A MSR, V-3551 and V-3645 o 1B MSR, V-3550 and V-3646 o 2A MSR, V-3553 and V-3647 o 2B MSR, V-3552 and V-3648
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