ML17309A490

Revised Eops,Including Rev 1 to Att,Rev 2 to Att,Rev 8 to AP-SW.1,Rev 6 to FR-S.1 & Rev 11 to FR-H.1.W/920626 Ltr

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 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000244 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/~i+g I/N/gE'ECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1 1.PD1-3 PD, 2 2 COPIES LTTR ENCL 1 1 a d nce with 10CFR2,2.109(9/19/72).

-05000244 INTERNAL: NRR/DLPQ/LHFB11 EXTERNAL: NRC PDR 1 1 1 1 1 1 OC/LFMB RES/DSIR/EIB NSIC 1 0 1 1 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 ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!pP TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9 t ZIIIIIIIZ ZZZZZIZ ZZZ ZI ZZIZZZZ ROCHESTER GAS AND ELECTRIC CORPORATION ROBERT C MECREDY Vice Prerldent Ginna Nudear Production 4 89 EAST AVENUE, ROCHESTER N.K 14649-0001 TELEPHONE AAEACOOE716 546 2700 June 26, 1992'.S.Nuclear Regulatory Commission Document Control Desk'ttn: Mr.Allen Johnson 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 emergency.

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la Y l v 1 ATT ATT ATT AP-SW.1 AP-TURB.1 FR-S.1 FR-H.1 Abnormal Procedures Index-issued 6/23 EOP/AP Attachment Index-6/23/92 EOP/AP Attachments

-Rev.1-5/1 3/92-SW Isolation EOP/AP Attachments

-SW Loads in CNMT EOP/AP Attachments

-Rev.2-5/1 4/92-Flow Through MFW Pump B Service Water Leak-Rev.8 Turbine Trip Without RX Trip Required, Rev.5 Response to Reactor Restart/ATWS

-Rev.6 Response to Loss of Secondary Heat Sink-Rev.11 5u-ZKSQ 6/2m~4~joey 9 r~~m-ye.0~@DP~e&~~'P~~~d~~S~~

P4 b/P4o/FM FM~F&l~SSS0 9 SOCEOVEES XSS ISSUED: 03/20/92 RROCED TITLE EFFECTIVE REV DATE AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 90/02/28 AP-CCW.2 V 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 l'

ABNORMAL PROCEDURES INDEX XSSDED: D3/2S/92 PRDCEDDRE TITLE EFFECTIVE 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

(,l~.l ABNORMAL PROCEDURES INDEX ISSUED: 03/28/92 PROCEDURE AP-RHR.1 T XTLE LOSS OF RHR EFFECTIVE REV DATE 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 PROCEDURE TITLE EFFECTIVE 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 g P~(I ENERGENCY CON'NGENCY ACTIONS PROCEDURES INDEX ISSUED: 03/28/92 TITLE EFFECTIVE 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 lJ EMERGENCY CONTINGENCY ACTIONS PROCEDURES INDEX ISSUED: 03/28/92 PROCEDVRE pZ~EFFECTIVE REV DATE ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 6 91/05/03

EQUIPMENT.

SUB-PROCEDURES INDEX ISSUED: 03/28/92 PROCED EFFECTIVE 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 PROCED EFFECTIVE REV DATE ES-3.3 I POST-SGTR COOLDOWN USING STEAM DUMP 5 91/05/03 (l

CRITICAL SAFETY FUNCTION STATUS TREES INDEX ISSUED: 03/28/92~TTLE EFFECTIVE 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 TITLE EFFECT?VE 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 TITLE LEVEL EFFECTIVE REV DATE 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 CI 2 90/04/09 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 PROCEDURE'ITLE EFFECTIVE 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 TITLE EFFECTIVE 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 I e EOP AP ATTA&969FI'NDEX ISSUED: 03/28/92 PROCED EFFECTIVE 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 k 3 91/09/05 ATT SAFW 2 91/10/11 0

EOP AP ATTACf969lT INDEX ISSUED: 03/28/92 PROCEDURE ATT TITLE SD-1 EFFECTIVE REV DATE 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 PROCED EFFECTIVE 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 TITLE EFFECTIVE 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 TITLE EFFECTIVE 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 4rI P FUNCTIONAL RESTORATION GUIDELINES PROCEDURES INDEX ISSUED: 01/08/92 PROCEDURE TITLE LEVEL EFFECTIVE REV DATE 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 PROCEDURE TITLE EFFECTIVE REV DATE FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 2 90/04/09

EOP AP ATTACE969iT EX ISSUED: Ol./08/92 PROCED TITLE EFFECTIVE 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

)

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 1~'l EOP: ATT TITLE: EOP/AP ATTACHMENTS REV: 1 PAGE 1 of 2 ATTACHMENT SD-1 Supt.Date'Perform the following local a tions to-piete normal secondary system I','hutdown:

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 ATT EOP/AP ATTACHMENTS REV: 1 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 if adequate power available to start turning gear.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: ATT EOP/AP ATTACHMENTS REV 1 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: ATT TITLE: ATTACHMENTS REV: 1 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.*******************************'k***************************************

PART B.2)3)4)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).Close flange heating isolation valves, MOV-3601A and MOV-3602A.

Verify MSIV bypass valves shut.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 l