ML17308A135

Forwards Revised Eops,Including Rev 12 to E-3, Steam Generator Tube Rupture & Rev 12 to ECA-0.0, Loss of All AC Power.

ML17308A135
Person / Time
Site:	Ginna
Issue date:	08/21/1991
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML17250B228	List: ML17250B227 ML17250B229 ML17308A135
References
NUDOCS 9108300185
Download: ML17308A135 (174)

Text

'CCELERATED DI TRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9108300185 DOC.DATE: 91/08/21 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECXP.NAME RECIPXENT AFFILIATION so/e/~l JOHNSON,A. Project Directorate I-3

SUBJECT:

Emergency operating procedures,Rev 12 to E-3 "Steam Generator Tube Rupture 6 Rev 12 to ECA-O.O "Loss of All AC Power." W/910821 ltr. D DISTRIBUTION CODE: A003D COPXES RECEIVED:LTR ENCL SIZE:

TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PDl-3 LA 1 1 PD1-3 PD 1 1 JOHNSON,A 2 2 D INTERNAL: ERR/+LPQ/LHFBl1 1 1 OC/LFMB 1 0 EG F 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 P72y59 o~7 R

D D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATLYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9

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~uzz/ //I//I///i ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY TELEPHONE Vice Prerldent ArtEA cooE 7 t B 546-2700 Ctnna Nudear Production August. 21, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen Johnson Project Directo ate 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 Enclosure xc: Mr. Robert Gallo, USNRC, Region 3:

Resident Inspector, Ginna Station 9108300185 910821 PDR ADOCK 05000244 F PDR

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E-3, Rev. 12 ECA-O.O, Rev. 12 Abnormal Procedures Index Emergency Procedures Index Emergency Contingency Actions Procedures Index Equipment Restoration Procedures Index Equipment Sub-Procedures Index Critical Safety Function Status Trees Index Functional Restoration Guidelines Procedures Index EOP/AP Attachments List

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Y ABNORMAL PROCED S I ISSUED 08/2 1/9 1 EFFECTIVE PROCED TITLE REV ~DA AP-CCW-1 LEAKAGE INTO THE COMPONENT COOLING LOOP 7 90/02/28 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 CONTROL ROOM INACCESSIBILITY 11 91/05/10 AP-CVCS.1 CVCS LEAK 5 89/12/19 AP-CVCS.2 IMMEDIATE BORATION 7 90/02/23 I

AP-CW.1 LOSS OF A CIRC WATER PUMP 4 90/02/23 AP-ELEC.1 LOSS OF g12A OR 12B TRANSFORMER 8 91/06/17 4

AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 5 90/02/23

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ABNORMAL PROCEDURES I ISSUED 08/21/91 PROCEDURE REV 'ATE AP-FW. 1 PARTIAL OR COMPLETE LOSS OF MAIN FEEDWATER 8 91/05/10 AP-IA.1 LOSS OF INSTRUMENT AIR 4 89/12/19 AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 4 90/02/23 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 6 90/02/23 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 PROCED ZSSUED: 08/21/91 EFFECTIVE PROCEDURE 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 3 90/04/20 AP-SW.1 SERVICE WATER LEAK 7 90/02/23 AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 4 90/02/23 AP-TURB.2 AUTOMATIC TURBINE RUNBACK 9 91/05/03 AP-TURB.3 TURBINE VIBRATIONS 5 90/02/23 AP-TURB.4 LOSS OF CONDENSER VACUUM 6 90/02/23

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EMERGENCY PROCEDURES 1 EZ ISSUED. 08/21/91 EFFECTIVE PROCED REV DATI$

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

GENCY CONTINGENCY ACTIONS ROCEDURES INDEX ISSUED: 08/21/91 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 6 90/04/09 ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 6 91/05/03 ECA-1.2 LOCA OUTSIDE CONTAINMENT 90/04/09 ECA-2 ' 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

• w GENCY CONTINGENCY ACTION OCEDURES INDEX ISSUED - 08/2 1/9 1 EFFECTZVE PROCED TXTLg REV DATl$

ECA-3.3 SGTR WITHOUT PRESSURIZER PRESSURE CONTROL 6 91/05/03

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RESTORATION PROC ISSUED- 08/21/91 EFFECTIVE TITLE REV DATg ER-AFW.1 ALTERNATE WATER SUPPLY TO THE AFW PUMPS 10 91/08/20 ER-BA.1 BAST TEMPERATURE CONCERNS LOSS OF ALL AC 2 91/06/17 ER-CVCS.1 REACTOR MAKEUP CONTROL, MALFUNCTION 1 91/06/17 ER-DG.1 RESTORING D/Gs 4 90/04/07 ER-DG.2 ALTERNATE COOLING FOR EMERGENCY D/Gs 5 91/01/17 ER-ELEC.1 RESTORATION OF OFFSITE POWER 6 91/07/23 ER-ELEC.2 RECOVERY FROM LOSS OF A OR B DC BUS 4 90/03/02 ER-ELEC.3 EMERGENCY OFFSITE BACKFEED VIA UNIT AUX TRANSFORMER 1 89/10/12 ER-ELEC.4 TSC D/G FEED TO BUSS 16 TO SUPPLY CHARGING PUMPS 2 89/09/28

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PMBlT RESTORATION PROCES S INDEX XSSUED 08/21/91.

PROCEDSRE TXTLE REV ~DAT ER-ELEC.5 SECURITY DIESEL FEED TO BUS 13 1 89/04/01 ER-ELEC.6 89/09/05 ER-ELEC.7 DELETED 89/09/05 ER-INST.1 REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENT LOOP FAILURE 8 91/07/03 ER-INST.2 LOSS OF ANNUNCIATOR 2 91/01/11 ER-NIS.1 SR MALFUNCTION 6 91/05/10 ER-NIS.2 IR MALFUNCTION 1 89/05/13 ER-NIS.3 PR MALFUNCTION 7 90/01/23 ER-PRZR.1 RESTORATION OF PRZR HEATERS DURING BLACKOUT 3 91/06/17

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PN19lT RESTORATION PR ISSUED: 08/21/91 PROCEDURE DATg ER-RCC.1 RETRIEVAL OF A DROPPED RCC 8 90/04/07 ER-RCC.2 RESTORING A MISALIGNED RCC 4 90/01/23 ER-RHR. 1 RCDT PUMP OPERATION FOR CORE COOLING 4 90/01/13 ER-RMS.1 LOCATING SOURCE OF HIGH ACTIVITY PLANT VENT. 2 91/07/23 ER-SFP.1 LOSS OF SPENT FUEL PIT COOLING 2 89/05/13 ER-SW.1 LOSS OF SW RETURN OUTSIDE AUX BUILDING 2 89/05/13

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E UIPMENT SUB-PROCEDURES NDEX ISSUED 08/21/91 PROCED REV DATE ES-O.O REDIAGNOSIS 7 90/04/09 ES-0.1 REACTOR TRIP RESPONSE 7 90/12/19 ES-0.2 NATURAL CIRCULATION COOLDOWN 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 12 91/05/10 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 4 91/05/03 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN 5 91/05/03

E UIPMENT SUB-PROCEDURE NDEX

~SSUED: 08/21/91 EFFECTIVE PROCED ~D ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 5 91/05/03

ISSUED: 08/21/91 PROCEDURE TITLE 'EV TICAL SAFETY FUNCT SUBCRITICALITY CSFST ON ST S TIMES INDEX 1

DATE 89/07/21 F-0 ' 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

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AL RESTORATXON GUXDELXNE XSSUED. 08/21/91 EFFECTXVE PRI.'RDURE gXTLE 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.1 RESPONSE TO HIGH PRESSURIZER

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AL RESTORATION GUIDEL ROCEDURBS XND ZEEDED: 08/21/91 PROCEDDRE TITIE LEVEL 3 91/05/03 FR-I.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 CONDITION 6 91/05/03 FR-P.2 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION 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

AL RESTORATION GUIDELINE ROCEDURES INDEX ISSUED: 08/2 1/9 1 PROCED REV DATE FR-2 ' RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL 2 90/04/09

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EOP AP ATTACHMENT ISSUED. 08/2 1/9 1 ZHE PROCEDURE TITLE REV DATAN 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 3 91/05/10 ATT LETDOWN 3 91/01/17

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EOP AP ATTACHN xssmm: os/21/91 PROCEDURE DATg 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 2 90/09/17 ATT SAFW 1 . 90/04/09

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gV, EOP AP ATTAINT E'SSUED: 08/21/91 EFFECTIVE PROCEDURE 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 1 90/04/30 ATT SI/UV 1 90/04/09 ATT VENT TIME 1 90/04/30

/~A~A 8'u;< vuu~ra Cme end TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 40 g/~/pg g~'g +0/P~

ROCHESTER GAS AND ELECTRIC CORPORAT N GINNA STATION ONTROLLED COPY NUMBER CHNICAL REV EW PORC REVIEW DA T SUPERIN N NT E FE IVE "'DATE CATEGO 1.0 REV EWED BY:

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EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 40 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-O, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or b~ I E 0 g REACTOR TRIP OR SAFETY NJECT ION g E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g E-2, FAULTED STEAM GENERATOR ISOLATION, and FR H 3g RESPONSE TO STEAM GENERATOR HIGH LEVEL/

when secondary radiation is abnormal, or

c. E-O, REACTOR TRIP OR SAFETY INJECTION, E 1g LOSS OF REACTOR OR SECONDARY COOLANT/

ES 1 '~ POST LOCA COOLDOWN AND DEPRESSURIZATIONg ECA 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 PRES SURI ZER PRESSURE CONTROL/

pressurizer pressure control is restored.

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e. E-1 seri'es FOLDOUT page whenever, either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.

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EOP: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).

o Personnel should be available for sampling during this procedure.

o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is

~ R/hr.

greater than 4 psig or CNMT radiation is greater than 10-1 Check Stopped:

If RCPs Should Be

a. RCP status - ANY RCP RUNNING a. Go to Step 2.

b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 2.

c. RCS pressure minus maximum S/G c. Go to Step 2.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs

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EOP:

REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 4 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Identify Ruptured S/G(s): Continue with Steps 5 through 10.

MHEN ruptured S/G(s) identified, o Unexpected increase in either THEN do Steps 3 and 4.

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 AO reports local indication of high steamline radiation

-OR-o HP reports high radiation from S/G activity sample

h EOP) TITLE:

REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

• • • • 4' ***********************************

CAUTION o IF THE TDAPW PUMP IS THE ONLY AVAILABLE SOURCE OF PEED FLOW, STEAM SUPPLY TO THE TDAPW PUMP MUST BE MAINTAINED PROM ONE S/G.

o AT LEAST ONE S/G MUST 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 I

b. Check ruptured S/G ARV - CLOSED b. WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed. IF NOT closed, THEN place controller in MANUAL and close S/G ARV.

IF S/G ARV can NOT be closed, THEN dispatch AO to locally isolate.

c. Close ruptured S/G TDAPW pump c. IF at least one MDAFW pump steam supply valve and place in running, THEN dispatch AO with PULL STOP locked valve key to locally isolate steam from ruptured S/G

~ S/G A, MOV-3505A to TDAPW pump.

~ S/G B, MOV-3504A

~ S/G A) V-3505

~ S/G B, V-3504

d. Verify ruptured S/G blowdown d. Place S/G blowdown and sample valve - CLOSED valve isolation switch to CLOSE.

~ S/G A, AOV-5738 IP blowdown can NOT be isolated

~ S/G B, AOV-5737 manually, THEN dispatch AO to locally isolate blowdown.

~ S/G A) V-5701

~ S/G B) V-5702 This Step continued on the next page.

0 EOP: T!TLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 3 continued from previous page)

e. Close ruptured S/G MSIV e. Perform the following:

1) Close intact S/G MSIV.

2) Place intact S/G ARV controller at 1005 psig in AUTO'.

3) Place condenser steam dump mode selector switch to MANUAL.

4) Ad)ust reheat steam supply controller cam to close reheat steam supply valves.

5) Ensure turbine stop valves-CLOSED. I

6) Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).

IF the ruptured S/G can NOT be isolated from the intact S/G, THEN go to ECA-3.1, SGTR VITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1

f. Dispatch AO to complete ruptured S/G isolation (Refer to appropriate sections of Attachment RUPTURED S/G)

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EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

4 Check Ruptured S/G Level:

a. Narrow range level - GREATER a. IF ruptured S/G NOT faulted, THAN 5% [25X adverse CNMT] THEN perform the following:

1) Maintain feed flow to ruptured S/G until level greater than 5X [25X adverse CNMT].

2) Continue with Step 5. WHEN ruptured S/G level greater than 5X [25X adverse CNMT],

THEN do Steps 4b through e.

b. Close MDAFW pump discharge valve b. Dispatch AO to locally close to ruptured S/G valve.

~ S/G A, MOV-4007

~ S/G B, MOV-4008

c. Pull stop MDAFW pump for ruptured S/G

d. Close TDAFW pump flow control d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve

~ S/G A, AOV-4297 to ruptured S/G.

~ S/G B, AOV-4298

~ S/G A, V-4005

~ S/G B, V-4006

e. Verify MDAFW pump crosstie e. Manually close valves.

valves - CLOSED

~ MOV-4000A

~ MOV-4000B

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EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

5 Check PRZR PORVs And Block Valves:

a. Power to PORV block valves- a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

~ MOV-515, MCC C position 6C ~

~ MOV-516, MCC D position 6C

b. PORVs - CLOSED 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 go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.

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EOP: TITLE REV: 11 E-3 STEAM GENERATOR TUBE. RUPTURE PAGE 9 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Is Intact:

If S/G Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

o Pressure in both S/Gs - GREATER ~ Steamlines THAN 100 PSIG ~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW

'FW PUMPS).

NOTE: TDAFW pump flow control valves fail open ll on loss of IA.

7 Check Intact S/G Level:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5X [25X adverse CNMT] than 200 gpm until narrow range level greater than 5X [25X adverse CNMT] in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in the narrow range level between 17X intact S/G continues to increase

[25X adverse CNMT] and 50X in an uncontrolled manner, THEN j go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

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EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, SELECTED SV PUMPS AND ONE CCW PUMP VILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

8 Reset SI 9 Reset CI:

a. Depress CI reset pushbutton

b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.

2) Depress CZ reset pushhutteu.

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EOP: TITLE REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE ll of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT] THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

10 Check Stopped:

If RHR Pumps Should Be

a. Check RCS pressure: a. Go to Step 11.

o Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]

o Pressure - STABLE OR INCREASING

b. Stop RHR pumps and place both in AUTO NOTE: If ruptured S/G needed for cooldovn, isolation is not necessary.

ll Verify Ruptured S/G Isolated:

a. Check ruptured MSIV - CLOSED a. IF neither S/G nor intact S/G MSIV can be closed, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

b. Ruptured S/G pressure - GREATER b. Go to ECA-3.1, SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

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EOP:

REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Ad)ust S/G ARV controllers to maintain intact S/G pressure in o Intact S/G MSIV - OPEN AUTO and go to Step 13.

o Annunciator G-15, STEAM DUMP LIT

b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO

c. Place steam dump mode selector svitch to MANUAL

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EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 13 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.

13 Initiate RCS Cooldown:

a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE ('F) 1100 PSIG 525 [505 adverse CNMT) 1000 PSIG 510 [490 adverse CNMT]

900 PSIG 500 [475 adverse CNMT]

800 PSIG 485 [460 adverse CNMT) 700 PSIG 465 [440 adverse CNMT]

600 PSIG 450 [420 adverse CNMT]

500 PSIG 425 [395 adverse CNMT]

400 PSIG 405 [370 adverse CNMT]

300 PSIG 375 [330 adverse CNMT]

b. Initiate dumping steam to b. Manually or locally initiate condenser from intact S/G at steam dump from intact S/G at maximum rate maximum rate using S/G ARV.

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR-o IF both S/Gs ruptured, THEN go to ECA-3.1, SGTR VITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1

c. Core exit T/Cs - LESS THAN c. Continue with Step 14. MHEN REQUIRED TEMPERATURE core exit T/Cs less than required, THEN do Step 13d.

d. Stop RCS cooldown and maintain RCS temperature

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EOP: TITLE:

REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 14 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify All AC Busses- Perform the following:

ENERGIZED BY OFFSITE POWER

a. IF any AC emergency bus normal o Normal feed breakers to all 480 feed breaker open, THEN ensure volt busses - CLOSED associated D/G breaker closed.

o 480 volt bus voltage - GREATER b. Perform the following as THAN 420 VOLTS necessary:

o Emergency D/G output breakers- 1) Close non-safeguards bus tie OPEN breakers:

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

2) Place the following pumps in' PULL STOP:

~ EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

3) Restore power to MCCs.

~ A from Bus 13

~ B from Bus 15

~ E from Bus 15

~ F from Bus 15

4) Start CNMT RECIRC fans as necessary.

5) 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).

~P p

EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 4O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Verify Adequate SW Flow:

a. Check't least two SW pumps- a. Manually start SW pumps as power RUNNING supply permits (258 kw each).

IP 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) Go to Step 17.

b. Dispatch AO. to establish normal shutdown alignment' (Refer to Attachment SD-1)

~ .

4

EOP REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 16 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR- ~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NCT, THEN evaluate ff CNMT RRCIRC fans should be stopped (Refer to Attachment CNMT RECIRC PANS).

b. Verify turbine building SV b. Manually align valves.

isolation valves - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify at least two air c. Manually start air compressors compressors - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

d. Check IA supply: d'. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.l, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING '2) Continue with Step 17. VHRN IA restored, THEN do Steps 16e and f.

e. Reset both trains of XY relays for IA to CNMT AOV-5392

f. Verify IA to CNMT AOV-5392 - OPEN

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EOP:

REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Charging Flow:

a. Charging pumps - ANY RUNNING a. Perform the following:

1) IR CCW flow is lost to any RCP thermal barrier OR any RCP fl seal outlet temperature offscale high, THEN dispatch AO with RWST area key to locally close seal injection needle valves to affected RCP.

~ V-300A for RCP A

~ V-300B for RCP B

2) Ensure HCV-142 demand at OX.

b. Align charging pump suction to b. IR LCV-112B'can NOT be opened, RWST: THEN perform the following:

o LCV-112B - OPEN 1) Verify charging pump A NOT running and place in PULL o LCV-112C - CLOSED STOP.

2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).

3) WHEN V-358 open, THEN 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

4s ft P~

EOP: T!TLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 18 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS COOLDOWN IN STEP 13 SHOULD BE COMPLETED BEFORE CONTINUING TO STEP 18.

18 Check Ruptured S/G Pressure IF pressure continues to decrease STABLE OR INCREASING to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

19 Check .RCS Subcooling Based On Go to ECA-3.1, SGTR WITH LOSS OR Core Exit T/Cs GREATER THAN REACTOR COOLANT - SUBCOOLED 20.'F USING FIGURE MIN RECOVERY DESIRED, Step 1 SUBCOOLING

d EOP: TI JLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 19 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SI ACCUMs may inject during RCS depressurization.

20 Depressurize RCS To Minimize Break Flow And Refill PRZR:

a. Check the following: a. Go to Step 21.

o Ruptured S/G level - LESS THAN 90X [85X 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%

[65X 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% [30X adverse CNMT]

c. Close normal PRZR spray valves: c. Stop RCPs.

1) Ad)ust normal spray valve controller to OP.'EMAND

2) Verify RCS pressure-INCREASING

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 23

TI EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 20 of 40 STEP ACTION/EXPECTED RESPONSE 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, spray flow may be increased by AOV-294 and normal'RZR spray valves.

closing normal charging valve o When using a PRZR PORV select one with an operable block valve.

21 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:

a. Verify IA to CNMT - AVAILABLE a. Refer to Attachment N2 PORVS to operate PORVs.

b. PRZR PORVs - AT LEAST ONE b. IF auxiliary spray available, AVAILABLE THEN return to Step 20b.

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.

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EOP:

REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 21 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 21 continued from previous page)

c. Open one PRZR PORV until ANY of the following conditions satisfied:

o PRZR level - GREATER THAN 75X

[65X adverse CNMT]

-OR-o RCS pressure - LESS THAN SATURATION USING FIGURE MIN SUBCOOLING

-OR-o BOTH of the following:')

RCS pressure - LESS THAN RUPTURED S/G PRESSURE

2) PRZR level - GREATER THAN 5X [30% adverse CNMT]

d. Close PRZR PORVs d. IF either PRZR PORV can NOT be closed, THEN close associated block valve.

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EOP:

REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 22 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check RCS Pressure Close block valve for the PRZR PORV INCREASING that was opened.

IP 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 OP REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

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EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 23 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OP THE RUPTURED S/G.

23 Check If Terminated:

SI Flow Should Be

a. RCS subcooling based on core a. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN O' ECA-3.1, SGTR WITH LOSS OP USING FIGURE MIN SUBCOOLING REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

b. Secondary heat sink: b. IP neither condition satisfied, THEN do NOT stop SI pumps. Go to o Total feed flow to S/G(s)- ECA-3.1, SGTR WITH LOSS OP GREATER THAN 200 GPM AVAILABLE REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5% [25X adverse CNMT]

c. RCS pressure - STABLE OR c. Do NOT stop SI pumps. Go to INCREASING ECA-3.1, SGTR WITH LOSS OP REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

d. PRZR level - GREATER THAN 5X d. Do NOT stop SI pumps. Return to

[30X adverse CNMT] Step 11.

24 Stop SI Pumps And Place In AUTO

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EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 24 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION ALIGNING SI PUMP SUCTION TO RWST BEFORE ISOLATING BAST MAY RESULT IN BACKFLOW FROM RWST TO BASTS.

25 Verify SI Pump Suction Aligned To RWST:

a. SI pump suction valves from a. Ensure at least one valve in BASTs - CLOSED each flow path closed.

~ MOV-826A ~ MOV-826A or MOV-826B

~ MOV-826B ~ MOV-826C or MOV-826D

~ MOV-826C

~ MOV-826D

b. SI pump suction valves from RWST b. Ensure at least one valve is

- OPEN open.

~ MOV-825A

~ MOV-825B

c. Consult TSC to determine if SI flush is required (Refer to Attachment SI FLUSH)

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EOP) TITLE:

REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Establish Required Charging Line Flow:

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a. Charging pumps - ANY RUNNING a. Perform the following:

1) IP CCW flow is lost to any RCP thermal barrier OR any RCP gl 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 27 Verify SI Flow Not Required:

a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary and go to ECA-3.1, USING FIGURE MIN SUBCOOLING SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

b. PRZR level - GREATER THAN 5% b. Manually operate SI pumps as

[30% adverse CNMT] necessary.

IP PRZR level can NOT be maintained, THEN go to ECA-3.1, SGTR WITH LOSS OP REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

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EOP: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 26 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check Stopped:

If CNMT Spray Should Be

a. CNMT spray pumps - ANY RUNNING a. Go to Step 29.

b. Verify CNMT pressure - LESS THAN b. Continue with Step 29.. VHRN 4 PSIG CNMT pressure less than 4 psig, THEN do Steps 28c through f.

c. Reset CNMT spray

d. Check NaOH tank outlet valves- d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

~ AOV-836A

~ AOV-836B

e. Stop CNMT spray pumps and place in AUTO

f. Close CNMT spray pump discharge valves

~ MOV-860A

~ MOV-860B

~ MOV-860C

~ MOV-860D

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EOP:

REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 27 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Check Isolated:

If SI ACCUMs Should Be

a. Check the following: a. Manually operate SI pumps as necessary and go to ECA-3.1, o RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit T/Cs - GREATER THAN O' COOLANT - SUBCOOLED RECOVERY USING FIGURE MIN SUBCOOLING DESIRED, Step 1.

o PRZR level - GREATER THAN 5X

[30X adverse CNMT]

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

~ MOV-841, MCC C position 12F

~ MOV-865, MCC D position 12C

c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:

~ MOV-841 1) Open vent valves for

~ MOV-865 unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.

d. Locally reopen breakers for MOV-841 and MOV-865

f

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EOP:

E-3 STEAM GENERATOR TUBE RUPTURE REV: ll PAGE 28 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Verify Adequate SW Flow To CCW Hx:

a. Verify at least three SW pumps- a. Manually start pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps can be

.operated, THEN go to Step 37.

b. Verify AUX BLDG SW isolation b. Establish SW to AUX BLDG (Refer valves - AT LEAST ONE SET OPEN to Attachment AUX BLDG SW).

~ MOV-4615 and MOV-4734

~ MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

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EOP:

REV: 11 E-3 STEAN GENERATOR TUBE RUPTURE-PAGE 29 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Normal Operation CVCS Can Be Established

a. Verify IA restored: a. Continue with Step 37- WHEN IA restored, THEN do Steps,31 o- IA to CNMT (AOV-5392) - OPEN through 36.

o IA pressure - GREATER THAN 60 PSIG

b. Verify instrument bus D- b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

c. CCV pumps - ANY RUNNING c. Perform the following:

1) IF any RCP $ 1 seal outlet temperature offscale high, THEN isolate CCV to thermal barrier of affected RCP(s).

~ RCP A, MOV-749A and MOV-759A

~ RCP B, MOV-749B and MOV-7598

2) Manually start one CCV pump.

d. Charging pump - ANY RUNNING d. Continue with Step 37. VHBN any charging pump running, THEN do Steps 32 through 36.

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EOP: REV 11 E-3 STEAN GENERATOR TUBE RUPTURE PAGE 30 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check If Seal Return Flow Should Be Established:

a. Verify RCP fl seal outlet 235'F

a. Go to Step 33.

temperature LESS THAN

b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.

~ AOV-270A

~ AOV-270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313

d. Open RCP seal return isolation d. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

e. Verify RCP gl seal leakoff flow e. IF any RCP seal leakoff flow

- LESS THAN 5.5 GPM greater than 5.5 gpm, THEN:

o Close the affected RCP seal discharge valve

~ RCP A, AOV-270A

~ RCP B, AOV-270B o Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.

f. Verify RCP gl seal'eakoff flow f. Refer to AP-RCP.1, RCP SEAL

- GREATER THAN 0.25 GPM MALFUNCTION.

33 Verify PRZR Level GREATER Continue with Step 35. WHEN PRZR THAN 13% [404 adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Step 34.

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EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 4O STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Establish Normal Letdown: IP RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdovn as follows:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Place the following svitches to valve, AOV-312, to NORMAL.

CLOSE:

o Ensure CCV from excess letdown

~ Letdown orifice valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) o Open excess letdown isolation

~ Letdown isolation valve AOV-371 valve AOV-310.

~ Loop B cold leg to REGEN Hx AOV-427 o Slovly open HCV-123 to maintain excess letdown temperature less

c. Place letdovn controllers in than 195'P and pressure less ~

MANUAL at 25X open than 100 psig.

~ TCV-130 o Adjust charging pump speed as

~ PCV-135 necessary.

d. Reset both trains of XY relays IP RCP seal return NOT established, for AOV-371 and AOV-427 THEN consult TSC to determine if excess letdown should be placed in

e. Open AOV-371 and AOV-427 service.

f. Open letdown orifice valves as necessary

g. Place TCV-130 in AUTO at 105'P

h. Place PCV-135 in AUTO at 250 psig

i. Adjust charging pump sp'eed and HCV-142 as necessary

f A

EOP: TlTLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check VCT Makeup System:

I

a. BAST levels - ANY GREATER THAN 5X a. Go to Step 36.

b. Check Annunciator B-23, BORIC b. Perform the following:

ACID TANK LO LO LEVEL-EXTINGUISHED 1) Adjust boric acid flow control valve to required flow from table.

BAST BORIC ACID LEVEL FLOW (GPM)

<10% 4.5 10-15X 6e7 15-20X 8.9

>20% 10.0

2) Go to Step 35d.

c. Ad)ust boric acid flow control valve in AUTO to 4.5 gpm

d. Verify the following: d. Adjust controls as necessary.

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

e. Check VCT level: e. Manually increase VCT makeup flow as follows:

o Level - GREATER THAN 20X

1) Ensure BA transfer pumps and

-OR- RMH pumps runntng. IF NOT, THEN reset MCC C and MCC D UF o Level - STABLE OR INCREASING lockouts as necessary.

2) Place RMW flow control valve HCV-ill in MANUAL and increase RMW flow.

3) Increase boric acid flow as necessary.

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EOP:

REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 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 37. WHEN VCT level greater than 40%,

THEN do Step 36b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED

44 a,l 1

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EOP: T!TLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 37 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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 llA or llB 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% [80%

adverse CNMT].

o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.

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

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EOP: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

43 Check If Source Detectors Should Range Be Energized:

a. Source range channels- a. Go to Step 43e.

DEENERGIZED 5

b. Check intermediate range flux- b. Perform the following:

EITHER CHANNEL LESS THAN 1O xo AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 44. WHEN flux is LESS'HAN 10-'mps on any operable channel, THEN do Steps 43c through e.

c. Check the following: c. Continue with Step 44. WHEN either condition met, THEN do o Both intermediate range Steps 43d and e.

channels - LESS THAN 10-'MPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source, range detectors- d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

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EOP: T!TLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 39 of 40 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b. Perform the following:

o Open generator disconnects

~ 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) Check IA to CNMT - AVAILABLE 1) Go to Step 45.

2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)

3) Verify one Rx compartment 3) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD COMPLETE

EOP: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 40 of 40 STEP ACTION/EXPECTED RESPONSE 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 1

-OR-o Go to ES-3.3, POST-SGTR COOLDOVN USING STEAM DUMP, Step 1

-END-

7 lt

T!TLE REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING

3) ATTACHMENT CNMT RECIRC FANS

4) ATTACHMENT D/G STOP

5) ATTACHMENT N2 PORVS

6) ATTACHMENT NC

7) ATTACHMENT SEAL COOLING

8) ATTACHMENT RCP START ATTACHMENT RUPTURED S/G 2' 9)

10) ATTACHMENT SD-1

11) ATTACHMENT SD-2

12) ATTACHMENT AUX BLDG SW

13) ATTACHMENT SI FLUSH

14) FOLDOUT

EOP: TITLE: REV 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY Nuclear power greater than 54

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 434 [46%

adverse CNMT]

c ~ HEAT SINK Narrow range level in all S/Gs less than 54

[254 adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F

e. CONTAINMENT CNMT pressure greater than 60 psig

4 k

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EOP: TITLE: REV: 11 E-3 STEAM GENERATOR,TUBE RUPTURE PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200

'1100

-1000 900 800 INADEQUATE 700 SUBCOOLING 600 DVERS REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS,10'F 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

C 4,

A

EOP: TITLE: REV: 11 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate 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 O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54

[304 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 ~ COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

4 ~ AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

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EOP:

REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 1 of 22 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE MI I T SUPERINTEND N FFE IVE DATE CATEGORY 1.0 REVIEWED BY:

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EOP: 11 REV ECA-O.O LOSS OF ALL AC POWER PAGE 2 of 22 A. PURPOSE This procedure provides actions to respond to a loss of all AC power.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure may be entered directly or from:

a. E-O, REACTOR TRIP OR SAFETY INJECTION, on the indication that neither train of AC emergency busses is energized.

2. SYMPTOMS Which indicate a loss of all AC power are:

a. Neither train of 480 volt AC emergency busses available.

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EOP:

ECA-O.O LOSS OF ALL AC POWER REV ll PAGE 3 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Steps 1 through 4 are IMMEDIATE ACTION steps.

o CSFSTs should be monitored for information only. FR procedures should not be implemented.

o Local actions may require portable lighting and communication devices.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10 ~ R/hr.

O 1 Verify Reactor Trip:

o At least one train of reactor Manually trip reactor.

trip breakers - OPEN o Neutron flux - DECREASING o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM

'Manually close MSIVs.

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EOP: TITLE: REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 4 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED O 3 Check If RCS Is Isolated:

a. PRZR PORVs - CLOSED a. IR PRZR pressure less than 2335 psig, THEN manually close PORVs.

b. Verify RCS isolation valves closed:

1) Place letdown orifice valve switches to CLOSE

~ AOV-200A

~ AOV-200B

~ AOV-202

2) Place letdown isolation valve switches to CLOSE

~ AOV-371

~ AOV-427

3) Place excess letdown isolation valve switch to CLOSE (AOV-310) h

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EOP:

REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 5 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify Adequate TDAFW Flow:

a. Verify TDAPW pump - RUNNING a. Perform the following:

1) Verify governor valve, V-3652, latched.

IF governor valve tripped, THEN dispatch AO to locally reset valve.

2) Manually or locally open TDAFW pump steam supply valves.

~ MOV-3505A

~ MOV-3504A

b. Verify TDAFW pump flow - GREATER b. Verify proper TDAPW valve THAN 200 GPM alignment:

1) TDAFW pump discharge valve (MOV-3996) open.

2) Intact S/G TDAFW pump flow control valves open.

Iy NOT, THEN manually align valves as necessary.

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ECA-O.O LOSS OP ALL AC POWER REV: ll PAGE 6 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o AO should increase surveillance of TDAFW pump until AC power is restored.

5 Try To Restore Power to Any Train Of AC Emergency Busses:

a. Verify emergency D/G aligned for a. Manually align switches on rear unit operation of MCB.

o Mode switch in UNIT o Voltage control selector in AUTO

b. Reset and start available b. Dispatch AO to locally start emergency D/Gs - ANY D/G RUNNING emergency D/Gs.

IF no emergency D/G available, THEN perform the following:

1) Direct AO to attempt to restore emergency D/G (Refer to ER-D/G.l, RESTORING D/G)

2) Go to Step 6.

c. Verify at least one SW pump c. Manually start pumps. IF running for each running D/G adequate cooling can NOT be supplied to a running D/G, THEN trip affected D/G.

d. Verify at least one train of AC d. Manually energize AC emergency emergency busses - ENERGIZED busses.

~ Bus 14 and Bus 18 IF at least one train of AC

~ Bus 16 and Bus 17 emergency busses can NOT be energized, THEN go to Step 6.

e. Return to procedure and step in effect

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EOP: TITLE: REV: 11 ECA-0. 0 LOSS OF ALL AC POWER PAGE 7 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o WHEN POWER IS RESTORED TO ANY TRAIN OF AC EMERGENCY BUSSES, RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 24.

o IF AN SI SIGNAL EXISTS OR IF AN SI SIGNAL IS ACTUATED DURING THIS PROCEDURE, IT SHOULD BE RESET TO PERMIT MANUAL LOADING OF EQUIPMENT ON AN AC EMERGENCY BUS.

6 Establish The Following Equipment Alignment:

a. Pull stop AC emergency bus loads

~ RHR pumps

~ CNMT RECIRC fans

~ CNMT spray pumps

~ SI pumps

~ CCW pumps

~ Charging pumps

~ MDAFW pumps

b. Evaluate non-vital loads (Refer to Attachment NON-VITAL)

c. Place SW pump switches to STOP, then return to AUTO

d. Place switches for SI pump suction from BAST to CLOSE

~ MOV-826A

~ MOV-826B

~ MOV-826C

~ MOV-826D

e. Place switch for MOV-313, RCP seal return isolation valve, to CLOSE

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EOP: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 8 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Try To Restore Offsite Power:

a. Consult Power Control to a. IF normal offsite power supply determine if either normal NOT readily available, THEN offsite power supply - AVAILABLE perform the following:

o 12B transformer via breaker 1) Evaluate the following 76702 temporary power supplies and direct personnel to perform

-OR- desired procedures:

o 12A transformer via breaker o Security D/G to power an 75112 IA compressor (Refer to ER-ELEC.5, SECURITY DIESEL FEED TO BUS 13).

o TSC D/G to power a charging pump (Refer to ER-ELEC.4, TSC D/G FEED TO BUS 16 TO'SUPPLY CHARGING PUMP).

o Main transformer backfeed for long term concerns (Refer to ER-ELEC.3, EMERGENCY OFFSITE BACKFEED VIA UNIT AUX TRANSFORMER).

2) Go,to Step 8.

b. Reset SI, if necessary

c. Restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER)"

8 Dispatch AO To Locally Isolate RCP Seals And BASTs (Refer to ATTACHMENT RCS ISOLATION)

t EOP:

ECA-O.O LOSS OF ALL AC POWER REV: ll PAGE 9 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Isolate Makeup And Reject IF valves can NOT be manually From Hotwell To CST By closed, THEN dispatch AO to locally Placing Hotwell Level isolate makeup and reject lines as Controller (LC-107) In Manual necessary.

AT 50~o

~ Makeup isolation V-4058

~ Reject isolation V-4055 10 Check S/G Status: Manually close valves.

a. MFW flow control valves - CLOSED IF valves can NOT be manually closed, THEN dispatch AO to locally

~ MFW regulating valves isolate the affected, flow path.

~ MFW bypass valves

b. S/G blowdown and sample valves-CLOSED

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EOP: TITLE: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 10 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION A PAULTED OR RUPTURED S/G THAT IS ISOLATED SHOULD REMAIN ISOLATED. STEAM SUPPLY TO THE TDAPW PUMP MUST BE MAINTAINED PROM AT LEAST ONE S/G.

ll Check If S/G Is Intact:

Secondary Side Perform the following:

a. IP any S/G pressure decreasing o Pressure in both S/Gs - STABLE in an uncontrolled manner OR OR INCREASING completely depressurized, THEN isolate faulted S/G unless o Pressure in both S/Gs - GREATER needed for RCS cooldown:

THAN 100 PSIG

1) Close faulted S/G MDAPW pump discharge valve.

~ S/G A, MOV-4007

~ S/G B, MOV-4008

2) Close faulted S/G TDAPW flow control valve.

~ S/G A, AOV-4297

~ S/G B, AOV-4298

3) Verify faulted S/G ARV controller in MANUAL with output at OX.

~ S/G A, AOV-3411

~ S/G B, AOV-3410

4) Pull stop faulted S/G TDAPW pump steam= supply valve.

~ S/G A, MOV-3505A

~ S/G B, MOV-3504A IP valves can NOT be closed manually, THEN~ispatch AO to locally close valves, as necessary, to isolate flow.

b'. Dispatch AO to complete faulted S/G isolation (Refer to Attachment PAULTED S/G).

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EOP: TITLE:

REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE ll of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If S/G Tubes Are Intact: Try to identify ruptured S/G.

Continue with, Step 13. VHEN o Steamline radiation monitors ruptured S/G identified, THEN (R-31 and R-32) - NORMAL perform the following:

o S/G blowdown liquid monitor a. Isolate ruptured S/G unless (R-19) - NORMAL needed for RCS cooldown:

o Dispatch HP technician to 1) Close ruptured S/G MDAFW pump locally check steamline discharge valve.

radiation - NORMAL

~ S/G A, MOV-4007

~ S/G B, MOV-4008

2) Pull stop ruptured S/G MDAFV pump.

3) Close ruptured S/G TDAFV flow control valve.

~ S/G A, AOV-4297

~ S/G B, AOV-4298

4) WHEN S/G pressure less than 1050 psig, THEN verify ruptured S/G ARV closed.

~ S/G A, AOV-3411

~ S/G B, AOV-3410

'5) Pull stop ruptured S/G TDAFV pump steam supply valve.

~ S/G A, MOV-3505A

~ S/G B, MOV-3504A IF valves can NOT be closed manually, THEN dispatch AO to locally close valves, as necessary, to isolate flow.

b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G).

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EOP: TlTLE:g REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 12 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: TDAFW pump flow control valves fail open on loss of IA.

13 Check Intact S/G Levels:

a. Narrow range level - GREATER a. Maintain maximum AFW flow until THAN 5% [25X adverse CNMT] narrow range level greater than 5X [25X adverse CNMT] in at least one S/G.

b. Dispatch AO to locally control b. IF valves can NOT be throttled, AFW flow by throttling TDAFW THEN control AFW flow by flow control valves starting and stopping TDAFW pump.

~ S/G A, AOV-4297

~ S/G B, AOV-4298

c. Control AFW flow to maintain c. IF narrow range level in any narrow range level between 17% intact S/G continues to increase

[25X adverse CNMT] and 50X in an uncontrolled manner, THEN return to Step 12.

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EOP: TITLE: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 13 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Degassing of main generator should commence as soon as possible to allow the air side seal oil backup pump to be stopped within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

14 Check DC Bus Loads:

a. Pull stop all large non-essential DC loads o MFW pump DC oil pumps o WHEN turbine is stopped, THEN stop turbine DC lube oil pump (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) o Evaluate other DC loads (Refer to Attachment DC LOADS)

b. Perform the following:

1) Dispatch AO to locally degas main generator (Refer to Attachment GEN DEGAS)

2) WHEN generator has been degassed, THEN stop air side seal oil backup pump (within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

c. Check DC bus voltage - GREATER c. IF either DC bus less than THAN 105 VOLTS DC 105 volts DC, THEN refer to ER-ELEC.2, RECOVERY FROM LOSS OF

~ Bus A A or B DC BUS.

~ Bus B

d. Direct electricians to locally monitor DC power supply

e. Dispatch personnel with DC panel key to deenergize CNMT emergency lights (DC panel turbine building basement west, switch g2)

t$ f EOP: 717LE: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 14 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION WHEN POWER IS RESTORED TO ANY TRAIN OF AC EMERGENCY BUSSES, RECOVERY ACTIONS SHOULD CONTINUE STARTING WITH STEP 24.

15 Check CST Level GREATER Switch to alternate AFW pump THAN 5 FEET suction supply. (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

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EOP: TITLE: REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 15 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o S/G PRESSURES SHOULD BE MAINTAINED GREATER THAN 200 PSIG TO PREVENT INJECTION OF SI ACCUM NITROGEN INTO THE RCS.

o S/G NARROW RANGE LEVEL SHOULD BE MAINTAINED GREATER THAN 5X [25X ADVERSE CNMT] IN AT LEAST ONE INTACT S/G. IF LEVEL CANNOT BE MAINTAINED, S/G DEPRESSURIZATION SHOULD BE STOPPED UNTIL LEVEL IS RESTORED IN AT LEAST ONE S/G.

NOTE: o The S/Gs should be depressurized at maximum rate to minimize RCS inventory loss.

o PRZR level may be lost and reactor vessel upper head voiding may occur due to depressurization of S/Gs. Depressurization should not be stopped to prevent these occurrences.

o S/G ARV nitrogen pressure should be monitored and nitrogen supply bottles changed as necessary.

16 Initiate Depressurization Of Intact S/Gs To 300 PSIG:

a. Check S/G narrow range levels- a. Perform the following:

GREATER THAN 17X [25% adverse CNMT] IN AT LEAST ONE S/G 1) Maintain maximum AFW flow until narrow range level greater than 17X [25X adverse CNMT] in at least one S/G.

2) Continue with Step 17. WHEN narrow range level greater than 17X [25X adverse CNMT]

in at least one'/G, THEN do Steps 16b and 17.

b. Manually dump steam from intact b. Locally dump steam from intact S/Gs at maximum rate using S/G S/Gs at maximum rate using S/G ARVs ARV.

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EOP: TITLE: REV'1 ECA-O.O LOSS OF ALL AC POWER PAGE 16 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

17 Check Reactor Subcritical:

a. Verify source range detector a. Dispatch personnel with relay N ENERGIZED rack key to turn off 120 VDC power switches in REACTOR PROTECTION racks RLTR-1 and RLTR-2 to deenergize source range block relays.

b. Monitor Reactor power: b. Control S/G ARVs to stop S/G depressurization and allow RCS o Intermediate range, N to heat up.

'TABLE OR DECREASING o Source range, N STABLE OR DECREASING NOTE: Depressurization of S/Gs will result in a SI actuation. SI should be reset to permit manual loading of equipment on emergency busses.

18 Check SI Signal Status:

a. Any SI annunciator - LIT a. Go to Step 22.

VHEN SI actuated, THEN do Steps 18b, 19, 20 and 21.

b. Reset SI

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EOP: TITLE: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 17 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Verify CI And CVI:

a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.

~ Annunciator A-26, CNMT ISOLATION

~ Annunciator A-25, CONTAINMENT VENTILATION ISOLATION

b. Verify CI and CVI valve status b. Manually close CI and CVI lights - BRIGHT valves. IF valves can NOT be closed, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI).

c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights- valves.

BRIGHT

~ AOV-4561

~ AOV-4562 20 Check If S/G Depressurization Should Be Stopped:

a. Check RCS cold leg temperatures a. Perform the following:

- GREATER THAN 315'F

1) Control S/G ARVs to stop S/G depressurization.

2) Go to Step 21.

b. Check S/G pressures - LESS THAN b. Continue with Step 21. WHEN S/G 300 PSIG pressure decreases to less than 300 psig, THEN do Step 20c.

c. Manually control S/G ARVs to c. Locally control S/G ARVs to maintain S/G pressures at maintain S/G pressures at 300 psig 300 psig.

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EOPE TITLE: REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 18 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check CNMT Pressure HAS IF CNMT pressure is less than 28 REMAINED LESS THAN 28 PSIG psig,THEN perform the following:

o Annunciator A-27, CNMT SPRAY- a. Reset CNMT spray.

EXTINGUISHED

b. Place CNMT spray pump discharge o CNMT pressure indicators - LESS valve switches to CLOSE to THAN 28 PSIG deenergize open contactor.

IF NOT, THEN continue with step 22.

WHEN CENT pressure less than 28 psig, THEN place CNMT spray pump discharge valve switches to CLOSE.

22 Check'NMT Radiation LESS Dispatch AO to locally close THAN 100 R/HR following valves, as necessary:

~ MDAFW pump discharge valves

~ MOU-813 and MOU-8142 CCW to and from CNMT

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EOP: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 19 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check Is If AC Emergency Power Restored AT LEAST ONE Continue to control and RCS monitor plant status:

conditions TRAIN OF AC EMERGENCY BUSSES ENERGIZED a. Check status of desired actions:

~ Bus 14 and Bus 18 o AC power restoration

~ Bus 16 and Bus 17 o ARV nitrogen pressure o RCP seal isolation o DC power supply

b. Dispatch AO to locally check BAST temperature.

IF temperature less than 155'F, THEN dispatch personnel to dilute BASTs (Refer to ER-BA.1, BAST TEMPERATURE CONCERN - LOSS OF ALL AC).

c. Return to Step 11.

24 Manually Control S/G ARVs To Locally control S/G ARVs.

Stabilize S/G Pressures

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EOP:

REV: 11 ECA-O.O LOSS'OF ALL AC POWER PAGE 20 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SW isolation may occur when power is restored to AC emergency busses.

25 Verify SW System Operation:

a. Check normal power available to a. IF both D/Gs operating, THEN SW pumps ensure one SW pump running for each D/G.

o Bus 17 normal feed breaker-CLOSED IF only one D/G operating, THEN perform the following:

-OR-

1) Ensure at least one SW pump o Bus 18 normal feed breaker- running.

CLOSED

2) Manually perform SW isolation.

3) Go to Step 26.

b. Verify two SW pumps - RUNNING b. IF normal power available, THEN manually start SW pumps as necessary.

IF adequate cooling can NOT be supplied to a running D/G, THEN trip affected D/G and refer to ER-D/G.1.

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EOP: TITLE: REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 21 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION THE LOADS PLACED ON THE ENERGIZED AC EMERGENCY BUS SHOULD NOT EXCEED THE CAPACITY OF THE POWER SOURCE.

26 Verify Following Equipment Manually load equipment as power Loaded On Available AC supply permits.

Emergency Busses:

o 480 volt MCCs - ENERGIZED

~ MCC C from Bus 14

~ MCC D from Bus 16 o Verify instrument busses-ENERGIZED

~ Bus A from MCC C (A battery)

~ Bus B from MCC C

~ Bus C from MCC D (B battery) o Dispatch personnel to verify proper operation of battery chargers

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EOP: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 22 of 22 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Select Recovery Procedure:

a. Check RCS subcooling based on a. Go to ECA-0.2, LOSS OF ALL AC core exit T/Cs - GREATER THAN POWER RECOVERY WITH SI REQUIRED, O'F USING FIGURE MIN SUBCOOLING Step 1.

b. Check PRZR level - GREATER THAN b. Go to ECA-0.2, LOSS OF ALL AC

'5% [30% adverse CNMT] POWER RECOVERY WITH SI REQUIRED, Step 1'.

c. Check SI annunciators- c. IF SI signal is present and vas EXTINGUISHED NOT previously reset, THEN go to ECA-0.2, LOSS OF ALL AC POWER

~ D-19, PRESSURIZER LO PRESS RECOVERY WITH SI REQUIRED, 1750 PSIG Step l.

~ D-21, STEAM LINE LOOP A LO LO PRESS 514 PSIG

~ D-22, STEAM LINE LOOP B LO LO PRESS 514 PSIG

~ D-28, CONTAINMENT PRESSURE 4 PSIG

d. Go to ECA-0.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, Step 1

-END-

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EOP: REV: 11 ECA-O.O LOSS OF ALL AC POWER PAGE 1 of 1 ECA-O.O APPENDIX LIST TITLE PAGES

1) FIGURE MIN SUBCOOLING

2) ATTACHMENT DC LOADS

3) ATTACHMENT FAULTED S/G

4) ATTACHMENT RUPTURED S/G

5) ATTACHMENT CI/CVI

6) ATTACHMENT NONVITAL

7) ATTACHMENT GEN DEGAS

8) ATTACHMENT RCS ISOLATION

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EOP TITLE: REV 11 ECA-O.O LOSS OF ALL AC POWER PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING

-=600 REGION ADVERSE CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

C A,