ML041400109

R. E. Ginna - Emergency Operating Procedures

ML041400109
Person / Time
Site:	Ginna
Issue date:	04/29/2004
From:	Widay J Rochester Gas & Electric Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NPSP0200
Download: ML041400109 (53)

Text

Joseph A. Widay RAWe Always at Your Service Vice President and Plant Manager April 29, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.

- Very truly yours, p A' d

--lseph A. WidayC)

JAW/jdw xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

ATT Index E Index AlT-16.0, Rev 12 E-3, Rev 37 An equal opportunity employer AOOR2 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com An Energy East Company

0 NPSP0200 Ginna Nuclear Power Plant Thu 4/29/2004 9:34:12 am WRIGHTJ PROCEDURE INDEX Page 1 of 2 INPUT PARAMETERS: IYPE: PRATT STATUS VALUE(S): EF, QU 5YEARS ONLY:

PRATT EOFI ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 003 0211212003 02V12/2003 02/12V2008 E:

ATT-1.1 ATTACHMENT NORMAL CCW FLOW 000 05/18/2000 05118/2000 05/18/2005 E:

ATT-2.1 ATTACHMENT MIN SW 005 02/01/2001 02103/2003 02V03/2008 E:

ATT-2.2 ATTACHMENT SW ISOLATION 008 03/06/2002 03/27/2003 03/27/2008 E:

ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03/06/2002 04/06/2004 04/06/2009 ATT-2.4 ATTACHMENT NO SW PUMPS 002 05/30/2003 10/31/2001 10/31/2006 E:

ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/26/2002 06/26/2002 06/26/2007 E:

ATT-3.0 ATTACHMENT CVCVI 007 0217/2004 0217/2004 02V17/2009 E:

ATT-3.1 ATTACHMENT CNMT CLOSURE 005 02117/2004 02117/2004 02/17/2009 E:

ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 07/26/1994 03/27/2003 03/27/2008 E:

ATT-5.0 ATTACHMENT COND TO S/G 006 10/10/2003 04/06/2004 04/06/2009 E:

ATT.5.1 ATTACHMENT SAFW 008 05/30/2002 04/06/2004 04/06/2009 ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 01/14/1999 01/28/2004 01/28/2009 E:

ATT-6.0 ATTACHMENT COND VACUUM 003 12/18/1996 02103/2003 02103/2008 E:

ATT-7.0 ATTACHMENT CR EVAC 006 03/06/2002 02/03/2003 02103/2008 E:

ATT-8.0 ATTACHMENT DC LOADS 007 02104/2004 02/04/2004 02104/2009 E:

ATT-8.1 ATTACHMENT D/G STOP 005 03/06/2002 02/03/2003 02/03/2008 E:

ATT-8.2 ATTACHMENT GEN DEGAS 008 06/20/2002 08/17/1999 08/17/2004 E:

ATT-8.3 ATTACHMENT NONVITAL 004 03/06/2002 02/03/2003 02/03/2008 E:

ATT-8.4 ATTACHMENT SVUV 005 03/06/2002 02103/2003 02103/2008 6:

ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 001 08/26/2003 05/0212002 05/02/2007 E:

ATT-9.0 ATTACHMENT LETDOWN 009 01/07/2004 03/06/2002 03/06/2007 E:

ATT-9.1 ATTACHMENT EXCESS L/D 005 03/06/2002 10/31/2001 10/31/2006 E:

ATT-10.0 ATTACHMENT FAULTED SIG 006 03/06/2002 03/27/2003 03/27/2008 E:

ATT-11.0 ATTACHMENT IA CONCERNS 003 06/26/2003 03/27/2003 03/27/2008 E:

ATT-11.1 ATTACHMENT IA SUPPLY 003 03/06/2002 03/27/2003 03/27/2008 E:

ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/2002 03/10/2003 03/10/2008 E:

ATT-12.0 ATTACHMENT N2 PORVS 005 02/12/2003 02/12/2003 02/12/2008 ATT-13.0 ATTACHMENT NC 003 021212003 02/12V2003 02/12/2008 ATT-14.0 ATTACHMENT NORMAL RHR COOLING 003 03/06/2002 04/06/2004 04/06/2009

NPSPLO2 Ginna Nuclear Power Plant Thu 4/29/2004 9:34:12 am WRIGHTJ PROCEDURE INDEX Page 2 of 2 INPUT PARAMETERS: TYPE: PRATT STATUS VALUE(S): EF. QU 5 YEARS ONLY:

PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-14.1 ATTACHMENT RHR COOL 006 04/3012003 01/08/2002 01/08/2007 EF ATT-14.2 ATTACHMENT RHR ISOL 003 02V12V2003 02/1122003 02V12V2008 EF ATT-14.3 ATTACHMENT RHR NPSH 003 03106/2002 01/28/2004 01/2812009 EF ATT-14,5 ATTACHMENT RHR SYSTEM 003 03120/2003 02V0312003 02103/2008 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/28/2004 01/2812009 EF ATT-14.7 ATTACHMENT ADJUST RHR FLOW 000 02117/2004 0217/2004 02V17/2009 EF ATT-15.0 ATTACHMENT RCP START 009 03/06/2002 03/17/2000 03/17/2005 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 02103/2003 02103/2008 EF ATT-15.2 ATTACHMENT SEAL COOUNG 005 03/0612002 02103/2003 0210312008 EF ATT-16.0 ATTACHMENT RUPTURED S/G 012 04/2912004 01/11/2000 01/11/2005 EF ATT-16.1 ATTACHMENT SGTL 002 03/06/2002 09108/2000 09/0812005 EF ATT-1 6.2 ATTACHMENT RCS BORON FOR SGTL 003 11/26/2003 09/08/2000 09108/2005 EF ATT-17.0 ATTACHMENT SD-1 016 10/10/2003 02/29/2000 02/2812005 EF ATT-17.1 ATTACHMENT SD-2 006 03/06/2002 01/30/2001 01/3012006 EF ATT-18.0 ATTACHMENT SFP - RWST 005 03/06/2002 0210312003 02103/2008 EF ATT-20.0 ATTACHMENTVENTTIME 003 07/26)1994 02103/2003 02103/2008 EF ATT-21.0 ATTACHMENT RCS ISOLATION 002 03106/2002 02V0312003 02V03/2008 EF ATT-22.0 ATTACHMENT RESTORING FEED FLOW 003 05/0212002 01/22/2002 011222007 EF ATT-23.0 ATTACHMENTTRANSFER 4160V LOADS 000 02/26/1999 01/28/2004 01/28/2009 EF ATT-24.0 ATTACHMENT TRANSFER BATTERY TO TSC 000 09/08/2000 09108/2000 09108/2005 EF ATT-26.0 ATTACHMENT RETURN TO NORMAL OPERATIONS 000 10131/2001 10/31/2001 10/31/2006 EF PRATT TOTAL: 51 GRAND TOTAL: 51

C. ( (

NPSP0200 Ginna Nuclear Power Plant Thu 4/29/2004 9:34:36 am WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: PRE STATUS VALUE(S): EF. QU 5 YEARS ONLY:

P E e ERNR  :. PROCEDURE k , -

PROCEDURE EFFECT LAST. NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST E-0 REACTOR TRIP OR SAFETY INJECTION 036 02/17/2004 03/24/2003 03/24/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 029 02/17/2004 03/24/2003 03/24/2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/24/2003 03/24/2008 EF E-3 STEAM GENERATOR TUBE RUPTURE 037 04/29/2004 03/24/2003 03/24/2008 EF PRE TOTAL: 4 GRAND TOTAL: 4

EOP: TITLE:

REV: 12 ATT-16.0 ATTACHMENT RUPTURED S/G PAGE 1 of 4 Responsible Manager Q2 0 e Date _____

NOTE: Intermediate Building environment should be assessed for radiological and other personnel safety concerns.

PART A. -Dispatch AO with locked valve key to complete local isolation of ruptured S/G as follows:

1) Check closed the ruptured S/G MSIV o S/G A, V-3517 OR o S/G B, V-3516 IF ruptured S/G MSIV is NOT closed, THEN perform the following to close ruptured SIG MSIV:

o S/G A

• Close IA isol to S/G A MSIV, V-5408A

• Open emerg vent valves V-5471 AND V-5473

• Notify Control Room S/G A MSIV is closed OR o S/G B

• Close IA isol to S/G B MSIV, V-5409B

• Open emerg vent valves V-5472 AND V-5474

• Notify Control Room S/G B MISV is closed

2) Ensure BOTH SIG MSIV bypass valves closed (INT BLDG steam header area):

o S/G A, V-3615 o S/G B, V-3614

3) IF the ruptured S/G MSIV can NOT be closed, THEN perform the I following:

a) Close Air Ejector/Gland steam root valve, V-3540 (Main steam header TURB BLDG).

b) Close flange heating isolation valves, MOV-3601A and MOV-3602A.

c) Notify Control Room that main flowpaths are isolated. I

EO.f: TITLE:

REV: 12 ATT-16.0 ATTACHMENT RUPTURED S/G PAGE 2 of 4 CAUTION CONTROL ROOM SHOULD BE NOTIFIED BEFORE ISOLATING TDAFW PUMP STEAM FLOW.

NOTE: The following steps may be done in any order for PART A.

4) Locally close TDAFW Pump steam root valve o S/G A, V-3505

-OR-o S/G B, V-3504

5) Locally close the following steam valves from the ruptured S/G:

o Steam to sampling system valve (INT BLDG steam header area):

S/G A, close V-3413A

-OR-S/G B, close V-3412A o Support heating steam valve (INT BLDG steam header area):

S/G A, close V-3669

-OR-S/G B, close V-3668 o Upstream trap isolation valve (TURB BLDG near MFW reg vlvs):

S/G A, close V-3521

-OR-S/G B, close V-3520 CAUTION CONTROL ROOM SHOULD BE NOTIFIED BEFORE ISOLATING TDAFW PUMP FEED FLOW.

6) Locally close TDAFW pump manual feedwater isolation valve to ruptured S/G (INT BLDG steam header area):

S/G A, V-4005

-OR-S/G B, V-4006

EOP: TITLE:

REV: 12 ATT-16.0 ATTACHMENT RUPTURED S/G

,; PAGE 3 of 4

7) Bypass condensate polishing demineralizers as follows:

a. Place AVT bypass valve controller in MANUAL (east end of AVT panel).

b. Open bypass valve.

c. Isolate ALL inservice demineralizers as follows:

1) Place the Mixed Bed Service Selector switch to override AND select the bed to be removed from service.

2) Place the 4 position selector switch for the selected bed to OFF.

3) Repeat steps 1 and 2 for each inservice bed.

8) Locally place TURB RM WALL EXH FAN switches to CLOSE.

9) Locally place TURB RM ROOF VENT switches to CLOSE.

EOP: TITLE:

REV: 121 ATT-16.0 ATTACHMENT RUPTURED S/G PAGE 4 of 4

.I CAUTION PART B OF THIS ATTACHMENT SHOULD ONLY BE PERFORMED IF RUPTURED S/G MSIV CANNOT BE CLOSED.

PART B. Dispatch AO to locally perform the following when ruptured S/G MSIV cannot be closed, if areas are accessible:

1) Complete isolation by closing the following valves:

NOTE: Substeps may be done in any order.

a) MFW regulating valve and bypass valve manual isolation valves for both SIGs:

o S/G A, V-3985 and V-3989 o S/G B, V-3984 and V-3988 b) Reheat steam chain valves:

o 1A MSR, V-3551 o 1B MSR, V-3550.

o 2A MSR, V-3553 o 2B MSR, V-3552 c) Steam dump header isolation and bypass valves (Main steam header TURB BLDG on platform overhead) o V-3532 and V-3659 o V-3533 and V-3658 d) Reheat steamline warmup valves (warmup vlvs located east end of 1A and 2A MSRs TURB BLDG middle floor):

o V-3645 o V-3646 o V-3647 o V-3648 e) Reheat steamline common-vent, V-8500 (at condenser north of 1A MSR).

f) Steam to trap header isolation valves o V-8513 (Main steam header TURB BLDG) o V-8529 (south side EH skid) g) Steam trap isolation and bypass valves o V-3596 (south side of EH skid) o V-3598 (south side of EH skid)

Eop: TITLE: R V E-3 l STEAM GENERATOR TUBE RUPTURE PAGE I of 42 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER___

RESPONSIB E MANAGER 1-g'- 0z004 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 42 A. PURPOSE - This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-0, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or

b. E-0, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation is abnormal, or

c. E-0, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when an intact S/G narrow range level increases in an uncontrolled manner.

d. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when pressurizer pressure control is restored.

e. Any FOLDOUT page that has E-3 transition criteria whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 42 P

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 greater than 4 psig or CNMT radiation is greater than 10+05 R/hr.

• 1 Monitor RCP Trip Criteria:

a. RCP status - ANY RCP RUNNING 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

EP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. . PAGE 4 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 4 4 4 * * * * *

• 4 4 4

• 4 4 * *

• C

• 4

• 4 4

• 4 * *

• 4

• 4

• 4

• 4 4 4 4

• 4 CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN-MANUAL ACTION MAY BE REQUIRED TO RESTART-SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER) 4 4 4

• 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 2 Identify Ruptured SIG(s): Perform the following:

o Unexpected increase in either a. Reset SI S/G narrow range level

b. Continue with Steps 10

-OR- through 16. WHEN ruptured S/G(s) identified. THEN do Steps o High radiation indication on 3 through 9.

main steamline radiation monitor

• R-31 for S/G A

. R-32 for S/G B -

-OR-o AO reports local indication of high steamline radiation

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

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 42 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED

• 4 * *

• 4 .

• 4 . . . 4 4

• 4* . 4

• 4

• 4 * * *

• 4

• 4 4 4 4 4 4 * , 4 * *

• 4 CAUTION o IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW. STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE SIG.

o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

4 4 *

• 4 4 4 4 4

• 4 4

• 4 4 4* * . 4

• 4 . 4 4 4

• 4 4 4 4

• 4 4

• 4 4 4 4 4 ,

• 3 Isolate Flow From Ruptured S/G(s):

a. Adjust ruptured S/G ARV controller to 1050 psig in AUTO

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

IF S/G ARV can NOT be closed.

THEN dispatch AO to locally isolate.

c. Close ruptured SIG TDAFW pump c. Dispatch AO with locked valve steam supply valve and place in key to locally isolate steam PULL STOP from ruptured S/G to TDAFW pump.

. S/G A. MOV-3505A

• S/G A. V-3505

. S/G B. MOV-3504A

• SIG 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 IF blowdown can NOT be isolated

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

• S/G A. V-5701

• S/G B. V-5702

EMPTL: REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE P

. ~PAGE.6 of '42.

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl-4 Complete Ruptured S/G Isolation:

a. Close ruptured SIG MSIV - a. Perform the following:

RUPTURED S/G MSIV CLOSED

1) Close intact S/G MSIV.

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

3) Adjust condenser steam dump controller to 1050 psig in AUTO.

4) Place condenser'steam dump mode selector switch to MANUAL.

5) Adjust reheat steam supply controller cam to close

-reheat steam supply valves.

6) Ensure turbine stop valves -

CLOSED.

7) Dispatch AO to complete ruptured S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G, parts A and B).

8) Go to step 5.

b. Dispatch AO to complete ruptured S/G isolation (Refer to " .

ATT-16.0. ATTACHMENT RUPTURED*

S/G part A)

S P ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 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 4 4 *. 4

. 4 4 * * *

• 4

. 4 * *

• 4.

• 5 Check Ruptured S/G Level: -

a. Narrow range level - GREATER a. IF ruptured S/G NOT faulted.

THAN 5% [25% adverse CNMT] THEN perform the following: -

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

2) Continue with Step 6. WHEN ruptured S/G level greater than 5% [25% adverse CNMT].

THEN do Steps 5b through e.

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

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED1 6 Verify Ruptured S/G Isolated:

a. Check ruptured MSIV - CLOSED a. Direct AO to immediately isolate air ejector/gland steam supply and flange heating steam.

(Refer to ATT-16.0. ATTACHMENT RUPTURED SIG. part A).

b. Check TDAFW pump steam supply b. Continue efforts to isolate from ruptured S/G - ISOLATED steam supply from ruptured S/G:

• S/G A. MOV-3505A OR V-3505

• S/G B. MOV-3504A OR V-3504

c. Ruptured S/G pressure - GREATER c. Go to ECA-3.1. SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

7 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Adjust S/G ARV controllers to maintain intact S/G pressure in o Intact S/G MSIV - OPEN AUTO and go to Step 8.

o Annunciator G-15, STEAM DUMP ARMED - LIT

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

c. Place steam dump mode selector switch to MANUAL

EOP: TITLE:

E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED CAUTION IF OFFSITE.POWER IS LOST AFTER SI RESET. THEN MANUAL ACTION MAY BE REQUIRED TO RESTART-SAFEGUARDS EQUIPMENT. (REFER TO ATT-8.5. ATTACHMENT LOSS OF OFFSITE POWER)

• * * * * * * * * * * * * * * * * * *

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

• 8 Reset SI

IEI.OfP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. PAGE 10 of 42 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINEDI

• *

• a a * * * - . . . a a a a a a a a *

• a a a a a a a a a a a a a a a a . a

• CAUTION RUPTURED S/G LEVEL SHALL BE MAINTAINED GREATER THAN 5% [25% ADVERSE CNMT]

DURING THE RCS COOLDOWN. UNLESS THE RUPTURED SIG IS ALSO FAULTED.

• a a a a a a a a . a a a a a a a a a . a a a a a a a a a a a a a . a a a a a .

• NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.

9 Initiate RCS Cooldown:

a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE (0F) 1100 PSIG 525 [517 adverse CNMTI 1000 PSIG 512 [504 adverse CNMT]

900 PSIG 499 [490 adverse CNMT]

800 PSIG 484 [475 adverse CNMT]

700 PSIG 468 [457 adverse CNMT]

600 PSIG 449 [437 adverse CNMT]

500 PSIG 428 [413 adverse CNMT]

400 PSIG 402 [384 adverse CNMT]

300 PSIG 369 [344 adverse CNMT]

b. IF ruptured S/G MSIV closed, b. Manually or locally initiate THEN initiate dumping steam to steam dump from intact SIG at condenser from intact S/G at maximum rate using S/G ARV.

maximum rate IF no intact S/G available. THEN perform the following:

o Use faulted S/G.

-OR-o IF a ruptured S/G must be used. THEN go to ECA-3.1.

SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

c. Core exit T/Cs - LESS THAN c. Continue with Step 10. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required. THEN do Step 9d.

d. Stop RCS cooldown and stabilize core exit T/Cs less than required temperature

EOP: TITLE:

REV: .37 E-3 ' STEAM GENERATOR TUBE RUPTURE PAGE.11 of 42 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

10 Monitor Intact S/G Level:

a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one S/G.

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

[25% adverse CNMT] and 50% in an uncontrolled manner. THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

M EP: TITLE:

° REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. PAGE 12 of 42 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE. IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP liB).

• * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• a * * * * *

• 11 Monitor PRZR PORVs And Block Valves:

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

e MOV-515. MCC D position 6C

• MOV-516. MCC C 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.

EOP: TITLE:RE :3 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 13 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 12 Reset CI:

a. Depress CI reset pushbutton

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

ISOLATION - EXTINGUISHED

1) Reset SI.

2) Depress CI reset pushbutton.

t

[EOP: TITLE:

EREV: 37

. E-3 STEAM GENERATOR TUBE RUPTURE

. .PAGE 14 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses - Perform the following:

BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open. THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.

volt busses - CLOSED

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

THAN 420 VOLTS

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

OPEN

• Bus 13 to Bus 14 tie

• Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:

• EH pumps

• Turning gear oil pump

- HP seal oil backup pump

3) Restore power to MCCs.

• A from Bus 13

• B from Bus 15

• E from Bus 15

• F from Bus 15

4) Start HP seal oil backup pump.

5) Start CNMT RECIRC fans as necessary.

6) Ensure D/G load within limits.

7) WHEN bus 15 restored. THEN reset control room lighting.

c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER). .

EOP: TITLE:W Ed:REV: R V 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 42 ACTION/EXPECTED RESPONSE 1RESPONSE STEP NOT OBTAINEDl 14 Verify Adequate SW Flow:

a. Check at least two SW pumps - a. Manually start SW pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps running. THEN:

1) Ensure SW isolation.

2) IF NO SW pumps running, THEN perform the following:

a) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress VOLTAGE SHUTDOWN pushbutton.

b) Refer to ATT-2.4.

ATTACHMENT NO SW PUMPS.

3) IF only one SW pump running, THEN refer to AP-SW.2. LOSS OF SERVICE WATER.

b. Dispatch AO to establish normal shutdown alignment (Refer to ATT-17.0. ATTACHMENT SD-1)

EOP: TITLE: R V E-3 STEAM GENERATOR TUBE RUPTURE

[.. . PAGE 16 of 42 TEst ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT:

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

energized

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

-OR-

• Bus 13 to Bus 14 tie

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

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

IF NOT, THEN perform the following:

o Start diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL AIR COMPRESSOR)

-OR-o Evaluate if CNMT RECIRC fans should be stopped (Refer to ATT-4.0.

ATTACHMENT CNMT RECIRC FANS)

b. Check SW pumps - AT LEAST TWO b. Perform the following:

PUMPS RUNNING

1) Restore IA using service air compressor OR diesel air compressor (refer to ATT-11.2. ATTACHMENT DIESEL.

AIR COMPRESSOR)

2) Go to step 15d.

c. Verify turbine building SW c. Manually align valves.

isolation valves - OPEN

• MOV-4613 and MOV-4670

• MOV-4614 and MOV-4664 This Step continued on the next page.

EOP: TITLE:

I REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 15 continued from previous page)

d. Verify adequate air compressors d. Manually start air compressors

- RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started. THEN dispatch AO to locally reset compressors as necessary.

e. Check IA supply: e. Perform the following:

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

o Pressure - STABLE OR INCREASING 2) Continue with Step 16. WHEN IA restored. THEN do Steps 15f and g.

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

g. Verify IA to CNMT AOV-5392 - OPEN

• * * * * , * * * * * .

• 4 *

• 4* . 4 * * * ,* *

• 4 *

• 4 * *

• 4 4 4 * .

• 4 *

• CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT]. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

• 4 4 *

• 4

• 4 * * * . * * * * * * * * * * * * *

• 4 * * * * * * *

• 4 *

• 4 *

• 16 Check If RHR Pumps Should Be, Stopped:

a. Check RCS pressure - GREATER a. Go to Step 17.

THAN 250 psig [465 psig adverse CNMT]

b. Stop RHR pumps and place both in AUTO

EOP: TITLE: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 18 of 42 ACTION/EXPECTED RESPONSE STEP lRESPONSE NOT OBTAINED 17 Establish Charging Flow:

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

1) IF CCW flow-is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO 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 0%.

b. Align charging pump suction to b. IF LCV-112B can NOT be opened.

RWST: THEN dispatch AO to locally open V-358. manual charging pump o LCV-112B - OPEN suction from RWST (charging pump room).

o LCV-112C - CLOSED

. IF LCV-112C can NOT be closed, THEN perform the following:

1) Direct AO to locally open V-358, manual charging pump suction from RWST (charging pump room).

2) Verify charging pump A NOT running and place in PULL STOP.

3) WHEN V-358 open. THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (charging pump room).

c. Start charging pumps as necessary and establish 75 gpm total charging flow

• Charging line flow

. Seal injection

E~f~:TITLE

[

lEOP E-3 J0 TITE:

STEAM GENERATOR TUBE RUPTURE i.~~

IREV:

P 37 PAGE 19 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 18 Check If RCS Cooldown Should Be Stopped:

a. Core-exit T/Cs - LESS THAN a. Do NOT proceed until core exit REQUIRED TEMPERATURE T/Cs less than required temperature.

b. Stop RCS cooldown

c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE 19 Check Ruptured S/G Pressure - IF pressure continues to decrease STABLE OR INCREASING to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

20 Check RCS Subcooling Based On Go to ECA-3.1. SGTR WITH LOSS OF Core Exit T/Cs - GREATER THAN REACTOR COOLANT - SUBCOOLED 20 0 F USING FIG-1.0, FIGURE RECOVERY DESIRED. Step 1 .

MIN SUBCOOLING

EOP: TITLE: Ed: R V 37 REV:

E-3 STEAM GENERATOR TUBE RUPTURE PAGE 20 of 42 ACTION/EXPECTED RESPONSE 1RESPONSE STE NOT OBTAINEDl NOTE: SI ACCUMs may inject during RCS depressurization.

21 Depressurize RCS To Minimize Break Flow And Refill PRZR:

a. Check the following: a. Go to Step 22.

o Ruptured S/G level - LESS THAN 90% [80% adverse CNMT]

o Any RCP - RUNNING o IA to CNMT - AVAILABLE

b. Spray PRZR with maximum available spray until'ANY of the following conditions satisfied:

o PRZR level - GREATER THAN 75%

[65% adverse CNMT]

-OR-o RCS pressure - LESS THAN SATURATION USING FIG-1.0.

FIGURE MIN SUBCOOLING

-OR-o BOTH of the following:

1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE

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

c. Close normal PRZR spray valves: c. Stop associated RCP(s).

1) Adjust normal spray valve controller to 0% DEMAND

2) Verify PRZR spray valves -

CLOSED

• PCV-431A

• PCV-431B

d. Verify auxiliary spray valve d. Decrease charging speed to (AOV-296) - CLOSED minimum and ensure charging valve to loop B cold leg open (AOV-294).

e. Go to Step 24

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 21 of 42

.i ,

ACTION/EXPECTED RESPONSE lRESPONSE STP NOT OBTAINEDl

• ,* * . . * * * * . * * * * . * * * * *

• 4.* *4 * * * * * . * * * * *

• A . *

• 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.

• 4 4 4

• 4 * * * * * * * *

• 4 * *

• 4

• 4 4

• * ** * * *

• 4

• 4 4

• 4 NOTE: o If auxiliary spray is in use. spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

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

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

a. Verify IA to CNMT - AVAILABLE a. Refer to ATT-12.0, ATTACHMENT N2 PORVS to operate PORVs.

b. PRZR PORVs - AT LEAST ONE b. IF auxiliary spray available.

AVAILABLE THEN return to Step 21b.

IF auxiliary spray can NOT be established. THEN go to ECA-3.3.

SGTR WITHOUT PRESSURIZER PRESSURE CONTROL. Step 1.

This Step continued on the next page.

EOP: TITLE:

REV: 3 7 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 22 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINED (Step 22 continued from previous page)

c. Open one PRZR PORV until ANY of c. IF auxiliary spray available, the following conditions THEN return to step 21b.

satisfied:

1) IF auxiliary spray can NOT be o PRZR level - GREATER THAN 75% established. THEN go to

[65% adverse CNMT] ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.

-OR- Step 1.

o RCS pressure - LESS THAN SATURATION USING FIG-l.0.

FIGURE MIN SUBCOOLING

-OR-o BOTH of the following:

1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE

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

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

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 23 of 42 ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED 23 Check RCS Pressure - Close block valve for the PRZR PORV INCREASING that was opened.

IF pressure continues to decrease.

THEN perform the following:

a. Monitor the following conditions for indication of leakage from PRZR PORV:

o PORV outlet temp (TI-438) NOT decreasing.

o PRT pressure. level or temperature continue to increase.

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

STP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINED

• * * * * , * * * * * * * * * * * * * * *

• 4 * *

• 4 * * * * * * *4 * * * *

• CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED S/G.

• 4 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 4 24 Check If SI Flow Should Be .

Terminated: . -

a. RCS subcooling based on core- a. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN 00 F ECA-3.1. SGTR WITH LOSS OF USING FIG-1.0. FIGURE MIN. REACTOR COOLANT - SUBCOOLED SUBCOOLING RECOVERY DESIRED. Step 1.

b. Secondary heat sink: b. IF neither condition satisfied.

THEN do NOT stop SI pumps. Go to o Total feed flow to S/G(s) - ECA-3.1. SGTR WITH LOSS OF GREATER THAN 200 GPM AVAILABLE REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

-OR-o Narrow range level in at least one intact S/G -

GREATER THAN 5% [25% adverse CNMT]

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

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

[30% adverse CNMT] Step 6. -

EOP: TIRE: REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 42 ACTION/EXPECTED RESPONSE STP RESPONSE NOT OBTAINED 25 Stop SI Pumps And Place In AUTO 26 Establish Required Charging Line Flow:

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

1) IF CCW flow is lost to any RCP thermal barrier OR any RCP #1 seal outlet temperature offscale high.

THEN dispatch AO to locally isolate seal injection to affected RCP:

• RCP A. V-300A

• RCP B. V-300B

2) Ensure HICV-142 open.

3) Start one charging pump.

b. Establish 20 gpm charging line flow 27 Monitor SI Reinitiation Criteria:

a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN 0 0F necessary and go to ECA-3.1.

USING FIG-1.O, FIGURE MIN SGTR WITH LOSS OF REACTOR SUBCOOLING COOLANT --SUBCOOLED RECOVERY DESIRED. Step 1.

b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained. THEN manually start SI pumps as necessary and go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

EP: TITLE: REV: 37 E-L3 STEAM GENERATOR TUBE RUPTURE l . . . PAGE 26 of 42 ACTION/EXPECTED RESPONSNED 28 Check If SI ACCUMs Should Be Isolated:

a. Check the following: a. Manually operate SI pumps as necessary and go to ECA-3.1.

o RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit T/Cs - GREATER THAN 0F COOLANT - SUBCOOLED RECOVERY USING FIG-1.0. FIGURE MIN DESIRED. Step 1.

SUBCOOLING o PRZR level - GREATER THAN 5%

[30% adverse CNMTI

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.

IF an accumulator can NOT be isolated or vented. THEN consult TSC to determine contingency actions.

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

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE -

PAGE 27 of 42 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 29 Verify Adequate SW Flow To CCW Hx:

a. Verify at least three SW pumps - a. Manually start pumps as power RUNNING supply permits (257 kw each).

IF less than two SW pumps can be operated. THEN perform the following:

1) IF NO SW pumps running. THEN perform the following:

a) Pull stop any D/G that is NOT supplied by alternate cooling. AND immediately depress VOLTAGE SHUTDOWN pushbutton.

b) Refer to ATT-2.4.

ATTACHMENT NO SW PUMPS.

2) IF only one SW pump running.

THEN refer to AP-SW.2, LOSS OF SERVICE WATER.

3) Go to Step 36.

b. Verify AUX BLDG SW isolation b. Manually align valves.

valves - AT LEAST ONE SET OPEN

- MOV-4615 and MOV-4734

- MOV-4616 and MOV-4735 This Step continued on the next page.

EDP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

PAGE 28 of 42 ACTION/EXPECTED RESPONSE E lRESPONSE NOT OBTAINED (Step 29 continued from previous page)

c. Verify CNMT RECIRC fan c. Perform the following:

annunciator C-2. HIGH TEMPERATURE ALARM - EXTINGUISHED 1) Determine required SW flow to CCW HXs per table:

SW DISCHARGE CCW HXs IN REQUIRED SW FLOW ALIGNMENT SERVICE Normal 2 Total of 5000 - 6000 gpm equally divided to both HXs Normal 1 5000 - 6000 gpm to in-service HX Alternate 2 30-33" d/p across each HX Alternate 1 95-100" d/p across in-service HX

2) Direct AO to adjust SW flow to required value.

o IF on normal SW discharge:

. V-4619, CCW Hx A

• V-4620. CCW Hx B

-OR-o IF on alternate SW discharge:

• V-4619C, CCW Hx A

. V-4620B. CCW Hx B

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored: a. Continue with Step 36. WHEN IA restored, THEN do Steps 30 o IA to CNMT (AOV-5392) - OPEN through 35.

o IA pressure - GREATER THAN 60 PSIG

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

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

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

1) IF any RCP #1 seal outlet temperature offscale high.

THEN isolate CCW to thermal barrier of affected RCP(s).

• RCP A. MOV-749A and MOV-759A

• RCP B. MOV-749B and MOV-759B

2) Manually start one CCW pump.

d. Charging pump - ANY RUNNING d. Continue with Step 36. WHEN any

- charging pump running, THEN do Steps 31 through 35.

EOP: TITLE: R V Ed: .REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 30 of 42 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED I 31 Check If Seal Return Flow Should Be Established:

a. Verify RCP #1 seal outlet a. Go to Step 32.

temperature - LESS THAN 235 0F

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 to locally open MOV-313.

e. Verify RCP #1 seal leakoff flow e. Perform the following:

- LESS THAN 6.0 GPM

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down. THEN close the affected RCP seal discharge valve

. RCP A. AOV-270A

• RCP B. AOV-270B IF both RCP seal discharge valves are shut. THEN go to Step 32.

f. Verify RCP #1 seal leakoff flow f. Refer to AP-RCP.1. RCP SEAL

- GREATER THAN 0.8 GPM MALFUNCTION.

EOP: TITLE:

. . REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 42

.~~. .. .` .

ACTION/EXPECTED RESPONSENED 32 Verify PRZR Level - GREATER Continue with Step 34. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%

[40% adverse CNMT]. THEN do Step 33.

33 Establish Normal Letdown: IF RCP seal return has been established. THEN establish excess

a. Establish charging line flow to letdown as follows:

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

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

CLOSE:

o Ensure CCW from excess letdown

• Letdown orifice valves open. (AOV-745).

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

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

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

c. Place letdown controllers in than 1950F and pressure less MANUAL at 40% open than 100 psig.

• TCV-130 o Adjust charging pump speed as

. PCV-135 necessary.

d. Reset both trains of XY relays IF RCP seal return NOT established.

for AOV-371 and AOV-427 THEN consult TSC to determine if excess letdown should be placed in

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

f. Open letdown orifice valves as necessary

g. Place PCV-135 in AUTO at 250 psig

h. Place TCV-130 in AUTO at the normal setpoint

i. Adjust charging pump speed and HCV-142 as necessary

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. .PAGE 32 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDl 34 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm

b. Adjust RMW flow control valve in AUTO to 40 gpm

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

1) RMW mode selector switch in AUTO

2) RMW control armed - RED LIGHT LIT

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

o Level - GREATER THAN 20%

1) Ensure BA transfer pumps and

-OR- RMW pumps running. IF NOT.

THEN reset MCC C and MCC D UV o Level - STABLE OR INCREASING lockouts as necessary.

2) Place RMW flow control valve HCV-l11 in MANUAL and increase RMW flow.

3) Increase boric acid flow as necessary.

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 42 ACTION/EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED 35 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater -than 5%. THEN perform the following:

1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step 36. WHEN VCT level greater than 40%.

THEN do Step 35b.

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

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

.\11,

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

• a * * * * * * * * * * *

• a a * * * * *. *

• a

. * * *

• a *

• a a a * * * *

• CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

• a * * *

• a * * * * * *

• a

• a * *

• a * * * * * * * * * * *

• a * *

• a *

• a

• 36 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:

a. Perform appropriate action(s) from table:

PRZR *RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase Increase o Increase

[40% ADVERSE CNMT] charging flow charging charging flow flow o Depressurize RCS o Maintain RCS and using Step 36b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and

[40% ADVERSE CNMT] using Step 36b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and

[65% ADVERSE CNMT] using Step 36b PRZR ruptured S/G heaters pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS and

[65% ADVERSE CNMTI charging flow PRZR ruptured S/G heaters pressure equal

b. Control pressure using normal b. IF letdown is in service, THEN PRZR spray, if available. to use auxiliary spray (AOV-296).

obtain desired results for IF NOT. THEN use one PRZR PORV.

Step 36a

EOP: TITLE:

I REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 42 ACTION/EXPECTED RESPONSE SP lRESPONSE NOT OBTAINEDl 37 Monitor If CNMT Spray Should Be Stopped:

a. CNMT-spray pumps - ANY RUNNING a. Go to Step 38.

b. Verify CNMT pressure - LESS THAN b. Continue with Step 38. WHEN 4 PSIG CNMT pressure less than 4 psig.

THEN do Steps 37c through f.

c. Reset CNMT spray

d. Check NaOH flow (FI-930) - NO d. Place NaOH tank outlet valve FLOW switches to CLOSE.

• 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 a MOV-860D

[EDP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. . . PAGE 36 of 42 ACTION/EXPECTED RESPONSE STE lRESPONSE NOT OBTAINED 38 Check If Emergency D/Gs Should Be Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

o Emergency DIG output breakers

- OPEN o- AC emergency bus voltage -

GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency DIG and place in standby (Refer to ATT-8.1. ATTACHMENT D/G STOP) 39 Minimize Secondary System Contamination:

a. Isolate reject from hotwell to a. IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.

o Place hotwell level controller (LC-107) in MANUAL at 50%

o Verify hotwell level - STABLE

b. Check status of local actions to complete ruptured S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G)

EOP: TITLE:

REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE

. PAGE 37 of 42 ACTION/EXPECTED RESPONSE STEP 1RESPONSE NOT OBTAINED-40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: Establish normal cooling to RCPs (Refer to ATT-15.2, ATTACHMENT SEAL

a. Check CCW to RCPs: COOLING).

o Annunciator A-7. RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW

- EXTINGUISHED o Annunciator A-15. RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW

- EXTINGUISHED

b. Check RCP seal injection:

o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER

-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM

SE ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINEDl

• * * * * * * * * * * *

• 4 * * * *

• 4

• 4 * * * * * * * * * - * * * * * * * *

• CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

• C h e c k * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 4 42 Check RCP Status

a. Both RCPs - STOPPED a. Stop all but one RCP and go to step 43.

b. Ensure conditions for starting b. IF conditions can NOT be met.

an RCP. THEN perform the following:

o Bus 11A or 11B energized. 1) Verify natural circulation (Refer to ATT-13.0.

o Refer to ATT-15.0. ATTACHMENT ATTACHMENT NC).

RCP START.

IF natural circulation can NOT be verified. THEN increase dumping steam.

2) Go to step 43.

This Step continued on the next page.

LOP: TITLE:

REV: 37 E-3 . STEAM GENERATOR TUBE RUPTURE PAGE 39 of 42 ACTION/EXPECTED RESPONSE STP lRESPONSE NOT OBTAINED (Step 42 continued from previous page)

c. Check RVLIS level (no RCPs) c. IF RVLIS level (no RCPs) less 2 95% than 95%. THEN perform the following:

o Increase PRZR level to greater than 65% [82% adverse CNMT].

, o Dump steam to establish RCS subcooling based on core exit

- - T/Cs to greater than 201F using FIG-1.0. FIGURE MIN SUBCOOLING.

o Energize PRZR heaters as necessary to saturate PRZR water IF conditions NOT met. THEN continue with step 43. WHEN

- conditions met, THEN do

step 42d.

d. Start one RCP d. IF an RCP can NOT be started.

THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).

IF natural circulation can NOT be verified. THEN increase dumping steam.

EOP: TITLE: REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 40 of 42 ACTION/EXPECTED RESPONSE llRESPONSE STP NOT OBTAINEDI NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

43 Check If Source Range Detectors Should Be Energized:

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

DEENERGIZED

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

EITHER CHANNEL LESS THAN 10-10 AMPS 1) IF neither intermediate range channel is decreasing. THEN initiate boration.

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

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

channels - LESS THAN 10-10 AMPS

-OR-o Greater than 20 minutes since reactor trip

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

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

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

EOP: TITLE: REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 41 of 42 ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform ATT-17.1.

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) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)

2) Verify one Rx compartment 2) Perform the following:

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

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

d. Verify ATT-17.0. ATTACHMENT SD-1

- COMPLETE

EOP: TITLE:

I REV: 3 7 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 42 of 42 CTION/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 COOLDOWN USING STEAM DUMP. Step 1

-END-

.EDP: TIREV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)

3) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)

4) ATTACHMENT D/G STOP (AnT-8.1)

5) ATTACHMENT N2 PORVS (ATT-12.0)

6) ATTACHMENT NC (ATT-13.0)

7) ATTACHMENT SEAL COOLING (A1T-15.2)

8) ATTACHMENT RCP START (ATT-lS.0)

9) ATTACHMENT RUPTURED S/G (ATT-16.0)

10) ATTACHMENT SD-1 (ATT-17.0)

11) ATTACHMENT SD-2 (ATT-17.1)

12) ATTACHMENT NO SW PUMPS (ATT-2.4)

13) ATTACHMENT LOSS OF OFFSITE POWER (ATT-8.5)

14) ATTACHMENT DIESEL AIR COMPRESSOR (ATT-11.2)

15) FOLDOUT

EOP: TITLE:

REV: 37 E-3 - STEAM GENERATOR TUBE RUPTURE

. PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 5%

b. CORE COOLING - Core exit T/Cs greater than 12000F

-OR-Core exit-T/Cs greater than 700°F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

[25% adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY.- Cold leg temperatures decrease greater than

. 100'F in last 60 minutes AND RCS cold leg temperature less than 2850F

-e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:REV: 37 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE

1. LOSS OF SW CRITERIA IF no SW pumps are available, THEN perform the following:

a. Pull stop any DIG that is NOT supplied by alternate cooling, AND immediately depress associated VOLTAGE SHUTDOWN pushbutton.

b. Refer to ATT-2.4, ATTACHMENT NO SW PUMPS.

2. SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:

o RCS subcooling based on core exit T/Cs - LESS THAN 00 F USING REQUIREMENTS OF FIG-1.0, FIGURE MIN SUBCOOLING.

OR o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].

3. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.

4. 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.

5. 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).

6. MULTIPLE S/G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.