ML040020416

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Revised Emergency Operating Procedures, Including Rev. 35 to E-0, Rev. 28 to E-1, Rev. 11 to E-2 & Rev. 35 to E-3
ML040020416
Person / Time
Site: Ginna 
(DPR-018)
Issue date: 12/17/2003
From: Widay J
Rochester Gas & Electric Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML040020416 (47)
v • d • e


Text

ROe Always at Your Servke Joseph A. Widay Vice President and Plant Manager December 17, 2003 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, 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):

E Index E-3, Rev 35 An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com EE An Erg Ea st Company

-- -are C

NPSP0200 WRIGHTJ Ginna Nuclear Power Plant PROCEDURE INDEX Wed 12/17/2003 11:09:32 am Page 1 of I INPUT PARAMETERS: TYPE:

STATUS VALUE(S):

EF. 0Qt 5 YEARS ONLY:

_PRE EMERGENCY PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVmW ST E-0 REACTOR TRIP OR SAFETY PINECTION 035 1011012003 03/24/003 03124/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 028 05/30/2003 03/2412003 03/24)2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/2412003 03/24/2008 EF E-3 STEAM GENERATOR TUBE RUPTURE 035 12/17/2003 4/120143/2 03/24/2008 EF PRE TOTAL:

4 GRAND TOTAL:

4

Il ElF:

TITL:

REV: 3 5 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 42 ROCHESTER GAS AND ELECTRIC CORPORATION '

GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLO MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

[EOP:

TIT:

REV: 35 E-3 STAM 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:

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 42 NOTE:

_ACTION/EXPECTED RESPONSEREPNEOTBAID 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
b. SI pumps - AT LEAST TWO RUNNING
c. RCS pressure minus maximum SIG pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs
a. Go to Step 2.
b. Go to Step 2.
c. Go to Step 2.

EOP:

TITLE:

REV: 3 5 E-3 STEAM GENERATOR TUBE RUPTURE l

PAGE 4 of 42 l STEP ACTION/EXPECTED RESPONSE l

RSPONSE NOT OBTAINED 0

0 0

0*

0*

0 0*

0

  • O CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET.

TO RESTART SAFEGUARDS EQUIPMENT.

(REFER OFFSITE POWER)

THEN MANUAL ACTION MAY BE REQUIRED TO ATT-8.5. ATTACHMENT LOSS OF 0

00 0

0 0

0 0*

00 0

0 0

0 0

0 0

0 0

0 2 Identify Ruptured S/G(s):

Perform the following:

o Unexpected increase in either SIG narrow range level

-OR-o High radiation indication on main steamline radiation monitor

a. Reset SI
b. Continue with Steps 10 through 16. WHEN ruptured S/G(s) identified. THEN do Steps 3 through 9.
  • 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

MP:

TITLE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 42 STEP

_ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINEDl ii 0

ii 0

h 0

0 0

  • * * * * * * *
  • 0 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 SG.

o AT LEAST ONE SG SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

0*

  • 0 0*

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

a. Adjust ruptured SIG ARV controller to 1050 psig in AUTO
b. Check ruptured SIG ARV - CLOSED
b. WHEN ruptured SG pressure less than 1050 psig. THEN verify S/G ARV closed.

IF NOT closed. THEN place controller in MANUAL and close SIG ARV.

IF SIG ARV can NOT be closed.

THEN dispatch AO to locally isolate.

c. Close ruptured SIG TDAFW pump steam supply valve and place in PULL STOP
  • S/G A. MOV-3505A
  • S/G B. MOV-3504A
d. Verify ruptured S/G blowdown valve - CLOSED
  • SIG A. AOV-5738
  • SIG B. AOV-5737
c. Dispatch AO with locked valve key to locally isolate steam from ruptured SG to TDAFW pump.
  • S/G A, V-3505
  • S/G B. V-3504
d. Place S/G blowdown and sample valve isolation switch to CLOSE.

IF blowdown can NOT be isolated manually, THEN dispatch AO to locally isolate blowdown.

  • S/G A. V-5701
  • S/G B. V-5702

EOP:

TITE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:

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

RUPTURED SG MSIV CLOSED

1) Close intact S/G MSIV.
2) Place intact SG 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 SG, parts A and B).
8) Go to step 5.
b. Dispatch AO to complete ruptured S/ isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G part A)

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P

l

~~~~~~~~~~~~~~PAGE 7 of 42l SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINED h

CAUTION IF ANY RUPTURED S/G IS FAULTED. FEED FLOW TO THAT SIG SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

R -

5 Check Ruptured S/G Level:

a. Narrow range level -

GREATER THAN 5 [25% adverse CNMT]

a. IF ruptured S/G NOT faulted.

THEN perform the following:

1) Maintain feed flow to ruptured SIG until level greater than 5% [25% adverse CNMT].
2) Continue with Step 6. WHEN ruptured SG level greater than 5% [25% adverse CNMT],

THEN do Steps 5b through e.

b. Close MDAFW pump discharge valve to ruptured S/G
b. Dispatch AO to locally close valve.
  • SIG A. MOV-4007
  • S/G B. MOV-4008
c. Pull stop MDAFW pump for ruptured S/G
d. Close TDAFW pump flow control-valve to ruptured S/G
  • S/G A. AOV-4297
  • S/G B. AOV-4298
e. Verify DAFW pump crosstie valves - CLOSED
d. Dispatch AO with locked valve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.
  • S/G A. V-4005
  • S/G B. V-4006
e. Manually close valves.
  • MOV-4000A
  • MOV-4000B

lOP TITLE:

RV E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 42 STEP TION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 6 Verify Ruptured S/G Isolated:

a. Check ruptured MSIV - CLOSED
a. Ensure air supply and isolated.

ATTACHMENT ejector/gland steam flange heating steam (Refer to ATT-16.0.

RUPTURED SG, part B).

b. Check TDAFW pump steam supply from ruptured SG -

ISOLATED

b. Continue efforts to isolate steam supply from ruptured S/G:
  • SIG A. MOV-3505A OR V-3505
  • S/G B. MOV-3504A OR V-3504
c. Go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
c. Ruptured S/G pressure - GREATER THAN 300 PSIG 7 Establish Condenser Steam Dump Pressure Control:
a. Verify condenser available:

o Intact SG MSIV - OPEN

a. Adjust S/G ARV controllers to maintain intact S/G pressure in 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:

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE 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) a

.a *

  • a a

8 Reset SI

EOP:

TITLE:

1 REV: 3 5I E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 42 STEP

_ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

4 4

  • 4 4

4 4

4 4

4 44*

4

  • 4 4

4 4

4 *

  • 4
  • 4 4
  • 4 4

4 4

  • 4 CAUTION RUPTURED SIG LEVEL SHALL BE MAINTAINED GREATER THAN 5

[25% ADVERSE CNMT]

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

4.

4 *

  • 4
  • 4

.4 4

  • 4 4 * *
  • 4.4*
  • 4 4

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 (F) 1100 PSIG 525 [517 adverse CNMTI 1000 PSIG 512 [504 adverse CNMTI 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.

THEN initiate dumping steam to condenser from intact S/G at maximum rate

b. Manually or locally initiate steam dump from intact SG at maximum rate using SIG ARV.

IF no intact SG available. THEN perform the following:

o Use faulted SG.

-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 REQUIRED TEMPERATURE
c. Continue with Step 10.

WHEN core exit T/Cs less than required. THEN do Step 9d.

d. Stop RCS cooldown and stabilize core exit TCs less than required temperature

l EOP:

TITLE:I

~~~~~~~~~~~~~~REV:

35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 11 of 42 I~~~~~~~~~~~~~~~~~~~~~~~~~~~~-'-

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINE NOTE: TDAFW pump flow control AOVs may drift open on loss of IA.

10 Monitor Intact SG Level:

a. Narrow range level -

GREATER THAN 5 [25% adverse CNMT]

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one SIG.

b. IF narrow range level in the intact SIG continues to increase in an uncontrolled manner. THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

EW:

TIThE:

i TIILE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 42 SE ACTION/EXPECTED RESPONSE l

RESPONSE NOT OBTAINED1 h

a * * * * * * * * * * * * * *

  • 0 * *
  • 0 * * * *
  • 0
  • 0 0 *
  • 0 0
  • 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).

0 * *

  • 0
  • 0 * *
  • 0
  • 0 0

0

  • a a

U *.

a a *

  • 11 Monitor PRZR PORVs And Block Valves:
a. Power to PORV block valves -

AVAILABLE

a. Restore power to block valves unless block valve was closed to isolate an open PORV:
  • MV-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.tOpen one block valve unless it was closed to isolate an open PORV.

c. Block valves - AT LEAST ONE OPEN

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE j

PAGE 13 of 42 E li ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26. CNMT ISOLATION - EXTINGUISHED
b. Perform the following:
1) Reset SI. -
2) Depress CI reset pushbutton.

EOP:

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l

~~~~~~~~~~~~~~PAGE 14 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses -

BUSSES ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses - CLOSED o 480 volt bus voltage - GREATER THAN 420 VOLTS o Emergency D/G output breakers -

OPEN Perform the following:

a. IF any AC emergency bus normal feed breaker open. THEN ensure associated D/G breaker closed.
b. Perform the following as necessary:
1) Close non-safeguards bus tie breakers:
  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie
2) Place the following pumps in PULL STOP:
  • EH pumps
  • 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).

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 42 STEP ~ACTION/EXPECTED RESPONSE lRESPONSE 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 DG 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.O. ATTACHMENT SD-1)

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 16 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 15 Establish IA to CNMT:

a. Verify non-safeguards busses energized o Bus 13 normal feed - CLOSED

-OR-o Bus 15 normal feed - CLOSED

a. Perform the following:
1) Close non-safeguards bus tie breakers:
  • Bus 13 to Bus 14 tie
  • Bus 15 to Bus 16 tie
2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT. THEN 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 PUMPS RUNNING
b. Perform the following:
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 isolation valves - OPEN
c. Manually align valves.
  • MOV-4613 and MOV-4670
  • MOV-4614 and MOV-4664 This Step continued on the next page.

EOP:

TIRE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 42 STEP ACTION/EXPECTED RESPONSE PRESPONSE NOT OBTAINEDl (Step 15 continued from previous page)

d. Verify adequate air compressors

- RUNNING

d. Manually start air compressors as power supply permits (75 kw each).

IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.

e. Check IA supply:

o Pressure - GREATER THAN 60 PSIG o Pressure - STABLE OR INCREASING

e. Perform the following:
1) Continue attempts to restore IA (Refer to AP-IA.1. LOSS OF INSTRUMENT AIR).
2) Continue with Step 16.

WHEN IA restored. THEN do Steps 15f and g.

f. Reset both trains of XY relays for IA to CNMT AOV-5392
g. Verify IA to CNMT AOV-5392 - OPEN 0

0 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.

0 0

0

  • 0 0

0 0

0 16 Check If RHR Pumps Should Be Stopped:

a. Check RCS pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
a. Go to Step 17.
b. Stop RHR pumps and place both in AUTO

,W:

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REV:

3 5 E-3 STEAUM GENERATOR TUBE RUPTURE l

~~~~~~~~~~~~~~PAGE 18 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE 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

MP:

TILE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 19 of ** 42 STE ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 18 Check If RCS Cooldown Should Be Stopped:

a. Core exit T/Cs - LESS THAN REQUIRED TEMPERATURE
a. Do NOT proceed until core exit T/Cs less than required temperature.,.
b. Stop RCS cooldown
c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE 19 Check Ruptured S/G Pressure -

STABLE OR INCREASING 20 Check RCS Subcooling Based On Core Exit T/Cs -

GREATER THAN 20 0F USING FIG-1.0, FIGURE MIN SUBCOOLING IF pressure continues to decrease to less. than 250 psi above the pressure of the intact S/G. THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

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

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l

~~~~~~~~~~~~~~PAGE 20 of 42 STEP ACTION/EXPECTED RESPONSE llRESPONSE 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 SIG 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-l.0, FIGURE MIN SUBCOOLING

-OR-o BOTH of the following:

1) RCS pressure - LESS THAN RUPTURED SIG 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

ACTI~~~~~~~~~~~O/XETE RESPONE X

4 4

4 44*

4 4

4 4

4 X

4 4

4 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

.44

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

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

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

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

AVAILABLE AT LEAST ONE

b. IF auxiliary spray available.

THEN return to Step 21b.

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

SGTR WITHOUT PRESSURIZER PRESSURE CONTROL. Step 1.

This Step continued on the next page.

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 22 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED (Step 22 continued from previous page)

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

o PRZR level - GREATER THAN 75%

[65% adverse CNMT]

-OR-

c. IF auxiliary spray available.

THEN return to step 21b.

1) IF auxiliary spray can NOT be established. THEN go to ECA-3.3. SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.

Step 1.

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 SIG 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.

STP ACTION/EXPECTED RESPONSE lRESPONSE 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.

REV: 3 5 E-3 STESAM GENERATOR TUBE RUPTURE l

l l ~~~~~~~~~~~~PAGE 24 of 42 STEP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl a * * -

CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED SIG.

a * *

  • a * * * * *
  • a * * * *
  • a * ***

24 Check If SI Flow Should Be Terminated:

a. RCS subcooling based on core exit T/Cs - GREATER THAN F

USING FIG-l.O. FIGURE MIN SUBCOOLING

b. Secondary heat sink:

o Total feed flow to S/G(s) -

GREATER THAN 200 GPM AVAILABLE

-OR-

a. Do NOT stop SI pumps. Go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED, Step 1.

b. IF neither condition satisfied, THEN do NOT stop SI pumps. Go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.

o Narrow range level in at least one intact SG -

GREATER THAN 5% 25% adverse CNMTI

c. RCS pressure - STABLE OR INCREASING
c. Do NOT stop SI pumps. Go to ECA-3.1, STR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
d. PRZR level - GREATER THAN 5%

[30% adverse CNMT]

d. Do NOT stop SI pumps. Return to Step 6.

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 42ll STP ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINED 25 Stop SI Pumps And Place In AUTO I

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 B. V-300B

2) Ensure HCV-142 open.
3) Start one charging pump.
b. Establish flow 27 Monitor SI Criteria:

20 gpm charging line Reinitiation

a. RCS subcooling based on core exit T/Cs - GREATER THAN 0F -

USING FIG-1.O. FIGURE MIN SUBCOOLING

b. PRZR level - GREATER THAN 5%

[30% adverse CNMT]

a. Manually start SI pumps as necessary and go to ECA-3.1.

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

b. Control charging flow to maintain PRZR level.

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

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE P

PAGE 26 of 42 STEP ACTION/EXPECED RESPONSEREPNEOTBAID 28 Check If SI ACCUMs Should Be Isolated:

a. Check the following:

o RCS subcooling based on core exit T/Cs - GREATER THAN 0F USING FIG-l.O. FIGURE MIN SUBCOOLING

a. Manually operate SI pumps as necessary and go to ECA-3.1.

SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED.

Step 1.

o PRZR level - GREATER THAN 5%

[30% 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
  • MOV-865
1) Open vent valves for 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

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Verify Adequate CCW Hx:

SW Flow To

a. Verify at least RUNNING three SW pumps
a. Manually start pumps as power 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) I only one SW pump running, THEN refer to AP-SW.2. LOSS OF SERVICE WATER.
3) Go to Step 36.
b. Verify AUX BLDG SW isolation valves - AT LEAST ONE SET OPEN
b. Manually align valves.
  • MOV-4615 and MOV-4734
  • MOV-4616 and MOV-4735 This Step continued on the next page.

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REV: 35 fJ E-3 STEAM GENERATOR TUBE RUPTURE P

l

~~~~~~~~~~~~~~PAGE 28 of 42l STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 29 continued from previous page)

c. Verify CNMT RECIRC fan annunciator C-2. HIGH TEMPERATURE ALARM - EXTINGUISHED
c. Perform the following:
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

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TM:IREV:35IE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored:

o IA to CNMT (AOV-5392) - OPEN

a. Continue with Step 36.

WHEN IA restored. THEN do Steps 30 through 35.

o IA pressure -

GREATER THAN 60 PSIG

b. Verify instrument bus D -

ENERGIZED

b. Energize MCC B. IF MCC B NOT available, THEN perform the following:
1) Verify MCC A energized.
2) Place instrument bus D on maintenance supply.
c. 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.

charging pump running.

Steps 31 through 35.

WHEN any THEN do

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINEDl 31 Check If Seal Return Flow Should Be Established:

a. Verify RCP 1 seal outlet temperature - LESS THAN 2350F
b. Verify RCP seal outlet valves -

OPEN

a. Go to Step 32.
b. Manually open valves as.

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 valve MOV-313
d. Perform the following:
1) Place MOV-313 switch to OPEN.
2) Dispatch AO to locally open MOV-313.
e. Verify RCP #1 seal leakoff flow

- LESS THAN 6.0 GPM

e. Perform the following:
1) Trip the affected RCP
2) Allow 4 minutes for pump coast down. THEN close the affected RCP seal discharge valve
  • 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

- GREATER THAN 0.8 GPM

f. Refer to AP-RCP.1. RCP SEAL MALFUNCTION.

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~~~~~~~~~~~~~~REV:

35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 32 Verify PRZR Level -

GREATER THAN 13% [40% adverse CNMT]

33 Establish Normal Letdown:

a. Establish charging line flow to REGEN Hx - GREATER THAN 20 GPM
b. Place the following switches to CLOSE:
  • Letdown orifice valves (AOV-200A. AOV-200B. and AOV-202)
  • Letdown isolation valve AOV-371
  • Loop B cold leg to REGEN Hx AOV-427
c. Place letdown controllers in MANUAL at 40% open
  • TCV-130
  • PCV-135 Continue with Step 34. WHEN PRZR level increases to greater than 13%

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

IF RCP seal return has been established. THEN establish excess letdown as follows:

o Place excess letdown divert valve. AOV-312. to NORMAL.

o Ensure CCW from excess letdown open. (AOV-745).

o Open excess letdown isolation valve AOV-310.

o Slowly open HCV-123 to maintain excess letdown temperature less than 1950F and pressure less than 100 psig.

o Adjust charging pump speed as necessary.

d. Reset both trains of XY relays for AOV-371 and AOV-427 -
e. Open AOV-371 and AOV-427 IF RCP seal return NOT established.

THEN consult TSC to determine if excess letdown should be placed in service.

f. Open letdown orifice valves as necessary
g. Place TCV-130 in AUTO at 105°F
h. Place PCV-135 in AUTO at 250 psig
i. Adjust charging pump speed and HCV-142 as necessary

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35 E-3 STEAM GENERATOR TUBE RUPTURE RVJ

-~~~~~~~~.

PAGE 32 of 42 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED I 34 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
b. Adjust RMW flow control valve in AUTO to 40 gpm
c. Verify the following:
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
d. Check VCT level:

o Level - GREATER THAN 20%

-OR-o Level - STABLE OR INCREASING

c. Adjust controls as necessary.
d. Manually increase VCT makeup flow as follows:
1) Ensure BA transfer pumps and RMW pumps running.

IF NOT.

THEN reset MCC C and CC D UV lockouts as necessary.

2) Place RMW flow control valve HCV-l11 in MANUAL and increase RMW flow.
3) Increase boric acid flow as necessary.

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REV: 35 li E-3 STEAM GENERATOR TUBE RUPTURE l

.PAGE 33 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 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 VCT
b. Manually align valves as necessary.

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

SP ACTION/EXPECTED RESPONSE l

lRESPONSE NOT OBTAINED 4

4 4

4 4

4 4

44 44 4

  • 4
  • 4
  • *
  • 44 4

4 CAUTION RCS AND RUPTURED SIG PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

4 44 4

  • 4 4
  • 4 4

4 4

44 4

4 4

4 4

4.4

  • 4 44 4
  • 36 Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakage:
a. Perform appropriate action(s) from table:

PRZR RUPTURED SIG NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%

o Increase Increase o Increase

[40% ADVERSE CNMT]

charging flow charging charging flow flow o Depressurize RCS o Maintain RCS and using Step 36b ruptured S/G pressure equal BETWEEN 13%

Depressurize RCS Energize Maintain RCS and

[40% ADVERSE CNMT]

using Step 36b PRZR ruptured S/G AND 50%

heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and

[65% ADVERSE CNMT]

using Step 36b PRZR ruptured S/G heaters pressure equal o Decrease charging flow GREATER THAN 75%

o Decrease Energize Maintain RCS and

[65% ADVERSE CNMT]

charging flow PRZR ruptured S/G heaters pressure equal

b. Control pressure using normal PRZR spray. if available. to obtain desired results for Step 36a
b. IF letdown is in service. THEN use auxiliary spray (AOV-296).

IF NOT. THEN use one PRZR PORV.

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE E

PAGE 35 of 42 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I 37 Monitor If CNMT Spray Should Be Stopped:

a. CNMT spray pumps - ANY RUNNING
b. Verify CNMT pressure - LESS THAN 4 PSIG
a. Go to Step 38.
b. Continue with Step 38.

WHEN CNMT pressure less than.4 psig, THEN do Steps 37c through f.

c. Reset CNMT spray
d. Check NaOH flow (FI-930) - NO FLOW
d. Place NaOH tank outlet valve 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
  • MOV-860D

~~~~~~~~~~~~~~

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REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l

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

a. Verify AC emergency busses energized by offsite power:

o Emergency DIG output breakers

- OPEN

a. Try to restore offsite power (Refer to ER-ELEC.1. RESTORATION OF OFFSITE POWER).

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 CST:

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

a. IF hotwell level increasing.

THEN direct RP to sample hotwells for activity.

o Verify hotwell level - STABLE

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

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PAGE 37 of '42l STP ACTION/EXPECTED RESPONSE lRESPONSE 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 B 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

E:

P TITLE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of' 42 STEP ACTION/EXPECTED RESPONSE l RESPONSE NOT OBTAINEDl h

4 4

4 X

4 4

4 4

4 4

4 4

4 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.

4 4

0 4

4 0

4 0

4 S

t*

0 0

4 0*

0 42 Check RCP Status

a. Both RCPs - STOPPED
b. Ensure conditions for starting an RCP.

o Bus 11A or 11B energized.

a. Stop all but one RCP and go to step 43.
b. IF conditions can NOT be met.

THEN perform the following:

1) Verify natural circulation (Refer to ATT-13.0.

ATTACHMENT NC).

o Refer to ATT-15.0, RCP START.

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

2) Go to step 43.

This Step continued on the next page.

EP:

TITLE:

REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 39 of 42 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED]

(Step 42 continued from previous page)

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

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

o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20°F using FIG-1.0, FIGURE IN 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.

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RV Il REV: 35 E-3 STEAM GENERATOR TUBE RUPTURE l

PAGE 40 of 42 STP ACTION/EXPECTED RESPONSE REPNENTOTIE 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 -

DEENERGIZED

b. Check intermediate range flux -

EITHER CHANNEL LESS THAN 10-10 AMPS

a. Go to Step 43e.
b. Perform the following:
1) IF neither intermediate range channel is decreasing. THEN initiate boration.
2) Continue with Step 44.

WHEN flux is LESS THAN 10-10 amps on any operable channel. THEN do Steps 43c through e.

c. Check the following:

o Both intermediate range channels - LESS THAN 10-10 AMPS

c. Continue with Step 44.

WHEN either condition met. THEN do Steps 43d and e.

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors --

ENERGIZED

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

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

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

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~~~~~~~~~~~~~~PAGE 41 of 42 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE
b. Perform the following:

o Open generator disconnects

  • 1G13A71
  • 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump
c. Verify adequate Rx head cooling:
1) Verify at least one control rod shroud fan - RUNNING
2) Verify one Rx compartment cooling fan - RUNNING
a. Dispatch AO to perform ATT-17.1, ATTACHMENT SD-2.
1) Manually start one fan as power supply permits (45 kw)
2) Perform the following:

o Dispatch AO to reset UW relays at NCC C and MCC D.

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

d. Verify ATT-17.0. ATTACHMENT SD-1

- COMPLETE

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~~~~~~~~~~~~~PAGE 42 of 42l 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 COOLDOWN USING STEAM DUMP. Step 1

-END-

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RV Ed:

~~~~~~~~~~~~REV:

35 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of l E-3 APPENDIX LIST TITLE

1)

RED PATH

SUMMARY

2) 3)

4) 5)

6) 7)

8) 9)

10) 11) 12) 13) 14) 15)

FIGURE MIN ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT ATTACHMENT FOLDOUT SUBCOOLING (FIG-i.0)

CNMT RECIRC FANS (ATT-4.0)

D/G STOP (ATT-8.1)

N2 PORVS (ATT-12.0)

NC (ATr-13.0)

SEAL COOLING (ATT-15.2)

RCP START (ATT-15.0)

RUPTURED SG (ATT-16.0)

SD-1 (AT-17.0)

SD-2 (ATT--17.1)

NO SW PUMPS (ATT-2.4)

LOSS OF OFFSITE POWER (ATT-8.5)

DIESEL AIR COMPRESSOR (ATT-11.2)

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REV: 35 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 7000F AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

c. HEAT SINK -

Narrow range level in all S/Gs less than 5%

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

d. INTEGRITY -

Cold leg temperatures decrease greater than 1000F in last 60 minutes AND RCS cold leg temperature less than 2850F

e. CONTAINMENT -

CNMT pressure greater than 60 psig

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35 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 DG 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 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 SG 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.

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