ML053260413

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Rev. 5 to Emergency Operating Procedure AP-SG.1, Steam Generator Tube Leak
ML053260413
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/04/2005
From: Holm D
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AP-SG.1, Rev 5
Download: ML053260413 (37)
v • d • e


Text

1503 Lake Road Ontario, New York 14519-9364 585.771.3000 Constellation Energy R.E. Ginna Nuclear Power Plant, LLC November 4, 2005 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 Dave A. Holm DAH/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):

AP Index AP-SG. 1, Rev 5 00)(

C C

f NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Frn 11/4/2005 9:42:23 am Page 1 of 2 INPUT PARAMETERS: TYPE:

PRAP STATUSVALUE(S):

EFQU 5 YEARS ONLY:

PRAP ABNORMAL PROCEDURE PROCEDURE NUMBER mrAIl.VV. I AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CVCS.3 AP-CW.1 AP-ELEC.1 AP-ELEC2 AP-ELEC.3 AP-ELEC.13/15 AP-ELEC.14/16 AP-ELEC.17/18 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.1 AP-RCC2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4 AP-RHR.1 AP-RHR.2 AP-SG.1 AP-SW.1 AP-SW.2 AP-TURB.1 PROCEDURE TIl, E LEAKAGE INTO THE COMPONENT COOUNG LOOP LOSS OF CCW DURING POWER OPERATION LOSS OF CCW-PLANT SHUTDOWN CONTROL ROOM INACCESSIBILITY CVCS LEAK LOSS OF ALL CHARGING FLOW LOSS OF A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)

LOSS OF BUS 13/15 LOSS OF SAFEGUARDS BUS 14116 LOSS OF SAFEGUARDS BUS 17118 ABNORMAL MAIN FEEDWATER FLOW LOSS OF INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAIANSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTMv1TY SHUTDOWN LOCA LOSS OF RHR.

LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDnlONS STEAM GENERATOR TUBE LEAK SERVICE WATER LEAK LOSS OF SERVICE WATER TURBINE TRIP Wn'HOUT RX TRIP REQURED EFFECT LAST REV DATE REVIEW 017 0613012004 0612612002 020 0412812005 06/2612002 017 04/28/2005 06/26/2002 023 10/28/2005 06/26/2002 014 06/30/2004 06/03/2002 005 04I10/2005 02/27/2004 012 09/17/2004 04/16/2003 028 0112112005 0612612002 O11 0611012004 06/26/2002 013 0112112005 06/26/2002 001 06/30/2004 09124/2003 009 01/21/2005 06/26/2002 008 01121/2005 06/26/2002 016 06/30/2004 06126/2002 018 0612612002 04/16/2003 015 06/30/2004 06/26/2002 009 06/30/2004 04/16/2003 012 04/1012005 2112015112 007 04/2812005 02125/2003 017 06/3012004 04/24/2003 017 06/3012004 04/1612003 012 06/30/2004 04/16/2003 O11 08630/2004 04/01/2002 017 03/18/2005 04/30/2003 019 04/30/2003 04/30/2003 015 04/05/2005 04/30/2003 005 11/0412005 06126/2002 021 09/17/2004 04121/2003 007 01/21/2005 11120/5013 015 06/10/2005 06126/2002 NEXT REVIEW ST 06126/2007 EF 06/26/2007 EF 06/26/2007 EF.

06126/2007 EF 06/03/2007 EF 02/27/2009 EF 04/16/2008 EF 06126/2007 EF 06/26/2007 EF 06/26/2007 EF 09/24/2008 EF 06/26/2007 EF 0612612007 EF 06/26/2007 EF*

04/1612008 EF 06126/2007 EF 04/16/2008 EF 01122/2007 EF 02/25/2008 EF 04124/2008 EF 04/16/2008 EF 04/16/2008 EF 0122/2007 EF 04/30/2008 EF 04/30/2008 EF 04/30/2008 EF 06126/2007 EF 04/21/2008 EF

.10/31/2008 EF 06/26/2007 EF

(

C

(

NPSP0200 E66429 Ginna Nuclear Power Plant PROCEDURE INDE)

Fri 11/412005 9:42:23 am Page 2 of 2 INPUT PARAMETERS: TYPE:

PRAP STATUSVALUE(S):

EF, QU 5 YEARS ONLY:

PRAP ABNORMALPROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 021 0411012005 06/26/2002 06/26/2007 EF AP-TURB.3 TURBINEVIBRATION 014 0710112005 06/26/2002 06/2612007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 018 04110/2005 04/30/2003 04/3012008 EF AP-TURB.5 RAPID LOAD REDUCTION 008 04110/2005 06126/2002 06/26/2007 EF PRAP TOTAL 34 GRAND TOTAL 34

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 1 of 33 GINNA STATION CONTROLLED COPY NUMBER C

RESPONSIBL9 MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

Of EOP:

TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 2 of 33 A. PURPOSE -

This procedure provides the necessary instructions to be taken in the event of a Steam Generator tube leak within the capacity of the charging pumps.

B.

ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITION - This procedure is entered from:
a. AP-RCS.1, REACTOR COOLANT LEAK, if S/G tube leak is indicated.
b. AR-PPCS-1, SGTL INDICATED, when R-15A-5 is increasing for greater than one minute.
c. AR-RMS-15, R15 AIR EJECTOR, AR-RMS-19, R-19 STEAM GEN
BLOWDOWN, when SG sample indicates a tube leakrate of greater than 5 gpd.
d. AR-RMS-31, R31 STEAM LINE A and AR-RMS-32, R32 STEAM LINE B when other indications of SG tube leakage exist.
e. Shift Supervisor discretion.
2.

SYMPTOMS -

Symptoms of STEAM GENERATOR TUBE LEAK are:

a. Primary to secondary tube leak rate in one S/G has been verified by sampling to be greater than or equal to 5 gpd.
b. Either of the following indicating a leak rate of greater than or equal to 5 gpd AND increasing for greater than one minute:

o R15A5G OR o Sping (using R15A5 conversion table, Curve Book #06-004)

STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 1 Monitor PRZR Level -

STABLE AT PROGRAM LEVEL IF PRZR level decreasing. THEN start additional charging pumps and increase speed as necessary to stabilize PRZR level.

IF PRZR level continues to decrease. THEN close letdown isolation. AOV-427 and excess letdown AOV-310.

IF available charging pumps are running at maximum speed with letdown isolated. AND PRZR level is decreasing. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

  • 2 Monitor S/G Tube Leak Rate:..
a. Estimate S/G tube leak rate:

o Charging/Letdown mismatch o A VCT o PPCS Point R15A5G o

SPING (using R15A5 conversion table, Curve Book #06-004)

b. Check total RCS to secondary leak rate - LESS THAN 1 GALLON PER MINUTE (1440 GPD)
b. Go to Step 8.

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TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 4 of 33 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 3 Trend SIG Leak Rate:

a. While continuing.with this procedure. perform Part A of ATT-16.1, ATTACHMENT SGTL
b. Determine S/G leak rate:

o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table. Curve Book #06-004)

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 5 of 33 ACTION/EXPECTED RESPONSEINED 4 Determine If Shutdown Required:

a. SIG tube leak rate - GREATER
a. Perform-the following:

THAN OR EQUAL TO 5 GPD

1) Notify higher supervision
2) Return to guidance in effect
b. S/G tube leak rate - GREATER
b. Perform the following:

THAN OR EQUAL TO 30 GPD

1) Notify higher supervision
2) Determine S/G tube leak rate at least once per hour o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table. Curve Book #06-004)

3) IF leak rate is stable OR decreasing for 4 consecutive hours. THEN reduce leak rate trending to at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table. Curve

- Book #06-004)

4) Return to Step 1.

This Step continued on the next page.

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 6 of 33

_STEP _ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 4 continued from previous page)

c. S/G tube leak rate - GREATER
c. Perform the following:

THAN OR EQUAL TO 75 GPD

1) Notify higher supervision
2) Determine S/G leak rate every 15 minutes (IF performing a procedural loop. THEN use trending rates previously determined in Step 5) o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table, Curve Book #06-004)

3) Go to Step 5.
d. S/G tube leak rate - STABLE OR
d. Perform the following:

INCREASING

1) Notify higher supervision
2) IF the leak rate spiked to greater than 144 gpd, THEN go to Step 6.

IF the leak rate spiked to less than 144 gpd but has remained greater than 75 gpd for at least one hour, THEN go to Step 6.

IF the leak rate spiked to less than 144 gpd AND has decreased to less than 75 gpd within one hour. THEN return to Step 4b.

e. Go to Step 6.

EOP:

TIRLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 7 of 33 STEP ACTION/EXPECTED RESPONSE H RESPONSE NOT OBTAINEDl 5 Determine Trending Requirements:

a. SIG leak rate - INCREASES LESS' THAN 10% DURING A ONE HOUR PERIOD o

PPCS point R15A5G o

SPING (using R15A5 conversion table. Curve Book #06-004) o Grab sample

b. Trend S/G leak rate at least once per hour o

PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table. Curve Book #06-004)

a. Return to Step 1.
c. Review E-3, STEAM GENERATOR TUBE RUPTURE.
d. At least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> since one-hour leak rate trending began.
e. S/G leak rate - INCREASES LESS THAN 10% DURING the last 24 HOURS
d. Return to Step 1.
e. Return to Step 1.
f. Trend S/G leak rate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table, Curve Book #06-004)

g. Return to Step 1.

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 8 of 33 STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 6 Confirm S/G Leak Rate:

a. At least two independent indications - TREND IN THE SAME DIRECTION o

R-31

a. IF an instrument failure can be confirmed, THEN return to guidance in effect.

Otherwise return to Step 4.

o R-32 o PPCS point R15A5G OR SPING (using R15A5. conversion table, Curve Book #06-004) o R-15 o R-19 o Grab samples (only allowed for confirming leaks less than 144 gpd which increase at less than 30 gpd/hr)

b. Notify higher supervision
c. While continuing with this procedure, perform Parts A AND B of ATT-16.1. ATTACHMENT SGTL

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REV:

5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 9 of 33

  • r CAUTION

-MAINTAIN PRZR LEVEL AT 50% TO ACCOMMODATE RCS SHRINKING DURING PLANT SHUTDOWN AND COOLDOWN NOTE:

Measured leakrate depends.on RCS activity level, which may increase or decrease during power reduction, depending on fuel condition.

Therefore, once the power reduction has begun, R-15A should NOT be used to determine if the rate of power reduction should be changed.

7 Initiate Plant Shutdown

a. Determine S/G leakrate every 15 minutes o PPCS point R15A5G

-OR-o SPING (using R15A5 conversion table, Curve Book #06-004)

b. Check SIG leak rate - INCREASING LESS THAN 30 GPD/HR o Leak increases less than 15 gpd in 30 minutes (R15A5G or SPING) o Grab samples indicate less than 30 GPD increase in 60 minutes
b. Perform the following:
1) Reduce power to less than 50%

RTP within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of exceeding 30 gpd/hr.

(Refer to AP-TURB.5. RAPID LOAD REDUCTION)

2) Be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of exceeding 30 gpd/hr.

(Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN)

3) Go to Step 7g.

This Step continued on the next page.

EOP:

TITLE:REV:

5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 10 of 33 STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED (Step 7 continued from previous page)

c.

Check R15A5 -

OPERABLE

c. Perform the following:
1) Be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of exceeding 75 gpd.

(Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN)

2)

Go to Step 7g.

d. Check S/G leak rate -

HAS REMAINED LESS THAN 144 GPD SINCE LEAK INITIATION

d. Perform the following:
1) Be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of exceeding 144 gpd.

(Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN)

2)

Go to Step 7g.,

e. Check S/G leak rate -

REMAINED GREATER THAN 75 GPD FOR GREATER THAN ONE HOUR

e. Return to Step 1.
f.

Be in Mode 3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of exceeding 75 gpd (Refer to 0-2.1. NORMAL SHUTDOWN TO HOT SHUTDOWN)

g. Refer to ITS o

LCO 3.4.13 o

LCO 3.4.16 o

LCO 3.7.14

h. Check reactor - IN MODE 3
h. Return to Step 7a.
i.

Go to Step 28.

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 11 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

8 Initiate Load Reduction

a. Notify higher supervision.
b. Verify rods in AUTOMATIC
c. Reduce turbine load in Auto as follows:
1) Place Turbine EH Control in OPER PAN.. IMP PRESS IN. if desired.
2) Select rate of 3%/min on thumbwheel.
3) Reduce the setter to zero.

.4) Depress the GO button.

d. Initiate boration at -2 gal/%

load reduction.

e. Place PRZR backup heaters switch to ON.
f. Transfer 4160V Auxiliary load from #11 Transformer.

(Refer to ATT-23.0. ATTACHMENT TRANSFER 4160V LOADS)

b. Perform the following:
1) Place rods to MANUAL.
2) Adjust rods to match Tavg and Tref.
c. IF Auto Control is inoperable, THEN reduce turbine load in manual at 3%/min.

EOP:

TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 12 of 33 ACTION/NSEECOTDOBTAINEDEI a

a C*

.I*

CAUTION.

EXTREME AND RAPID ROD MOTION TO MITIGATE POWER EXCURSIONS AND SHOULD BE AVOIDED.

TAVG SWINGS MAY RESULT IN LARGE

-a

  • 9 Monitor RCS Tavg o

Tavg - GREATER THAN 545°F o Tavg - LESS THAN 566°F Verify control rods responding in AUTO.

IF NOT, THEN place rods to MANUAL and adjust control rods to restore Tavg within limits.

IF Tavg is outside limits AND can NOT be controlled. THEN trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

10 While Continuing With This Procedure, Perform The Following:

a. Perform parts A AND B of ATT-16.1. ATTACHMENT SGTL
b. Dispatch an AO to perform T-35H.

NUCLEAR HOUSE HEATING STEAM TO BOILER STEAM SUPPLY CHANGE OVER 11 Request RP to obtain the, following-samples:

STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl NOTE:

It is permissible to operate RCPs for limited periods without seal injection, provided CCW is being supplied to the thermal barriers.

12 Check IA Available To CNMT o IA pressure - > 60 psig o Instr Air to CNMT Isol Valve.

AOV-5392 - OPEN Control PRZR level and pressure as follows:

o Adjust load reduction rate o Ensure control rods are moving to control Tavg o IF CCW supplied to BOTH RCP thermal barrier heat exchangers, THEN start/stop charging pumps as necessary to control PRZR level o

Operate proportional and backup heaters to control PRZR pressure NOTE:

With PRZR pressure controller 431K in manual. PORV-431C will not operate in the automatic mode.

(Refer to TR 3.4.3)

  • 13 Monitor PRZR Pressure -

TRENDING TO 2235 PSIG IN AUTO Control PRZR pressure by one of the following:

  • 431K in MANUAL
  • Manual control of PRZR heaters and sprays IF PRZR pressure can NOT be controlled manually. THEN refer to AP-PRZR.1. ABNORMAL PRESSURIZER PRESSURE.

. EOP:

TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK

.PAGE 14 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 14 Monitor MFW Regulating Valves RESTORING S/G LEVEL TO 52%

IN AUTO Perform the following:

a. Place affected S/G(c) MFW regulating valve in MANUAL
b. Restore S/G level to 52%

IF S/G level can NOT be controlled manually, THEN refer to AP-FW.1, ABNORMAL MAIN FEEDWATER FLOW.

  • 15 Monitor PRZR Level -

TRENDING TO PROGRAM IN AUTO CONTROL Perform the following:

a. Place affected charging pumps in MANUAL
b. Adjust charging pump speed to restore PRZR level to program IF PRZR level can NOT be controlled manually. THEN refer to AP-RCS.1.

REACTOR COOLANT LEAK.

  • 16 Check Steam Dump Status:

o Annunciator G-15. STEAM DUMP ARMED - LIT o Steam dump operating properly in AUTO IF steam dump required but NOT operating. THEN perform the following:

a. Place STEAM DUMP MODE SELECTOR

-Switch to MANUAL.

b. Place steam dump controller, HC-484. to MANUAL.
c. Operate steam dump valves manually as necessary.

EOP:

TITLE:

R V AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 15 of 33

_STEP _ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Adjust Boric Acid Addition Rate As Necessary To (refer to OPG-REACTIVITY-CALC):

o Maintain or return A Flux to the target band o Maintain control rods above insertion limits o Match Tavg and Tref o Compensate for Xenon CAUTION IF CONDENSATE BOOSTER PUMP "A" IS OPERATING IN PARALLEL WITH EITHER CONDENSATE BOOSTER PUMP "B" OR "C" THEN CONDENSATE BOOSTER PUMP "B" OR "C"t SHOULD BE SECURED FIRST IN ORDER TO MINIMIZE OPERATING AT MINIMUM FLOW CONDITIONS.

NOTE: The load reduction should not be delayed to perform the remaining steps.

18 Check If Condensate Booster Pumps Should Be Secured

a. Power < 65% OR Trim Valve
a. WHEN power < 65% OR Trim Valve V-9508G indicates > 80% open V-9508G indicates 80% open. THEN continue with Step 18b.
b. Place the auto condensate booster pump to the trip position
c. Stop one condensate booster pump
d. WHEN condensate system pressures stabilize. THEN stop the remaining condensate booster pump

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 16 of 33 ACTION/EXPECTED RESPONSENE 19 Check If One MFW Pump Should Be Secured

a. Power < 50%
a. WHEN power < 50%. THEN continue with step 19b.
b. Verify at least one MEWP Seal Booster pump in service
c. Two MEW Pumps running
b. Notify AO to start one MFWP Seal Booster pump
c. Go to Step 20.
d. Close discharge valve for the pump to be secured

. MEW Pump A - MOV-3977

  • MEW Pump B - MOV-3976
e. Stop the desired MEW Pump
f. Close the secured MEW pump recirc valve by placing the control switch in pull stop
g. Close the service water block valve to the secured MEW pump oil cooler

. MEW Pump A - V-4701

. MEW Pump B - V-4702 20 Verify Trim Valves Controlling Condensate System Pressure In Auto (300-375 PSIG)

Place controller in manual and control pressure between 300-375 psig 111

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RREV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 17 of 33 AtO/XPECTEDREPN

RESPONSE

NO BAN CAUTION IF MAIN FEEDWATER FLOW SHOULD DECREASE TO 25% OF FULL POWER VALUE

(.825 E+6 LBM/HR) PRIOR TO THE AMSAC SYSTEM AUTOMATICALLY BLOCKING. THEN A TURBINE TRIP AND AUX FEED PUMPS START COULD RESULT.

21 Check ANSAC System Status.

a. Power < 35% (-150 psig first stage pressure)
b. Verify AMSAC Auto Block Status Light is ON 22 Check Heater Drain Tank Pump Status
a. Continue with Step 22. WHEN power < 35% (-150 psig first stage pressure), THEN do Step 21b.
b. Place AMSAC Manual Block switch to the BLOCK position
a. Generator load < 175 MWe
a. WHEN generator load < 175 MWe.

THEN continue with Step 22b.

b. Stop one Heater Drain Tank Pump
c. WHEN Beater Drain Tank level control is stable. THEN stop the second Heater Drain Tank Pump

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 18 of 33 STEP ACTION/EXPECTED RESPONSEREPNE OT BAI D

23 Check MFW Regulating Bypass Vlv Status

a. Power < 30%
a. WHEN power < 30%. THEN continue with Step 23b.
b. MFW Regulating Bypass Vlvs in AUTO
  • HCV-480

. HCV-481

b. Perform the following:
1) Slowly open the MEW Regulating Bypass Vlvs while verifying the associated MEW Regulating Vlv compensates by closing slightly
2) Place MFW Regulating Bypass Vlvs in AUTO 24 Align Systems for Low Power Operation
a. Place AOV-3959. CNDST Bypass Vlv to CLOSE
b. Place LC-107. Hotwell Level Control, to MANUAL at 50%
c. Generator load < 100 MWe
c. WHEN generator load < 100 MWe, THEN continue with step 24d.
d. Open turbine drain valves

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 19 of 33 P

ACTION/EXPECTED RESPONSE l[RESPONSE NOT OBTAINED 25 Check If Turbine Should Be Tripped:

a. Check turbine load -
a. WHEN turbine load is

THEN continue with Step 25b.

b. Trip the turbine.

c'. Check turbine stop valves -

-CLOSED

c. Direct an AO to locally trip the turbine by placing the red TRIP lever to TRIP (west end of turbine).

IF the turbine will NOT trip.

THEN close both MSIVs.

EOP:

TITLE:

REV:

5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 20 of 33 ACTION/EXPECTED RESPONSENED 26 Verify Proper Operation Of I

Steam Dump:

a. Verify annunciator G-15. STEAM DUMP ARMED - LIT
b. Condenser steam dump operating in AUTO
a. Place steam dump mode selector switch to MANUAL.
b. IF steam dump NOT available.

THEN perform the following:

1) IF power is greater than 8%.

THEN ensure reactor trip and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

2) Adjust intact SIG ARV setpoint to 1005 psig and verify proper operation.
c. Tavg - TRENDING TO PROGRAM

.c. IF temperature less than 547 0F and decreasing, THEN perform the following:

1) Stop dumping steam
2) IF cooldown continues. THEN close both MSIVs.

IF temperature greater than 5470 and increasing. THEN dump steam to stabilize and slowly decrease temperature to 5470F.

IF Tavg can NOT be controlled, THEN manually trip the reactor and go to E-O. REACTOR TRIP OR SAFETY INJECTION.

EOP:

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REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 21 of 33 NOTE: Transition to E-O is NOT required when the reactor trip breakers are opened in the following step.

27 Shutdown The Reactor

a. Place rode in MANUAL
b. Drive control rode until < 1% RTP
c. Press Rx trip pushbutton
d. Verify Rx Trip breakers open
d. Dispatch AO to locally open reactor trip breakers
e. Verify MRPI indicates all control and shutdown rode on bottom NOTE:

The following step is intended to start an RCS boration at the earliest opportunity. The boration endpoint is determined in Step 34.

28 Initiate RCS Boration At

.Maximum Rate Using FCV-11OA

a. Open AOV-11OB. Reactor Makeup to Charging Pump Suction.

I IF normal boration can NOT be performed, THEN align charging pump suction to RWST o LCV-112B - OPEN o LCV-112C - CLOSED

b. Start BOTH BAST pumps
c. Place FCV-11OA controller to MANUAL AND adjust to full open.

I I

I

d. Verify boration flow.

EOP:

TITLE:

REV:

5 AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 22 of 33 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF ANY SIG LEVEL ABOVE 52%,

THEN AFW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT SIG ISOLATION.

29 Check S/G Feed Flow Status:

a. Manually start both MDAFW pumps
b. Verify MDAFW Pump flow -
b. Perform the following:

SUFFICIENT FLOW TO MAINTAIN S/G LEVELS

1) Establish MFW flow using MEW regulating valve bypass valves.

IF MFW NOT available. THEN perform the following:

a) Manually start TDAFW pump from the non-leaking SIG and establish flow.

b) Adjust feed flow to restore S/G level to 52%.

c) Go to Step 29c.

2) Adjust feed flow to restore S/G level to 52%.
3) Go to Step 31.
c. Verify MFW flow control valves -
c. Place A and B MFW regulating and CLOSED bypass valve controllers in manual at 0% demand.

. MFW regulating valves

  • MFW bypass valves
d. Close pump discharge valve for the MFP to be secured:
  • MOV-3977. A MFW pump
  • MOV-3976, B MFW pump This Step continued on the next page.

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TITLE:I REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK

.PAGE 23 of 33 STEP ACTION/EXPECTED RESPONSEREPNEOTBAID (Step 29 continued from previous page)

e. Stop the running MFW pump
f. Close the secured MFW pump recirc valve by placing the control switch in PULL STOP
g. Place A and B MEW regulating and bypass valve controllers in manual at 0% demand
h. Adjust AEW pump flow to restore S/G level to 52%.

30 Establish Normal AFW Pump Shutdown Alignment:

a. Place AFW bypass switches to DEE
b. Close MDAEW pump discharge valves
  • MOV-4007

. MOV-4008

c. Adjust AEW bypass valves to control S/G levels at 52%

. AOV-4480

  • AOV-4481

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TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 24 of 33 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 31 Complete Leaking SIG Isolation:

a. Close leaking SIG MSIV - LEAKING
a. Perform the following:

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 leaking S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G, parts A for the leaking S/G AND B).
b. Dispatch AO to complete leaking S/G isolation (Refer to ATT-16.0. ATTACHMENT RUPTURED S/G part A for the leaking S/G)

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TITLE:

REV:

5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 25 of 33 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINEDl 32 Check Leaking S/G Level:

a. Narrow range level - GREATER THAN 17%
a. Perform the following:
1) Maintain feed flow to leaking SIG until level greater than 17%.
2) Continue with Step 33.

WHEN leaking S/G level greater than 17%. THEN do Steps 32b through f.

b. Close MDAFW pump discharge valve to leaking SIG
b. Dispatch AO to locally close valve.

SIG A. MOV-4007

  • S/G B. MOV-4008
c. Close MDAPW pump bypass valve for leaking S/G
  • SIG A, AOV-4480
  • S/G B. AOV-4481
d. Pull stop MDAFW pump for leaking S/G
e. Close TDAFW pump flow control valve to leaking S/G

. S/G A. AOV-4297

. SIG B. AOV-4298

f. Verify MDAFW pump crosstie valves -

CLOSED

e. Dispatch AO with locked valve key to locally close TDAFW pump manual feedwater isolation valve to leaking S1G.

SIG A. V-4005 S/G B. V-4006

f. Manually close valves.
  • MOV-4000A

. MOV-4000B

STE ACTION/EXPECTED RESPONS RESPONSE NOT OBTAINE

  • 33 Reduce RCS Pressure To Minimize Tube Leak:
a. Maintain RCS pressure low in the desired operating range (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)
b. WHEN RCS pressure is less than 1950 psig, THEN place SI block switches to BLOCK

. Train A

. Train B

c. Verify SAFETY INJECTION BLOCKED status light - LIT

')

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TITLE:

REV: 5 AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 27 of 33 ACTIN/EX ECTEORESOBNSE I

  • O-* * * * * * * * * * * * * * * * * * * *
CAUTION OPERATION OF BOTH RCPS IS PREFERRED TO SUBSEQUENT COOLDOWN.

MINIMIZE REQUIRED BORON ADDITION FOR 34 Increase RCS Boron

a. Determine desired RCS boron concentration for subsequent cooldown (Refer to ATT-16.2.

ATTACHMENT RCS BORON FOR SGTL)

b. Borate RCS to desired concentration using FCV-llOA
b. IF normal boration can NOT be performed, THEN align charging pump suction to RWST o LCV-112B - OPEN o LCV-112C - CLOSED
c. If desired. request Reactor Engineer evaluate an alternate desired RCS boron concentration to maintain SDM during subsequent cooldown

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TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 28 of 33 I.

_STE P

_ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED 35 Establish Normal Shutdown Alignment:

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

ATTACHMENT SD-2.

b. Perform the following as necessary:

o Open generator disconnects

  • IG13A71

. 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 and place in PULL STOP (Refer to T-5F, STARTING OR STOPPING THE CONDENSATE PUMPS)

c. Verify Bus 11A and Bus liB energized - BOTH BUSSES GREATER THAN 4 KV
c. IF either bus NOT energized.

THEN refer to 0-6.9.2.

ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/BUS 12B.

d. Dispatch AO to perform ATTACHMENT SD-1 ATT-17.0.

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TITLE:I REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 29 of 33 36 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
c. Check the following:

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

a. Go to Step 36e.
b. Continue with Step 37.

WHEN flux is less than 10-10 amps on any operable channel. THEN do Steps 36c, d and e.

c. Continue with Step 37.

WHEN either condition met. THEN do Steps 36d 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.1, SR MALFUNCTION, and go to Step 37.

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

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TITLE:

AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 30 of 33 P

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Check Rx Trip Breakers - OPEN DO NOT continue until Rx trip breakers open.

38 Check RCS Boron Concentration

a. RCS Boron Concentration - equal to or greater than required for cooldown to 500 degrees per step 34
b. Verify MRPI indicates all control and shutdown rods on bottom
a. Continue boration. WHEN RCS boron equal to or greater than required value, THEN go to step 38b.
b. Borate an additional 650 gallons of boric acid for each rod not fully inserted. WHEN boration complete. THEN continue with Step 39.

39 Initiate RCS Cooldown To 500 degrees:

a. Check leaking S/G MSIV - CLOSED
a. Perform the following:
1) Manually or locally initiate steam dump from intact S/G using S/G ARV
2) Go to step 39d
b. Place Steam Dump Mode Selector switch to MANUAL
c. Initiate dumping steam to condenser from intact SIG
c. IF condenser steam dumps not available, THEN manually or locally initiate steam dump from intact S/G using S/G ARV
d. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 500F/HR
e. Maintain RCS pressure low in the desired operating range (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)

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REV: 5l AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 31 of 33 STEP ACTION~/EXPECTED RESPONSEREP NE OT BAI D

40 Notify RP To Obtain Primary Samples Required By ITS LCO 3.4.16 (load reduction > 15%

in one hour) 41 Check RCS Boron Concentration

a. RCS boron - equal to or greater than required for cooldown to 450 degrees per step 34
a. Perform the following:
1) Stop cooldown AND maintain stable RCS temperature above 500 degrees and stable.
2) Continue boration. WHEN RCS boron equal to or greater than required value, THEN go to step 41b.
b. Verify MRPI indicates all control and shutdown rods on bottom
b. Request Rx Engineer determine amount of boration required due to rods not fully inserted.
c. Borate to 2.45% CSD Curve per 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN -

MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN

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TITLE:

REV: 5 AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 32 of 33 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 42 Cooldown RCS To 450 Degrees

a. Initiate dumping steam
b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 50OF/HR
c. Maintain RCS pressure low in the desired operating range
d. WHEN RCS pressure is less than 1500 psig. THEN isolate SI ACCUMs as follows:
1) 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
2) Close SI ACCUM outlet valves
  • ACCUM A. MOV-841
  • ACCUM B. MOV-865
3) Locally reopen breakers for MOV-841 and MOV-865
e. Check RCS temperature - LESS
e. Continue RCS cooldown THAN 460 DEGREES
f. Stop the cooldown AND maintain RCS between 450 and 460 degrees
g. WHEN RCS pressure equals leaking S/G pressure. THEN maintain stable RCS pressure

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TITLE:

REV: 5 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 33 of 33 ACTION JEXPECTED RESPONSE

'RESPONSE NOT OBTAINED 43 Check Normal Or Excess Letdown -

IN SERVICE IF normal letdown desired, THEN establish normal letdown (Refer to ATT-9.O. ATTACHMENT LETDOWN)

IF normal letdown NOT available.

THEN establish excess letdown if desired (Refer to ATT-9.l, ATTACHMENT EXCESS L/D).

44 Evaluate Long Term Plant Status:

a. Consult the following groups:
  • Operations Staff
  • Plant Engineering Staff
  • Chemistry
b. RCS boron - MEETS 2.45% CSD CURVE PER 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN
b. Perform the following:
1) Continue RCS boration to CSD concentration.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

2) Continue with Step 44e. WHEN RCS boron meets 2.45% CSD curve requirement, THEN do steps 44c and d.
c. Stop RCS boration
d. Restore RCS makeup to desired alignment
  • e. Determine if condensate cleanup is desired
f. Determine appropriate cooldown method

-END-

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TITLE:

REV 5

AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 1 of 1 AP-SG.1 APPENDIX LIST.

TITLE

1) ATTACHMENT TRANSFER 4160V LOADS (ATT-23.0)
2) ATTACHMENT SD-I' (ATT-17.0)
3) ATTACHMENT SD-2 (ATT-17.1)
4) ATTACHMENT RUPTURED S/G (ATT-16.0)
5) ATTACHMENT SGTL (ATT-16.1)
6) ATTACHMENT RCS BORON FOR SGTL (ATT-16.2)
7) ATTACHMENT EXCESS L/D' (ATT-9.1)
8) ATTACHMENT LETDOWN (ATT-9.0)
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