ML023390115

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Emergency Operating Procedures for R. E. Ginna Nuclear Power Plant
ML023390115
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/21/2002
From: Widay J
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, NRC/NRR/DLPM/LPD1
References
NPSP0200
Download: ML023390115 (36)
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Text

--A R 1MT ~' A Subsidiaryof RGS Energy Group, Inc ROCHESTER GAS AND ELECTRIC CORPORATION

  • 89 EAST AVENUE, ROCHESTER, N Y 14649-0001
  • 716-771-3250 wwwrge com JOSEPH A. WI DAY VICEPRESIDENT & PLANT MANAGER GINNA STATION November 21, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Robert Clark Project Directorate I Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Clark:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, AWiday 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):

AP Index AP-SG.1, Rev 3

REPORT NO 01 REPORT: NPSP0200 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX C 11/21/02 PAGE- 1 C

DOC TYPE PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRRSSP STATUS- EF QU 5 YEARS ONLY-PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 06/26/02 06/26/02 06/26/07 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 017 11/19/02 06/26/02 06/26/07 EF AP-CCW. 3 LOSS OF CCW - PLANT SHUTDOWN 015 11/19/02 06/26/02 06/26/07 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 018 06/26/02 06/26/02 06/26/07 EF AP-CVCS. 1 CVCS LEAK 013 06/26/02 06/03/02 06/03/07 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 003 06/26/02 02/26/99 02/26/04 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 011 06/26/02 05/01/98 05/01/03 EF AP-ELEC 1 LOSS OF 12A AND/OR 12B BUSSES 023 06/26/02 06/26/02 06/26/07 EF AP-ELEC 2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 06/26/02 06/26/02 06/26/07 EF AP-ELEC. 3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 011 06/26/02 06/26/02 06/26/07 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 004 06/26/02 06/26/02 06/26/07 EF AP-ELEC. 17/18 LOSS OF SAFEGUARDS BUS 17/18 004 06/26/02 06/26/02 06/26/07 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 014 07/25/02 06/26/02 06/26/07 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/02 05/01/98 05/01/03 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 013 06/26/02 06/26/02 06/26/07 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 008 06/26/02 05/14/98 05/14/03 EF AP-RCC.2 RCC/RPI MALFUNCTION 010 06/26/02 01/22/02 01/22/07 EF AP-RCC.3 DROPPED ROD RECOVERY 005 06/26/02 02/27/98 02/27/03 EF AP-RCP.1 RCP SEAL MALFUNCTION 014 06/26/02 05/01/98 05/01/03 EF AP-RCS.1 REACTOR COOLANT LEAK 016 06/26/02 05/01/98 05/01/03 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 011 06/26/02 05/01/98 05/01/03 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 010 06/26/02 04/01/02 01/22/07 EF AP-RCS.4 SHUTDOWN LOCA 012 06/26/02 05/01/98 05/01/03 EF AP-RHR.1 LOSS OF RUR 018 07/25/02 05/01/98 05/01/03 EF

REPORT NO. 01 REPORT: NPSP0200 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX 11/21/02 PAGE- 2

(

DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRRSSP STATUS EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-RHR .2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 012 05/30/02 03/31/00 03/31/05 EF AP-SG. 1 STEAM GENERATOR TUBE LEAK 003 11/21/02 06/26/02 06/26/07 EF AP-SW. 1 SERVICE WATER LEAK 017 06/26/02 06/03/98 06/03/03 EF AP-SW.2 LOSS OF SERVICE WATER 002 06/26/02 10/31/01 10/31/06 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.2 TURBINE LOAD REJECTION 018 06/26/02 06/26/02 06/26/07 EF AP-TURB.3 TURBINE VIBRATION 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 016 07/25/02 05/01/98 05/01/03 EF AP-TURB.5 RAPID LOAD REDUCTION 006 06/26/02 06/26/02 06/26/07 EF TOTAL FOR PRAP 33

EOP: TITLE: RV AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 1 of 32 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER AQ3 RESPONSIBLE JNAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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.l, REACTOR COOLANT LEAK, if S/G tube leak is indicated.
b. AR-PPCS-l, SGTL INDICATED, when R-15A-5 is increasing for greater than one minute.
c. AR-RMS-15, RI5 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 RI5A5G OR o Sping (using RI5A5 conversion table, Curve Book #06-004)

EOP: TITLE: REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 3 of 32 SE ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI

  • 1 Monitor PRZR Level - STABLE IF PRZR level decreasing. THEN AT PROGRAM LEVEL 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-0. REACTOR TRIP OR SAFETY INJECTION.

  • 2 Monitor S/G Tube Leak Rate:
a. Estimate SIG 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 b. Go to Step 8.

leak rate - LESS THAN 1 GALLON PER MINUTE (1440 GPD)

" EOP: TITLE: REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 4 of 32 3 Trend S/G Leak Rate:

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

o PPCS point Rl5A5G

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

"EOP: TITLE: R REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 5 of 32 SE ACTION/EXPECTED RSPONSEI RESPONSE NOT OBTAINEDI 4 Determine If Shutdown Required:

a. S/G 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 samples, 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.

EOP: TITLE: REV 3 AP-SG.1 STEAM GENERATOR TUBE LEAK

- PAGE 6 of 32 STEPH ACTIoNExP=ECT RESPONSEI RESPONSE NOT OBTAINEDI (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) I__F 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 ieak 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: TITLE: REV 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 7 of 32 5 Determine Trending Requirements:

a. SIG leak rate - INCREASES LESS a. Return to Step 1.

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)

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 d. Return to Step 1.

leak rate trending began.

e. SIG leak rate - INCREASES LESS e. Return to Step 1.

THAN 10% DURING the last 24 HOURS

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.

6 Confirm S/G Leak Rate:

a. At least two independent a. IF an instrument failure can be indications - TREND IN THE SAME confirmed. THEN return to DIRECTION guidance in effect. Otherwise return to Step 4.

"o R-31 "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

EOP: TITLE: REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 9 of 32 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 S/G leak rate - INCREASING b. Perform the following:

LESS THAN 30 GPD/HR

1) Reduce power to less than 50%

"o Leak increases less than 15 RTP within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of gpd in 30 minutes (R15A5G or exceeding 30 gpd/hr. (Refer SPING) to AP-TURB.5. RAPID LOAD REDUCTION)

"o Grab samples indicate less than 30 GPD increase in 60 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 /> minutes 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: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 10 of 32 (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 d. Perform the following:

REMAINED LESS THAN 144 GPD SINCE LEAK INITIATION 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 e. Return to Step 1.

GREATER THAN 75 GPD FOR GREATER THAN ONE HOUR

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 26.

S EOP: TITLE: REV3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 11 of 32 SE ACTION/EXPECTED RESPOSEt RESPONSE NOT OBTAINEDI 8 Initiate Load Reduction

a. Notify higher supervision.
b. Verify rods in AUTOMATIC b. Perform the following:
1) Place rods to MANUAL.
2) Adjust rods to match Tavg and Tref.
c. Reduce turbine load in Auto as c. IF Auto Control is inoperable.

follows: THEN reduce turbine load in manual at 3%/min.

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. Steam dump armed and operating: d. IF steam dump required but NOT operating, THEN perform the "o Annunciator G-15, STEAM DUMP following:

ARMED - LIT

1) Place STEAM DUMP MODE "o Steam dump operating properly SELECTOR Switch to MANUAL.

in AUTO

2) Place steam dump controller, HC-484, to MANUAL.
3) Operate steam dump valves manually as necessary.
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)
  • r * - * * * * * * *r * * * * *r * * * *
  • S * * * *r
  • S S * * * * * * * *
  • CAUTION EXTREME AND RAPID ROD MOTION TO MITIGATE TAVG SWINGS MAY RESULT IN LARGE POWER EXCURSIONS AND SHOULD BE AVOIDED.
  • 9 Monitor RCS Tavg Verify control rods responding in AUTO. IF NOT. THEN place rods to "o Tavg - GREATER THAN 545°F MANUAL and adjust control rods to restore Tavg within limits.

"o Tavg - LESS THAN 566°F IFF Tavg is outside limits AND can NOT be controlled. THEN trip the reactor and go to E-0. REACTOR TRIP OR SAFETY INJECTION.

NOTE: The thumb rule for initial boron addition is -2 gal/% load reduction.

10 Add Boric Acid As Necessary To:

"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

EOP: TITLE: RV AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 13 of 32 11 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 12 Request RP to obtain the following samples:

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

13 Check IA Available To CNMT Control PRZR level and pressure as follows:

"o IA pressure - > 60 psig "o Adjust load reduction rate "o Instr Air to CNMT Isol Valve, AOV-5392 - OPEN "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

"EOP: TITLE: REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 14 of 32 NOTE: With PRZR pressure controller 431K in manual, PORV-431C will not operate in the automatic mode. (Refer to TR 3.4.3)

"*14 Monitor PRZR Pressure - Control PRZR pressure by one of the TRENDING TO 2235 PSIG IN AUTO following:

e 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.

"*15 Monitor MFW Regulating Valves Perform the following:

- RESTORING S/G LEVEL TO 52%

IN AUTO a. Place affected S/G(s) MFW regulating valve in MANUAL

b. Restore S/G level to 52%

IF SIG level can NOT be controlled manually, THEN refer to AP-FW.1.

ABNORMAL MAIN FEEDWATER FLOW.

"*16 Monitor PRZR Level - TRENDING Perform the following:

TO PROGRAM IN AUTO CONTROL

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.

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

17 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 17b.
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

"EOP: TITLE:

REV: 3 AP-SG. 1 STEAM GENERATOR TUBE LEAK

,PAGE I 16 of 32 SE ACTT0N/EXPECTED RSPONSE REPOS NOT 0BTAINEI 18 Check If One MFW Pump Should Be Secured

a. Power < 50% a. WHEN power < 50%, THEN continue with step 18b.
b. Verify at least one MFWP Seal b. Notify AO to start one MFWP Seal Booster pump in service Booster pump
c. Two MFW Pumps running c. Go to Step 19.
d. Close discharge valve for the pump to be secured

"*MFW Pump A - MOV-3977

"*MFW Pump B - MOV-3976

e. Stop the desired MFW Pump
f. Close the secured MFW pump recirc valve by placing the control switch in pull stop
g. Close the service water block valve to the secured MFW pump oil cooler

"*MFW Pump A - V-4701

"*MFW Pump B - V-4702 19 Verify Trim Valves Place controller in manual and Controlling Condensate System control pressure between Pressure In Auto 300-375 psig (300-375 PSIG)

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 17 of 32 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.

20 Check AMSAC System Status

a. Power < 35% (-150 psig first a. Continue with Step 21. WHEN stage pressure) power < 35% (-150 psig first stage pressure), THEN do Step 20b.
b. Verify AMSAC Auto Block Status b. Place AMSAC Manual Block switch Light is ON to the BLOCK position 21 Check Heater Drain Tank Pump Status
a. Generator load < 175 MWe a. WHEN generator load < 175 MWe, THEN continue with Step 21b.
b. Stop one Heater Drain Tank Pump
c. WHEN Heater Drain Tank level control is stable, THEN stop the second Heater Drain Tank Pump

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 18 of 32 22 Check MFW Regulating Bypass Vlv Status

a. Power < 30% a. WHEN power < 30%. THEN continue with Step 22b.
b. MFW Regulating Bypass Vlvs in b. Perform the following:

AUTO I

1) Slowly open the MFW

"*HCV-480 Regulating Bypass Vlvs while

"*HCV-481 verifying the associated MFW Regulating Vlv compensates by closing slightly

2) Place MFW Regulating Bypass Vlvs in AUTO 23 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 23d.
d. Open turbine drain valves

EOP: TITLE: REV : 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 19 of 32 24 Check If Turbine Should Be Tripped:

a. Check turbine load -
  • 15 MW a. WHEN turbine load is < 15 MW.

THEN continue with Step 24b.

b. Trip the turbine.
c. Verify annunciator G-15, STEAM c. Place steam dump mode selector DUMP ARMED - LIT switch to MANUAL.
d. Condenser steam dump operating d. IF steam dump NOT available.

in AUTO THEN perform the following:

1) IF power is greater than 8%.

THEN ensure reactor trip and go to E-0, REACTOR TRIP OR SAFETY INJECTION.

2) Adjust intact S/G ARV setpoint to 1005 psig and verify proper operation.
e. Tavg - TRENDING TO PROGRAM e. IF temperature less than 547°F and decreasing, THEN perform the following:
1) Stop dumping steam
2) IF cooldown continues, THEN close both MSIVs.

IF temperature greater than 547' and increasing, THEN dump steam to stabilize and slowly decrease temperature to 547 0 F.

IF Tavg can NOT be controlled.

THEN manually trip the reactor and go to E-0, REACTOR TRIP OR SAFETY INJECTION.

NOTE: Transition to E-0 is NOT required when the reactor trip breakers are opened in the following step.

25 Shutdown The Reactor

a. Place rods in MANUAL
b. Drive control rods until
c. Press Rx trip pushbutton
d. Verify Rx Trip breakers open d. Dispatch AO to locally open reactor trip breakers
e. Verify all control and shutdown rods on bottom NOTE: The following step is intended to start an RCS boration at the earliest opportunity. The boration endpoint is determined in Step 32.

26 Initiate RCS Boration At IF normal boration can NOT be Maximum Rate Using FCV-11OA performed, THEN align charging pump suction to RWST

a. Start BOTH BAST pumps o LCV-112B - OPEN
b. Place FCV-11OA controller to MANUAL AND adjust to full open. o LCV-112C - CLOSED

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 21 of 32 CAUTION IF ANY S/G LEVEL ABOVE 52%, THEN AFW FLOW MAY BE THROTTLED IMMEDIATELY TO PREVENT SIG ISOLATION.

27 Check S/G Feed Flow Status:

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

FLOW TO MAINTAIN S/G LEVELS

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

IF MFW NOT available, THEN manually start TDAFW pump from the non-leaking S/G and establish flow and go to Step 27c.

2) Adjust feed flow to restore S/G level to 52%.
3) Go to Step 29.
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 MFW pump discharge valves

"*MOV-3977, A MFW pump

"*MOV-3976, B MFW pump

e. Stop any running MFW pump and place in pull stop
f. Place A and B MFW regulating and bypass valve controllers in manual at 0% demand.
g. Adjust AFW pump flow to restore S/G level to 52%.

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 22 of 32

  • STEPH ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEO 28 Establish Normal AFW Pump Shutdown Alignment:
a. Place AFW bypass switches to DEF
b. Close MDAFW pump discharge valves
  • MOV-4007 o MOV-4008
c. Adjust AFW bypass valves to control SIG levels at 52%
  • AOV-4480
  • AOV-4481

EOP: TITLE: REV 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 23 of 32 29 Complete Leaking S/G Isolation:

a. Close leaking S/G MSIV - LEAKING a. Perform the following:

SIG 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)

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK 7 LPAGE 24 of 32 30 Check Leaking SIG Level:

a. Narrow range level - GREATER a. Perform the following:

THAN 17%

1) Maintain feed flow to leaking S/G until level greater than 17%.
2) Continue with Step 31. WHEN leaking S/G level greater than 17%. THEN do Steps 30b through f.
b. Close MDAFW pump discharge valve b. Dispatch AO to locally close to leaking S/G valve.

"*S/G A. MOV-4007

"*S/G B. MOV-4008

c. Close MDAFW pump bypass valve for leaking S/G

"* S/G A. AOV-4480

"* S/G B, AOV-4481

d. Pull stop MDAFW pump for leaking S/G
e. Close TDAFW pump flow control e. Dispatch AO with locked valve valve to leaking S/G key to locally close TDAFW pump manual feedwater isolation valve

- S/G A. AOV-4297 to leaking SIG.

- S/G B, AOV-4298

- S/G A. V-4005

- S/G B, V-4006

f. Verify MDAFW pump crosstie" f. Manually close valves.

valves - CLOSED a MOV-4000A

  • MOV-4000B

EOP: TITLE: REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 25 of 32

"*31 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 o Train A o Train B
c. Verify SAFETY INJECTION BLOCKED status light - LIT

"EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 26 of 32

.... A.... IN *...XECE..SONE. *. ..... R O . NO OBTAINED CAUTION OPERATION OF BOTH RCPS IS PREFERRED TO MINIMIZE REQUIRED BORON ADDITION FOR SUBSEQUENT COOLDOWN.

32 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 b. IF normal boration can NOT be concentration using FCV-11OA 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

"EOP: TITLE: ,* REV: 3 AP-SG.l STEAM GENERATOR TUBE LEAK PAGE 27 of 32 33 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

"* 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

" 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 1IB c. IF either bus NOT energized.

energized - BOTH BUSSES GREATER THEN refer to 0-6.9.2.

THAN 4 KV ESTABLISHING AND/OR TRANSFERRING OFFSITE POWER TO BUS 12A/BUS 12B.

d. Dispatch AO to perform ATT-17.0.

ATTACHMENT SD-i

EOP: TITLE:

REV: 3 AP-SG.1 STEAM GENERATOR TUBE LEAK PAGE 28 of 32 34 Check If Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 34e.

DEENERGIZED

b. Check intermediate range flux b. Continue with Step 35. WHEN EITHER CHANNEL LESS THAN flux is less than 10-10 amps on 10-10 AMPS any operable channel, THEN do Steps 34c, d and e.
c. Check the following: c. Continue with Step 35. WHEN either condition met, THEN do "o Both intermediate range Steps 34d 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 35.

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

EOP: TITLE:

REV: 3 AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 29 of 32

-iSTEP ACTION/EXPECTED IRSOS RESPONSE NOT OBTAINED 35 Check Rx Trip Breakers - OPEN DO NOT continue until Rx trip breakers open.

36 Check RCS Boron Concentration

a. RCS Boron Concentration - equal a. Continue boration. WHEN RCS to or greater than required for boron equal to or greater than cooldown to 500 degrees per required value. THEN go to step 32 step 36b.
b. Verify MRPI indicates all b. Borate an additional 650 gallons control and shutdown rods on of boric acid for each rod not bottom fully inserted. WHEN boration complete, THEN continue with Step 37.

37 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 SIG using SIG ARV
2) Go to step 37d
b. Place Steam Dump Mode Selector switch to MANUAL
c. Initiate dumping steam to c. IF condenser steam dumps not condenser from intact S/G 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 50°F/HR
e. Maintain RCS pressure low in the desired operating range (Refer to 0-2.2. PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS)

"EOP: TITLE: R REV: : 3 AP-SG.l STEAM GENERATOR TUBE LEAK PAGE 30 of 32 38 Notify RP To Obtain Primary Samples Required By ITS LCO 3.4.16 (load reduction > 15%

in one hour) 39 Check RCS Boron Concentration

a. RCS boron - equal to or greater a. Perform the following:

than required for cooldown to 450 degrees per step 32 1) Stop cooldown AND maintain stable RCS temperature above 500 degrees and stable.

2) Continue boration. WHEN RCS I boron equal to or greater than required value. THEN go to step 39b.
b. Verify MRPI indicates all b. Request Rx Engineer determine

'control and shutdown rods on amount of boration required due bottom 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

STEP ACTION/EXPECTED RESPONSE1 - RESPONSE NOT OBTAINED 40 Cooldown RCS To 450 Degrees

a. Initiate dumping steam
b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 50°F/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 o MOV-841, MCC C position 12F o MOV-865. MCC D position 12C
2) Close SI ACCUM outlet valves e ACCUM A, MOV-841 o 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

SSTEP ACTION/EXPECTED-RESPONSE RESPONSE NOT OBTAINED 41 Check Normal Or Excess IF normal letdown desired, THEN Letdown - IN SERVICE establish normal letdown (Refer to ATT-9.0. ATTACHMENT LETDOWN)

IF normal letdown NOT available, THEN establish excess letdown if desired (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D).

42 Evaluate Long Term Plant Status:

a. Consult the following groups:

"* Operations Staff

"*Plant Engineering Staff

"* Chemistry

b. RCS boron - MEETS 2.45% CSD b. Perform the following:

CURVE PER 0-3.1. BORON CONCENTRATION FOR THE XENON FREE 1) Continue RCS boration to CSD ALL RODS IN - MOST REACTIVE ROD concentration. (Refer to STUCK OUT SHUTDOWN MARGIN 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

2) Continue with Step 42e. WHEN RCS boron meets 2.45% CSD curve requirement. THEN do steps 42c 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 -

  • EOP: TITLE:

REV: 3 AP-SG. 1 STEAM GENERATOR TUBE LEAK PAGE 1 of 1

ýj 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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