ML17309A652

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Rev 14 to AP-RCS.1, Reactor Coolant Leak.
ML17309A652
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/14/1999
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17309A651 List:
References
AP-RCS.1, NUDOCS 9904200392
Download: ML17309A652 (62)
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Text

EOP TITLE:

REV: 14 AP-RCS.1 ~ REACTOR COOLANT LEAK PAGE 1 of 11

'OCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

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EOP TITLE:

REV 14 AP-RCS. 1- REACTOR COOLANT LEAK PAGE 2 of ll A. PURPOSE This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.

1 B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:
a. S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE, when a significant increase in RCS leakage is indicated.
b. AP-CVCS.l, CVCS LEAK, when leak cannot be isolated.
2. SYMPTOMS The symptoms of REACTOR COOLANT LEAK are;
a. Annunciator F-14, CHARGING PUMP SPEED, lit, or
b. Annunciator A-2, VCT LEVEL 14% 86, lit, or
c. Annunciator E 16'MS PROCESS MON1TOR HIGH ACTIVITY~

lit, or

d. Annunciator E-24, or RMS AREA MONITOR HIGH ACTIVITY, lit,
e. Annunciator F-4, PRESSURIZER LEVEL DEVIATION -5 NORMAL +5, lit, or
f. Annunciator F-10, PRESSURIZER LO PRESS 2205 PSI, lit, or
g. Annunciator F-ll, PRESSURIZER LO LEVEL 13%, lit.

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BOP: TITLE:

REV: 14 AP-RCS. 1. REACTOR COOLANT LEAK PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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CAUTION IF, AT ANY TIME DURING THIS PROCEDURE. A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY. INJECTION, SHALL BE PERFORMED.

NOTE: Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.

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

IF PRZR level continues to decrease, THEN close loop B cold leg to REGEN Hx isolation valve, AOV-427.

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.

4 EOP: TITLE:

REV 14 AP-RCS.1 REACTOR COOLANT LEAK PAGE 4 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF VCT level decreases to 5%. charging pump suction will swap to the RWST. This may require a load reduction.

2 Check VCT Makeup System:

a. Verify VCT level - GREATER THAN a. Ensure charging pump suction 5% aligned to RWST.

~ LCV-112B - OPEN

~ LCV-112C - CLOSED

b. Verify the following: b. Adjust controls as necessary.
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
c. Check VCT level: c. Check letdown, divert valve, LCV-112A, closed.

o Level GREATER THAN 20%

IF VCT makeup flow NOT adequate,

-OR- THEN perform the following:

o Level - STABLE OR INCREASING 1) Ensure BA transfer pumps and RMW pumps running.

2) Adjust RMW flow control valve. HCV-ill. to increase RMW flow.
3) Increase boric acid flow as necessary to maintain required concentration.

IF VCT level can NOT be maintained, THEN refer to ER-CVCS.1, REACTOR. MAKEUP CONTROL MALFUNCTION, necessary'.

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EOP: TITLE:

REV: 14 AP-RCS.1 REACTOR COOLANT LEAK PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If RCS Leakage In CNMT: ~ IF leakage is indicated in CNMT, THEN perform the following:

o Check CNMT radiation monitors NORMAL a. Direct RP to sample CNMT for entry.

~ R-2

~ R-7 b. Continue with Step 4. WHEN CNMT

~ R-10A cleared for entry. THEN dz'spatch

~ R-11 personnel to investigate CNMT

~ R-12 for RCS leakage.

o CNMT sump A pump run freguency-NORMAL (Refer to RCS Daily Leakage Log)

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  • CAUTION RADIATION PROTECTION TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.

4 Dispatch AO To AUX'LDG To Investigate For CVCS Leak (locked area keys required) 5 Check For Leak To CCW System: Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.

o CCW surge tank level APPROXIMATELY 50'/i AND STABLE o CCW radiation monitor, R-17 NORMAL

EOP TITLE:

REV,: 14 .

AP-RCS. 1. REACTOR COOLANT LEAK PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check CVCS Conditions:

a. Letdown indication: a. IF letdown isolated, THEN continue with Step 6b. IF NOT o Letdown flow - APPROXIMATELY isolated, THEN go to AP-CVCS.1.

40 GPM CVCS LEAK. Step 6.

o Low pressure LTDN pressure-APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand APPROXIMATELY 35'/i OPEN

b. Charging indication: b. Go to AP-CVCS.1, CVCS LEAK, Step 6.

o Seal injection flows GREATER THAN 6 GPM AND STABLE o RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL o Charging pump discharge pressure - GREATER THAN RCS PRESSURE

c. AUX BLDG radiation levels c. Go to AP-CVCS.l, CVCS LEAK, NORMAL Step 6 and refer to CVCS piping diagrams for further guidance.

~ R-4

~ R-9

~ R-10B

~ R-13

~ R-14

EOP: .TITLE:

REV: 14 AP-RCS. 1" REACTOR COOLANT LEAK PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRT Indications: Check tailpipe and valve leakoff temperatures for the PRZR safety

a. Level - BETWEEN 61'/. AND 84'/. valves and PORVs for indication of leakage.
b. Pressure - APPROXIMATELY 1.5 PSIG AND STABLE IF no PORV or safety valve leakage is indic'ated, THEN check other leak
c. Temperature - AT CNMT AMBIENT paths from the RCS to the PRT.

TEMPERATURE AND STABLE

~ Letdown relief valve, RV-203

~ Seal return relief valve, RV-314

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CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED O.l GPM WHEN AVERAGED OVER 24 HOURS.

8 Check S/Gs For Leakage: IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION o Air ejector radiation monitors WITH A S/G TUBE LEAK INDICATION.

NORMAL

~ R-15

~ R-15A o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors NORMAL

~ R-31

~ R-32 o S/G sample activity - NORMAL (Check with RP Department for normal)

EOP TITLE:

REV: 14 AP-RCS. 1". REACTOR COOLANT LEAK PAGE 8 of 11, STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check SI Accumulator Levels Calculate inleakage to SI STABLE accumulators (Refer to S-16.11.

MONITORING INLEAKAGE TO SI ACCUMULATORS) 10 Check RCP Seal Leakoff Flows: Go to AP-RCP.l. RCP SEAL MALFUNCTION.

o Leakoff flows - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF o Leakoff flows - STABLE ll Check (Refer RCDT to Leak Rate RCS NORHAL Daily Leakage Check to other sources of in leakage RCDT:

Log and PPCS point ID L1003)

a. IF Rx vessel flange leakoff temperature has increased, THEN close Rx VESS FLANGE SEAL LEAKOFF VLV. AOV-521.
b. Verify excess letdown isolated.

IF NOT, THEN ensure RCDT divert valve. AOV-312, in the VCT position.

c. IF source of leakage NOT determined'HEN suspect loop drains.

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EOP:

REV: 14 AP-RCS. 1" REACTOR COOLANT LEAK PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Valve Leakoff IF any valve leakoff temperature is Temperatures NORMAL (Refer ,abnormally high, THEN initiate to Pressurizer Valve Leak-Off, investigation of that leakage path.

Temperature Record Log) 13 Establish Stable Plant Conditions:

a. PRZR level - TRENDING TO PROGRAM a. Control charging and letdown flows to restore PRZR. level to'rogram.
b. Check PRZR pressure control: b. Verify proper operation of PRZR heaters and spray or take manual o Pressure - TRENDING TO control of PRZR pressure 2235 PSIG controller 431K. IF pressure can NOT be controlled, THEN o PRZR backup heaters - OFF refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

14 Evaluate RCS Leakage:

a. Leakage within limits (Refer to a. IF leak NOT isolable, but PRZR leakage surveillance sheet and level and seal injection can be ITS section 3.4.13) maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).
b. Leak location identified b. Return to Step 1.

~ A

'EOP:

REV: 14

'AP-RCS.l"'EACTOR COOLANT LEAK PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC INNEDIATE NOTIFICATION, for reporting requirements.

1S Notify Higher Supervision

-END-

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/ REV: 14 AP-RCS.1" REACTOR COOLANT LEAK PAGE ll of 11 AP-RCS.1 APPENDIX LIST TITLE

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)

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EOP TITLE:

REV: 18 ES-1.1 SI TERMINATION PAGE 1 of 24 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBLE NAGER 3 3I Jc-od-EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 2 of 24 A. PURPOSE This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions'.

ENTRY CONDITIONS/SYMPTOMS 1 ~ ENTRY CONDITIONS This procedure is entered from:

a. E-O, REACTOR TRIP OR SAFETY INJECTION, and E-l, LOSS OF REACTOR OR SECONDARY COOLANT, when specified termination criteria are sati'sfied.
b. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and SI has been terminated.

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  • EOP: TITLE:

REV 18 ES-1.1 SI TERMINATION PAGE 3 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET. THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL.AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

NOTE: o FOLDOUT page should be open AND monitored periodically.

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

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 Reset SI 2 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

3 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 4 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT'BTAINED 4 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 perform the following:

1) Ensure SW isolation.
2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1).
3) Go to Step 7.
b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 5 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Establish IA to CNMT:

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

energized from offsite power

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

-OR- ~ Bus 13 to Bus 14 tie

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

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

IF NOT, THEN evaluate RECIRC fans should be if CNMT stopped (Refer to Attachment CNMT RECIRC FANS).

3)'HEN bus 15 restored, THEN reset control room lighting.

b. Verify SW isolation valves to b. Manually align valves.

turbine building - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify adequate air c. Manually start air compressors compressor(s) - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
d. Check IA supply: d. Perform the following:

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

o Pressure - STABLE OR INCREASING 2) Continue with Step 6. WHEN IA restored. THEN do Steps 5e and f.

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

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EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 6 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Been If Charging Established:

Flow Has

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:

~ RCP A, V-300A

~ RCP B, V-300B

2) Ensure HCV-142 open, demand at 0/o.
b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.

o LCV-112B - OPEN IF LCV-112B can NOT be opened.

THEN dispatch AO to locally open o LCV-112C - CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).

IF LCV-112C can NOT be closed,"

THEN perform the following:

1) Verify charging pump A NOT running and place in PULL STOP.
2) Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 7 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Stop SI And RHR Pumps And Place In AUTO

  • 8 Monitor SI Reinitiation Criteria:
a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN 0 F necessary and go to E-l, LOSS OF USING FIGURE MIN SUBCOOLING REACTOR OR SECONDARY COOLANT, Step l.
b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

~c 4 ~ e

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 8 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 9 Monitor Be Stopped:

If CNMT Spray Should

a. CNMT spray pumps - RUNNING a. Go to Step 10.
b. Check CNMT pressure - LESS THAN b. Continue with Step 10; WHEN 4 PSIG CNMT pressure less than 4 psig, THEN do Steps 9c through f.
c. Reset CNMT spray
d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

~ AOV-836A

~ AOV-836B

e. Stop CNMT spray pumps and place

~

in AUTO

f. Close CNMT spray pump discharge valves

~ MOV-860A

~ MOV-860B

~ MOV-860C

~ MOV-860D

t EOP:

REV 18 ES-l. 1 SI TERMINATION PAGE 9 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Verify MRPI Indicates ALL IF one or more control rods NOT CONTROL AND SHUTDOWN RODS ON fully inserted, THEN perform the BOTTOM following:

a. Place RMW mode selector switch to BORATE.
b. Adjust boric acid flow control valve. FCV-llOA, for desired flowrate.
c. Set boric acid integrator to desired amount (650 gallons for each control rod not fully inserted).
d. Place RMW control to start and verify flow. IF flow can NOT be established. THEN refer to ER-CVCS.1. REACTOR MAKEUP CONTROL MALFUNCTION.

ll Establish Dump Condenser Steam Pressure Control:

a. Verify condenser available: a. Place S/G ARV controllers in AUTO at desired pressure and go o Any MSIV - OPEN to Step 12.

o Annunciator G-15. STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to desired pressure and verify in AUTO.
c. Place steam dump mode selector switch to MANUAL.

d < 1 EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 10 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify Adequate SW Flow To CCW Hx:

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

IF less than two SW pumps can be operated, THEN go to Step 18.

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

valves - OPEN

~ MOV-4615 and MOV-4734

~ MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan c. Manually start an additional SW annunciator C-2, HIGH pump as power supply permits TEMPERATURE ALARM - EXTINGUISHED (257 kw each).

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 11 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check Operation If Normal CVCS Can Be Established

a. Verify IA restored: a. Continue with Step 18. WHEN IA can be restored. THEN do Steps o IA to CNMT (AOV-5392) - OPEN 13 through 17.

o IA pressure - GREATER THAN 60 PSIG

b. Verify instrument bus D- b. Energize MCC B. IF MCC B NOT ENERGIZED available. THEN perform the following:
1) Verify MCC A energized.
2) Place instrument bus D on maintenance supply.
c. CCW pumps - ANY RUNNING c. Perform the following:
1) IF any RCP ¹1 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 18. WHEN any charging pump running, THEN do Steps 14 through 17.

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 12 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify PRZR Level GREATER Continue with Step 16. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Step 15.

15 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdown as follows:

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

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

CLOSE:

o Ensure CCW from excess letdown

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

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

~ AOV-371, letdown isolation valve AOV-310.

valve

~ AOV-427, loop B cold leg to o Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195 F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open o Adjust charging pump speed as

~ TCV-130 necessary.

~ PCV-135 IF RCP seal return NOT established,

d. Reset both trains of XY relays THEN consult Plant Staff to for AOV-371 and AOV-427 determine if excess letdown should be placed in service.
e. Open AOV-371 and AOV-427
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 to control PRZR level

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 13 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check VCT Makeup System:

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

o Level - GREATER THAN 20/

1) Ensure BA transfer pumps and

-OR- RMW pumps running. IF NOT, THEN dispatch AO to locally o Level - STABLE OR INCREASING reset MCC C and MCC D UV lockouts as necessary.

2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
3) Increase boric acid flow as necessary.

I A. ~ , a EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 14 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. XF 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 18. WHEN VCT level greater than 40%.

THEN do Step 17b.

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

o LCV-112C - OPEN o LCV-112B - CLOSED 18 Check RCS Hot Leg Control steam dump and total feed Temperatures STABLE flow as necessary to stabilize RCS temperature.

EOP:

REV 18 ES-1.1 SI TERMINATION PAGE 15 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o WHEN using a PRZR PORV. THEN select one with an operable block valve.

o If auxiliary spray is in use, spray flow may be increased by AOV-294 and normal PRZR spray valves.

closing normal charging valve 19 Control PRZR Heaters And IF normal spray NOT available and Operate Normal Spray To letdown is in service, THEN perform Stabilize RCS Pressure the following:

a. Verify Regen Hx Chg outlet temp to PRZR Vapor temp hT less than 320'F. IF NOT, THEN control pressure using one PRZR PORV and go to Step 20.
b. Control pressure using auxiliary spray.

IF auxiliary spray NOT available.

THEN use one PRZR PORV.

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

  • 20 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT] in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase, THEN stop

[25% adverse CNMT] and 50% feed flow to that S/G.

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 16 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT 'OBTAINED NOTE: SW should be aligned to CCW Hxs before restoring RCP seal cooling.

21 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs:

o Annunciator A-7. RCP lA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15 'CP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check RCP seal injection:

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

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

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REV 18 ES-1.1 SI TERMINATION PAGE 17 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check If Seal Return Flow Should Be Established:

I

a. Verify RCP 0'1 seal outlet a. Go to Step 23.

temperature - LESS THAN 235'F

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

~ AOV-270A

~ AOV-270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
d. Open RCP seal return isolation d. Perform the following:

,valve MOV-313

1) Place MOV-313 switch to OPEN.
2) Dispatch AO with key to RWST gate to locally open MOV-313.
e. Verify RCP 8'1 seal leakoff flow e. Perform the following:

LESS THAN 6.0 GPM

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

~ RCP A, AOV-270A

~ RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 23.

f. Verify RCP tl seal leakoff flow f. Refer to AP-RCP.l. RCP SEAL GREATER THAN 0.8 GPM MALFUNCTION.
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EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 18 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Verifv All AC Busses Perform the following:

ENERGIZED BY OFFSITE POWER

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

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

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

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

2) Reset Bus 13 and Bus 15 lighting breakers.
3) Dispatch AO to locally reset and start two IA compressors.
4) Place the following pumps in PULL STOP:

~ EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

5) Restore power to MCCs.

~ A from Bus 13

~ B from Bus 15

~ E from Bus 15

~ F from Bus 15

6) Start HP seal oil backup pump.
7) Start CNMT RECIRC fans as necessary.
8) Ensure D/G load within limits.
9) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.l. RESTORATION OF OFFSITE POWER).

e a ~ e s ~ ~ t

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 19 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

24 Check If Source Range Channels Should Be Energized:

a. Source range channels a. Go to Step 24e.

DEENERGIZED

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

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

2) Continue with Step 25. WHEN flux is LESS THAN 10 10 amps on any operable channels THEN do Steps 24c. d and e.
c. Check the following: c. Continue with step 25. WHEN either condition met, THEN do o Both intermediate range Steps 24d 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 MALFUNCTIONS and go to Step 25.

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

g V EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 20 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If Emergency D/Gs Should Be Stopped:

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

o Emergency D/G output breakers

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

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

EOP: TITLE:

REV 18 ES-1.1 SI TERMINATION PAGE 21 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED t t t t t *

  • t
  • t t t ~ 1 t ~ t t ~
  • t t t
  • t t *
  • t t 1 ~ t t
  • t ~ t
  • CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

t t t ~ t

  • t
  • I *
  • t t
  • t
  • t 1 t t t t t ~ t t t t t t t ~ ~ *
  • t t t 1 1 t 26 Check RCP Status AT LEAST Perform the following:

ONE RUNNING

a. IF RVLIS level (no RCPs) less than 95%%d, 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 Figure MIN SUBCOOLING.

o Energize PRZR heaters as necessary to saturate PRZR water.

b. Establish conditions for starting an RCP:

o Verify bus 11A or 11B energized.

o Refer to Attachment RCP START.

c. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation NOT verified, THEN increase dumping steam frorii intact S/Gs.

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 22 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
b. Perform the following:

o Open generator disconnects

~ 1G13A71

~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump

c. Verify adequate Rx head cooling:
1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
2) Verify one Rx compartment, 2) Perform the following:

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

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

d. Verify Attachment SD COMPLETE

EOP: TITLE:

REV: 18 ES-1.1 SI TERMINATION PAGE 23 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Maintain Plant Conditions Stable:

a. RCS .pressure - BETWEEN 1800 PSIG a. Control PRZR heaters and spray AND 2235 PSIG as necessary.
b. PRZR level BETWEEN 35% AND 40% b. Control charging as necessary.
c. Intact S/G narrow range levels c. Control S/G feed flow as BETWEEN 17% AND 52% necessary.
d. RCS cold leg temperature - STABLE d. Control dumping steam as necessary. IF cooldown continues, THEN close both MSIVs.
  • 29 Monitor SI Reinitiation Criteria:
a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN O' necessary and go to E-l, LOSS OF USING FIGURE MIN SUBCOOLING REACTOR OR SECONDARY COOLANT, Step l.
b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained. THEN manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

k \A ~ Ol E EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 24 of 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Go To Procedure 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN

-END-

EOP:

REV 18 ES-1.1 SI TERMINATION PAGE 1 of 1 ES-1.1 APPENDIX LIST TITLE

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING (FIG-1.0)
3) ATTACHMENT CNMT RECIRC FANS (Arr-ii.o)
4) ATTACHMENT D/G STOP (Arr-s.I)
5) ATTACHMENT NC (ATr-13.0)
6) ATTACHMENT SEAL COOLING (ATT-15.2)
7) ATTACHMENT RCP START (ATT.15.0)
8) ATTACHMENT SD-1 (ATT-17.0)
9) ATTACHMENT SD-2 (Arr-17.1)
10) ATTACHMENT SI/UV (ATT-8.CL)
11) FOLDOUT

EOP:

REV: 18 ES-1. 1 SI TERMINATION PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY Nuclear power greater than 5%
b. CORE COOLING Core exit T/Cs greater than 1200'

-OR-Core exit T/Cs greater than 700' AND RVLIS level (no RCPs) less than 52% [55%

adverse CNMT]

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

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

d. INTEGRITY Cold leg temperatures decrease greater than 100' in last 60 minutes AND RCS cold leg temperature less than 285'
e. CONTAINMENT CNMT pressure greater than 60 psig

EOP:

REV: 18 ES-1.1 SI TERMINATION PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:

o RCS subcooling based on core exit T/Cs LESS THAN 0 F USING FIGURE MIN SUBCOOLING OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%

[30% adverse CNMT]

2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
3. 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).
4. E-3 TRANSITION CRITERIA IF any S/G level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN manually start SI Pumps as necessary AND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

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