ML17309A652

Rev 14 to AP-RCS.1, Reactor Coolant Leak

ML17309A652
Person / Time
Site:	Ginna
Issue date:	04/14/1999
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17309A651	List: ML17309A650 ML17309A652 ML17311A070
References
AP-RCS.1, NUDOCS 9904200392
Download: ML17309A652 (62)

Text

EOP AP-RCS.1

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TITLE:

REACTOR COOLANT LEAK REV:

14 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 AP-RCS. 1-TITLE:

REACTOR COOLANT LEAK REV 14 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 c.

Annunciator lit, or A-2, VCT LEVEL 14% 86, lit, or E 16'MS PROCESS MON1TOR HIGH ACTIVITY~

d.

Annunciator E-24, RMS AREA MONITOR HIGH ACTIVITY, lit, or 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:

AP-RCS. 1.

TITLE:

REACTOR COOLANT LEAK REV:

14 PAGE 3 of 11 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 1 I 4

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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 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 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:

AP-RCS.1 TITLE:

REACTOR COOLANT LEAK REV 14 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 5%

a.

Ensure charging pump suction aligned to RWST.

~ LCV-112B -

OPEN

~ LCV-112C -

CLOSED

b. Verify the following:

1)

RMW mode selector switch in AUTO

b. Adjust controls as necessary.

2)

RMW control armed RED LIGHT LIT c.

Check VCT level:

o Level GREATER THAN 20%

-OR-o Level STABLE OR INCREASING c.

Check letdown, divert valve, LCV-112A, closed.

IF VCT makeup flow NOT adequate, THEN perform the following:

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, if necessary'.

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EOP:

AP-RCS.1 TITLE:

REACTOR COOLANT LEAK REV:

14 PAGE 5 of 11 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 3 Check If RCS Leakage In CNMT:

o Check CNMT radiation monitors NORMAL

~ R-2

~ R-7

~ R-10A

~ R-11

~ R-12 o

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

~ IF leakage is indicated in CNMT, THEN perform the following:

a. Direct RP to sample CNMT for entry.

b. Continue with Step 4.

WHEN CNMT cleared for entry.

THEN dz'spatch personnel to investigate CNMT for RCS leakage.

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1 I 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:

o CCW surge tank level APPROXIMATELY 50'/i AND STABLE Go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.

o CCW radiation monitor, R-17 NORMAL

EOP AP-RCS. 1.

TITLE:

REACTOR COOLANT LEAK REV,:

14 PAGE 6 of 11 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 6 Check CVCS Conditions:

a.

Letdown indication:

o Letdown flow - APPROXIMATELY 40 GPM o

Low pressure LTDN pressure-APPROXIMATELY 250 PSIG a.

IF letdown isolated, THEN continue with Step 6b.

IF NOT

isolated, THEN go to AP-CVCS.1.

CVCS LEAK. Step 6.

o Letdown pressure control

valve, PCV-135, demand APPROXIMATELY 35'/i OPEN

b. Charging indication:

o Seal injection flows GREATER THAN 6 GPM AND STABLE o

RCP Labyrinth seal D/Ps GREATER THAN 15 INCHES AND APPROXIMATELY EQUAL b.

Go to AP-CVCS.1, CVCS LEAK, Step 6.

o Charging pump discharge pressure GREATER THAN RCS PRESSURE c.

AUX BLDG radiation levels NORMAL

~ R-4

~ R-9

~ R-10B

~ R-13

~ R-14 c.

Go to AP-CVCS.l, CVCS LEAK, Step 6 and refer to CVCS piping diagrams for further guidance.

EOP:

AP-RCS. 1"

.TITLE:

REACTOR COOLANT LEAK REV:

14 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 7 Check PRT Indications:

a. Level BETWEEN 61'/. AND 84'/.

b. Pressure APPROXIMATELY 1.5 PSIG AND STABLE

c. Temperature

- AT CNMT AMBIENT TEMPERATURE AND STABLE Check tailpipe and valve leakoff temperatures for the PRZR safety valves and PORVs for indication of leakage.

IF no PORV or safety valve leakage is indic'ated, THEN check other leak paths from the RCS to the PRT.

~ 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:

o Air ejector radiation monitors NORMAL IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION WITH A S/G TUBE LEAK INDICATION.

~ 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 AP-RCS. 1".

TITLE:

REACTOR COOLANT LEAK REV:

14 PAGE 8 of 11, STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 9 Check SI Accumulator Levels STABLE Calculate inleakage to SI accumulators (Refer to S-16.11.

MONITORING INLEAKAGE TO SI ACCUMULATORS) 10 Check RCP Seal Leakoff Flows:

o Leakoff flows - WITHIN THE NORMAL OPERATING RANGE OF FIGURE RCP SEAL LEAKOFF Go to AP-RCP.l.

RCP SEAL MALFUNCTION.

o Leakoff flows - STABLE ll Check RCDT Leak Rate NORHAL (Refer to RCS Daily Leakage Log and PPCS point ID L1003)

Check other sources of in leakage to RCDT:

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.

g

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EOP:

AP-RCS. 1" REACTOR COOLANT LEAK REV:

14 PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 12 Check Valve Leakoff Temperatures NORMAL (Refer to Pressurizer Valve Leak-Off, Temperature Record Log)

IF any valve leakoff temperature is

,abnormally high, THEN initiate investigation of that leakage path.

13 Establish Stable Plant Conditions:

a.

PRZR level

- TRENDING TO PROGRAM b.

Check PRZR pressure control:

o Pressure

- TRENDING TO 2235 PSIG o

PRZR backup heaters OFF

a. Control charging and letdown flows to restore PRZR. level to'rogram.

b. Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.

IF pressure can NOT be controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.

14 Evaluate RCS Leakage:

a.

Leakage within limits (Refer to leakage surveillance sheet and ITS section 3.4.13)

b. Leak location identified

a. IF leak NOT isolable, but PRZR level and seal injection can be maintained, THEN shut the plant down (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN or AP-TURB.5, RAPID LOAD REDUCTION).

b. Return to Step 1.

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A

'EOP:'AP-RCS.l"'EACTOR COOLANT LEAK REV:

14 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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EOP:

w AP-RCS.1" TITLE:

/

REACTOR COOLANT LEAK REV:

14 PAGE ll of 11 AP-RCS.1 APPENDIX LIST TITLE 1)

FIGURE RCP SEAL LEAKOFF (FIG-4.0)

V

-=s P

EOP ES-1.1 TITLE:

SI TERMINATION REV:

18 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:

ES-1.1 SI TERMINATION REV:

18 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:

ES-1.1 TITLE:

SI TERMINATION REV 18 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 ISOLATION - EXTINGUISHED

b. Perform the following:

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:

ES-1.1 SI TERMINATION REV:

18 PAGE 4 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT'BTAINED 4 Verify Adequate SW Flow:

a.

Check at least two SW pumps RUNNING

a. Manually start SW pumps as power 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).

b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1) 3)

Go to Step 7.

EOP:

ES-1.1 SI TERMINATION REV:

18 PAGE 5 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 5 Establish IA to CNMT:

a. Verify non-safeguards busses energized from offsite power o

Bus 13 normal feed CLOSED

-OR-o Bus 15 normal feed CLOSED

b. Verify SW isolation valves to turbine building -

OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify adequate air compressor(s)

RUNNING d.

Check IA supply:

o Pressure GREATER THAN 60 PSIG o

Pressure STABLE OR INCREASING e.

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

f. Verify IA to CNMT AOV-5392 OPEN a.

Perform the following:

1) Close non-safeguards bus tie breakers:

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

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

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

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

b. Manually align valves.

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

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

d. Perform the following:

1) Continue attempts to restore IA (Refer to AP-IA.1.

LOSS OF INSTRUMENT AIR).

2) Continue with Step 6.

WHEN IA restored.

THEN do Steps 5e and f.

e 0

EOP:

ES-1.1 SI TERMINATION REV:

18 PAGE 6 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 6 Check If Charging Flow Has Been Established:

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

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RCP B, V-300B

2) Ensure HCV-142 open, demand at 0/o.

b. Charging pump suction aligned to RWST:

o LCV-112B -

OPEN o

LCV-112C -

CLOSED

b. Manually align valves as necessary.

IF LCV-112B can NOT be opened.

THEN dispatch AO to locally open 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:

ES-1.1 SI TERMINATION REV:

18 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 exit T/Cs GREATER THAN 0 F

USING FIGURE MIN SUBCOOLING b.

PRZR level GREATER THAN 5%

[30% adverse CNMT]

a. Manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.

b. Control charging flow to maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to E-1.

LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

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EOP:

ES-1.1 SI TERMINATION REV:

18 PAGE 8 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED

• 9 Monitor If CNMT Spray Should Be Stopped:

a.

CNMT spray pumps RUNNING b.

Check CNMT pressure

- LESS THAN 4 PSIG

c. Reset CNMT spray d.

Check NaOH tank outlet valves CLOSED

~ AOV-836A

~ AOV-836B a.

Go to Step 10.

b. Continue with Step 10; WHEN CNMT pressure less than 4 psig, THEN do Steps 9c through f.

d. Place NaOH tank outlet valve controllers to MANUAL and close valves.

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:

ES-l. 1 SI TERMINATION REV 18 PAGE 9 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 10 Verify MRPI Indicates ALL CONTROL AND SHUTDOWN RODS ON BOTTOM IF one or more control rods NOT fully inserted, THEN perform the 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 Condenser Steam Dump Pressure Control:

a. Verify condenser available:

o Any MSIV -

OPEN o

Annunciator G-15.

STEAM DUMP ARMED - LIT a.

Place S/G ARV controllers in AUTO at desired pressure and go to Step 12.

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:

ES-1.1 SI TERMINATION REV:

18 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-RUNNING

b. Verify AUX BLDG SW isolation valves OPEN

a. Manually start pumps as power supply permits (257 kw each).

IF less than two SW pumps can be

operated, THEN go to Step 18.

b. Manually align valves.

~ MOV-4615 and MOV-4734

~ MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM - EXTINGUISHED

c. Manually start an additional SW pump as power supply permits (257 kw each).

EOP:

ES-1.1 SI TERMINATION REV:

18 PAGE 11 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 13 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored:

o IA to CNMT (AOV-5392)

OPEN o

IA pressure

- GREATER THAN 60 PSIG a.

Continue with Step 18.

WHEN IA can be restored. THEN do Steps 13 through 17.

b. Verify instrument bus D-ENERGIZED c.

CCW pumps ANY RUNNING

b. Energize MCC B.

IF MCC B NOT available.

THEN perform the following:

1) Verify MCC A energized.

2) Place instrument bus D on maintenance supply.

c. 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

d. Charging pump ANY RUNNING

2) Manually start one CCW pump.

d. Continue with Step 18.

WHEN any charging pump running, THEN do Steps 14 through 17.

EOP:

ES-1.1 SI TERMINATION REV:

18 PAGE 12 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 14 Verify PRZR Level GREATER THAN 13%

[40% adverse CNMT]

Continue with Step 16.

WHEN PRZR level increases to greater than 13%

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

15 Establish Normal Letdown:

a. Establish charging line flow to REGEN Hx -

GREATER THAN 20 GPM

b. Place the following switches to CLOSE:

~ Letdown orifice valves (AOV-200A. AOV-200B, and AOV-202)

~ AOV-371, letdown isolation valve

~ AOV-427, loop B cold leg to REGEN Hx

c. Place letdown controllers in MANUAL at 40% open

~ TCV-130

~

PCV-135

d. Reset both trains of XY relays for AOV-371 and AOV-427 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 IF RCP seal return has been established, THEN establish excess letdown as follows:

o Place excess letdown divert

valve, AOV-312, to NORMAL.

o Ensure CCW from excess letdown

open, (AOV-745).

o Open excess letdown isolation valve AOV-310.

o Slowly open HCV-123 to maintain excess letdown temperature less than 195 F and pressure less than 100 psig.

o Adjust charging pump speed as necessary.

IF RCP seal return NOT established, THEN consult Plant Staff to determine if excess letdown should be placed in service.

EOP:

ES-1.1 SI TERMINATION REV:

18 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:

1)

RMW mode selector switch in AUTO

c. Adjust controls as necessary.

2)

RMW control armed RED LIGHT LIT d.

Check VCT level:

o Level GREATER THAN 20/

-OR-o Level STABLE OR INCREASING

d. Manually increase VCT makeup flow as follows:

1) Ensure BA transfer pumps and RMW pumps running.

IF NOT, THEN dispatch AO to locally 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.

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EOP:

ES-1.1 SI TERMINATION REV:

18 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

b. Verify charging pumps aligned to VCT o

LCV-112C -

OPEN o

LCV-112B -

CLOSED

2) Continue with Step 18.

WHEN VCT level greater than 40%.

THEN do Step 17b.

b. Manually align valves as necessary.

18 Check RCS Hot Leg Temperatures STABLE Control steam dump and total feed flow as necessary to stabilize RCS temperature.

EOP:

ES-1.1 SI TERMINATION REV 18 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 closing normal charging valve AOV-294 and normal PRZR spray valves.

19 Control PRZR Heaters And Operate Normal Spray To Stabilize RCS Pressure IF normal spray NOT available and letdown is in service, THEN perform 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 THAN 5%

[25% adverse CNMT]

a. Maintain total feed flow greater 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 narrow range level between 17%

[25% adverse CNMT] and 50%

b. IF narrow range level in any S/G continues to increase, THEN stop feed flow to that S/G.

EOP:

ES-1.1 SI TERMINATION REV:

18 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:

a.

Check CCW to RCPs:

Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

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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f r 5 4 j

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EOP:

ES-1.1 TITLE:

SI TERMINATION REV 18 PAGE 17 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 22 Check If Seal Return Flow Should Be Established:

a. Verify RCP 0'1 seal outlet temperature

- LESS THAN 235'F

b. Verify RCP seal outlet valves OPEN

~ AOV-270A

~ AOV-270B I

a.

Go to Step 23.

b. Manually open valves as necessary.

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313 d.

Open RCP seal return isolation

,valve MOV-313

e. Verify RCP 8'1 seal leakoff flow LESS THAN 6.0 GPM

d. Perform the following:

1) Place MOV-313 switch to OPEN.

2) Dispatch AO with key to RWST gate to locally open MOV-313.

e.

Perform the following:

1) Trip the affected RCP

2) Allow 4 minutes for pump coast down.

THEN close the affected RCP seal discharge valve.

f. Verify RCP tl seal leakoff flow GREATER THAN 0.8 GPM

~

RCP A, AOV-270A

~

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

f. Refer to AP-RCP.l.

RCP SEAL MALFUNCTION.

• 1 ICI t

t

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ES-1.1 SI TERMINATION REV:

18 PAGE 18 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 23 Verifv All AC Busses ENERGIZED BY OFFSITE POWER o

Normal feed breakers to all 480 volt busses CLOSED o

480 volt bus voltage GREATER THAN 420 VOLTS o

Emergency D/G output breakers OPEN Perform the following:

a. IF any AC emergency bus normal feed breaker

open, THEN ensure associated D/G breaker closed.

b. Perform the following as necessary:

1) Close non-safeguards

.bus tie breakers:

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

2) 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

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ES-1.1 SI TERMINATION REV:

18 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 DEENERGIZED a.

Go to Step 24e.

b.

Check intermediate range flux-EITHER CHANNEL LESS THAN 10 10 AMPS

b. Perform the following:

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:

o Both intermediate range channels LESS THAN 10 10 AMPS

c. Continue with step 25.

WHEN either condition met, THEN do Steps 24d 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).

e. Transfei Rk-45 recorder to one source range and one intermediate range channel IF source ranges can NOT be restored.

THEN refer to ER-NIS.1, SR MALFUNCTIONS and go to Step 25.

g V

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ES-1.1 SI TERMINATION REV:

18 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 energized by offsite power:

o Emergency D/G output breakers OPEN

a. Try to restore offsite power (Refer to ER-ELEC.l.

RESTORATION OF OFFSITE POWER).

o AC emergency bus voltage GREATER THAN 420 VOLTS o

AC emergency bus normal feed breakers CLOSED

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

EOP:

ES-1.1 TITLE:

SI TERMINATION REV 18 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 ONE RUNNING Perform the following:

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.

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ES-1.1 SI TERMINATION REV:

18 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 rod shroud fan RUNNING

1) Manually start one fan as power supply permits (45 kw)

2) Verify one Rx compartment, cooling fan RUNNING

2) Perform the following:

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-1 COMPLETE

EOP:

ES-1.1 TITLE:

SI TERMINATION REV:

18 PAGE 23 of 24 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 28 Maintain Plant Conditions Stable:

a.

RCS.pressure BETWEEN 1800 PSIG AND 2235 PSIG b.

PRZR level BETWEEN 35%

AND 40%

c. Intact S/G narrow range levels BETWEEN 17%

AND 52%

d.

RCS cold leg temperature STABLE

a. Control PRZR heaters and spray as necessary.

b. Control charging as necessary.

c. Control S/G feed flow as necessary.

d. Control dumping steam as necessary.

IF cooldown continues, THEN close both MSIVs.

• 29 Monitor SI Reinitiation Criteria:

a.

RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING b.

PRZR level GREATER THAN 5%

[30% adverse CNMT]

a. Manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step l.

b. Control charging flow to maintain PRZR level.

IF PRZR level can NOT be maintained.

THEN manually start SI pumps as necessary and go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.

k

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Ol E

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ES-1.1 SI TERMINATION REV:

18 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:

ES-1.1 SI TERMINATION REV 18 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

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ES-1. 1 SI TERMINATION REV:

18 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:

ES-1.1 SI TERMINATION REV:

18 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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