ML17250B128
| ML17250B128 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/09/1990 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250B096 | List:
|
| References | |
| FR-H.4, NUDOCS 9004200748 | |
| Download: ML17250B128 (78) | |
Text
EOP:FR-H.4'ITLE:
RESPONSE
TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES REV 1
PAGE 1 of 4 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER A3 TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERINT ND T
aj~
V EFFECTIVE DATE QAM NON-QA CATEGORY 1.0 REVIEWED BY'004200748 9004 10 PDR ADQCK 05000244 I
p PNU GINfiIASTATION START:
DATE'IIVIE COVPLETED'ATE 1 TIME:
l>
1
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FR-H.4 TITLE:
RESPONSE
TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES REV:
1 PAGE 2 of 4 A.
PURPOSE This procedure provides actions to respond to a failure of the S/G ARVs and Condenser Dump Valves.
B.
ENTRY CONDITIONS/SYMPTOMS l.
ENTRY CONDITIONS This procedure is entered from F-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW condition.
C s
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FR-H.4 TITLE:
RESPONSE
TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES REV:
1 PAGE 3 of 4 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF AFFECTED S/G(S)
NARROV RANGE LEVEL INCREASES TO GREATER THAN 90X [85X ADVERSE CNMT], THEN STEAM SHOULD NOT BE RELEASED FROM THE AFFECTED S/G(S).
NOTE:
o Throughout this procedure, "affected" refers to any S/G in which pressure is greater than 1085 psig.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10
~ R/hr.
1 Try To Restore Normal Steam Release Capability Of Affected S/G(s):
a.
Check if condenser available o
Affected S/G MSIV(s) -
OPEN o
Either CV pump - RUNNING o
Condenser vacuum - GREATER THAN 20 INCHES HG
- a. Perform the following:
- 1) Place affected S/G(s)
ARV controller to manual and attempt to open ARV.
IF S/G ARV(s) can NOT be
~
ARVs.
- b. Operate condenser steam dump manually:
- 1) Place steam dump mode selector to MANUAL 2)
Go to Step 2.
- 2) Place condenser steam dump controller to MANUAL
- 3) Open steam dump valves as required
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FR-H.4 TITLE:
RESPONSE
TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES REV:
1 PAGE 4 of 4 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2
Check S/G Pressures LESS THAN 1085 PSIG Perform the following:
- a. Manually open affected S/G(s)
TDAFV pump steam supply valves
~ S/G A, MOV-3505A
~ S/G B, MOV-3504A
- b. Dispatch AO to perform the following:
- 1) Open affected S/G MSIV bypass valve.
- 2) Open priming air ejector steam isolation valves.
~ V-3580
~ V-3581
- c. Local operation of affected S/G ARV may be attempted.
(Establish communications with control room.)
3 Return To Procedure And Step In, Effeet
-END-
EOP:
FR-P.1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 1 of 20 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERINTE E T
~l>lti EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
0
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FR-P.1 TITLE:
RESPONSE
TO IBRIINENT PRESSURIZED THERMAL SHOCK CONDITXON REU:
6'AGE 2 of 20 A.
PURPOSE This procedure provides actions to avoid, or limit, thermal shock or pressurized thermal shock to the reactor pressure
- vessel, or overpressure conditions at low temperature.
l B.
ENTRY CONDITIONS/SYMPTOMS l.
ENTRY CONDITIONS This procedure is entered from:
a.
F-0.4, INTEGRITY Critical Safety Function Status
- Tree, on either a
RED or ORANGE condition.
74'l
~ S aC
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FR-P. 1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 3 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o A faulted S/G is any S/G that is depressurizing in an uncontrolled manner or is completely depressurized.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10
~ R/hr.
1 Check RCS Cold Leg Temperatures STABLE OR INCREASING Try to stop RCS cooldown:
a.
Ensure S/G ARVs closed.
- b. Close both S/G MSIVs.
- c. Ensure MFW flow control valves closed.
~
MFW regulating valves
~
MFW bypass valves
- d. Ensure MFW pumps tripped.
- e. IF S/G pressure less than condensate
- pressure, THEN stop all condensate pumps.
- g. Control total feed flow to non-faulted S/G(s) greater than 200 gpm until narrow range level greater than 5X [25X adverse CNMT] in at least one non-faulted S/G.
WHEN S/G level greater than 5X [25X adverse CNMT] in one non-faulted S/G, THEN limit feed flow to stop RCS cooldown.
This Step continued on the next page.
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FR-P. l T I TI.E:
RESPONSE
TO IP24INENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 4 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
-(Step 1 continued from previous page)
- h. Minimize cooldown from faulted S/G(5):
- 1) Close faulted S/G(s)
TDAFV pump steam supply valve(s).
~ S/G A, MOV-3505A
~ S/G B, MOU-3504A
- 2) IF both S/G(s) faulted, THEN control feed flow at 50 gpm to each S/G.
- 3) IF any S/G NOT faulted, THEN isolate all feedwater to faulted S/G unless necessary for RCS temperature control.
IF a faulted S/G is necessary for RCS temperature
- control, THEN control feed flow at 50 gpm to that S/G.
2 Check PRZR PORV Block Valves:
a.
Power to PORV block valves-AUAILABLE
- b. Block valves
- AT LEAST ONE OPEN
- a. Restore power to block valves unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C b.
Open one block valve unless it was closed to isolate an open PORU.
IF at least one block valve can NOT be opened, THEN dispatch AO to locally check breaker.
~ MOV-515, MCC C position 6C
~ MOU-516, MCC D position 6C
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FR-P.1 TlTLE:
'RESPONSE TO IMMXNENT PRESSURIZED THERMAL SHOCK CONDITXON REK PAC STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE)
IT SHOULD BE CLOS, AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 3B).
3 Check Xf PRZR PORVs Should Be Closed:
a.
Check the following:
o PRZR pressure
- LESS THAN 2335 PSXG XF RCS OVERPRESSURE PROTECTION SYSTEM NOT XN SERVXCE
-OR-o RCS pressure
- LESS THAN 4lO PSIG XF RCS OVERPRESSURE PROTECTION SYSTEM XN SERVICE
- b. Verify PRZR PORVs -
CLOSED a.
Perform the folloving:
- 1) Ensure at least one PRl open.
- 2) Continue vith Step 4.
pressure less than setp THEN do Step 3b.
- b. Manually close valve.
IF any valve can NOT be cl THEN manually close its bl valve.
4 Check SI Pumps ANY"RUNNING Go to Step 13
lpga f
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FR-P.1 TlTLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 6 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 5
Check If SI Can Be Terminated:
o RCS subcooling based on core exit T/Cs - GREATER THAN 50'F USING FIGURE MIN SUBCOOLING o
Check RVLIS indication:
o Level (no RCPs)
- GREATER THAN 68%
[73% adverse CNMT]
-OR-o Fluid fraction (any RCP running) - GREATER THAN 80%
Do NOT stop SI pumps.
Perform the folloving:
- a. IF RCS subcooling based on core exit T/Cs greater than O'F using Figure MIN SUBCOOLING and no RCP
- running, THEN attempt,to start an RCP:
- 1) Establish conditions for starting an RCP:
o Bus llA or llB energized o
Refer to Attachment RCP START
- 2) IF conditions established, THEN start one RCP.
b.
Go to Step 25.
- * * * * * * *
- A' CAUTION IF OFFSITE POVER IS LOST AFTER SI RESET, SELECTED SV PUMPS AND ONE CCV PUMP VILL AUTO START ON EMERGENCY D/G.
MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
- * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- k * + * * * * * *
- 6 Reset SI 7
Stop SI And RHR Pumps And Place In AUTO
l,l 0
+4
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FR-P.1 TITLE:
RESPONSE
TO IIG4INENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 7 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Reset CI:
a.
Depress CI reset pushbutton
- b. Verify annunciator A-26, CNMT ISOLATION - EXTINGUISHED
- b. Perform the folloving:
- 1) Reset SI.
- 2) Depress CI reset pushbutton.
9 Verify Adequate SN Flow:
a.
Check at least two SV pumps-RUNNING b, Dispatch AO to establish normal shutdovn alignment (Refer to Attachment SD-1)
- a. Manually start SV pumps as power'upply permits (258 kv each).
IF less than tvo SV pumps
- running, THEN perform the folloving:
- 1) Ensure SV isolation.
- 2) Dispatch AO to establish normal shutdovn alignment (Refer to Attachment SD-1).
3)
Go to Step ll.
WHEN adequate SV available, THEN do Step 10.
l
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FR-P. 1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 8 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 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 SV isolation valves to turbine building -
OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 -and MOV-4664
- c. Verify at least two air compressors
- RUNNING d.
Check IA supply:
o Pressure
- GREATER THAN 6C PSIG o
Pressure
- STABLE OR INCREASING
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)
WHEN 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 j (- er Lo AP-IA.1, LOSS OF INSTRUMENT AIR).
- 2) Continue with Step ll.
MHRN IA restored, THEN do Steps 10e and f.
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FR-P.l TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 9 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- * * * * * * * * * * * * * * *
- 4' CAUTION ALIGNING SI PUMP SUCTION TO RWST BEFORE ISOLATING BAST MAY RESULT IN BACKFLOW FROM RWST TO BASTS.
ll Verify SI Pump Suction Aligned To RWST:
a.
SI pump suction valves from BASTs -
CLOSED
~ MOV-826A
~ MOV-826B MOV-826C
~ MOV-826D
~ MOV-825A MOV-825B a.
Ensure at least one valve in each flow path closed.
~ MOV-826A or MOV-826B
~ MOV-826C or MOV-826D
- b. Ensure at least one valve is open.
N
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FR-P. 1 TITLE:
RESPONSE
TO IYidIINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 10 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 12 Check If Charging Flow Has Been Est:ablished:
- a. Charging pumps
- ANY RUNNING
- a. Perform the following:
- 1) IR 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 locally close seal in)ection needle valve(s) to affected RCP:
~ RCP A, V-300A
~ RCP B) V-300B
- b. Align charging pump suction to RWST:
o LCV-112B -
OPEN o
LCV-112C -
CLOSED
- 2) Ensure HCV-142 open, demand at OX.
- b. IR LCV,-112B can NOT be opened, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- c. Start charging pumps as necessary and ad)ust charging flow to restore PRZR level
- 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
3)
WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump roam).
~ C
~ l
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FR-P. 1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL'HOCK CONDITION REV 6
PAGE ll of 20
.STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 13 Verify SI Flow Not Remi'red:
o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o
RVLIS indication:
o Level - GREATER THAN 68%
[73%
adverse CNMT]
-OR-,,
o Fluid fraction (any RCP running) - GREATER THAN 80%
Manually operate SI pumps as necessary and 'perform the following:
- a. IF RCS subcooling based on core exit T/Cs greater than 0
F Figure MIN SUBCOOLING and no RCP
- running, THEN attempt to start an RCP:
- 1) Establish conditions for starting an RCP:
o Bus llA or 11B energized o
Refer to Attachment RCP START
- 2) IF conditions established, THEN start one RCP.
b.
Go to Step 25.
14 Check RCS Hot Leg Temperatures STABLE IF increasing, THEN control feed flow and dump steam to stabilize RCS hot leg temperatures.
.IF decreasing, THEN verify that actions of Step 1 have been performed before continuing with procedure.
'F>'
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FR-P.1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 12 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 15 Check If SI ACCUMs Should Be Isolated:
a.
Check the following:
o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING
- a. Return to Step 13.
o RVLIS indication:
o Level -
GREATER THAN 68%
[73% adverse CNMT]
-OR-o Fluid fraction (any RCP running)
GREATER THAN 80%
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves
~ MOV-841
~ MOV-865
- d. Locally reopen breakers for MOV-841 and MOV-865
- c. Vent any unisolated ACCUMs:
- 1) Open vent valves for unisolated SI ACCUMs.
ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
3). Continue with Step 16.
Do NOT decrease RCS pressure to less than unisolated ACCUM pressure.
A J
y I
~.
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FR-P.1 TITLE:
RESPONSE
TO IMMINENT PRESSURXZED THERMAL SHOCK CONDITION REV 6
PAGE 13 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAXNED CAUTION THE RCS SHOULD NOT BE DEPRESSURIZED TO LESS THAN SI ACCUM PRESSURE UNTIL SI ACCUMS ISOLATED.
- * * * * * * * * * * * * * * * * * * * 'k * * * * * * * * * * * * * * * * * * *
- NOTE:
o
@hen using a PRZR PORV select one with an operable block valve.
o Select PORV with operable block valve.
16 Depressurize RCS To Decrease RCS Subcooling:
- a. Depressurize using normal PRZR spray if available
- a. IF normal spray NOT available, THEN use one PRZR PORV.
IF IA NOT available, THEN refer to Attachment N2 PORVS.
- b. Depressurize RCS until either of the following conditions satisfied:
o RCS subcooling based on core exit T/Cs -
LESS THAN 10'F USING FIGURE MIN SUBCOOLING IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).
-OR-o PRZR level
- GREATER THAN 87%
, [75% adverse CNMT]
- c. Stop RCS depressurization
le
'i 0
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FR-P. 1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 14 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION AN INCREASE IN RCS PRESSURE MAY RESULT IN EXCESSIVE REACTOR VESSEL STRESS.
RCS PRESSURE AND TEMPERATURE SHOULD BE MAINTAINED STABLE MHILE PERRORMING SUBSEQUENT STEPS IN THIS PROCEDURE.
17 Check PRZR Level GREATER THAN 13%
[40~ adverse CNMT]
Try to restore.level with charging while maintaining stable RCS pressure.
IR level can NOT be
- restored, THEN go to Step 24.
0
EOP:
FR-P.1 TITLE:
RESPONSE
TO XYidlINENT PRESSURIZED THERMAL SHOCK CONDXTXON REV' PAGE 15 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 18 Check Xf Normal CVCS Operation Can Be Established
- a. Verify XA,restored:
OPEN o
IA pressure
- GREATER THAN 60 PSIG b.
CCW pumps
- ANY RUNNING
- c. Verify instrument bus D-ENERGIZED
- d. Charging pump -
ANY RUNNING
- a. Continue with Step 22.
WHEN XA
- restored, THEN do Steps 18.
through 21.
k
- b. Perform the following:
- 1) IF any RCP gl 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.
', 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.
d Continue with Step 23.
WHEN any charging pump running, THEN do Steps 19 through 23.
~%a I,
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FR-P. 1 TlTLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 16 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 19 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 25% 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 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 TSC to determine if excess letdown should be placed in service.
1
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FR-P. 1 TlTLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 17 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Check VCT Makeup System:
a.
BAST levels - ANY GREATER THAN 5%
b.
Check Annunicator B-23, BORIC ACID TANK LO LO LEVEL-EXTINGUISHED a.
Go to Step 21.
- b. Perform the following:
- 1) Adjust boric acid flow control valve to required flow from table.
BAST LEVEL (10%
10-15%
15-20%
>20%
BORIC ACID RLOW (GPM) 4.5 6.7 8.9 10.0
- c. Adjust boric acid flow control valve in AUTO to 4.5 gpm
- d. Verify the following:
1)
RMW mode selector switch in AUTO 2)
Go to Step 20d.
- d. Adjust controls as necessary.
2)
RMW control armed - RED LIGHT LIT e.
Cbeck VCT level:
o Level - GREATER THAN 20%
-OR-o Level -
STABLE OR INCREASING Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMW pumps running.
IR NOT, THEN 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.
II
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FR-P. 1 TlTEE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 18 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 21 Check Charging Pump Suction Aligned To VCT:
a.
VCT level - GREATER THAN 20X
- a. IF VCT level can NOT be maintained greater than 5%,
THEN perform the following:
- 1) Ensure charging pump suction aligned to RVST 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 22.
MHBN VCT level greater than 40%,
THEN do Step 2lb.
- b. Manually align valves as necessary.
22 'Check PRZR Level LESS THAN 87>
r'75% adverse CNMT]
Control charging and letdown as necessary to reduce PRZR level to less than 87%
[75% adverse CNMT].
If necessary establish excess letdown.
IF no letdown available AND CCV to RCPs established, THEN cycle charging pumps as necessary to control PRZR level.
23 Energize PRZR Heaters And Operate Normal PRZR Spray As Necessary To Maintain Pressure Stable IF normal spray NOT available and letdown is in service, THEN use auxiliary spray valve (AOV-296).
IF auxiliary spray NOT available, THEN use one PRZR PORV.
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FR-P.1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 19 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 24 Check RCS Subcooling Based On Core Exit T/Cs BETWEEN 10'F AND 20'F USING FIGURE MIN SUBCOOLING IF normal spray NOT available and letdown is in service, THEN use auxiliary spray for any further depressurization.
Return to Step 16b.
IF auxiliary spray NOT available, THEN return to Step 16a.
25 Check Cool Down Rate In RCS Cold Legs GREATER THAN 100'F IN ANY 60 MINUTES PERIOD Return to procedure and step in effect.
26 Maintain RCS Pressure And Temperature Stable For At Least 1 Hour
- a. Control steam dump and feed flow as necessary
- b. Perform actions of other procedures in effect which do not cool down the RCS or increase RCS pressure until the RCS. temperature soak has been completed 27 WHEN 1
HOUR Soak Is
- Complete, THEN Continue RCS Cooldown And Depressurization As Necessary
- a. Maintain RCS pressure and cold leg temperature within the limits of Figure SOAK LIMITS
- b. Maintain cooldown rate in RCS cold legs LESS THAN 50'F IN ANY 60 MINUTES PERIOD
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FR-P. 1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV:
6 PAGE 20 of 20 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 28 Return To Procedure And Step In Effect;
-END-
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FR-P.1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION REV 6
PAGE 1 of 1 FR-P.1 APPENDIX LIST TITLE PAGES 1)
FIGURE MIN SUBCOOLING 2)
FIGURE SOAK LIMITS 3)
ATTACHMENT RCP START 4)
ATTACHMENT SD-1 5)
ATTACHMENT CNMT RECIRC FANS 6)
ATTACHMENT N2 PORVS 7)
ATTACHMENT SI FLUSH
4 C
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FR-P,1 TITLE:
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDXTXON REU 6
PAGE 1 of 1
FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Belov t'-] Core Exit T/C Xndication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 200 200 100 0
S PRESSURE (PSIG)
RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION E CNMT ADVERS NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'P 200 250
. 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('P)
P V
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PAGE 1 of 1
RCS 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 900 800 700 600 500 400 300 200 100 0
PRESSURE (PSIG)
RCS PRESSURE INCREMENTS 20 PSIG FIGURE SOAK LIMITS ACCEPTABLE REGION FOR COOLDOW TPMPP RATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE ('F)
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6 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT E FECT VE DATE CATEGORY 1.0 REVIEWED BY'
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TO REACTOR RESTART/ATWS REV' PAGE 2 of 10 A.
PURPOSE This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.
B.
ENTRY CONDITIONS/SYMPTOMS l.
ENTRY CONDITIONS This procedure is entered from:
a.
E-O, REACTOR TRIP OR SAFETY INJECTION, when reactor trip is not verified and manual trip is not effective.
b.
F-0.1, SUBCRITICALITY Critical Safety Function Status Tree on either a
RED or ORANGE condition.
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6 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o Steps l through 4 are IMMEDIATE ACTION steps.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+
R/hr.
Ol Verify Reactor Trip:
o At least one train of reactor
- trip breakers OPEN o
Neutron flux - DECREASING o
MRPI indicates
- ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.
IF reactor trip breakers NOT open, THEN manually insert control rods.
O 2
Verify Turbine Stop Valves CLOSED Manually trip turbine.
IF turbine trip can NOT be
- verified, THEN close both MSIVs.
O 3
Check AFW Pumps Running:
a.
MDAFW pumps
- RUNNING b.
TDAFW pump
- RUNNING IF NECESSARY
- a. Manually start MDAFW pumps.
- b. Manually open steam supply valves.
~ MOV-3505A
~ MOV-3504A
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PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o If borating for stuck control rod(s),
then at least 175 gallons of boric acid should be added for each rod not fully inserted.
o If offsite power is lost coincident with SI, then MCC C and MCC D lockout relays must be reset to restore BA and RMW pumps.
~
~
~
4 Initiate Emergency Boration Of RCS:
a.
Check SI status:
o All SI annunciators EXTINGUISHED
- a. IF SI flow indicated, THEN go to Step 5.
IF NOT, THEN
'So to Step 4b.
o All'Ipumps OFF IN AUTO
- b. Verify at least one charging pump
- RUNNING
- c. Align boration path:
- 1) Start two BA transfer pumps
- 2) Open MOV-350
- 3) Verify BA flow
- d. Verify charging flow path:
o Charging valve to loop B cold leg (AOV-294) -
OPEN o
Charging flow control valve (HCV-142)
DEMAND AT 0%
- b. Perform the following:
- 1) Reset SI if necessary.
- 2) Start one charging pump.
- c. IF flow can NOT be established, THEN refer to AP-CVCS.2, IMMEDIATE BORATION.
- d. Manually align valves.
IF IA to CNMT isolated, THEN verify alternate charging valve, (AOV-392A), relieving 'to RCS.
i1 II
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NOT OBTAINED 5
Check If The Following Trips Have Occurred:
- a. Reactor trip
- a. Dispatch AO to locally trip reactor:
- b. Turbine trip o
Trip MG set breakers at bus 13 and bus 15.
o Open reactor trip breakers locally.
- b. Dispatch operator to locally trip turbine using manual trip lever on west end of HP turbine.
CAUTION ACTIONS TAKEN TO INITIATE RCS BORATION SHALL NOT BE REVERSED WHEN PERFORMING IMMEDIATE ACTIONS OF E-O, REACTOR TRIP OR SAFETY INJECTION.
6 Complete The Immediate Actions Of E-O, REACTOR TRIP OR SAFETY INJECTION, While Continuing With This Procedure 7
Check PRZR PORV Status:
o RCS pressure
- LESS THAN 2335 PSIG o
PORVs CLOSED Verify CNMT ventilation isolation.
IF dampers NOT closed, THEN momentarily deenergize CNMT particulate monitor, R-ll, to actuate CVI.
o Annunciator F-19, PRZR PORV OUTLET HI TEMP - EXTINGUISHED
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NOT OBTAINED CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
8 Check S/G Level:
- a. Narrow range level in at least one S/G GREATER THAN 5%
[25%
adverse CNMT]
- b. Control feed flow to maintain narrow range level between 17%
[25% adverse CNMT] and 50%
- a. Perform the following:
- 1) Verify total feed flow greater than 400 gpm.
IF NOT, THEN manually start pumps and align valves as necessary.
- 2) Maintain total feed flow greater than 400 gpm until narrow range level greater than 5%
[25% adverse CNMT] in at least one S/G.
9 Verify Dilution Paths ISOLATED Manually isolate dilution paths.
o Place RMW mode switch to BORATE o
Verify RMW to blender (HCV-ill)
CLOSED o
Verify RMW pumps
- OFF
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NOT OBTAINED 10 Stabilize RCS Temperature:
- a. Control steam dump as necessary
- b. Verify the following:
o Core exit T/Cs
- STABLE OR INCREASING
o Pressure in both S/Gs STABLE OR INCREASING o
Pressure in both S/Gs GREATER THAN 100 PSIG c.
Go to Step 15 11 Verify MFW Isolation:
a.
MFW pumps
- TRIPPED b.
MFW flow control valves CLOSED
~
MFW regulating valves
~ MFW bypass valves
- b. Place A and B S/G MFW regulating valve and bypass valve controllers to MANUAL at 0%
demand.
12 Identify Faulted S/G:
o Any S/G Pressure DECREASING IN AN UNCONTROLLED MANNER Go to Step 15.
-OR-o Any S/G COMPLETELY DEPRESSURIZED
I
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PAGE 8 of 10 STEP ACTION/FZPECTED RESPONSE
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NOT OBTAINED CAUTION o
AT LEAST ONE S/G MUST BE MAINTAINEDAVAILABLEFOR RCS COOLDOWN.
o IF BOTH S/GS ARE FAULTED, AT LEAST 50 GPM FEED FLOW SHOULD BE MAINTAINED TO EACH S/G.
13 Isolate Feed Flow To Faulted S/G:
o Close faulted S/G MDAFW pump discharge valve
~ S/G A, MOV-4007
~ S/G B, MOV-4008 o
Pull stop faulted S/G MDAFW pump o
Close faulted S/G TDAFW flow control valve Manually close valves.
IF valves can NOT be closed, THEN *
'ispatch AO to locally isolate flowpaths as necessary.
~ S/G A, AOV-4297
~ S/G B, AOV-4298 o
Verify faulted S/G MFW regulating valve and bypass valve CLOSED
~ S/G A, HCV-466 and HCV-480
~ S/G B, HCV-476 and HCV-481 o
Verify MFW pump discharge valves CLOSED
~ S/G A, MOV-3977
~ S/G B, MOV-3976 o
Verify MDAFW pump crosstie valves CLOSED
~ MOV-4000A
~ MOV-4000B
U
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NOT OBTAINED 14 Isolate Steam Flow From Faulted S/G:
o Verify faulted S/G ARV -
CLOSED
~ S/G A, AOV-3411
~ S/G B; AOV-3410 o
Close faulted S/G TDAFW pump steam supply valve and place in PULL STOP Manually close valves.
IF valves can NOT be closed, THEN dispatch AO to locally isolate flowpaths as necessary.
~ S/G A, MOV-3505A
~ S/G B, MOV-3504A o
Verify faulted S/G blowdown and sample valves CLOSED
~ S/G A, AOV-5738 and AOV-5735
~ S/G B, AOV-5737 and AOV-5736 o
Dispatch AO to complete faulted S/G isolation (Refer to Attachment FAULTED S/G)
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6 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE
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NOT OBTAINED NOTE:
Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
15 Verify Reactor Subcritical:
o Power range channels
- LESS THAN 5S o
Intermediate range channels STABLE OR DECREASING o
Intermediate range channels startup rate
- NEGATIVE o
Core exit T/Cs STABLE Perform the following:
- a. Stabilize RCS temperature.
I
- b. Continue to inject boric acid.
- d. Verify boron concentration greater than Figure SDM (Add 100 ppm to required SDM for each stuck rod).
IF adequate shutdown margin
- verified, THEN return to procedure and step in effect.
IF NOT, THEN perform the following:
- a. Allow RCS to heat up.
- b. Perform actions of other FR procedures in effect which do NOT cooldown or otherwise add positive reactivity to the core.
- c. Return to Step 5.
CAUTION BORATION SHOULD CONTINUE TO OBTAIN ADEQUATE SHUTDOWN MARGIN DURING SUBSEQUENT ACTIONS.
16 Return to Procedure And Step In Effect
-END-
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6 PAGE 1 of 1 FR-S.1 APPENDIX LIST TITLE 1)
FIGURE SDM 2)
ATTACHMENT FAULTED S/G PAGES I
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6 PAGE 1 of 1 BORON CONCENTRATION (PPH) 1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000 ADEQUATE SDM 100 PPM CONSERVATISM INCLUDED Qy Soo 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0
1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)
NOTE: To obtain core burnup, use PPCS turn on code BURNUP.