ML17263A199
| ML17263A199 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/24/1993 |
| From: | Marlow T ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A191 | List: |
| References | |
| ES-.1, ES-0.1, NUDOCS 9304080164 | |
| Download: ML17263A199 (46) | |
Text
EOP:
ES-F 1 TITLE:
REACTOR TRIP RESPONSE REV:
8 PAGE 1 of 19 ROCHESTER GAS AND ELECTRIC CORPORATXON GXNNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVXEWED BY:
9304080i64 930330 PDR "ADOCK 05000244 p~
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EOPI ES-0.1 TITLE:
REACTOR TRIP RESPONSE REV:
8 PAGE 2 of 19 A.
PURPOSE This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from:
a.
E-O, REACTOR TRIP OR SAFETY INJECTION, when SI is neither actuated nor required.
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ES-0.1 TITLE:
REACTOR TRIP RESPONSE REV 8
PAGE 3 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF SI ACTUATION OCCURS DURING THIS PROCEDURE, THEN E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * '+
- NOTE:
o FOLDOUT page should be open and monitored periodically.
o Critical Safety Function Status Trees should be monitored.
(Refer to Appendix l for Red Path Summary.)
(
IF temperature less than 547'F and TRENDING TO 547'F decreasing, THEN perform the following:
a.
Stop dumping steam.
- b. Rotate reheater steam supply controller cam to close reheater steam supply valves.
- c. IF MDAFW pumps supplying greater than 200 gpm, THEN ensure TDAFW pump steam supply valves in PULL STOP.
- d. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level, greater than 5% in at least one S/G.
WHEN S/G level reater than 5% in one S/G, THEN imit feed flow to that required to maintain S/G level.
- e. IF cooldown continues, THEN close both MSIVs.
IF temperature greater than 547'F and increasing, THEN perform the following:
o Place condenser steam dump mode control to MANUAL
-OR-o Manually dump steam using S/G ARVs.
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ES-0.1 TITLE:
REACTOR TRIP RESPONSE REV:
8 PAGE 4 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF A MFW PUMP IS LEFT RUNNING ON RECIRC FOR EXTENDED PERIODS OF TIME, OVERHEATING MAY OCCUR.
2 Check S/G Feed Flov Status:
a.
Check RCS Tavg
- LESS THAN 554'F
- b. Verify MFW flow control valves CLOSED
~ MFW regulating valves
~ MFW bypass valves
- c. Verify total AFW flow -
GREATER THAN 200 GPM
- a. Continue with Step 3.
WHEN temperature less than 554'F, THEN do Steps 2b, c, d and e.
- b. Place A and B MFW regulating valve and bypass valve controllers in MANUAL at 0%
demand.
- c. Manually start both MDAFW pumps.
IF total AFW flow greater than 200 gpm can NOT be established, THEN perform the following:
o Manually start TDAFW pump.
-OR-o Perform the following:
l) Establish MFW on bypass valves.
- d. Close MFW pump discharge valves
~ MOV-3'.77, A MFW pump
~ MOV-3976, B MFW pump e.
Stop MFW pumps 2)
Go to step 3.
- d. Manually stop MFW pumps.
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REACTOR TRIP RESPONSE REV:
9 PAGE 5 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3 Verify MRPI Indicates ALL CONTROL AND SHUTDOWN RODS ON BOTTOM IF one or more control rods NOT fully inserted, THEN perform the following:
Place RMW mode selector switch to BORATE.
- b. Adjust boric acid flow control
- valve, FCV-110A, for desired flowrate.
- c. Set boric acid integrator to desired amount (175 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.
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ES-0.1 REACTOR TRIP RESPONSE REV:
8 PAGE 6 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4 Verify 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 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:
o Emergency D/G output breakers OPEN
- 1) Ensure one CCW pump running.
- 2) Close non-safeguards bus tie breakers:
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 3) Reset Bus 13 and Bus 15 lighting breakers.
- 5) Place the following pumps in PULL STOP:
~
EH pumps
~ Turning gear oil pump
~ HP seal oil backup pump
- 6) Restore power to MCCs.
~ A from Bus 13
~
B from Bus 15
~
E from Bus 15
~ F from Bus 15
- 7) Start CNMT RECIRC fans as necessary.
- c. Try to restore offsite power to all AC busses (Refer'to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
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PAGE 7 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 5 Verify At Least Two SW Pumps RUNNING Manually start SW pumps as necessary.
6 Verify IA Available:
o At least 2 air compressors RUNNING o
IA pressure GREATER THAN 60 PSIG Dispatch AO to locally reset and start air compressors as necessary.
IF IA pressure can NOT be maintained, THEN perform the following:
- a. Refer to AP-IA.l, LOSS OF INSTRUMENT AIR.
- b. Verify charging pump A NOT running and place in PULL STOP.
- c. Dispatch AO to locally open manual charging pump suction from RWST (V-358 in charging pump room).
d.
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 room).
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ES-F 1 REACTOR TRIP RESPONSE REV 8
PAGE 8 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 7
Check PRZR Level Control:
- a. Verify charging pumps
- ANY RUNNING b.
PRZR level GREATER THAN 13%
- a. Manually start charging pumps as necessary.
- b. Perform the following:
- 1) Place loop B cold leg isolation valve to REGEN Hx (AOV-427) switch to close.
- 2) Verify excess letdown isolation valve (AOV-310) closed.
- 3) Ensure PRZR heaters off.
- 4) Control charging to restore PRZR level greater than 13%.
- 5) Continue with Step 8.
WHEN PRZR level greater than 13%,
THEN do Steps 7c through e.
- c. Verify letdown - IN SERVICE
- c. Verify excess letdown in service.
IF NOT, THEN manually place letdown in service (Refer to Attachment LETDOWN).
d.
PRZR level
- TRENDING TO 20%
- d. Control charging and letdown to maintain PRZR level at 20%.
e.
Check PRZR heaters ENERGIZED AS NECESSARY o
PRZR heater control group o
PRZR heater backup group
- e. Reset PRZR heaters and energize as necessary to restore PRZR pressure.
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'REACTOR TRIP RESPONSE REV:
8 PAGE 9 of 19 STEP ACTION/EXPECTED RESPONSE
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NOT OBTAINED 8
Check PRZR Pressure Control:
a.
PRZR pressure
- GREATER THAN 1750 PSIG b.
PRZR pressure GREATER THAN 2210 PSIG
- a. Perform the following:
- 1) Verify SI actuation.
IF NOT, THEN manually actuate SI.
2)
Go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step l.
- b. IF pressure less than 2210 PSIG and decreasing, THEN'perform the following:
- 1) Ensure PRZR PORVs closed.
IF any valve can NOT be
- closed, THEN manually close its block valve.
~ PCV-430, MOV-516
~ PCV-431C, MOV-515
- 2) Ensure normal PRZR spray valve controller, demand at Oe.
- 3) IF PRZR pressure decreasing AND PRZR level increasing, THEN stop RCPs one at a time until PRZR pressure stabilizes.
- 4) Ensure PRZR heaters energized.
This Step continued on the next page.
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ES-0.1 REACTOR TRIP RESPONSE REV' PAGE 10 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED (Step 8 continued from previous page) c.
PRZR pressure
- LESS THAN 2260 PSIG
- c. IF pressure greater than 2260 psig 'and increasing, THEN perform the following:
- 1) Verify demand on PRZR
.pressure controller PCV-431 greater than 50%.
IF NOT, THEN place controller in MANUAL and increase as necessary.
- 2) Ensure PRZR heaters off.
- 3) Control pressure using normal PRZR spray.
IF normal PRZR spray NOT available and letdown is in
- service, THEN perform the following:
a) Verify spray line fluid to PRZR hT less than 320'F.
IF NOT, THEN use one PORV.
b) Use auxiliary spray.
IF PRZR spray NOT available, THEN use one PRZR PORV.
REACTOR TRIP RESPONSE REV:
8 PAGE 11 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
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).
- 9 Monitor S/G Levels:
- a. Narrow range level GREATER THAN 5%
- b. Control feed flow to maintain narrow range level between 17%
and 39%.
- a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5% in at least one S/G.
- b. IF narrow range level in any S/G continues to increase, THEN stop feed to that S/G.
10 Check If TDAFW Pump Can Be Stopped:
- a. Both MDAFW pumps RUNNING b.
PULL STOP TDAFW pump steam supply valves
~ MOV-3504A
~ MOV-3505A a.
Go to Step 11.
C
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ES-0.1 REACTOR TRIP RESPONSE REV:
9 PAGE 12 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 11 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available:
o Any MSIV -
OPEN o
Annunciator G-15, STEAN DUMP ARMED - LIT
- b. Ad)ust condenser steam dump controller HC-484 to 1005 psig in AUTO
- a. Perform the following:
- 1) Place S/G ARV controller in AUTO at 1005 psig and verify proper operation.
IF S/G
2)
Go to Step lid.
- c. Place steam dump mode selector switch to MANUAL
- d. Verify RCS Tavg -
STABLE AT OR TRENDING TO 547'F
- d. Return to Step l.
12 Check RCP Status AT LEAST ONE RUNNING Perform the following:
- a. Establish conditions for starting an RCP:
o Verify bus 11A or 11B energized.
o Refer to Attachment RCP STARTS
- b. 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.
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REACTOR TRIP RESPONSE REVS 8
PAGE 13 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Loss of forced air cooling may result in failure of NIS detectors.
13 Check If Source Range Detectors Should Be Energized:
a.
Source range channels DEENERGIZED a.
Go to Step 13e.
b.
Check intermediate range flux-EITHER CHANNEL LESS THAN 10 10 AMP
- b. Perform the following:
- 1) IF neither intermediate range channel is decreasing THEN initiate boration.
- 2) Continue with Step 14.
WHEN flux is less than 10 1
amps on any operable
- channel, THEN do Steps
- 13c, d and e.
c.
Check the following:
o Both intermediate range channels
- LESS THAN 10 AMPS
- c. Continue with Step 14.
When either condition met, THEN do Steps 13d and e.
-OR-o Greater than 20 minutes since reactor trip
- d. Verify source range detectors ENERGIZED
- d. Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2
of 2).
IF source ranges can NOT be restored,'HEN refer to ER-NIS.1, SR MALFUNCTION, and go to Step 14.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
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ES-0.1 REACTOR TRIP RESPONSE REV:
8 PAGE 14 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 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:
- 2) Verify at least one control rod shroud fan RUNNING 1)
Go to Step 15.
- 2) Manually start one fan as power supply permits (45 kw).
- 3) Verify one Rx compartment cooling fan - RUNNING
- d. Dispatch AO to perform Attachment SD-1
- 3) Manually start one fan as power supply permits (23 kw).
EOP ES-0.1 REACTOR TRIP RESPONSE REV:
8 PAGE 15 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 15 Maintain Stable Plant Conditions:
a.
PRZR pressure BETWEEN 1800 PSIG AND 2260 PSIG b.
PRZR level BETWEEN 20%
AND 30%
c.
S/G narrow range levels-BETWEEN 17%
AND 39%
d.
RCS Tavg GREATER THAN 540'F
- 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.
16 Check VCT Makeup System:
- a. Verify the following:
- 1) Adjust boric acid flow control valve to 4.5 gpm 2)
RMW mode selector switch in AUTO 3)
RMW control armed RED LIGHT LIT b.
Check VCT level o
Level
- GREATER THAN 20%
O ~
-OR-o Level
- STABLE OR INCREASING
- b. Manually increase VCT makeup flow as follows:
- 1) Ensure BA transfer pumps and RMW pumps running.
- 2) Place RMW flow control valve HCV-ill in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
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ES-0.1 REACTOR TRIP RESPONSE REV:
8 PAGE 16 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 17 Check Charging Pump Suction Aligned To VCT:
a.
VCT level
- GREATER THAN 20%
- a. IF VCT 1'evel 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.
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ES-0 1
REACTOR TRIP RESPONSE REV:
8 PAGE 17 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 18 Verify TDAFW Pump Aligned For AUTO Start:
- a. Any MDAFW pump
- AVAILABLE
- b. Verify AHSAC TRIPPED status light - EXTINGUISHED
- c. Verify both S/G levels
- GREATER THAN 17$
- d. Verify the following:
1)
TDAFW pump - OFF 2)
TDAFW pump steam supply valve switches in AUTO
- a. Verify TDAFW pump operating if necessary and go to Step 20.
- b. Reset AMSAC.
- c. Continue with Step 20.
WHEN S/G level greater than 17%,
THEN do Steps 18d and 19.
- 1) IF TDAFW pump NOT required to maintain S/G level, THEN stop pump if desired.
- 2) Place TDAFW pump steam supply valve switches in AUTO.
TITLE REACTOR TRIP RESPONSE REV:
8 PAGE 18 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 19 Establish Normal AFW Pump Shutdown Alignment:
- a. Verify the following:
o Both S/G levels
- STABLE OR INCREASING
- a. Continue with Step 20.
WHEN conditions met, THEN do Steps 19b through f.
o Total AFW flow - LESS THAN 200 GPM
- b. Close MDAFW pump discharge valves
~ MOV-4007
~ MOV-4008
- d. Stop all but one MDAFW pump e.
Open AFW discharge crossover valves
~ MOV-4000A
~ MOV-4000B
- f. Open AFW bypass valves as necessary to control S/G levels
~ AOV-4480
~ AOV-4481
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8 PAGE 19 of 19 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Determine If Cooldown Is Required:
- a. Consult Plant staff to determine if RCS cooldown is necessary
- b. At least one RCP
- RUNNING c.
Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN
- a. IF cooldown NOT required, THEN go to 0-3, HOT SHUTDOWN WITH
, XENON PRESENT.
- b. Perform the following:
- 1) Ensure 2 control rod shroud fans running.
2)
Go to ES-0.2, NATURAL CIRCULATION COOLDOWN, Step 1.
-END-
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ES-F 1 REACTOR TRIP RESPONSE REV 8
PAGE 1 of 1 ES-O.1'PPENDIX LIST TITLE 1)
RED PATH
SUMMARY
2)
FIGURE MIN SUBCOOLING 3)
ATTACHMENT LETDOWN 4)
ATTACHMENT RCP START 5)
ATTACHMENT NC 6)
ATTACHMENT SD-1 7)
ATTACHMENT SD-2 8)
FOLDOUT PAGES
ES-F 1 REACTOR TRIP RESPONSE REV:
8 PAGE 1 of 1 RED PATH
SUMMARY
a.
SUBCRITICALITY Nuclear power greater than 54 b.
CORE COOLING Core exit T/Cs greater than 1200'F
-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43%
[464 adverse CNMT]
c.
HEAT SINK Narrow range level in all S/Gs less than 54
[25% adverse CNMT] AND total feedwater flow less than 200 gpm d.
INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285 F
e.
CONTAINMENT CNMT pressure greater than 60 psig
EOP:
ES-0.1 REACTOR TRIP RESPONSE REV:
8 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit: T/C Indication RC 2500 2400 2300
'200 2100 2000
- 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400
~ 300 200 100 0
S PRESSURE (PSIG)
RCS PRESSURE INCREHENTS 20 PSIG SUBCOOLED REGION ADVERSE NORHAL CNHT INADEQUATE SUBCOOLING REGION TEHPERATURE INCREHENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEHPERATURE (')
EOP:
ES-0.1 REACTOR TRIP RESPONSE REV' PAGE 1 of 1 NOTE FOLDOUT PAGE The Critical Safety Function Red Path Summary is available in APPENDIX 1.
SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o RCS subcooling based on core exit T/Cs LESS THAN O' USING FIGURE MIN SUBCOOLING OR o
PRZR level LESS THAN 5% [304 adverse CNMT]
AND RCS subcooling based on core exit T/Cs LESS THAN 20'F USING FIGURE MIN SUBCOOLING OR o
Any automatic SI setpoint is reached 2 ~
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).
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