ML17263A197
| ML17263A197 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/24/1993 |
| From: | Marlow T ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A191 | List: |
| References | |
| E-1, NUDOCS 9304080163 | |
| Download: ML17263A197 (194) | |
Text
EOP:
E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 16 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE l v>>
PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
,9304080163 930330 05000244
"." PDR ADOCK P .."
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EOP:
E-1 TLTLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 2 of 16 A. PURPOSE This procedure provides actions to recover from a loss of reactor or secondary coolant.
B. ENTRY CONDITIONS/SYMPTOMS
- l. ENTRY CONDITIONS This procedure is entered from:
- a. E-O, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
- b. E-O, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
c ~ I E 0 g REACTOR TRI P OR SAFETY NJECTION g ECA 2 1 g UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.
- d. ES-1.1, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
- e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.
f ECA 0 ~ 2 g LOSS OF ALL AC POWER RECOVERY WITH S I REQUIRED I after normal injection mode conditions are established.
- h. FR-C.1, RESPONSE TO INADEQUATE CORE COOLING, and FR-C.2, RESPONSE TO DEGRADED CORE COOLING, after core cooling has been r established.
- i. FR-H.1, RESPONSE pressure is less than TO LOSS OF SECONDARY HEAT all SINK, if non-faulted S/G(s) pressure.
- j. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are close.
EOP: TITLE:
REV: 11 E-1 'LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP 1.
NOTE ' FOLDOUT page should be open AND monitored periodically.
o Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.),
o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).,
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 Monitor RCP Trip Criteria:
- b. SI pumps - AT LEAST TWO RUNNING b, Go to Step 2.
- c. RCS pressure minus maximum S/G c. Go to Step 2.
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
EOP I E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 4 of 16 STEP ACTION/EXPECTED RESPONSE ~
RESPONSE NOT OBTAINED 2 Check If S/G Is Intact:
Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:
o Pressure in both S/Gs - GREATER ~ Steamlines THAN 100 PSIG ~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.
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).
NOTE: TDAFW pump flow control valves fail open on loss of IA.
- 3 Monitor Intact S/G Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 58 [258 adverse CNMT] than 200 gpm until narrow range level greater than 58 [258 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 178 continues to increase in an
[258 adverse CNMT] and 508 uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.
W 1
N
EOP!
REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check Secondary Radiation IF steamline radiation monitors NOT Levels NORMAL available, THEN dispatch AO to locally check steamline radiation.
o Steamline radiation monitor (R-31 and R-32) IF abnormal radiation levels detected in any S/G, THEN go to o Request HP sample S/Gs for E-3, STEAM GENERATOR TUBE RUPTURE, activity Step l.
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
- 5 Monitor PRZR PORV Status:
- a. Power to PORV block valves- a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
- c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
K EOP!
E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 6 of 16
,STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 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.
6 Reset SZ 7 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.
8 .Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 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 10.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
EOP I REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 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 if CNMT fans should be stopped 'ECIRC (Refer to Attachment CNMT RECIRC FANS).
- 3) WHEN bus 15 restored, THEN reset control room lighting.
b, Verify turbine building SW b. Manually align valves.
isolation valves - OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify at least two air c. Manually start air compressors compressors - 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 10. WHEN IA restored, THEN do Steps 9e and f.
f)
REV: 11 E-l. LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).
o Bus 14 normal feed breaker-
'CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker- to Attachment CNMT RECIRC FANS)..
CLOSED
EOP:
REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Check If Charging Been 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 ¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal in)ection needle valve(s) to affected RCP:
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0%.
- b. Charging pump suction aligned to b. Manually align valves as RWST' necessary.
LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN perform the following:
o LCV-112C - CLOSED
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 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 room).
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level
lp ', ~
EOP: T1TLE:
REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If Terminated:
SI Should Be
o Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]
o Pressure - STABLE OR INCREASING
USING FIGURE MIN SUBCOOLING
- c. Secondary heat sink: c. IF neither condition satisfied, THEN do NOT stop SI pumps. Go o Total feed flow to intact to Step 14.
S/Gs - GREATER THAN 200 GPM
-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5% [25% adverse CNMT]
- d. PRZR level - GREATER THAN 5% d; Do NOT stop SI pumps'erform
[30% adverse CNMT] the following:
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
- 2) Go to Step 14.
EOP s E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 11 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Go To ES-1.1, SI TERMINATION/
Step 1
- 14 Monitor Be If CNMT Spray Stopped:
Should
- a. CNMT spray pumps - RUNNING a. Go to Step 15.
- b. Check the following: b. Continue with Step 15. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do 'Steps 14c through f.
4 PSIG o Sodium hydroxide tank level-LESS THAN 55%
- 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
C EOP: TITLE.
REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
, CAUTION o 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.
o RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
- 15 Monitor
.Be Stopped:
If RHR Pumps Should
- a. Check RCS pressure:
- 1) Pressure - GREATER THAN 1) Go to Step 17.
250 psig [465 psig adverse CNMT]
~ INCREASING
- a. Check pressures in both S/Gs a. Return to Step 1.
STABLE OR INCREASING
- b. Check pressures in both S/Gs- b. Monitor RCS pressure. IF RCS GREATER THAN 100 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.
DECREASING
EOP: TLTLE:
REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If Emergency Should Be Stopped:
D/Gs
- a. Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Close non-safeguards bus tie o Emergency D/G output breakers breakers as necessary:
OPEN
~ Bus 13 to Bus 14 tie o AC emergency bus voltage ~ Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS
- 2) Place the following pumps in o AC emergency bus normal feed PULL STOP' breakers - CLOSED EH pumps
~ Turning gear oil pump
~ HP seal oil backup pump
- 3) Ensure condenser steam dump mode control in MANUAL.
- 4) Restore power to MCCs:
~ A from Bus 13
~ B from Bus 15
~ E from Bus 15 F from Bus 15
- 5) WHEN bus 15 restored, THEN reset control room lighting breaker.
- 6) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- 7) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
- b. Stop any unloaded emergency D/G
~
and place in standby (Refer to Attachment D/G STOP)
EOP REV'1 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:
- 1) Power available to emergency IF at least one train of cold AC busses and MCCs required leg recirculation capability can for CNMT sump recirculation NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY o Bus 14 and bus 18 COOLANT RECIRCULATION, Step 1.
ENERGIZED o MCC C - ENERGIZED o Bus 16 and bus 17-ENERGIZED o MCC D - ENERGIZED
- b. Check SW pumps - AT LEAST 2 b. Attempt to restore at least 2 SW PUMPS AVAILABLE pumps to operable. IF only 1 SW pump available, THEN refer to Attachment MIN SW for additional guidance.
- c. Dispatch AO to check AUX BLDG c. IF any RHR pump seal leakage sub-basement for RHR system indicated, THEN leakage should.
leakage (AUX BLDG sub-basement be evaluated and isolated if key may'be required) necessary.
II REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Evaluate Plant Status:
- a. Check auxiliary building a. Notify HP and refer to radiation - NORMAL appropriate AR-RMS procedure.
~ Plant vent iodine (R-10B) IF the cause is a loss of RCS
~ Plant vent particulate (R-13) inventory outside CNMT, THEN go
~ Plant vent gas (R-14) to .ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
~ CCW liquid monitor (R-17)
~ LTDN line monitor (R-9)
~ CHG pump room (R-4)
- b. Direct HP to obtain following samples:
~ RCS activity
~ BASTs,boron
- c. Verify adequate Rx head cooling:
- 2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
- 3) Verify,one Rx compartment 3) 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)
EOP:
REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 16 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If RCS Cooldown And Depressurization Is Required:
- a. RCS pressure - GREATER THAN a. IF RHR pump flow greater than 250 psig [465 psig adverse CNMT] 475 gpm, THEN go to Step 21,
- b. Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1 21 Check If Transfer To Cold Leg Recirculation Is Required:
- a. RWST level - LESS THAN 28% a. Return to Step 18.
- b. Go to ES-1;3, TRANSFER TO COLD LEG RECIRCULATION, Step 1
-END-
I EOP:
REV: 11 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITIZ PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) ATTACHMENT CNMT RECIRC
- 4) ATTACHMENT D/G STOP
- 5) ATTACHMENT SD-1
- 6) ATTACHMENT SI/UV
- 7) ATTACHMENT MIN SW
- 8) ATTACHMENT AUX BLDG SW
- 10) FOLDOUT
EOP s E-1 T1TLE0 LOSS OF REACTOR OR SECONDARY COOLANT REV ll 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'34 [464 adverse CNMT]
- c. HEAT SINK Narrow range level in all S/Gs less than 54
[254 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.
E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION ADVERS E CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10' 100 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
EOP:
REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 FOLDOUT PAGE
- 1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:
o RCS subcooling based on core exit T/Cs - LESS THAN O'F USING FIGURE MIN SUBCOOLING OR-o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%
[30% adverse CNMT]
2 ~ SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
- a. RCS subcooling based on core exit T/Cs GREATER THAN 0 F USING FIGURE MIN SUBCOOLING
- b. Total feed flow to intact S/Gs GREATER THAN 200 GPM OR-Narrow range level in at least one intact S/G GREATER THAN 5% [25% adverse CNMT]
- c. RCS pressure:
o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]
o STABLE OR INCREASING
- d. PRZR level GREATER THAN 5% [30% adverse CNMT]
- 3. 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.
- 4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step .l.
- 5. AFW SUPPLY SWITCHOVER CRITERION IF CST 'evel decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).
- 6. E-3 TRANSITION CRITERIA IF any S/G 'level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.
EOP: TITLE:
REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 38 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW 1
PORC REVIEW DATE k'LANT SUPERINTENDENT EFFECTIV DATE CATEGORY 1.0 REVIEWED BY:
0 f IC K
c A aJ
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EOP: JITLE:
REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 38 A. PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.
B. ENTRY CONDITIONS/SYMPTOMS
- l. ENTRY CONDITIONS This procedure is entered from:
- a. E-O, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or b ~ E 0 g REACTOR TRIP OR SAFETY INJECTION/
E 1 / LOSS OF REACTOR OR SECONDARY COOLANT g E-2, FAULTED STEAM GENERATOR ISOLATION, and FR HE 3 RESPONSE TO STEAM GENERATOR HIGH LEVELS when secondary radiation is abnormal, or
- c. E-O, REACTOR TRIP OR SAFETY INJECTION/
E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g ES 1 ~ 2 g POST LOCA COOLDOWN AND DEPRESSURI ZATIONg ECA 3 ~ 3 g SGTR WITHOUT PRESSURI ZER PRESSURE CONTROLS when an intact S/G narrow range level increases in an uncontrolled manner.
d ECA 3 3~ ~ SGTR WITHOUT PRESSURI ZER PRESSURE CONTROL/
when pressurizer pressure control is restored.
- e. E-1 series FOLDOUT page 'whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
~A
$ r a.a
EOP:
REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open AND monitored periodically.
o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).
o Personnel should be available for sampling during this procedure.
o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
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 Monitor RCP Trip Criteria:
- b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 2.
- c. RCS pressure minus maximum S/G c. Go to Step 2.
pressure -- LESS THAN 175 psig (400 psig adverse CNMTj
- d. Stop both RCPs
\
EOP:
REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 4 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Identify Ruptured S/G(s): Continue with Steps 6 through 11.
WHEN ruptured S/G(s) identified, o Unexpected increase in either THEN do Steps 3, 4 and 5.
S/G narrow range level
-OR-o High radiation indication on main steamline radiation monitor
~ R-31 for S/G A
~ R-32 for S/G B
-OR-o AO reports local indication of high steamline radiation
-OR-o RP reports high radiation from S/G activity sample
4 WJ
EOP: TITLE:
REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x **** *% *******************
x CAUTION o IF THE TDAFW PUMP .IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
3 Isolate Flow From Ruptured S/G (s):
- a. Adjust ruptured S/G ARV controller to'050 psig in AUTO
- b. Check ruptured S/G ARV - CLOSED b. WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed. IF NOT closed, THEN place controller in MANUAL and close S/G ARV.
IF S/G ARV can NOT be closed, THEN dispatch AO to *locally isolate.
- c. Close ruptured S/G TDAFW pump c. IF at least one MDAFW pump steam supply valve and place in running, THEN dispatch AO with PULL STOP locked valve key to locally isolate steam from ruptured S/G
~ S/G A, MOV-3505A to TDAFW pump.
~ S/G B, MOV-3504A
~ S/G A, V-3505
~ S/G B, V-3504
- d. Verify ruptured S/G blowdown d. Place S/G blowdown and sample valve - CLOSED valve isolation switch to CLOSE.
~ S/G A, AOV-5738 IF blowdown can NOT be isolated
~ S/G B, AOV-5737 manually, THEN dispatch AO to locally isolate blowdown..
~ S/G A, V-5701
~ S/G B, V-5702
a1 IllI il't U
EOP: TITLE:
REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:
- a. Close ruptured S/G MSIV- a. Perform the following:
RUPTURED S/G MSIV CLOSED
- 1) Close intact S/G MSIV.
- 2) Place intact S/G ARV controller at 1005 psig in AUTO.
- 3) Place condenser steam dump mode selector switch to MANUAL.
- 4) Adjust condenser steam dump controller to 1050 psig in AUTO.
- 5) Adjust reheat steam supply controller cam to close reheat steam supply valves.
- 6) Ensure turbine stop valves CLOSED.
- 7) Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).
IF the ruptured S/G can NOT be isolated from the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1
- b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)
L~
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EOP: TITLE:
REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x * ***
a x x x x % *x x****************
CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
5 Check Ruptured S/G Level:
- a. Narrow range level - GREATER a. IF ruptured S/G NOT faulted, THAN 5% [25% adverse CNMT) THEN perform the following:
l) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT).
- 2) Continue with Step 6. WHEN ruptured S/G level greater than 5% [25% adverse CNMT],
THEN do Steps 5b through e.
~ S/G A, MOV-4007
~ S/G B, MOV-4008
- c. Pull stop MDAFW pump for ruptured S/G
- d. Close TDAFW pump flow control d. Dispatch AO with locked valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve
~ S/G A, AOV-4297 to ruptured S/G.
~ S/G B, AOV-4298
~ S/G A, V-4005
~ S/G B, V-4006
- e. Verify MDAFW pump crosstie e. Manually close valves.
valves - CLOSED
~ MOV-4000A
~ MOV-4000B
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x ******* *******************
x %
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 6B).
- P *** x 0 x *0 ***x **************
- 6 Monitor PRZR PORVs And Block Valves:
- a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
- c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check If S/G Is Intact:
Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:
o Pressure in both S/Gs - GREATER ~ Steamlines THAN 100 PSIG ~ Feedlines IF faulted S/G NOT isolated, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
- x% ** x% x x x x ** x *****************
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).
- x 4 * % x
- x **x**% ******************
NOTE: TDAFW pump flow control valves fail open on loss of IA.
- 8 Monitor Intact S/G Level:
- 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, the narrow range level between 17% intact S/G continues to increase
[25% adverse CNMT) and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x* x ~ *% x '.
- x x
- a CAUTION
- x x**xx***x *********
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.
- ** x x x x x
- x ***x *****************
9 Reset SI 10 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.
- % *****xx**x******************
11 Check Stopped:
If RHR Pumps Should Be
- a. Check RCS pressure: a. Go to Step 12.
o Pressure - GREATER THAN 250 psig [465 psig adverse CNMTj o Pressure - STABLE OR INCREASING
- b. Stop RHR pumps and place both in AUTO
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 11 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If ruptured S/G needed for cooldown, isolation is not necessary.
12 Verify Ruptured S/G Isolated:
- a. Check ruptured MSIV - CLOSED a. IF only intact S/G MSIV can be closed, THEN ensure air ejector/gland steam supply and flange heating steam isolated.
(Refer to ATTACHMENT RUPTURED S/G, part B).
IF neither S/G MSIV can be closed THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1
- b. Ruptured S/G pressure - GREATER b. Go to ECA-3.1, SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
13 Establish Condenser Steam Dump Pressure Control:
- a. Verify condenser available: a. Adjust S/G ARV controllers to maintain intact S/G pressure in o Intact S/G MSIV - OPEN AUTO and go to Step 14.
o Annunciator G-15, STEAM DUMP ARMED - LIT
- b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
- c. Place steam dump mode selector switch to MANUAL
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.
14 Initiate RCS Cooldown:
- a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE ('F) 1100 PSIG 525 [505 adverse CNMT) 1000 PSIG 510 [490 adverse CNMT) 900 PSIG 500 [475 adverse CNMT]
800 PSIG 485 [460 adverse CNMT) 700 PSIG 465 [440 adverse CNMT) 600 PSIG 450 [420 adverse CNMT) 500 PSIG 425 [395 adverse CNMT]
400 PSIG 405 [370 adverse CNMT) 300 PSIG 375 [330 adverse CNMT)
- b. Initiate dumping steam to b. Manually or locally initiate condenser from intact S/G at steam dump from intact S/G at maximum rate maximum rate using S/G ARV.
IF no intact S/G available, THEN perform the following:
o Use faulted S/G.
-OR-o IF both S/Gs ruptured, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1
- c. Core exit T/Cs - LESS THAN c. Continue with Step 15. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required, THEN do Step 14d.
- d. Stop RCS cooldown and maintain core exit T/Cs less than required temperature
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 13 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15 Monitor All AC Busses Perform the following:
BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.
volt busses - CLOSED
- b. Perform the following as o 480 volt bus voltage - GREATER necessary:
THAN 420 VOLTS
- 1) Close non-safeguards bus tie o Emergency D/G output breakers breakers:
OPEN
~ Bus 13 to Bus 14 tie
~ Bus 15 to Bus 16 tie
- 2) Place the following pumps in PULL STOP:
~ EH pumps
~ Turning gear oil pump
~ HP seal oil backup pump
- 3) Restore power to MCCs.
~ A from Bus 13
~ B from Bus 15
~ E from Bus 15
~ F from Bus 15
- 4) Start CNMT RECIRC fans as necessary.
- 5) WHEN bus 15 restored, THEN reset control room lighting.
- c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
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REV'5 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 14 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 kw each).
IF less than two SW pumps running, THEN:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- 3) Go to Step 18.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 26 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least three SW pumps a. Manually start pumps as power RUNNING supply permits (258 kw each).
IF less than two SW pumps can be operated, THEN go to Step 37.
- b. Verify AUX BLDG SW isolation b. Establish SW to AUX BLDG (Refer valves - AT LEAST ONE SET OPEN to Attachment AUX BLDG SW).
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 27 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Normal Operation CVCS Can Be Established
- a. Verify IA restored: a. Continue with Step 37. WHEN IA restored, THEN do Steps 31 o IA to CNMT (AOV-5392) - OPEN through 36.
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 tl 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 37. WHEN any charging pump running, THEN do Steps 32 through 36.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 28 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check Should IfBe Seal Return Flow Established:
- a. Verify RCP ¹1 seal outlet a. Go to Step 33.
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.
- e. Verify RCP ¹1 seal leakoff flow e. IF any RCP seal leakoff flow LESS THAN 5.5 GPM greater than 5.5 gpm, THEN:
o Close the affected RCP seal discharge valve
~ RCP A, AOV-270A
~ RCP B, AOV-270B o Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.
- f. Verify RCP ¹1 seal leakoff flow f. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.25 GPM MALFUNCTION.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Verify PRZR Level GREATER Continue with Step 35. WHEN PRZR THAN 13% [40: adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Step 34.
34 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
~ Letdown isolation valve AOV-371 valve AOV-310.
~ Loop B cold leg to REGEN Hx AOV-427 o Slowly open HCV-123 to maintain excess letdown temperature less
- c. Place letdown controllers in than 195'F and pressure less MANUAL at 40% open than 100 psig.
~ TCV-130 o Adjust charging pump speed as
~ PCV-135 necessary.
- d. Reset both trains of XY relays IF RCP seal return NOT established, for AOV-371 and AOV-427 THEN consult TSC to determine if excess letdown should be placed in
- e. Open AOV-371 and AOV-427 service.
- 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
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 30 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check VCT Makeup System:
- a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
- b. Verify the following: b. Adjust controls as necessary.
- 1) RMW mode selector switch in AUTO
- 2) RMW control armed - RED LIGHT LIT
o Level - GREATER THAN 20%
- 1) Ensure BA transfer pumps and
-OR- RMW pumps running. IF NOT, THEN reset MCC C and MCC D UV o Level - STABLE OR INCREASING ~
lockouts as necessary.
- 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Check Charging Pump Suction Aligned To VCT:
- a. VCT level - GREATER THAN 20% a. IF 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 37. WHEN VCT level greater than 40%,
THEN do Step 36b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
o LCV-112C - OPEN o LCV-112B - CLOSED
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- xx*******xxxxxxx*xx*x*xx****x*****
- 37 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage:
- a. Perform appropriate action(s) from table:
PRZR RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase RCS Increase RCS o Increase RCS
[40% ADVERSE CNMTJ makeup flow makeup flow makeup flow o Depressurize RCS o Maintain RCS and using Step 37b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and
[40% ADVERSE CNMT) using Step 37b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and
[65% ADVERSE CNMTj using Step 37b PRZR ruptured S/G heaters pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS and
[65% ADVERSE CNMT] makeup flow PRZR ruptured S/G heaters pressure equal
- b. Control pressure using normal b. IF letdown is in service, THEN PRZR spray, if available, to use auxiliary spray (AOV-296).
obtain desired results for IF NOT, THEN use one PRZR PORV.
Step 37a
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check Should IfBe Emergency D/Gs Stopped:
- a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, 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).
Minimize Secondary System 50'.
39 Contamination:
- a. Isolate reject from hotwell to IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.
o Place hotwell level controller (LC-107) in MANUAL at o Verify hotwell level - STABLE
- b. Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 34 of 38 STEP ACTION/EXPECTED'ESPONSE RESPONSE NOT OBTAINED 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
o Annunciator A-7, RCP 1A CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED
- b. Check RCP seal injection:
o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR-o RCP seal injection flow to each RCP - GREATER THAN 6 GPM
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- xx x*0 xxxxx%xx'xx%'*x4***x****x*******
CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
- 4 *4 x x w * ~ *********** *'* * * * * * * *
- 42 Check RCP Status:
- a. RCPs - AT LEAST ONE RUNNING a. Perform the following:
- 1) Try to start one RCP:
a) Ensure conditions for starting an RCP.
o Bus llA or 11B energized.
o Refer to Attachment RCP START.
b) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:
o Increase PRZR level to greater than 65% (80%
adverse CNMTj.
o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.
c) Start one RCP.
- 2) IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT be verified, THEN increase dumping steam.
- b. Stop all but one RCP
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 36 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
43 Check If Source Detectors Should Range Be Energized:
- a. Source range channels a. Go to Step 43e.
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 44. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 43c through e.
- c. Check the following: c. Continue with Step 44. WHEN either condition met, THEN do o Both intermediate range Steps 43d 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'OT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 37 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:
- a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
- b. Perform the following:
i 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 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
- 3) Verify one Rx compartment 3) 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
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:
o Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1
-OR-o Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1
-OR-o Go to ES-'3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1
-END-
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) ATTACHMENT CNMT RECIRC FANS
- 4) ATTACHMENT D/G STOP
- 5) ATTACHMENT N2 PORVS
- 6) ATTACHMENT NC
- 7) ATTACHMENT SEAL COOLING
- 8) ATTACHMENT RCP START
- 9) ATTACHMENT RUPTURED S/G
- 10) ATTACHMENT SD-1
- 11) ATTACHMENT SD-2
- 12) ATTACHMENT AUX BLDG SW
- 13) FOLDOUT
4 EOP:
REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH
SUMMARY
- a. SUBCRITICALITY Nuclear power greater than 5~
- 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
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REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below t'-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION DV ERS E C 500 400 300 200 NORMAL CNMT TEMPERATURE 100 INCREMENTS 10'F 0
200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE (')
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REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1:
o RCS subcooling based on core exit T/Cs LESS THAN 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [304 adverse CNMT).
2 4 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 ~ COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step l.
- 4. 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).
- 5. MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ' GENERATORS PAGE 1 of 31 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RES 0 SIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA 1 GENERATORS PAGE 2 of 31 A. PURPOSE This procedure provides actions to mitigate and minimize a loss of secondary coolant from both steam generators.
B. ENTRY CONDITIONS/SYMPTOMS 1- ENTRY CONDITIONS This procedure is entered from:
- a. E-2, FAULTED STEAM GENERATOR ISOLATION, when an uncontrolled depressurization of both steam generators occurs.
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REV: 12 UNCONTROLLED DEPRESSURIZATZON OF BOTH STEAM ECA-2.1 GENERATORS PAGE 3 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
NOTE: o FOLDOUT page should be open AND monitored periodically.
o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
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 Secondary Pressure Manually close valves one loop at a Boundary: time.
o MSIVs - CLOSED IF valves can NOT be closed, THEN dispatch AO to locally isolate o MFW flow control valves - CLOSED flowpaths, as necessary, one loop at a time.
~ MFW regulating valves
~ MFW bypass valves o MFW pump discharge valves CLOSED V
o S/G blowdown and sample valves CLOSED o TDAFW pump steam supply valves PULL STOP o TDAFW pump flow control valves CLOSED o S/G ARVs - CLOSED o Dispatch AO to locally isolate S/Gs (Refer to Attachment FAULTED S/G)
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 4 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION A MINIMUM FEED FLOW OF 50 GPM MUST BE MAINTAINED TO EACH S/G WITH A NARROW RANGE LEVEL LESS THAN 5% [25% ADVERSE CNMT].
2 Control Feed Flow To Minimize RCS Cooldown:
- a. Check cooldown rate in RCS cold a. Decrease feed flow to 50 gpm to legs -'ESS THAN 100'F/HR each S/G and go to Step 2c.
- b. Check narrow range level in both b. Control feed flow to maintain S/Gs - LESS THAN 50% narrow range level less than 50%
in both S/Gs.
- c. Check RCS hot leg temperatures c. Control feed flow or dump steam STABLE OR DECREASING to stabilize RCS hot leg temperatures.
3 Check Stopped:
If RCPs Should Be
- b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 4.
- c. RCS pressure minus maximum S/G Go to Step 4.
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 5 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check CST Level GREATER 'witch to alternate AFW suction THAN 5 FEET supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
- 5 Monitor PRZR PORVs And Block Valves:
- a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN dispatch AO to locally check breaker.
~ MOV-515, MCC C position 6C
~ MOV-516, MCC D position 6C
- c. Block valves - AT LEAST ONE OPEN c.'Open one block valve unless it was closed to isolate an open PORV.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 6 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels NORMAL RUPTURE, Step l.
o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity 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.
7 Reset SI
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REV 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 7 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED. IF .RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
- 8 Monitor Be If Stopped:
RHR Pumps Should
- a. RHR pumps - ANY RUNNING a. Go to Step 9.
- b. Check RCS Pressure:
- 1) Pressure - GREATER THAN 1) Go to E-l, LOSS OF REACTOR OR 250 psig [465 psig adverse SECONDARY COOLANT, Step 1.
CNMT]
- 2) Pressure - STABLE OR 2) Go to Step 9.
INCREASING
- c. Stop RHR pumps and place in AUTO
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 8 of 31 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 the following: b. Continue with Step 10. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do Steps 9c through f.
4 PSIG o Sodium hydroxide tank level LESS THAN 55%
- 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 ~ 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,
l~
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 9 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check RWST Level GREATER Go to ES-1.3, TRANSFER TO COLD LEG THAN 284 RECIRCULATION, Step l.
ll 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.
12 Verify Adequate SW Flow:
- a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 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 14.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
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REV: 12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 10 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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) WHEN 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 at least two air c. Manually start air compressors compressors - 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) C'ontinue attempts to restore 60 PSIG IA (Refer,to AP-IA.1, LOSS OF INSTRUMENT AIR).
o Pressure - STABLE OR INCREASING 2) Continue with Step 14. WHEN IA restored, THEN do Steps 13e and f.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ' GENERATORS PAGE 11 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If SI Isolated:
ACCUMs Should Be
- a. Both RCS hot leg temperatures a. Go to Step 15.
LESS THAN 400'F
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
~ MOV-841 1) Open vent valves for
~ MOV-865 unisolated SI ACCUMs,
~ ACCUM A, AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865 15 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).
o Bus 14 normal feed breaker CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker- to.Attachment CNMT RECIRC FANS).
CLOSED
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 12 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 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 ¹1 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 Oa.
- b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN perform the following:
o LCV-112B - OPEN 1) Verify charging pump A NOT running and place in PULL o LCV-112C - CLOSED STOP.
- 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 room).
- c. Start charging pumps as
'ecessary and adjust charging flow to restore PRZR level
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 13 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17 Monitor SI Termination Criteria:
pumps'
- a. SI pumps - ANY RUNNING a. Go to Step 19.
Perform the following:
o Pressure - GREATER THAN 1625 psig [1825 psig adverse 1) Energize PRZR heaters and CNMT] operate PRZR spray as necessary to stabilize RCS o Pressure - STABLE OR pressure greater than INCREASING 1625 psig [1825 psig adverse CNMT)
- 2) Return to Step 2.
- c. RCS subcooling based on core c. DO NOT stop SI pumps. Return to exit T/Cs - GREATER THAN O' Step 2.
USING FIGURE MIN SUBCOOLING
- d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Perform
[30% adverse CNMT) the following:
- 1) IF normal 'PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray,
- 2) Return to Step 17a.
NOTE: Foldout Page E-2 transition criteria does not apply while performing steps 18 and 19.
18 Stop SI and RHR Pumps And Place In Auto
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA 2. 1 GENERATORS PAGE 14 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 19 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary and return to Step 2.
USING FIGURE MIN SUBCOOLING
- 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 operate SI pumps as necessary and return to Step 2.
20 Check RCS Hot Leg Control feed flow or dump steam to Temperatures STABLE OR stabilize RCS hot leg temperatures.
DECREASING 21 Check Narrow Range Level In Control feed flow to maintain Both S/Gs LESS THAN 504 narrow range level less than 50% in both S/Gs.
22 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (258 kw per pump). IF less than two SW pumps can be operated, THEN go to Step 28
- b. Verify AUX BLDG SW isolation Establish SW to AUX BLDG (Refer valves - OPEN to Attachment AUX BLDG SW).
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE AIARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 15 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Normal CVCS Operation Can Be Established
- a. Verify IA restored: a. Continue with Step 28. WHEN IA restored, THEN do Steps 23 o IA to CNMT (AOV-5392) - OPEN through 27.
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 f
temperature of scale 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 28. WHEN any charging pump running, THEN do Steps 24 through 27.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 16 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Verify PRZR Level GREATER Continue with Step 26. WHEN PRZR THAN 134 [40% adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Step 25.
25 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess
- a. Verify 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 AOV-310. 'alve 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 TSC to determine if for AOV-371 and AOV-427 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
EOP: T1TLE REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 17 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 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
o Level - GREATER THAN 20%
- 1) Ensure BA transfer pumps 'and
-OR- RMW pumps running. IF NOT, THEN reset MCC C and MCC D UV o Level - STABLE OR INCREASING lockouts as necessary.
- 2) Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.
- 3) Increase boric acid flow as necessary.
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REV 12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 18 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check Charging Pump Suction Aligned To VCT:
- a. VCT level - GREATER THAN 20% a. IF 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 28. WHEN VCT level greater than 40%,
THEN do'tep'7b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT: necessary.
o LCV-112C - OPEN o LCV-112B - CLOSED
EOP: TITLES REV 12 UNCONTROLLED DEPRESSURXZATZON OF BOTH STEAM ECA-'2. 1 GENERATORS PAGE 19 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check RCP Cooling: 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, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED
- b. Check'RCP seal injection:
o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER
-OR-o RCP seal injection flov to each RCP - GREATER THAN 6 GPM
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 20 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Check If Seal Return Flow Should Be Established:
- a. Verify RCP ¹1 seal outlet a. Go to Step 30.
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.
- e. Verify RCP ¹1 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 30.
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UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM REV: 12 ECA-2. 1 GENERATORS PAGE 21 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.
o When using PRZR PORV, select one with an operable block valve.
30 Energize Heaters And Operate IF normal'pray NOT available and Normal Spray As Necessary To letdown is in service, THEN use Maintain RCS Pressure Stable auxiliary spray valve (AOV-296).
IF PRZR spray NOT'vailable', THEN use one PRZR PORV.
IF IA NOT available, THEN refer to Attachment N2 PORVS.
C EOP:
ECA-2.1'1ILE:
UNCONTROLLED REV 12 DEPRESSURIZATION OF BOTH STEAM GENERATORS PAGE 22 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Verify All, AC Busses Perform the following:
ENERGIZED BY OFFSITE PONER
- 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 bus voltage - GREATER THAN b. Perform the following, as 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) Place the following pumps in PULL STOP:
~ EH pumps
~ Turning gear oil pump
~ HP seal oil backup pump
- 3) Restore power to MCCs.
~ A from Bus 13 4 B from Bus 15
~ E from Bus 15
~ F from Bus 15
- 4) WHEN bus 15 restored, THEN reset control room lighting..
- 5) 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.1, RESTORATION OF OFFSITE POWER).
I EOP: T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 1 GENERATORS PAGE 23 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATIONS 32 Check RCP Status ONE RUNNING
'T LEAST Try to start one RCP:
- a. Establish conditions for starting an RCP.
o Bus 11A or 11B energized I
o Refer to Attachment RCP START.
- b. Start one RCP.
IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT be verified, THEN increase feed flow or dumping steam.
ilk EOP: TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 24 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
33 Check If Source Detectors Should Range Be Energized:
- a. Source range channels a. Go to Step 33e.
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 34. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 33c, d and e.
- c. Check the following: c. Continue with step 34. WHEN either condition met, THEN do o Both intermediate range Steps 33d 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.l, SR MALFUNCTION and go to Step 34.
- e. Transfer Rk-45 recorder 'to one source range and one intermediate range channel.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 25 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check If Emergency Should Be Stopped:
D/Gs
- a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, 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)
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 26 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 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
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1 GENERATORS PAGE 27 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Maintain Plant Conditions Control plant systems as necessary STABLE to maintain conditions stable.
o RCS pressure o PRZR level o RCS temperatures
- 37 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary. Return to Step 2.
USING FIGURE MIN SUBCOOLING
- 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 operate SI pumps as necessary.
Return to Step 2 ~
'I
'4
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1 GENERATORS PAGE 28 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check Isolated:
If SI ACCUMs Should Be
- a. Check the following: a. Go to Step 39.
o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%
[30% adverse CNMT]
~ MOV-841, MCC C position 12F
~ MOV-865, MCC D position 12C
- c. Close SI ACCUM discharge valves c. Vent any unisolated ACCUMs:
~ MOV-841 1) Open vent valves for
~ MOV-865 unisolated SI ACCUMs.
~ ACCUM A; AOV-834A
~ ACCUM B, AOV-834B
- 2) Open HCV-945.
- d. Locally reopen breakers for MOV-841 and MOV-865
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 29 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Check RCS Hot Leg Control feed flow and dump steam to Temperatures LESS THAN 350'F .establish RCS cooldown rate less than 100'F/hr in RCS cold legs.
NOTE: o If auxiliary spray is in use, spray flow may be increased by AOV-294 and normal PRZR spray valves.
closing normal charging valve o When using PRZR PORV, select one with operable block valve.
40 Check RCS Pressure LESS Use normal PRZR spray.
THAN 400 PSIG [300 PSIG adverse CNMT] e IF normal spray NOT available and letdown is in service, THEN use auxiliary spray.
IF NOT, THEN use one PRZR PORV.
IF IA NOT available, THEN refer to Attachment N2 PORVS.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 30 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Check Can Be IfEstablished:
RHR Normal Cooling
- a. RCS cold leg temperature - LESS a. Return to Step 37 THAN 350'F RCS pressure - LESS THAN b. Return to Step 40.
400 psig [300 psig adverse CNMT]
- c. Place letdown pressure controller (PCV-135) in MANUAL CLOSED
- d. Check following valves - OPEN d. Perform the following:
~ AOV-371, letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and
~ AOV-'427, loop B cold leg to AOV-427 REGEN Hx ')
~ At least one letdown orifice Open AOV-371 and AOV-427.
valve (AOV-200A, AOV-200B, or AOV-202) 3) Open one letdown orifice valve.
- e. Verify pressure on PI-135 - LESS e. Return to Step 40.
THAN 400 PSIG
- f. Place RCS overpressure f. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 31 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 42 Continue RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
,b. Check narrow range level in both b. Control feed flow to maintain S/Gs - LESS THAN 50% narrow range level less than 50% 'n both S/Gs.
43 Check Core Exit T/Cs LESS Return to Step 42.
THAN 200'F 44 Evaluate Long Term Plant Status:
- a. Maintain cold shutdown conditions
- b. Consult TSC
-END-
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS PAGE 1 of 1 ECA-2.1 APPENDIX LIST TITLE PAGES
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING
- 3) ATTACHMENT FAULTED S/G
- 4) ATTACHMENT CNMT RECIRC FANS
- 5) ATTACHMENT NC 6)- ATTACHMENT RCP START
- 7) ATTACHMENT N2 PORVS
- 8) ATTACHMENT SEAL COOLING
- 9) ATTACHMENT SI/UV
- 10) ATTACHMENT D/G STOP
- 11) ATTACHMENT SD-1
- 12) ATTACHMENT SD-2
- 13) ATTACHMENT RHR COOL
- 14) ATTACHMENT AUX BLDG SW
- 15) FOLDOUT
EOP: T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS 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
[254 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
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REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREHENTS 20 PSIG 2200 2100 2000 1900
'800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION ADVERSE CNHT 500 400 300 200 NORHAL CNHT TEHPERATURE INCREHENTS 10'F 100 0
20 0'50 300 350 EXIT 400 450 SATURATION 500 TEHPERATURE 550
('F) 600 650 700 CORE
EOP! TITLE!
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 1 of 1 FOLDOUT PAGE
if EITHER condition o RCS subcooling based on core exit TCs LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54
[304 ADVERSE CNMT]
- 2. E-2 TRANSITION CRITERIA IF any S/G pressure increases at any time (except while performing SI termination in Steps 18 and 19), THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
- 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
- 4. LOSS OF EMERGENCY COOLANT RECIRCULATION CRITERION IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, 'Step 1.