ML17265A515
| ML17265A515 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/14/1999 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17265A517 | List: |
| References | |
| PROC-990114, NUDOCS 9901220067 | |
| Download: ML17265A515 (159) | |
Text
EOP TITLE:
REV 14 AP-SW. 1 SERVICE WATER LEAK PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIB MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
vv<nmoosv esoxxs PDR ADQCK 05000244 F PDR
EOP: TITLE:
REV: 14 AP-SW. 1 SERVICE WATER LEAK PAGE 2 of 10 A. PURPOSE This procedure provides the necessary instructions to respond to a service water system leak.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. SYMPTOMS The symptoms of SERVICE WATER LEAK are:
- a. Service water header pressure low alarms on computer, or
- c. Unexplained increase in the waste hold-up tank, or
- d. Visual observation of a SW leak, or
- e. Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217 F, lit, or
- f. Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 1050 GPM, lit, or
- g. Annunciator E-31, CONTAINMENT RECIRC FAN CONDENSATE HI-HI LEVEL alarm, exhibits an unexplained increase in frequency, or
- h. Annunciator H-G, CCW SERVICE WATER LO FLOW 1000 GPM, lit.
EOP TITLE:
REV: 14 AP-SW.1 SERVICE WATER LEAK PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 l
- 0 l I I f 1 i f 0 t ~ ~
- i ~ 1
- 1 1 1
- 1 0 t 1
- I 4 t 1 4 ~ ~ 1 ~ ~
CAUTION o IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION. SHALL BE PERFORMED.
o IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.
1 Verify 480V AC Emergency Ensure associated D/G(s) running Busses 17 and 18 ENERGIZED and attempt to manually load busses 17 and/or 18 onto the D/G(s) if necessary.
2 Verify At Least One SW Pump IF a SW pump has tripped, THEN Running In Each Loop: ensure other pump in the affected loop is running.
~ A or B pump in loop A
~ C or D pump in loop B
, y h 0 A ~
EOP:
REV: 14 AP-SW.1 SERVICE WATER LEAK PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Abnormally low pressure in either SW loop may indicate that the idle pump check valve is open. This may be corrected by restarting or isolating the idle pump.
3 Check SW System Status:
- a. Check SW loop header pressures: a. IF three SW pumps operating and either loop pressure less than o Pressure in both loops- 40 psig. THEN trip the reactor APPROXIMATELY EQUAL and go to E-0. REACTOR TRIP OR SAFETY INJECTION.
o PPCS SW low pressure alarm status - NOT LOW IF only two SW pumps operating and either loop pressure less o Pressure in both loops than 45 psig, THEN start one STABLE OR INCREASING additional SW pump (243 kw each pump).
- b. Check SW loop header pressures b. IF either SW loop pressure is GREATER THAN 55 PSIG less than 55 PSIG with three SW pumps running AND cause can NOT be corrected, THEN initiate a controlled shutdown while continuing with this procedure (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).
~ ~
EOP:
REV: 14 AP-SW. 1 SERVICE WATER LEAK PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If SW is lost to any safeguards equipment, the affected component should be declared inoperable and appropriate actions taken as required by ITS, Section 3.
o CNMT sump A level of 10 feet is approximately 6 feet 6 inches below the bottom of the reactor vessel.
4 Check For SW Leakage In CNMT:
o Sump A level - INCREASING
-OR-o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)
- b. Evaluate Sump A conditions: b. Plant shutdown should be considered, consult plant staff.
- 1) Verify Leakage within capacity of one Sump A pump (50 gpm)
- 2) Check Sump A level - LESS THAN 10 FEET
V
& 4 r-
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REV 14 AP-SW.1 SERVICE WATER LEAK PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 ~ t 4 I
- 1 '0 I * ~ 4 1 1 4 1
- 1 0 *
- 4 t 1 1 4 4 0 ~ I I 4
- 1 1 1 1 t ~
CAUTION BEFORE ISOLATING SW TO CNMT RECIRC FANS. REFER TO ITS SECTION 3.6.6 FOR OPERABILITY REQUIREMENTS.
NOTE: o One Reactor Compartment cooling fan should be running whenever RCS temperature is greater than 135 F.'
CNMT recirc fan condensate collector level indicators may be helpful in identifying a leaking fan cooler.
5 Check CNMT fan indications: Dispatch AO to perform Attachment SW LOADS IN CNMT as necessary.
o CNMT recirc fan collector dump WHEN CNMT SW leak location frequency - NORMAL (Refer to RCS identified, THEN go to Step 9.
Daily Leakage Log) o CNMT recirc fan SW flows APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP) o Reactor compartment cooler SW outlet pressures - APPROXIMATELY EQUAL (INTER BLDG SAMPLE HOOD AREA)
~ Cooler A - PI 2232
~ Cooler B - PI 2141
1 4 ~ h 't I k
'l e ~' s > ~ ~ ~
EOP:
REV: 14 AP-SW. 1 SERVICE WATER LEAK PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Dispatch AO To Screenhouse To Perform The Following:
- a. Verify idle SW pump check valve a. Notify Control Room of any closed indication of check valve failure.
o Idle pump shaft stopped o Idle pump discharge pressure ZERO (unisolate and check local pressure indicator)
- b. Investigate for SW leak in b. Perform the following:
Screenhouse - NO EXCESSIVE LEAKAGE INDICATED 1) Identify leak location.
IP increase in leakage from underground header indicated, THEN isolation of header should be considered (Refer to Attachment SW ISOLATION)
- 2) Notify Control Room of leak location.
NOTE: Refer to Attachment SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.
7 Check Indications For Leak Dispatch AO to the specific area to Location: investigate for leakage.
o AUX BLDG sump pump start frequency - NORMAL (Refer to RCS Daily Leakage Log) o Annunciator L-9. AUX BLDG SUMP HI LEVEL - EXTINGUISHED o Annunciator L-17, INTER BLDG SUMP HI LEVEL " EXTINGUISHED
I
~ ' ~
EOP:
REV 14 AP-SW. 1 SERVICE WA'gER LEAK PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Dispatch AO To Locally Investigate For SW Leakage And To Monitor Operating Equipment
~ Turbine BLDG
~ SAFW pump room
I ~ ~ e ~ ~
I'
(
I ~ W 4\ ~ ~k
fOP:
REV: 14 AP-SW. 1 SERVICE WATER LEAK PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED If is lost to either to ER-D/G.2.
if coolingD/G,is refer NOTE: SW ALTERNATE COOLING FOR EMERGENCY D/Gs. required.
9 Evaluate SW Leak Concerns
- a. Check SW pump status - AT LEAST a. IF either SW header pressure THREE PUMPS RUNNING less than 45 psig, THEN start third SW pump.
o Close V-4669 OR V-4760 in B D/G room.
o Close V-4611 OR V-4612 in Screenhouse.
o Close V-4625 OR V-4626 in INT BLDG clean side.
o Close V-4639 OR V-4756 in INT BLDG clean side.
- 2) IF plant at power, THEN initiate a controlled shutdown (Refer to 0-2.1.
NORMAL SHUTDOWN TO HOT SHUTDOWN).
- 3) Go to Step 10.
- c. Verify leak location - IDENTIFIED c. Return to Step 3.
- d. Verify plant operating at power d. Verify SW system conditions appropriate for plant mode (Refer to ITS Section 3.7.8) and go to Step 10.
- e. Leak isolation at power- e. IF plant shutdown required. THEN ACCEPTABLE refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
'I I b EOP:
REV: 14 AP-SW.1 SERVICE WATER LEAK PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Dispatch AO(s) To Locally Isolate SW Leak As Necessary ll Verify SW Leak Isolated
- a. Monitor SW System Operation a. IF SW leak can NOT be isolated within the affected header, THEN o SW loop header pressure stop SW pumps in the affected RESTORED TO PRE-EVENT VALUE loop and go to Step 12.
Archive PPCS point,ID loop A P2160 OR loop B P2161) o Both SW loop header pressures STABLE
- b. Verify at least one SW pump b. Refer to ITS Section 3.7.8 for available from each screenhouse , limiting conditions for AC Emergency bus operation.
~ Bus 17 SW pumps B or D
~ Bus 18 SW pumps A or C NOTE: o Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
o An Action Report, per IP-CAP.1, should be submitted for a SW leak in CNMT.
12 Notify Higher Supervision
-END-
EOP:
REV: 14 AP-SW. 1 SERVICE WATER LEAK PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE
- 1) ATTACHMENT SW ISOLATION (ATT-2. 2)
EOP:
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INACTION PAGE 2 of 26 A. PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection and to assess plant conditions, and identify the appropriate recovery procedure.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. The following are symptoms that require a reactor trip,'f one has- not occurred:
o Any plant parameter reaches a reactor trip setpoint and logic as listed in procedure P-l, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discretion.
- 2. The following are symptoms of a reactor trip:
o Any, First Out reactor trip annunciator lit.
o A rapid decrease in core neutron level as indicated by nuclear instrumentation.
o MRPI Indicates all control and shutdown rods on bottom.
o Reactor trip breakers indicate open.
- 3. The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
o Any plant parameter reaches the Safety Injection setpoint and logic as listed in procedure P-l, REACTOR CONTROL AND PROTECTION SYSTEM.
o Operator discretion.
- 4. The following are symptoms of a reactor trip and safety injection:
o Any SI annunciator lit.
o Safeguards sequencing started.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Manually trip reactor.
o At least one train of reactor IF reactor trip breakers NOT open.
trip breakers - OPEN THEN perform the following:
o Neutron flux - DECREASING a. Open Bus 13 and-Bus 15 normal feed breakers.
o MRPI indicates - ALL CONTROL AND SHUTDOWN RODS ON BOTTOM b. Verify rod drive MG sets tripped.
- c. Close Bus 13 and Bus 15 normal feed breakers.
- d. Reset lighting breakers.
IF the reactor will NOT trip OR IF power range NIS indicates greater than 5'/., THEN go to FR-S.l, RESPONSE TO REACTOR RESTART/ATWS.
Step 1 2 Verify Turbine Stop Valves Manually trip turbine.
CLOSED IF turbine trip can NOT be verified. THEN close both MSIVs.
3 Verify Both Trains Of AC Attempt to start any failed Emergency Busses Energized To emergency D/G to restore power to At Least 420 VOLTS: all AC emergency busses.
~ Bus 14 and Bus 18 IF power can NOT be restored to at
~ Bus 16 and Bus 17 least one train. THEN go to ECA-O.O. LOSS OF ALL AC POWER.
Step 1.
EOP:
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- a. Any SI Annunciator - LIT a. IF any of the following conditions are met, THEN manually actuate SI and CI:
o PRZR pressure less than 1750 psig
-OR-o Steamline pressure less than 514 psig
-OR-o CNMT pressure greater than 4 psig
-OR-o SI sequencing started'OR-o Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.
STARTED.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open and monitored periodically.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+0> R/hr.
5 Verify SI and RHR Pumps Running:
- a. All SI pumps - RUNNING a. Perform the following:
- 2) Manually start pumps.
- b. Both RHR pumps - RUNNING b. Manually start pumps.
6 Verify CNMT RECIRC Fans Running:
- a. All fans - RUNNING a. Manually start fans.
- b. Charcoal filter- dampers green b. Dispatch personnel to relay room status lights EXTINGUISHED with relay rack key to locally open dampers by pushing in trip relay plungers.
~ AUX RELAY RACK RA-2 for fan A
~ AUX RELAY RACK RA-3 for fan C
EOP:
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
Required:
IF CNMT spray NOT initiated, THEN o Annunciator A-27. CNMT SPRAY- perform the following:
EXTINGUISHED
- b. Ensure CNMT spray pumps running.
IF no CNMT spray pump available.
THEN go to Step 8.
- c. Ensure CNMT spray pump discharge valves open for operating pump(s).
o CNMT spray pump A:
~ MOV-860A
~ MOV-860B o CNMT spray pump B:
0 MOV-860C
~ MOV-860D
- d. Ensure NaOH tank outlet valves open.
~ AOV-836A
~ AOV-836B
EOP:
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Main Should Be Steamlines Isolated:
- a. Any MSIV - OPEN a. Go to Step 9.
- c. Check if ANY main steamlines should be isolated:
- c. Go to Step 9.
o Low Tavg (545 F) AND high steam flow (0.4xl06 lb/hr) from either S/G
-OR-o High-High steam flow (3.6x106 lb/hr) from either S/G
- d. Verify MSIV closed on the d. Manually close valves.
affected S/G(s) 9 Verify MFW Isolation:
~ MFW regulating valves controllers in MANUAL at 0%
~ MFW bypass valves demand.
- c. S/G blowdown and sample valves c. Place S/G blowdown and sample CLOSED valve isolation switch to CLOSE.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 8 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Verify AFW Pumps Running:
- b. TDAFW pump - RUNNING IF b. Manually open steam supply NECESSARY valves.
~ MOV-3505A
~ MOV-3504A 11 Verify At Least Two SW Pumps Perform the following:
RUNNING
~ Bus 17
~ Bus 18
- b. IF offsite power NOT available, THEN ensure SW isolation.
EOP: TITLE:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 9 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify CI And CVI:
- a. CI and CVI annunciators - LIT a. Depress manual CI pushbutton.
~ Annunciator A-26. CNMT ISOLATION
~ Annunciator A-25. CNMT VENTILATION ISOLATION
- b. Verify CI and CVI valve status b. Manually close CI and CVI valves lights - BRIGHT as required'F valves can NOT be verified closed by MCB indication, THEN dispatch AO to locally close valves (Refer to Attachment CI/CVI for alternate isolation valves).
- c. CNMT RECIRC fan coolers SW c. Dispatch AO to locally fail open outlet valve status lights valves.
BRIGHT
~ FCV-4561
~ FCV-4562
~ ~ ~ I I I ~ ~ ~ I ~ I I I ~ I I *
- I ~ I ~ I I ~ ~ ~ I I I I I I I I * ~ ~ I ~
CAUTION RCP TRIP CRITERIA LISTED ON FOLDOUT PAGE SHOULD BE MONITORED PERIODICALLY'3 Check CCW System Status:
- a. Verify CCW pump - AT LEAST ONE a. IF offsite power available, THEN RUNNING manually start one CCW pump.
- b. Place switch for excess letdown AOV-310 to CLOSE
- c. Verify CCW from excess letdown c. Manually close valve.
AOV-745 - CLOSED
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 10 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify SI And RHR Pump Flow:
- a. SI flow indicators - CHECK FOR a. IF RCS pressure less than FLOW 1400 psig, THEN manually start pumps and align valves. IF NOT, THEN go to Step -15.
- b. RHR flow indicator - CHECK FOR b. IF RCS pressure less than FLOW 140 psig, THEN manually start pumps and align valves. IF NOT, THEN go to Step 15.
15 Verify Total AFW Flow IF S/G narrow range level greater GREATER THAN 200 GPM than 5% [25% adverse CNMT] in any S/G, THEN control AFW flow to maintain narrow range level.
IF narrow range level less than 5%
[25% adverse CNMT] in all S/Gs, THEN manually start pumps and align valves as necessary. IF AFW flow greater than 200 gpm can NOT be established, THEN go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. Step 1.
16 Verify AFW Valve Alignment: Manually align valves as necessary.
- a. AFW flow - INDICATED TO BOTH S/G(s)
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify SI Pump And RHR Pump Emergency Alignment:
- a. RHR pump discharge to Rx vessel a. Ensure at least one valve open.
deluge - OPEN
~ MOV-852A
~ MOV-852B
- b. Verify SI pump C - RUNNING b. Manually start pump on available bus.
- c. Verify SI pump A - RUNNING c. Perform the following:
- 1) Ensure SI pumps B and C running. IF either pump NOT.
running, THEN go to Step 17e.
- 2) Ensure SI pump C aligned to discharge line A:
o MOV-871A open o MOV-871B closed
- 3) Go to Step 18.
- d. Verify SI pump B - RUNNING d. Perform the following:
- 1) Ensure SI pumps A and C running. IF either pump NOT, running, THEN go to Step 17e.
- 2) Ensure SI pump C aligned to discharge line B:
o MOV-871B open o MOV-871A closed
- 3) Go to Step 18.
- e. Verify SI pump C discharge e. Manually open valves as valves OPEN necessary.
~ MOV-871A
~ MOV-871B
EOP: TITLE:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 0 4 ~ ~ 1 4 ~ ~ 1 1 4 1 i 1 ~ 0 I 4 ~ 1 1 4 ~ ~ P 4
- 0 0 I 1 4 0 ~ ~
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.
18 Check CCW Flow to RCP Thermal IF CCW to a RCP is lost, THEN Barriers: perform the following:
o Annunciator A-7, RCP 1A CCW a. Stop affected RCPs.
RETURN HI TEMP OR LO FLOW-EXTINGUISHED b. Reset SI.
o Annunciator A-15, RCP 1B CCW c. Verify adequate power available RETURN HI TEMP OR LO FLOW to run one charging pump (75 kw).
EXTINGUISHED
- d. Start one charging pump at minimum speed for seal injection.
- e. Adjust HCV-142 to establish either of the following:
o Labyrinth seal D/P to each RCP greater than 15 inches of water.
-OR-o RCP seal injection flow to each RCP greater than 6 gpm.
- f. IF large imbalance in seal injection flow exists, THEN consider local adjustment of V-300A and V-3008.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 13 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped:
- a. Both MDAFW pumps - RUNNING a. Go to Step 20.
- b. PULL STOP TDAFW-pump steam supply valves
~ MOV-3504A
~ MOV-3505A
- 20 Monitor RCS Tavg STABLE AT IF temperature less than 547'F and OR TRENDING TO 547 F decreasing, THEN perform the following:
- a. Stop dumping steam.
- b. Ensure reheater steam supply valves are closed.
- c. IF cooldown continues, THEN control total feed flow greater than 200 gpm until narrow range level greater than 5'5 [25/
adverse CNMT] in at least one S/G.
- d. WHEN S/G level greater than 5%
[251o adverse CNMT] in one S/G.
THEN limit feed flow to that required to maintain level in at least one S/G.
- e. IF cooldown continues, THEN close both MSIVs.
IF temperature greater than 547'F and increasing, THEN dump steam to stabilize and slowly decrease temperature to 547'F.
fop:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 14 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check PRZR PORVs And Spray Valves:
- a. PORVs - CLOSED a. IF PRZR pressure less than
'2335 psig, THEN manually close PORVs.
IF any valve can NOT be closed, THEN manually close its block valve.
~ MOV-516 for PCV-430
~ MOV-515 for PCV-431C IF block valve can NOT be closed. THEN go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT.
'tep 1 ~
- b. Auxiliary spray valve (AOV-296) b. Manually close auxiliary spray CLOSED valve. IF valve can NOT be closed. THEN perform the following:
- 1) Decrease charging pump flow to minimum.
- 2) Ensure charging valve to loop B cold leg open (AOV-294).
- c. Check PRZR pressure - LESS THAN c. Continue with Step 22. WHEN 2260 PSIG pressure less than 2260 psig.
THEN do Steps 21d.
- d. Normal PRZR spray valves - CLOSED d. Place controllers in MANUAL at 0/. demand. IF valves can NOT be
~ PCV-431A closed, THEN stop associated
~ PCV-431B RCP(s).
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 15 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22 Monitor RCP Trip Criteria:
- b. SI pumps - AT LEAST TWO RUNNING Go to Step 23.
- c. RCS pressure minus maximum S/G c. Go to Step 23.
pressure - LESS THAN 175 psig
[400 psig adverse CNMT]
- d. Stop both RCPs 23 Check If S/G Is Intact:
Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go o Pressure in both S/Gs - STABLE to E-2, FAULTED STEAM GENERATOR OR INCREASING ISOLATION, Step 1.
o Pressure in both S/Gs - GREATER THAN 110 PSIG 24 Check If S/G Tubes Are Intact: Go to E-3.
RUPTURE, STEAM GENERATOR TUBE Step 1.
o Air ejector radiation monitors (R-15 or R-15A) - NORMAL o S/G blowdown radiation monitor (R-19) - NORMAL o Steamline radiation monitors (R-31 and R-32) - NORMAL
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 16 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If RCS Is Intact: Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT. Step l.
- a. CNMT area radiation monitors NORMAL
~ R-2
~ R-7
~ R-29
~ R-30
- d. CNMT sump A level o Level - STABLE o Annunciator C-19. CONTAINMENT SUMP A HI LEVEL - EXTINGUISHED
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 17 of,26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If Terminated:
SI Should Be
o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING
USING FIGURE MIN SUBCOOLING
- c. Secondary heat sink: c. IF neither condition met, THEN do NOT stop SI pumps. Go to o Total feed flow to S/Gs Step 27.
GREATER THAN 200 GPM
-OR-o Narrow range level in at least one S/G - GREATER THAN 5%
- d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Perform the following:
- 1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
- 2) Go to Step 27.
Step 1.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 18 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o The Critical Safety Function Red Path Summary is available in APPENDIX 1.
27 Initiate Monitoring of Critical Safety Function Status Trees
- 28 Monitor S/G Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% than 200 gpm until narrow range level greater than 5% in at least one S/G.
- b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an and 50% uncontrolled manner. THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
29 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels NORMAL RUPTURE, Step 1.
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
EOP: TITLE:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 19 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- ~ ~ 0 1 I 1 ~ 0 I
- I l l *
- 0 ~ I ~ 1 I 1 0 ~ 1 0 * ~ ~ 4 1 1
- 4 4 1 ~ 1 4 ~
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.
- 0 i 1 4 ~ f 0 4 1 4 4 1 4 4 0 1 I ~ j 1 i 1 ~ 1 I
- 4 ~ ~
30 Reset SI 31 Reset CI:
- a. Depress CI reset pushbutton
- b. Verify annunciator A-26. CNMT b. Perform the following:
ISOLATION - EXTINGUISHED l) Reset SI.
- 2) Depress CI reset pushbutton.
32 Verify Adequate SW Flow:
- a. At least three SW pumps - RUNNING a. Manually start SW pumps as power supply permits (257 kw each).
IF less than three pumps running, THEN ensure SW isolation.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 20 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 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'ontrol room lighting.
- b. Verify SW isolation valves to b. Manually align turbine building OPEN valves'.
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify adequate air Manually start air compressors compressor(s) - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started. THEN dispatch AO to locally reset compressors as necessary.
d.'heck 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 34. WHEN IA restored, THEN do Steps 33e and f.
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 21 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check Auxiliary Building Evaluate cause of abnormal Radiation NORMAL conditions.
~ Plant vent iodine (R-10B) IF the cause is a loss of RCS
~ Plant vent particulate (R-13) inventory outside CNMT. THEN go to
~ Plant vent gas (R-14) ECA-1.2. LOCA OUTSIDE CONTAINMENT, Step 1.
~ CCW liquid monitor (R-17)
~ LTD line monitor (R-9)
~ CHG pump room (R-4) 35 Check PRT Conditions Evaluate the following flowpaths for cause of abnormal conditions:
o PRT level (LI-442) - LESS THAN 84% ~ RCP seal return relief
~ PRZR PORVs o PRT temperature (TI-439) - LESS ~ PRZR safeties THAN 120 F ~ Letdown line relief o PRT pressure (PI-440A) - LESS IF excess letdown previously in THAN 3 PSIG service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
EOP: TITLE:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 22 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~
- 4 ~ 4 4 ~ l 4 ~ i 1 ~ ~ I ~ 1 1 ~ ~ 4 4 4 1 I * ~
- 1 4 * ~ I 1 ~ 1 ~ 4 ~
CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG. THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
36 Check Stopped:
If RHR Pumps Should Be
- a. Check RCS pressure:
- 2) Pressure - STABLE OR 2) Go to Step 37.
INCREASING
- b. Stop both RHR pumps and place in AUTO 37 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: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check Been If Charging Established:
Flow Has
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 open, demand at 0/o.
- b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.
o LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN dispatch AO to locally open o 'CV-112C - CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).
IF LCV-112C can NOT be closed.
THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 24 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Maintain PRZR Pressure Between 1800 PSIG And 2235 PSIG o Reset PRZR heaters o Use normal PRZR spray
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Check If Emergency Should Be Stopped:
D/Gs
- a. Verify AC emergency busses a. Perform the following:
energized by offsite power:
- 1) Verify non-safeguards bus tie o Emergency D/G output breakers breakers closed:
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) Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- 8) Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Return to Step 20
-END-
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 E-0 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLXNG (FIG-1.0)
- 3) ATTACHMENT CX/CVX (ATT-3.0)
- 4) ATTACHMENT SD-1 (Arr-17.0)
- 5) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
- 6) ATTACHMENT D/G STOP (ATT-8.1)
- 7) ATTACHMENT SI/UV (Arr-s.a)
- 8) FOLDOUT
EOP:
REV: 27 E-0 REACTOR TRIP OR SAFETY INJECTION 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' AND RVLIS level (no RCPs) less than 52% [55%
- adverse CNMT]
- c. HEAT SINK Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY Cold leg temperatures decrease greater than 100' in last 60 minutes AND RCS cold leg temperature less than 285 F
- e. CONTAINMENT CNMT pressure greater than 60 psig
REV 27 E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 1 of 1 FOLDOUT PAGE RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
- a. SI pumps- AT LEAST TWO RUNNING
[400 psig adverse CNMT]
- 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).
t EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 21 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER OI +
RESPONSI E MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
I EOP:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 2 of 21 A. PURPOSE This procedure provides actions to recover from a loss of reactor or secondary coolant.
B. ENTRY CONDITIONS/SYMPTOMS
- 1. 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. E-O, REACTOR TRIP OR SAFETY INJECTION, ECA-2.1, 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-l.l, 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, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, 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 reestablished.
FR-H.l, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are closed.
EOP: TITLE:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
- I I I I I I I ~ ~ ~ I ~ ~
- I I ~ I I I I ~ I I I I I
- I
- I
- I I I ~
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: 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 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+05 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:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 4 of 21 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 110 PSIG ~ Feedlines IF NOT, THEN go to E-2. FAULTED STEAM GENERATOR ISOLATION, Step l.
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 5% [25% adverse CNMT] than 200 gpm until narrow range level greater than 5% [25%
adverse CNMT1 in at least one S/G.
- b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 17% continues to increase in an
[25% adverse CNMTl and 50% uncontrolled manner, THEN go to E-3. STEAM GENERATOR TUBE RUPTURE, Step l.
- 4 Monitor If Secondary IF steamline radiation monitors NOT Radiation Levels Are 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 RP sample S/Gs for E-3, STEAM GENERATOR TUBE RUPTURE, activity Step l.
~ I EOP: TITLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~
- l ~ 0 4 0 t ~ 1 1 I 0 1 ~ 4 0 4 0 1 1 * *
- l 1
- i
- 4 1
- 4 0 I 4 ~ 1 ~ ~
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:
o MOV-515, MCC D position 6C
~ MOV-516, MCC C 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 D position 6C
~ MOV-516. MCC C position 6C
- c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.
U I' ~ 4
EOP: TITLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 6 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ i i
- 0 4 ~ 0 1 0 l i l 0 1 t ~ *
- 1 ~ l ~ ~ 1 P ~ 4 4 ~ 4 4
- 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.
~ ~ P t 4 I
- l 1
- 4 4 0 ~ ~ ~ 4 0 ~ I 1
- 4 4 0 1 1 ~ i ~ 4 1 4 4 0 t I 1 ~ ~
6 Reset SI 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 (257 kw each).
IF less than two SW pumps running, THEN perform the following:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- 3) Go to Step 10.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- ~
EOP:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 21 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 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 turbine building SW b. Manually align valves.
isolation valves - OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify adequate air compressors c. Manually start air 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.
EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 21 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: TITLE REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 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 81 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:
~ V-300A for RCP A
~ V-300B for RCP B
- 2) Ensure HCV-142 open. demand at 0/o.
- b. Charging pump suction aligned to b. Manually align valves as RWST: necessary.
o LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN dispatch AO to locally open o LCV-112C - CLOSED manual charging pump suction from RWST (V-358 located in charging pump room).
IF LCV-112C can NOT be closed.
THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as necessary and adjust charging flow to restore PRZR level
EOP: TITLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT FAGE 10 of 21 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 FXGURE MIN SUBCOOLING FI
- c. Secondary heat sink: c. IF neither condition satisfied.
THEN do NOT stop SI pumps. Go o Total feed flow to intact to Step 13.
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 SX pumps. Perform
[30% adverse CNMT] the following:
- 1) IF normal PRZR spray available'HEN try to stabilize RCS pressure with PRZR spray.
- 2) Go to Step 13.
h EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE ll of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13 Monitor Be Stopped:
If CNMT Spray Should
- a. CNMT spray pumps - RUNNING a. Go to Step 14.
- b. Check the following: b. Continue with Step 14. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do Steps 13c 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
EOP: TITLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ 4 0 I 4 t
- 0 I 4
- 4 ~ 0 0 1 1 1 0 1 1 1 1
- I 4 1 4 I t 0 0 0 4 I ~ 0 4 ~
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 IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT7, THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
- 14 Monitor Be Stopped:
If RHR Pumps Should
- a. Check RCS pressure:
- 1) Pressure - GREATER THAN 1) Go to Step 16.
250 psig [465 psig adverse CNMT7
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 110 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.
DECREASING
EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Emergency D/Gs Should Be Stopped:
- 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) Start HP seal oil backup pump.
- 6) Ensure D/G load within limits.
- 7) WHEN bus 15 restored, THEN reset control room lighting breaker.
- 8) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
- 9) 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: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If RHR Throttled:
Should Be
- a. Check RHR Pumps - ANY RUNNING a. Go to step 18.
- b. Check RWST level - LESS THAN 70% b. Continue with Step 18. WHEN RWST level less than 70%, THEN perform step 17b.
- c. RHR flow - LESS THAN 1500 GPM c. Manually adjust RHR Hx outlet PER OPERATING PUMP valves equally to reduce flow to less than 1500 gpm per operating pump
~ RHR Hx A, HCV-625
~ RHR Hx B. HCV-624 IF flow can NOT be reduced manually, THEN dispatch an AO with locked valve key to locally adjust RHR Hx outlet valve handwheels equally to reduce flow.
~ RHR Hx A, HCV-625 handwheel
~ RHR Hx B. HCV-624 handwheel
I EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15 of 21 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 l.
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 key may be required) be evaluated necessary.
and isolated if
l a ll - ~ ll ~ ' 0 1 I ~
EOP:
REV: 21 LOSS OP REACTOR OR SECONDARY COOLANT PAGE 16 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Evaluate Plant Status:
- a. Check auxiliary building a. Notify RP 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 RP to obtain following samples:
~ RCS activity
- 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)
EOP:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 17 of 21 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.
EOP:
REV: 21 E-1 LOSS 05'EACTOR OR SECONDARY COOLANT PAGE 18 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: IF D/Gs supplying emergency AC busses. THEN non-essential loads may be shed as necessary to allow start of additional SW pumps.
21 Establish Adequate SW Flow:
- a. Verify at least two SW pumps- a. Start additional SW pumps as RUNNING power supply permits (257 kw each). IF only 1 SW pump operable, THEN perform the following:
- 1) Ensure Attachment MIN SW is in progress.
- 2) Go to Step 22.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves - OPEN
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735 This Step continued on the next page.
EOP: T1TLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 19 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 21 continued from previous page)
- c. Dispatch AO to perform the following:
- 1) Check BOTH CCW Hx - INSERVICE 1) Perform the following:
a) Locally place BOTH CCW Hxs in service b) Locally adjust total SW flow equally to available CCW Hxs to between 5000 gpm and 6000 gpm 0 V-4619
~ V-4620
Hxs - GREATER THAN 5000 GPM a) Isolate SW to screenhouse and air conditioning headers.
~ MOV-4609/MOV-4780 - AT LEAST ONE CLOSED
~ MOV-4663/MOV-4733 - AT LEAST ONE CLOSED b) Direct AO to locally adjust total SW flow equally to available CCW Hxs to between 5000 gpm and 6000 gpm (V-4619 and V-4620).
c) Direct AO to locally isolate SW return from SFP Hxs:
SFP Hx A (V-4622)
~ SFP Hx B (V-8689) d) Verify SW portions of Attachment SD-1 are complete.
EOP: TITLE:
REV: 21 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 20 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Establish CCW flow to RHR Hxs:
- a. Check both CCW pumps - RUNNING a. Perform the following:
- 1) Start CCW pumps as power supply permits (124 kw each)
- 2) IF both CCW pumps are running, THEN go to step 22b.
- 3) IF only one CCW pump is running, THEN perform the following:
a) Direct AO to isolate CCW to boric acid evaporator o Close V-760A b) Manually open CCW MOV to only one operable RHR Loop o Open MOV-738A
-OR-o Open MOV-738B c) Go to step 23.
~ MOV-738A
~ MOV-738B
EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Transfer To Cold Recirculation Is Required:
Leg
- a. RWST level - LESS THAN 28'/o a. Return to Step 17.
- b. Go to ES-1.3. TRANSFER TO COLD LEG RECIRCULATION, Step 1
-END-
EOP: TITLE:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG-1.0)
- 3) ATTACHMENT CNMT RECIRC FANS (A'rr-4. 0)
- 4) ATTACHMENT D/G STOP (Arr-s.I)
- 5) ATTACHMENT SD-1 (ATr-17.0)
- 6) ATTACHMENT SI/UV (nor-s.ii)
- 7) ATTACHMENT MIN SW (Arr-2.1)
- 8) FOLDOUT
EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 RED PATH
SUMMARY
- a. SUBCRITICALITY Nuclear power greater than 5%
- b. CORE COOLING Core exit T/Cs greater than 1200'
-OR-Coze exit T/Cs greater than 700' AND RVLIS level (no RCPs) less than 52% [55%
adverse CNMT]
- c. HEAT SINK Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY Cold leg temperatures decrease greater than 100' in last 60 minutes AND RCS cold leg temperature less than 285'
- e. CONTAINMENT CNMT pressure greater than 60 psig
EOP:
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 FOLDOUT PAGE
- a. Sl pumps -AT LEAST TWO RUNNING
2.. SI REINITIATIONCRITERIA IF EITHER condition listed below occurs, THEN manually start Sl pumps as necessary:
o RCS subcooling based on core exit T/Cs - LESS THAN 0 F USING FIGURE MIN SUBCOOLING
-OR-o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMTJ
- 3. SI TERMINATIONCRITERIA IF ALLconditions listed below occur, THEN go to ES-1.1, Sl TERMINATION, Step 1:
- a. RCS subcooling based on core exit T/Cs - GREATER THAN O' 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]
- 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.
- 5. E-3 TRANSITION CRITERIA IF any S/G level increased in an uncontrolled manner or any S/G has abnormal radiation, THEN manually start SI pumps as necessary AND go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
- 6. 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 1.
- 7. 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).
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 41 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONS LE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP: TITLE:
REV 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 41 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 CONDXTIONS/SYMPTOMS
- l. ENTRY CONDITIONS This procedure is entered from:
- a. E-O, REACTOR TRXP OR SAFETY INJECTXON, when condenser air ejector radiation or blowdown radiation is abnormal, or b E 0g REACTOR TRI P OR SAFETY INJECTION g E-l, LOSS OF REACTOR OR SECONDARY COOLANT, E-2, FAULTED STEAM GENERATOR ISOLATION, and FR-H.3, RESPONSE TO STEAM GENERATOR HIGH LEVEL, when secondary radiation is abnormal, or
- c. E-O, REACTOR TRIP OR SAFETY INJECTION, E-1, LOSS OF REACTOR OR SECONDARY COOLANT, E 2~ FAULTED STEAM GENERATOR ISOLATION ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when an intact S/G narrow range level increases in an uncontrolled manner.
- d. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, when pressurizer pressure control is restored.
- e. Any FOLDOUT page that has E-3 transition criteria whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
4 EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 41 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+05 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: TITLE:
REV 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 4 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ I ~ ~ ~ 1
- 4
- 1 I 1 l * ~ i ~ 1
- 1 0 4 ~ 0 I i 4 I 0 0 4 0 0 I ~ ~ j ~
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.
2 Identify Ruptured S/G(s): Perform the following:
o Unexpected increase in either a. Reset SI S/G narrow range level
- b. Continue with Steps 10
-OR- through 16. WHEN ruptured S/G(s) identified. THEN do Steps o High radiation indication on 3 through 9.
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
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 4 ~ ~ 1 4 4 l 4 I 0 ~ ~ ~ ~ 0 0 0 I 0 0 I 4 ~ ~ 4 l ~
- 0 1 1 4 l 4 i 1 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 1050 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. Dispatch AO with locked valve steam supply valve and place in key to locally isolate steam PULL STOP from ruptured S/G to TDAFW pump.
~ S/G A, MOV-3505A ~ S/G A, V-3505
~ S/G B. MOV-3504A ~ 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
0
~ g 4 I
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 41 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) Adjust condenser steam dump controller to 1050 psig in AUTO.
- 4) Place condenser steam dump mode selector switch to MANUAL.
- 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).
- b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)
1 EOP: TITLE:
REV: 27 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1 i f * ~ 1
- I 1 t 4 1 1
- 1 l t I * * * *
- 4 1 1 0 4 ~ f t 1 1 t ~ 4 l * *
- 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.
S 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%%d [25% adverse CNMT].
- 2) Continue with Step 6. WHEN ruptured S/G level greater than 5% [25%%d 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'alve 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 AD V-4005
~ S/G B. V-4006
- e. Verify MDAFW pump crosstie e. Manually close valves.
valves - CLOSED
~ MOV-4000A
~ MOV-4000B
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Ruptured S/G Isolated:
- a. Check ruptured MSIV - CLOSED a. Ensure air ejector/gland steam supply and flange heating steam isolated. (Refer to ATTACHMENT RUPTURED S/G, part B).
- b. Check TDAFW pump steam supply b. Continue efforts to isolate from ruptured S/G - ISOLATED steam supply from ruptured S/G:
~ S/G A, MOV-3505A OR V-3505
~ S/G B, MOV-3504A OR V-3504
- c. Ruptured S/G pressure - GREATER c. Go to ECA-3.1. SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
7 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 8.
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
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I ~ 0 ~ 1 0 ~ 4 1 0 ~ * ~ 1 ~ f 1 ~ 0 ~ ~ 4 I I
- 1 1 1 1 1 1 4 ~ ~ ~ 4 1 i ~ ~
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.
8 Reset SI
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ ~ 1 \ 1 ~ 1 1 1 1 ~
- 1
- 1 1 1 1 1 1 1 1 ~ ~ ~ 1 1 1 1
- 1
- 1 *
- 1 1 1 1 ~
CAUTION RUPTURED S/G LEVEL SHALL BE MAINTAINED GREATER THAN 5% [25% ADVERSE CNMT]
DURING THE RCS COOLDOWN, UNLESS THE RUPTURED S/G IS ALSO FAULTED.
NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.
9 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 PSXG 500 475 adverse CNMT]
800 PSIG 485 460 adverse CNMT]
700 PSXG 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. IF ruptured S/G MSIV closed, b. Manually or locally initiate THEN initiate dumping steam to steam dump from intact S/G at condenser from intact S/G at maximum rate using S/G ARV.
maximum rate IF no intact S/G available, THEN perform the following:
o Use faulted S/G.
-OR-o IF a ruptured S/G must be used. THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
- c. Core exit T/Cs - LESS THAN c. Continue with Step 10. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required, THEN do Step 9d.
- d. Stop RCS cooldown and stabilize core exit T/Cs less than required temperature
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE ll of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: TDAFW pump flow control valves fail open on loss of IA.
10 Monitor Intact S/G Level:
- a. Narrow range level '- GREATER a. Maintain total feed flow greater THAN 5% [25%%d 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 1.
II 4
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 f 1 4 1 1 4 4 ~ * ~ ~ ~ ~
- 1 4
- 1 * ~ 4 1 ~ ~ 4 0 I ~ f 0 I t ~ 0 ~
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 11B).
ll Monitor Valves:
PRZR PORVs And Block
- 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 D position 6C
~ MOV-516, MCC C 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.
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 13 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 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.
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 14 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 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 HP seal oil backup pump.i
- 5) Start CNMT RECIRC fans as necessary.
- 6) Ensure D/G load within limits.i
- 7) WHEN bus 15 restored, THEN reset control room lighting.
- c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).
l EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 15 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify Adequate SW Flow:
- a. Check at least two SW pumps- a. Manually start SW pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps running, THEN:
- 1) Ensure SW isolation.
- 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
- 3) Go to Step 16.
- b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
EOP:
REV: 27 STEAM GENERATOR TUBE RUPTURE PAGE 16 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT:
- a. Verify non-safeguards busses a. Perform the following:
energized
- 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).
- b. Verify turbine building SW b. Manually align valves.
isolation valves - OPEN
~ MOV-4613 and MOV-4670
~ MOV-4614 and MOV-4664
- c. Verify adequate air compressors ,
- c. Manually start air 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 16. WHEN IA restored, THEN do Steps 15e and f.
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 17 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- I
- I *
- I I I t
- I I
- I I I * ~ t I I I I I t I I I t I I t I I I ~ ~
CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES IN AN UNCONTROLLED MANNER TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT] . THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
~ I I ~ I I * * * * *
- I * * * ~ ~
- I I I I I I I ~ I ~ ~ * ~ I * ~ * ~ ~ ~
16 Check Xf RHR Pumps Should Be Stopped:
- a. Check RCS pressure - GREATER a. Go to Step 17.
THAN 250,psig [465 psig adverse CNMT]
- b. Stop RHR pumps and place both in AUTO
y'S & ~ 1 ~ I' ~ ~ ~. ~ ~ " % ~ I I EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 18 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Charging Flow:
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally close seal injection needle valves to affected RCP.
~ V-300A for RCP A
~ V-300B for RCP B 1
- 2) Ensure HCV-142 demand at 0%.
- b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN dispatch AO to locally open manual charging pump suction o LCV-112B - OPEN from RWST (V-358 located in charging pump room).
o LCV-112C - CLOSED IF LCV-112C can NOT be closed, THEN perform the following:
- 1) Verify charging pump A NOT running and place in PULL STOP.
- 2) Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
- c. Start charging pumps as necessary and establish 75 gpm total charging flow
~ Charging line flow
~ Seal injection
0
~ I IL t Hl k $ ~
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 19 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If Be Stopped:
RCS Cooldown Should
- a. Core exit T/Cs - LESS THAN a. Do NOT proceed until core exit REQUIRED TEMPERATURE T/Cs less than required temperature.
- b. Stop RCS cooldown
- c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE 19 Check Ruptured S/G Pressure IF pressure continues to decrease STABLE OR INCREASING to less than 250 psi above the pressure of the intact S/G, THEN go to ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
20 Check RCS Subcooling Based On Go to ECA-3.1. SGTR WITH LOSS OF Core Exit T/Cs GREATER THAN REACTOR COOLANT - SUBCOOLED 20 F USING FIGURE MIN RECOVERY DESIRED, Step 1 SUBCOOLING
\ ~" f W 5 ' ~
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 20 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SI ACCUMs may inject during RCS depressurization.
21 Depressurize RCS To Minimize Break Flow And Refill PRZR:
- a. Check the following: a. Go to Step 22.
o Ruptured S/G level - LESS THAN 90% [80% adverse CNMT]
o Any RCP - RUNNING o IA to CNMT - AVAILABLE
- b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
o PRZR level - GREATER THAN 75%
[65% adverse CNMT]
-OR-o RCS pressure - LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
-OR-o BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE
- 2) PRZR level - GREATER THAN 5% [30% adverse CNMT]
- c. Close normal PRZR spray valves: c. Stop associated RCP(s).
- 1) Adjust normal spray valve controller to 0% DEMAND
- 2) Verify PRZR spray valves CLOSED
~ PCV-431A
~ PCV-431B
- d. Verify auxiliary spray valve d. Decrease charging speed to (AOV-296) CLOSED minimum and ensure charging valve to loop B cold leg open (AOV-294).
- e. Go to Step 24
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 21 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION o THE PRT MAY RUPTURE IF A PRZR PORV IS USED TO DEPRESSURIZE THE RCS. THIS MAY RESULT IN ABNORMAL CNMT CONDITIONS.
o CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED.
o THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING. THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
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 a PRZR PORV select one with an operable block valve.
22 Depressurize RCS Using PRZR PORV To Minimize Break Flow And Refill PRZR:
- b. PRZR PORVs - AT LEAST ONE b. IF auxiliary spray available, AVAILABLE THEN return to Step 21b.
IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL. Step 1.
This Step continued on the next page.
~ e ~ & '4 ~ 4 ~ ll k "e II I. 'h '
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 22 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 22 continued from previous page)
- c. Open one PRZR PORV until ANY of c. IF auxiliary spray available, the following conditions THEN return to step 21b.
satisfied:
- 1) IF auxiliary spray can NOT be o PRZR level - GREATER THAN 75% established, THEN go to
[65% adverse CNMT] ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL,
-OR- Step 1.
o RCS pressure - LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
-OR-o BOTH of the following:
- 1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE
- 2) PRZR level - GREATER THAN 5% [30% adverse CNMT]
! n "1 EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 23 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCS Pressure Close block valve for the PRZR PORV INCREASING that was opened.
IF pressure continues to decrease, THEN perform the following:
- a. Monitor the following conditions for indication of leakage from PRZR PORV:
o PORV outlet temp (TI-438) NOT decreasing.
o PRT pressure, level or temperature continue t'o increase.
- b. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.
EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 24 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ 0 t 1 1 * ~ *
- 1 * * ~ 0 4
- 1 I 1 4 1 1 ~ ~ 0 1 I
- t 1 ~ f I
- 4 I 4 1 * ~
CAUTION SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT OVERFILLING OF THE RUPTURED S/G.
24 Check Terminated:
If SI Flow Should Be
- a. RCS subcooling based on core a. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN O' ECA-3.1. SGTR WITH LOSS OF USING FIGURE MIN SUBCOOLING REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
- b. Secondary heat sink: b. IF neither condition satisfied, THEN do NOT stop SI pumps. Go to o Total feed flow to S/G(s) ECA-3.1. SGTR WITH LOSS OF GREATER THAN 200 GPM AVAILABLE REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED'tep 1.
-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5% [25% adverse CNMT]
- c. RCS pressure - STABLE OR c. Do NOT stop SI pumps. Go to INCREASING ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
- d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Return to
[30% adverse CNMT] Step 6.
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 25 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Stop SI Pumps And Place In AUTO 26 Establish Required Charging Line Flow:
- a. Charging pumps - ANY RUNNING a. Perform the following:
- 1) IF CCW flow is lost to any RCP thermal barrier OR any RCP gl seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to locally isolate seal injection to affected RCP:
~ RCP A, V-300A
~ RCP B. V-3008
- 2) Ensure HCV-142 open.
- 3) Start one charging pump.
- b. Establish 20 gpm charging line flow
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 26 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27 Monitor SI Reinitiation Criteria:
- a. RCS subcooling based on core a. Manually start SI pumps as exit T/Cs - GREATER THAN O' necessary and go to ECA-3.1, USING FIGURE MIN SUBCOOLING SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
- b. PRZR level - GREATER THAN 5% b. Control charging flow to
[30% adverse CNMT] maintain PRZR levels IF PRZR level can NOT be maintained, THEN manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1.
1 . I~
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPl'URE PAGE 27 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check Isolated:
If SI ACCUMs Should Be
- a. Check the following: a. Manually operate SI pumps as necessary and go to ECA-3.1, o RCS subcooling based on core SGTR WITH LOSS OF REACTOR exit T/Cs - GREATER THAN 0 F COOLANT - SUBCOOLED RECOVERY USING FIGURE MIN SUBCOOLING DESIRED, Step 1.
o PRZR level - GREATER THAN 5'/o
[30%%d 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
EOP:
REV: 27 E-3 STEAM'GENERATOR TUBE RUPTURE PAGE 28 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Verify Adequate SW Flow To CCW Hx:
- a. Verify at least three SW pumps a. Manually start pumps as power RUNNING supply permits (257 kw each).
IF less than two SW pumps can be operated, THEN go to Step 36.
- b. Verify AUX BLDG SW isolation b. Manually align valves.
valves - AT LEAST ONE SET OPEN
~ MOV-4615 and MOV-4734
~ MOV-4616 and MOV-4735
- c. Verify CNMT RECIRC fan c. Dispatch'O to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check Operation If Normal CVCS Can Be Established
- a. Verify IA restored: a. Continue with Step 36. WHEN IA restored, THEN do Steps 30 o IA to CNMT (AOV-5392) - OPEN through 35.
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 gl seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).
~ RCP A, MOV-749A and MOV-759A
~ RCP B, MOV-749B and MOV-759B
- 2) Manually start one CCW pump.
- d. Charging pump - ANY RUNNING d. Continue with Step 36. WHEN any charging pump running, THEN do Steps 31 through 35.
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 30 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Seal Return Flow Should Be Established:
- a. Verify RCP gl seal outlet a. Go to Step 32.
temperature - LESS THAN 235 F
- b. Verify RCP seal outlet valves- b. Manually open valves as OPEN necessary.
~ AOV-270A
~ AOV-270B
- c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
- d. Open RCP seal return isolation d. Perform the following:
valve MOV-313
- 1) Place MOV-313 switch to OPEN.
- 2) Dispatch AO with key to RMST gate to locally open MOV-313.
- e. Verify RCP $ 1 seal leakoff flow e. Perform the following:
- LESS THAN 6.0 GPM
- 1) Trip the affected RCP
- 2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve
~ RCP A. AOV-270A
~ RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 32.
Ji tet fOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Verify PRZR Level GREATER Continue with Step 34. WHEN PRZR THAN 13% [40% adverse CNMT] level increases to greater than 13%
[40% adverse CNMT], THEN do Step 33.
33 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-2008, 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 excess consult TSC to determine letdown should be placed in if
- 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
~ I\ ~ ~
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 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.
A ' f~ I ~ '4 ( ~ wc ~ I ~
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 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 36. WHFN VCT level greater than 40%,
THEN do Step 35b.
- b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.
o LCV-112C - OPEN o LCV-112B - CLOSED
iV, EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 34 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~ 0 4 ~ 4 1 I 1 I 1 't I 4 4 1 ~ 4 ~ f f I ~ 1 1 4 4 I 4 ~ ~ 4 ~ * ~ * * * * ~ ~
CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
- 36 Control RCS Pressure And Charging 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 Increase o Increase
[40% ADVERSE CNMT] charging flow charging charging flow flow o Depressurize RCS o Maintain RCS and using Step 36b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and
[40% ADVERSE CNMT] using Step 36b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and
[65% ADVERSE CNMT] using Step 36b PRZR ruptured S/G heaters pressure equal o Decrease charging flow GREATER THAN 75% o Decrease Energize Maintain RCS and
[65% ADVERSE CNMT] charging 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 obtain desired results for use IF auxiliary spray (AOV-296).
NOT, THEN use one PRZR PORV.
Step 36a
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Monitor Be Stopped:
If CNMT Spray Should
- a. CNMT spray pumps - ANY RUNNING a. Go to Step 38
- b. Verify CNMT pressure - LESS THAN b. Continue with Step 38. WHEN 4 PSIG CNMT pressure less than 4 psig.
THEN do Steps 37c through f.
- c. Reset CNMT spray
- d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.
~ AOV-836A
~ AOV-836B
- e. Stop CNMT spray pumps and place in AUTO
- f. Close CNMT spray pump discharge valves
~ MOV-860A
~ MOV-860B
~ MOV-860C
~ MOV-860D
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 36 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 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.l, RESTORATION OF OFFSITE POWER).
o Emergency D/G output breakers OPEN o AC emergency bus voltage GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED
- b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 39 Minimize Secondary System Contamination:
- a. Isolate reject from hotwell to a. IF hotwell level increasing.
CST: THEN direct RP to sample hotwells for activity.
o Place hotwell level controller (LC-107) in MANUAL at 50/o o Verify hotwell level - STABLE
- b. Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
I ~ - 4 . ' 5 k
~ i
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 37 of 41 STEP ACTION/EXPECTED RESPONSE 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
I t EOP: TITLE:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 I 1 I 1 4 4 1 4 0 ~ 1 i 0 0 I
- 4 *
- 0
- 1 4 1 0 ~ 0 4 ~ 1 P I ~ 0 ~ ~ 4 *
- CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
42 Check RCP Status:
- a. RCPs - AT LEAST ONE RUNNING a. Perform the following:
l) Try to start one RCP:
a) Ensure conditions for starting an RCP.
o Bus llA or llB energized.
o Refer to Attachment RCP START.')
IF RVLIS level (no RCPs) less than 95%. THEN perform the following:
o Increase PRZR level to greater than 65% [82%
adverse CNMT].
o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20 F using Figure MIN SUBCOOLING.
o Energize PRZR heaters as necessary to saturate PRZR water 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
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 39 of 41 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 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 NOT be restored. THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 44.
- e. Transfer Rk-45 recorder to one source range and one intermediate range channel
EOP:
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 40 of 41 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:
o Open generator disconnects
~ 1G13A71
~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump
- c. Verify adequate Rx head cooling:
- 1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
- 2) Verify one Rx compartment 2) Perform the following:
cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.
o Manually start one fan as power supply permits (23 kw)
- d. Verify Attachment SD COMPLETE
EOP:
REV 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 41 of 41 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-
EOP:
REV: 27 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE
- 1) RED PATH
SUMMARY
- 2) FIGURE MIN SUBCOOLING (FIG-I.O)
- 3) ATTACHMENT CNMT RECIRC FANS (ATT-4.0)
- 4) ATTACHMENT D/G STOP (ATT-8.1)
S) ATTACHMENT N2 PORVS (Arr-12.0)
- 6) ATTACHMENT NC (Arr-13.0)
- 7) ATTACHMENT SEAL COOLING (Arr-15.2)
- 8) ATTACHMENT RCK" START (Arr-Is.o)
- 9) ATTACHMENT RUPTURED S/G (Arr-16.0)
- 10) ATTACHMENT SD-1 (Arr-17.0)
- 11) ATTACHMENT SD-2 (Arr-17.1)
- 12) FOLDOUT
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH
SUMMARY
a ~ SUBCRXTXCALITY Nuclear power greater than 5%
- b. CORE COOLING Core exit T/Cs greater than 1200'
-OR-Core exit T/Cs greater than 700 F AND RVLIS level (no RCPs) less than 52% [55%
adverse CNMT]
C. HEAT SINK Narrow range level in all S/Gs less than 5-:
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
- d. INTEGRITY Cold leg temperatures decrease greater than 100' in last 60 minutes AND RCS cold leg temperature less than 285'
- e. CONTAINMENT CNMT pressure greater than 60 psig
REV: 27 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA Following SI termination, IF either condition listed below occurs, THEN start 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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].
- 2. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1, UNLESS faulted S/G needed for RCS cooldown.
- 3. 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 1.
- 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.