ML17265A515: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:EOP AP-SW.1 TITLE: SERVICE WATER LEAK REV 14 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: AP-SW.1 TITLE: SERVICE WATER LEAK REV: 14 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 b.Sump pump activity increases in containment, the AUX BLDG@or INT BLDG@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.
{{#Wiki_filter:EOP         TITLE:
EOP AP-SW.1 TITLE: SERVICE WATER LEAK REV: 14 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.
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:
SHALL BE PERFORMED.
vv<nmoosv esoxxs PDR ADQCK 05000244 F             PDR
o IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.
1 Verify 480V AC Emergency Busses 17 and 18-ENERGIZED Ensure associated D/G(s)running and attempt to manually load busses 17 and/or 18 onto the D/G(s)if necessary.
2 Verify At Least One SW Pump Running In Each Loop:~A or B pump in loop A~C or D pump in loop B IF a SW pump has tripped, THEN ensure other pump in the affected loop is running.
, y h 0 A~
EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 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:
o Pressure in both loops-APPROXIMATELY EQUAL o PPCS SW low pressure alarm status-NOT LOW o Pressure in both loops STABLE OR INCREASING b.Check SW loop header pressures GREATER THAN 55 PSIG a.IF three SW pumps operating and either loop pressure less than 40 psig.THEN trip the reactor and go to E-0.REACTOR TRIP OR SAFETY INJECTION.
IF only two SW pumps operating and either loop pressure less than 45 psig, THEN start one additional SW pump (243 kw each pump).b.IF either SW loop pressure is 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: AP-SW.1 SERVICE WATER LEAK REV: 14 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: a.Check Sump A indication o Sump A level-INCREASING-OR-a.IF the SW leak is NOT in the CNMT, THEN go to Step 6.o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)b.Evaluate Sump A conditions:
1)Verify Leakage within capacity of one Sump A pump (50 gpm)2)Check Sump A level-LESS THAN 10 FEET b.Plant shutdown should be considered, consult plant staff.c.Direct RP to establish conditions for CNMT entry V&4 r-EOP: AP-SW.1 TITLE: SERVICE WATER LEAK REV 14 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:
o CNMT recirc fan collector dump frequency-NORMAL (Refer to RCS 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 Dispatch AO to perform Attachment SW LOADS IN CNMT as necessary.
WHEN CNMT SW leak location identified, THEN go to Step 9.
1 4~h't I k'l e~'s>~~~
EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 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 closed o Idle pump shaft stopped o Idle pump discharge pressure ZERO (unisolate and check local pressure indicator) b.Investigate for SW leak in Screenhouse
-NO EXCESSIVE LEAKAGE INDICATED a.Notify Control Room of any indication of check valve failure.b.Perform the following:
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 Location: o AUX BLDG sump pump start frequency-NORMAL (Refer to RCS Daily Leakage Log)o Annunciator L-9.AUX BLDG SUMP HI LEVEL-EXTINGUISHED Dispatch AO to the specific area to investigate for leakage.o Annunciator L-17, INTER BLDG SUMP HI LEVEL" EXTINGUISHED I~'~
EOP: AP-SW.1 SERVICE WA'gER LEAK REV 14 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: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If SW is lost to either D/G, refer to ER-D/G.2.ALTERNATE COOLING FOR EMERGENCY D/Gs.if cooling is required.9 Evaluate SW Leak Concerns a.Check SW pump status-AT LEAST THREE PUMPS RUNNING b.Intact SW loop header pressure GREATER THAN 45 PSIG a.IF either SW header pressure less than 45 psig, THEN start third SW pump.b.Dispatch AO to perform the following:
1)Split A and B SW headers: 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.c.Verify leak location-IDENTIFIED d.Verify plant operating at power e.Leak isolation at power-ACCEPTABLE 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.Return to Step 3.d.Verify SW system conditions appropriate for plant mode (Refer to ITS Section 3.7.8)and go to Step 10.e.IF plant shutdown required.THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
'I I b EOP: AP-SW.1 SERVICE WATER LEAK REV: 14 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 o SW loop header pressure RESTORED TO PRE-EVENT VALUE Archive PPCS point,ID loop A P2160 OR loop B P2161)o Both SW loop header pressures STABLE a.IF SW leak can NOT be isolated within the affected header, THEN stop SW pumps in the affected loop and go to Step 12.b.Verify at least one SW pump available from each screenhouse AC Emergency bus~Bus 17 SW pumps B or D~Bus 18 SW pumps A or C b.Refer to ITS Section 3.7.8 for , limiting conditions for operation.
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: AP-SW.1 SERVICE WATER LEAK REV: 14 PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE 1)ATTACHMENT SW ISOLATION (ATT-2.2)2)ATTACHMENT SW LOADS IN CNMT (ATT-2.3)
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 1 of 26 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSIBL MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:


EOP: E-0 REACTOR TRIP OR SAFETY INACTION REV: 27 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.
EOP:         TITLE:
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.
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.
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.
B. ENTRY CONDITIONS/SYMPTOMS
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.
: 1. SYMPTOMS    The symptoms of  SERVICE WATER LEAK are:
4.The following are symptoms of a reactor trip and safety injection:
: a. Service water header pressure low alarms on computer, or
o Any SI annunciator lit.o Safeguards sequencing started.  
: b. Sump pump  activity increases in containment, the AUX BLDG@  or INT BLDG@ 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: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 3 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED o At least one train of reactor trip breakers-OPEN o Neutron flux-DECREASING o MRPI indicates-ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manually trip reactor.IF reactor trip breakers NOT open.THEN perform the following:
EOP               TITLE:
a.Open Bus 13 and-Bus 15 normal feed breakers.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.
REV: 14 AP-SW.1                            SERVICE WATER LEAK PAGE 3     of 10 STEP       ACTION/EXPECTED RESPONSE                 RESPONSE     NOT OBTAINED 1 l
Step 1 2 Verify Turbine Stop Valves-CLOSED Manually trip turbine.IF turbine trip can NOT be verified.THEN close both MSIVs.3 Verify Both Trains Of AC Emergency Busses Energized To At Least 420 VOLTS: Attempt to start any failed emergency D/G to restore power to all AC emergency busses.~Bus 14 and Bus 18~Bus 16 and Bus 17 IF power can NOT least one train.ECA-O.O.LOSS OF Step 1.be restored to at THEN go to ALL AC POWER.  
* 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


EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 4 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED a.Any SI Annunciator
, y h 0 A ~
-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-b.SI sequencing
EOP:
-BOTH TRAINS STARTED.o Operator determines SI required IF SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.b.Manually actuate SI and CI.
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.
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 5 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open and monitored periodically.
3 Check  SW  System Status:
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 b.Both RHR pumps-RUNNING a.Perform the following:
: 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.
1)Ensure SI pump suction supply open from RWST.2)Manually start pumps.b.Manually start pumps.6 Verify CNMT RECIRC Fans Running: a.All fans-RUNNING b.Charcoal filter dampers green status lights-EXTINGUISHED a.Manually start fans.b.Dispatch personnel to relay room 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: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 6 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*7 Verify CNMT Spray Not Required: o Annunciator A-27.CNMT SPRAY-EXTINGUISHED o CNMT pressure-LESS THAN 28 PSIG Verify CNMT spray initiated.
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).
IF CNMT spray NOT initiated, THEN perform the following:
: 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).
a.Depress manual CNMT spray pushbuttons (2 of 2).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: E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 7 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Main Steamlines Should Be Isolated: a.Any MSIV-OPEN b.Check CNMT pressure-LESS THAN 18 PSIG c.Check if ANY main steamlines should be isolated: o Low Tavg (545 F)AND high steam flow (0.4xl06 lb/hr)from either S/G a.Go to Step 9.b~Ensure BOTH MSIVs closed and go to Step 9~c.Go to Step 9.-OR-o High-High steam flow (3.6x106 lb/hr)from either S/G d.Verify MSIV closed on the affected S/G(s)d.Manually close valves.9 Verify MFW Isolation:
~ ~
a.MFW pumps-TRIPPED b.MFW flow control valves-CLOSED~MFW regulating valves~MFW bypass valves c.S/G blowdown and sample valves CLOSED a.Manually close MFW pump discharge valves and trip MFW pumps.b.Place A and B S/G MFW regulating valve and bypass valve controllers in MANUAL at 0%demand.c.Place S/G blowdown and sample valve isolation switch to CLOSE.
EOP:
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 8 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Verify AFW Pumps Running: a.MDAFW pumps-RUNNING b.TDAFW pump-RUNNING IF NECESSARY a.Manually start MDAFW pumps.b.Manually open steam supply valves.~MOV-3505A~MOV-3504A 11 Verify At Least Two SW Pumps RUNNING Perform the following:
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.
a.Ensure one SW pump running on each energized screenhouse AC emergency bus:~Bus 17~Bus 18 b.IF offsite power NOT available, THEN ensure SW isolation.
o CNMT sump A    level of  10  feet is approximately    6  feet 6 inches below the bottom of the reactor vessel.
EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 9 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Verify CI And CVI: a.CI and CVI annunciators
4 Check For    SW  Leakage    In  CNMT:
-LIT~Annunciator A-26.CNMT ISOLATION~Annunciator A-25.CNMT VENTILATION ISOLATION a.Depress manual CI pushbutton.
: a. Check  Sump A  indication                a. IF the  SW  leak is NOT in the CNMT, THEN go    to Step 6.
b.Verify CI and CVI valve status lights-BRIGHT c.CNMT RECIRC fan coolers SW outlet valve status lights BRIGHT b.Manually close CI and CVI valves 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.Dispatch AO to locally fail open valves.~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 RUNNING b.Place switch for excess letdown AOV-310 to CLOSE a.IF offsite power available, THEN manually start one CCW pump.c.Verify CCW from excess letdown AOV-745-CLOSED c.Manually close valve.
o  Sump A  level  - INCREASING
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 10 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify SI And RHR Pump Flow: a.SI flow indicators
                        -OR-o  Sump A pump    start frequency-INCREASING  (Refer to  RCS Daily  Leakage Log)
-CHECK FOR FLOW b.RHR flow indicator-CHECK FOR FLOW a.IF RCS pressure less than 1400 psig, THEN manually start pumps and align valves.IF NOT, THEN go to Step-15.b.IF RCS pressure less than 140 psig, THEN manually start pumps and align valves.IF NOT, THEN go to Step 15.15 Verify Total AFW Flow-GREATER THAN 200 GPM IF S/G narrow range level greater 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.
: b. Evaluate  Sump A  conditions:            b. Plant shutdown should be considered, consult plant    staff.
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:
: 1) Verify  Leakage  within capacity of    one Sump A pump (50 gpm)
a.AFW flow-INDICATED TO BOTH S/G(s)b.AFW flow from each MDAFW pump-LESS THAN 230 GPM Manually align valves as necessary.
: 2) Check Sump A    level  - LESS THAN 10 FEET
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 11 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Verify SI Pump And RHR Pump Emergency Alignment:
: c. Direct  RP to establish conditions for CNMT entry
a.RHR pump discharge to Rx vessel deluge-OPEN~MOV-852A~MOV-852B b.Verify SI pump C-RUNNING c.Verify SI pump A-RUNNING d.Verify SI pump B-RUNNING e.Verify SI pump C discharge valves-OPEN~MOV-871A~MOV-871B a.Ensure at least one valve open.b.Manually start pump on available bus.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.Perform the following:
V
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.Manually open valves as necessary.
& 4 r-
EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 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 Barriers: o Annunciator A-7, RCP 1A CCW RETURN HI TEMP OR LO FLOW-EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HI TEMP OR LO FLOW EXTINGUISHED IF CCW to a RCP is lost, THEN perform the following:
EOP:              TITLE:
a.Stop affected RCPs.b.Reset SI.c.Verify adequate power available to run one charging pump (75 kw).d.Start one charging pump at minimum speed for seal injection.
REV      14 AP-SW.1                                  SERVICE WATER LEAK PAGE 6        of  10 STEP        ACTION/EXPECTED RESPONSE                      RESPONSE  NOT OBTAINED 1 ~   t  4  I
e.Adjust HCV-142 to establish either of the following:
* 1 '0  I  *  ~ 4  1 1 4  1
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.
* 1 0 *
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 13 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Check If TDAFW Pump Can Be Stopped: a.Both MDAFW pumps-RUNNING b.PULL STOP TDAFW-pump steam supply valves~MOV-3504A~MOV-3505A a.Go to Step 20.*20 Monitor RCS Tavg-STABLE AT OR TRENDING TO 547 F IF temperature less than 547'F and decreasing, THEN perform the following:
* 4 t 1  1  4 4  0 ~  I I 4
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.
* 1  1  1  1  t ~
fop: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 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 b.Auxiliary spray valve (AOV-296)CLOSED c.Check PRZR pressure-LESS THAN 2260 PSIG d.Normal PRZR spray valves-CLOSED~PCV-431A~PCV-431B IF block valve can NOT be closed.THEN go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT.'tep 1~b.Manually close auxiliary spray valve.IF valve can NOT be closed.THEN perform the following:
CAUTION BEFORE ISOLATING SW TO CNMT RECIRC FANS. REFER TO              ITS SECTION 3.6.6      FOR OPERABILITY REQUIREMENTS.
1)Decrease charging pump flow to minimum.2)Ensure charging valve to loop B cold leg open (AOV-294).
NOTE:    o   One  Reactor Compartment cooling fan should be running whenever                  RCS temperature is greater than 135 F.'
c.Continue with Step 22.WHEN pressure less than 2260 psig.THEN do Steps 21d.d.Place controllers in MANUAL at 0/.demand.IF valves can NOT be closed, THEN stop associated RCP(s).
CNMT recirc fan condensate          collector level indicators      may be helpful in identifying a leaking fan cooler.
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 15 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*22 Monitor RCP Trip Criteria: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 23'.Go to Step 23.c.Go to Step 23.23 Check If S/G Secondary Side Is Intact: o Pressure in both S/Gs-STABLE OR INCREASING o Pressure in both S/Gs-GREATER THAN 110 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.24 Check If S/G Tubes Are Intact: 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 Go to E-3.STEAM GENERATOR TUBE RUPTURE, Step 1.  
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.
: b. Intact  SW  loop header pressure          b. Dispatch      AO to perform the GREATER THAN 45 PSIG                            following:
: 1)  Split  A and B  SW headers:
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)
: 2) ATTACHMENT SW LOADS IN CNMT  (ATT-2.3)
 
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.
: b. SI sequencing  - BOTH TRAINS        b. Manually actuate SI and CI.
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:
: 1) Ensure SI pump   suction supply open from RWST.
: 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
* 7  Verify CNMT Spray Not                  Verify    CNMT spray  initiated.
Required:
IF CNMT spray NOT     initiated, THEN o  Annunciator A-27. CNMT SPRAY-       perform the following:
EXTINGUISHED
: a. Depress manual    CNMT  spray o  CNMT pressure - LESS THAN 28 PSIG       pushbuttons (2    of 2).
: 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.
: b. Check  CNMT  pressure  - LESS THAN  b ~ Ensure BOTH MSIVs closed and go 18 PSIG                                  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:
: a. MFW  pumps  - TRIPPED                a. Manually close  MFW pump discharge valves and  trip  MFW pumps.
: b. MFW  flow control valves    - CLOSED b. Place  A and B S/G MFW  regulating valve and bypass valve
          ~ 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:
: a. MDAFW pumps  - RUNNING                a. Manually    start  MDAFW  pumps.
: 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
: a. Ensure one    SW  pump running on each energized screenhouse      AC emergency bus:
                                                      ~  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)
: b. AFW  flow from  each  MDAFW pump-LESS THAN 230 GPM
 
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:
: a. RCP  status  - ANY RCP RUNNING        a. Go to Step  23
                                                                    '.
: 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
: b. CNMT  pressure    - LESS THAN 0.5 PSIG
: c. CNMT sump B    level  - LESS THAN 8 INCHES
: d. CNMT sump A    level o  Level  - STABLE o  Annunciator C-19. CONTAINMENT SUMP A  HI LEVEL - EXTINGUISHED


EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 16 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If RCS Is Intact: a.CNMT area radiation monitors NORMAL Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT.Step l.~R-2~R-7~R-29~R-30 b.CNMT pressure-LESS THAN 0.5 PSIG c.CNMT sump B level-LESS THAN 8 INCHES d.CNMT sump A level o Level-STABLE o Annunciator C-19.CONTAINMENT SUMP A HI LEVEL-EXTINGUISHED
,
,
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 17 of,26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check If SI Should Be Terminated:
EOP:
a.RCS pressure: o Pressure-GREATER THAN 1625 PSIG o Pressure-STABLE OR INCREASING b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING c.Secondary heat sink: o Total feed flow to S/Gs GREATER THAN 200 GPM a.Do NOT stop SI pumps.Go to Step 27.b.Do NOT stop SI pumps.Go to Step 27.c.IF neither condition met, THEN do NOT stop SI pumps.Go to Step 27.-OR-o Narrow range level in at least one S/G-GREATER THAN 5%d.PRZR level-GREATER THAN 5%e.Go to ES-l.l.SI TERMINATION.
REV: 27 E-0                   REACTOR   TRIP OR SAFETY   INJECTION PAGE 17   of,26 STEP       ACTION/EXPECTED RESPONSE             RESPONSE   NOT OBTAINED 26 Check     If Terminated:
Step 1.d.Do NOT stop SI pumps.Perform the following:
SI Should   Be
1)IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.2)Go to Step 27.
: a. RCS pressure:                         a. Do NOT  stop SI pumps. Go to Step 27.
EOP: E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 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   Pressure   - GREATER THAN 1625 PSIG o   Pressure   - STABLE OR INCREASING
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 THAN 5%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%in at least one S/G.b.Control feed flow to maintain narrow range level between 17%and 50%b.IF narrow range level in any S/G continues to increase in an uncontrolled manner.THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.29 Check Secondary Radiation Levels-NORMAL 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 Go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: b. RCS subcooling based on core         b. Do NOT  stop SI pumps. Go to exit T/Cs - GREATER THAN O'               Step 27.
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.
: e. Go  to ES-l.l. SI  TERMINATION.
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: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 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.
EOP:               TITLE:
*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 ISOLATION-EXTINGUISHED b.Perform the following:
REV: 27 E-0                   REACTOR     TRIP   OR SAFETY     INJECTION PAGE 19   of 26 STEP         ACTION/EXPECTED RESPONSE                     RESPONSE NOT OBTAINED
l)Reset SI.2)Depress CI reset pushbutton.
  * ~ ~ 0 1 I   1 ~ 0 I
32 Verify Adequate SW Flow: a.At least three SW pumps-RUNNING b.Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)a.Manually start SW pumps as power supply permits (257 kw each).IF less than three pumps running, THEN ensure SW isolation.  
* 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: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 20 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Establish IA to CNMT: a.Verify non-safeguards busses energized from offsite power o Bus 13 normal feed-CLOSED-OR-o Bus 15 normal feed-CLOSED b.Verify SW isolation valves to turbine building-OPEN~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify adequate air compressor(s)
EOP:
-RUNNING d.'heck IA supply: o Pressure-GREATER THAN 60 PSIG o Pressure-STABLE OR INCREASING e.Reset both trains of XY relays for IA to CNMT AOV-5392 f.Verify IA to CNMT AOV-5392-OPEN a.Perform the following:
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:
1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Verify adequate emergency D/G capacity to run air compressors (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS)~.-3)WHEN bus 15 restored, THEN reset'ontrol room lighting.b.Manually align valves'.Manually start air compressors as power supply permits (75 kw each).IF air compressors can NOT be started.THEN dispatch AO to locally reset compressors as necessary.
: a. Verify non-safeguards busses             a. Perform the     following:
d.Perform the following:
energized from    offsite  power
1)Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).2)Continue with Step 34.WHEN IA restored, THEN do Steps 33e and f.
: 1) Close   non-safeguards           bus   tie o  Bus 13 normal feed - CLOSED                  breakers:
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 21 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check Auxiliary Building Radiation-NORMAL~Plant vent iodine (R-10B)~Plant vent particulate (R-13)~Plant vent gas (R-14)~CCW liquid monitor (R-17)~LTD line monitor (R-9)~CHG pump room (R-4)Evaluate cause of abnormal conditions.
                        -OR-                                ~ Bus 13 to Bus 14         tie
IF the cause is a loss of RCS inventory outside CNMT.THEN go to ECA-1.2.LOCA OUTSIDE CONTAINMENT, Step 1.35 Check PRT Conditions o PRT level (LI-442)-LESS THAN 84%o PRT temperature (TI-439)-LESS THAN 120 F Evaluate the following flowpaths for cause of abnormal conditions:
                                                            ~ Bus 15 to Bus 16         tie o  Bus 15 normal feed - CLOSED
~RCP seal return relief~PRZR PORVs~PRZR safeties~Letdown line relief o PRT pressure (PI-440A)-LESS THAN 3 PSIG IF excess letdown previously in service, THEN close AOV-310, excess letdown isolation valve from loop A cold.
: 2) Verify adequate emergency               D/G capacity to run air compressors         (75 kw each).
EOP: E-0 TITLE: REACTOR TRIP OR SAFETY INJECTION REV: 27 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 NOT, THEN evaluate RECIRC fans should be if  CNMT stopped (Refer to Attachment             CNMT RECIRC FANS)       ~
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 If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 PSIG 2)Pressure-STABLE OR INCREASING 1)Go to E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.2)Go to Step 37.b.Stop both RHR pumps and place in AUTO 37 Check Normal Power Available To Charging Pumps: o Bus 14 normal feed breaker-CLOSED o Bus 16 normal feed breaker-CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
                                                      .-3) WHEN bus 15   restored,         THEN reset'ontrol             room lighting.
EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 23 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check If Charging Flow Has Been Established:
: b. Verify  SW  isolation
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 RWST: o LCV-112B-OPEN o'CV-112C-CLOSED b.Manually align valves as necessary.
valves to        b. Manually align turbine building      OPEN                                    valves'.
IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed.THEN perform the following:
          ~ MOV-4613 and MOV-4670
1)Verify charging pump A NOT running and place in PULL STOP.c.Start charging pumps as necessary and adjust charging flow to restore PRZR level 2)Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
          ~ MOV-4614 and MOV-4664
EOP: E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 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
: 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.
: e. Reset both  trains of XY relays for IA to CNMT AOV-5392
: f. Verify IA to CNMT AOV-5392 - OPEN


EOP: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 25 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 40 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by 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 a.Perform the following:
EOP:
1)Verify non-safeguards bus tie breakers closed:~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)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 21  of 26 STEP       ACTION/EXPECTED RESPONSE             RESPONSE   NOT OBTAINED 34 Check     Auxiliary  Building              Evaluate cause of abnormal Radiation      NORMAL                    conditions.
E-0 REACTOR TRIP OR SAFETY IN JECTION REV: 27 PAGE 26 of 26 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Return to Step 20-END-  
        ~ 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.


E-0 REACTOR TRIP OR SAFETY IN JECTION REV 27 PAGE 1 of 1 E-0 APPENDIX LIST TITLE 1)RED PATH  
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:
: 1) Pressure      - GREATER THAN                      1) Go  to E-l,  LOSS OF REACTOR OR 250 PSIG                                              SECONDARY COOLANT, Step 1.
: 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==
==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: E-0 REACTOR TRIP OR SAFETY INJECTION REV: 27 PAGE 1 of 1 RED PATH  
: 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==
==SUMMARY==
a.SUBCRITICALITY
: a. SUBCRITICALITY Nuclear power   greater than 5%
-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
: b. CORE COOLING   Core exit T/Cs greater than 1200 F
-CNMT pressure greater than 60 psig E-0 REACTOR TRIP OR SAFETY INJECTION REV 27 PAGE 1 of 1 FOLDOUT PAGE 2.RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs: a.SI pumps--AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG[400 psig adverse CNMT]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).
                                            -OR-Core exit T/Cs greater than 700' AND RVLIS level (no RCPs) less than 52% [55%
t EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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:
                        - adverse CNMT]
I EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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
: c. HEAT SINK Narrow range   level in all S/Gs less than 5%
-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.
[25% adverse   CNMT] AND total feedwater flow less than   200 gpm
d.ES-l.l, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
: d. INTEGRITY Cold   leg temperatures decrease greater than 100'   in last 60 minutes AND RCS cold leg temperature less than 285 F
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.
: e. CONTAINMENT CNMT pressure greater than 60 psig
g.ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.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.
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:
EOP: TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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.
: a. SI pumps-   AT LEAST TWO RUNNING
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).
: b. RCS pressure minus maximum S/G pressure   LESS THAN 175 PSIG
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: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 2.b.Go to Step 2.c.Go to Step 2.  
[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.
: g. ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA       outside containment   is isolated.
: 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:
: a. RCP   status   - ANY RCP RUNNING           a. Go to Step 2.
: 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
: b. PORVs    - CLOSED                            b. IF  PRZR  pressure less than 2335  psig,  THEN manually close PORVs.
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.
: e. Reset both  trains of XY relays for IA to CNMT AOV-5392
: f. Verify IA to CNMT AOV-5392 - OPEN
 
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
: a. RCS  pressure:                      a. Do NOT    stop SI pumps. Go to Step 13.
o  Pressure  - GREATER THAN 1625  psig [1825 psig adverse CNMT]
o  Pressure  - STABLE OR INCREASING
: b. RCS  subcooling based on core      b. Do NOT    stop SI pumps. Go  to exit T/Cs - GREATER THAN O'            Step 13.
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.
: e. Go  to ES-l.l, SI  TERMINATION, Step  l.
 
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
: 2) RCS  pressure    - STABLE OR                      2) Go  to Step    15.
INCREASING
: b. Stop  RHR pumps      and  place in      AUTO 15 Check RCS And S/G              Pressures
: 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.
: c. Check    RCS  pressure    - STABLE OR            c. Return to Step        l.
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:
: a. Check  RHR  and  CCW  systems:    a. Restore power to at least one train of emergency AC busses.
: 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
: 2) RHR pumps and      valves OPERABLE
: 3)  CCW  pumps and Hx - OPERABLE
: 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 boron
          ~  RCS activity
          ~ CNMT hydrogen
          ~ CNMT sump boron
: 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: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 4 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If S/G Secondary Side Is Intact: o Pressure in both S/Gs-STABLE OR INCREASING o Pressure in both S/Gs-GREATER THAN 110 PSIG IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN verify faulted S/G isolated unless needed for RCS cooldown:~Steamlines
EOP:
~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 THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMTl and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT1 in at least one S/G.b.IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3.STEAM GENERATOR TUBE RUPTURE, Step l.*4 Monitor If Secondary Radiation Levels Are Normal o Steamline radiation monitor (R-31 and R-32)o Request RP sample S/Gs for activity IF steamline radiation monitors NOT available, THEN dispatch AO to locally check steamline radiation.
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:
IF abnormal radiation levels detected in any S/G, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.
: 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.
~I EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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 AVAILABLE b.PORVs-CLOSED a.Restore power to block valves unless block valve was closed to isolate an open PORV: o MOV-515, MCC D position 6C~MOV-516, MCC C position 6C b.IF PRZR pressure less than 2335 psig, THEN manually close PORVs.c.Block valves-AT LEAST ONE OPEN 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.Open one block valve unless it was closed to isolate an open PORV.
: b. Go to ES-1.2. POST LOCA COOLDOWN AND DEPRESSURIZATION. Step 1
U I'~4 EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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 ISOLATION-EXTINGUISHED b.Perform the following:
1)Reset SI.2)Depress CI reset pushbutton.
8 Verify Adequate SW Flow: a.Check at least two SW pumps RUNNING b.Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)a.Manually start SW pumps as power supply permits (257 kw each).IF less than two SW pumps running, THEN perform the following:
1)Ensure SW isolation.
2)Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)3)Go to Step 10.
*~
EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 7 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish IA to CNMT: a.Verify non-safeguards busses energized from offsite power o Bus 13 normal feed-CLOSED-OR-o Bus 15 normal feed-CLOSED b.Verify turbine building SW isolation valves-OPEN~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify adequate air compressors RUNNING d.Check IA supply: o Pressure-GREATER THAN 60 PSIG o Pressure-STABLE OR INCREASING e.Reset both trains of XY relays for IA to CNMT AOV-5392 f.Verify IA to CNMT AOV-5392-OPEN a.Perform the following:
1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Verify adequate emergency D/G capacity to run air compressors (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).3)WHEN bus 15 restored, THEN reset control room lighting.b.Manually align valves.c.Manually start air compressors as power supply permits (75 kw each).IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
d.Perform the following:
1)Continue attempts to restore IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).2)Continue with Step 10.WHEN IA restored, THEN do Steps 9e and f.
EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 8 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Normal Power Available To Charging Pumps: o Bus 14 normal feed breaker CLOSED o Bus 16 normal feed breaker CLOSED Verify adequate emergency D/G capacity to run charging pumps (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer to Attachment CNMT RECIRC FANS).
EOP: E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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 RWST: o LCV-112B-OPEN o LCV-112C-CLOSED b.Manually align valves as necessary.
IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed.THEN perform the following:
1)Verify charging pump A NOT running and place in PULL STOP.2)Direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).c.Start charging pumps as necessary and adjust charging flow to restore PRZR level


EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 FAGE 10 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If SI Should Be Terminated:
EOP:
a.RCS pressure: o Pressure-GREATER THAN 1625 psig[1825 psig adverse CNMT]a.Do NOT stop SI pumps.Go to Step 13.o Pressure-STABLE OR INCREASING b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FXGURE MIN SUBCOOLING b.Do NOT stop SI pumps.Go to Step 13.FI c.Secondary heat sink: o Total feed flow to intact S/Gs-GREATER THAN 200 GPM c.IF neither condition satisfied.
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.
THEN do NOT stop SI pumps.Go to Step 13.-OR-o Narrow range level in at least one intact S/G GREATER THAN 5%[25%adverse CNMT]d.PRZR level-GREATER THAN 5%[30%adverse CNMT]e.Go to ES-l.l, SI TERMINATION, Step l.d.Do NOT stop SX pumps.Perform the following:
21 Establish Adequate        SW  Flow:
1)IF normal PRZR spray available'HEN try to stabilize RCS pressure with PRZR spray.2)Go to Step 13.
: 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:
h EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE ll of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*13 Monitor If CNMT Spray Should Be Stopped: a.CNMT spray pumps-RUNNING b.Check the following:
: 1) Ensure Attachment MIN SW is in progress.
o CNMT pressure-LESS THAN 4 PSIG a.Go to Step 14.b.Continue with Step 14.WHEN BOTH conditions satisfied, THEN do Steps 13c through f.o Sodium hydroxide tank level LESS THAN 55'/c.Reset CNMT spray d.Check NaOH tank outlet valves CLOSED~AOV-836A~AOV-836B d.Place NaOH tank outlet valve controllers to MANUAL and close valves.e.Stop CNMT spray pumps and place in AUTO f.Close CNMT spray pump discharge valves~MOV-860A~MOV-860B~MOV-860C~MOV-860D EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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.
: 2) Go  to Step  22.
o.RCS PRESSURE SHOULD BE MONITORED.
: b. Verify AUX  BLDG SW  isolation        b. Manually align valves.
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 If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT7 2)RCS pressure-STABLE OR INCREASING 1)Go to Step 16.2)Go to Step 15.b.Stop RHR pumps and place in AUTO 15 Check RCS And S/G Pressures a.Check pressures in both S/Gs STABLE OR INCREASING b.Check pressures in both S/Gs-GREATER THAN 110 PSIG c.Check RCS pressure-STABLE OR DECREASING a.Return to Step 1.b.Monitor RCS pressure.IF RCS pressure does NOT increase after faulted S/G dryout, THEN go to Step 16.c.Return to Step l.
valves - OPEN
EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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 energized by 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)a.Perform the following:
          ~ MOV-4615 and MOV-4734
1)Close non-safeguards bus tie breakers as necessary:
          ~ MOV-4616 and MOV-4735 This Step continued on the next page.
~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)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).
EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If RHR Should Be Throttled:
a.Check RHR Pumps-ANY RUNNING b.Check RWST level-LESS THAN 70%c.RHR flow-LESS THAN 1500 GPM PER OPERATING PUMP a.Go to step 18.b.Continue with Step 18.WHEN RWST level less than 70%, THEN perform step 17b.c.Manually adjust RHR Hx outlet 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: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 15 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:
a.Check RHR and CCW systems: 1)Power available to emergency AC busses and MCCs required for CNMT sump recirculation o Bus 14 and bus 18 ENERGIZED a.Restore power to at least one train of emergency AC busses.IF at least one train of cold leg recirculation capability can NOT be verified, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step l.o MCC C-ENERGIZED o Bus 16 and bus 17 ENERGIZED o MCC D-ENERGIZED 2)RHR pumps and valves OPERABLE 3)CCW pumps and Hx-OPERABLE b.Check SW pumps-AT LEAST 2 PUMPS AVAILABLE c.Dispatch AO to check AUX BLDG sub-basement for RHR system leakage (AUX BLDG sub-basement key may be required)b.Attempt to restore at least 2 SW pumps to operable.IF only 1 SW pump available, THEN refer to Attachment MIN SW for additional guidance.c.IF any RHR pump seal leakage indicated, THEN leakage should be evaluated and isolated if necessary.
l a ll-~ll~'0 1 I~
EOP: LOSS OP REACTOR OR SECONDARY COOLANT REV: 21 PAGE 16 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Evaluate Plant Status: a.Check auxiliary building radiation-NORMAL~Plant vent iodine (R-10B)~Plant vent particulate (R-13)~Plant vent gas (R-14)~CCW liquid monitor (R-17)~LTDN line monitor (R-9)~CHG pump room (R-4)b.Direct RP to obtain following samples:~RCS boron~RCS activity~CNMT hydrogen~CNMT sump boron c.Verify adequate Rx head cooling: 1)Verify at least one control rod shroud fan-RUNNING 2)Verify one Rx compartment cooling fan-RUNNING a.Notify RP and refer to appropriate AR-RMS procedure.
IF the cause is a loss of RCS inventory outside CNMT, THEN go to ECA-1.2.LOCA OUTSIDE CONTAINMENT.
Step 1.1)Manually start one fan as power supply permits (45 kw)2)Perform the following:
o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)


EOP: E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 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 250 psig[465 psig adverse CNMT]b.Go to ES-1.2.POST LOCA COOLDOWN AND DEPRESSURIZATION.
EOP:             T1TLE:
Step 1 a.IF RHR pump flow greater than 475 gpm, THEN go to Step 21.
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)
EOP: E-1 LOSS 05'EACTOR OR SECONDARY COOLANT REV: 21 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-RUNNING b.Verify AUX BLDG SW isolation valves-OPEN a.Start additional SW pumps as power supply permits (257 kw each).IF only 1 SW pump operable, THEN perform the following:
: c. Dispatch   AO to perform the following:
1)Ensure Attachment MIN SW is in progress.2)Go to Step 22.b.Manually align valves.~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 This Step continued on the next page.
: 1) Check BOTH   CCW Hx - INSERVICE   1) Perform   the following:
EOP: E-1 T1TLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 19 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (Step 21 continued from previous page)c.Dispatch AO to 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
1)Check BOTH CCW Hx-INSERVICE 1)Perform the following:
                                                          ~ V-4620
a)Locally place BOTH CCW Hxs in service 2)Verify total SW flow to CCW Hxs-GREATER THAN 5000 GPM b)Locally adjust total SW flow equally to available CCW Hxs to between 5000 gpm and 6000 gpm 0 V-4619~V-4620 2)Perform the following:
: 2) Verify total  SW  flow to CCW      2) Perform the     following:
a)Isolate SW to screenhouse and air conditioning headers.~MOV-4609/MOV-4780
Hxs - GREATER THAN 5000    GPM a) Isolate   SW to screenhouse and air conditioning headers.
-AT LEAST ONE CLOSED~MOV-4663/MOV-4733
                                                          ~ MOV-4609/MOV-4780 - AT LEAST ONE CLOSED
-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.
                                                          ~ 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).
EOP: E-1 TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 20 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Establish CCW flow to RHR Hxs: a.Check both CCW pumps-RUNNING b.Manually open CCW valves to RHR Hxs a.Perform the following:
c) Direct AO to locally isolate SW return from     SFP Hxs:
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:
SFP Hx A   (V-4622)
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.b.Dispatch AO to locally open valves.~MOV-738A~MOV-738B
                                                          ~ SFP Hx B   (V-8689) d) Verify   SW portions of Attachment SD-1 are complete.


EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 21 of 21 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Transfer To Cold Leg Recirculation Is Required: a.RWST level-LESS THAN 28'/o b.Go to ES-1.3.TRANSFER TO COLD LEG RECIRCULATION, Step 1 a.Return to Step 17.-END-  
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.
: b. Manually open    CCW valves to  RHR  b. Dispatch    AO  to locally    open Hxs                                      valves.
          ~ MOV-738A
          ~ MOV-738B


EOP: TITLE: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 E-1 APPENDIX LIST TITLE 1)RED PATH  
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==
==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: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 RED PATH  
: 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==
==SUMMARY==
a.SUBCRITICALITY
: a. SUBCRITICALITY Nuclear power   greater than 5%
-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
: b. CORE COOLING   Core exit T/Cs greater than 1200'
-CNMT pressure greater than 60 psig EOP: LOSS OF REACTOR OR SECONDARY COOLANT REV: 21 PAGE 1 of 1 1.RCP TRIP CRITERIA FOLDOUT PAGE IF BOTH conditions listed below occur, THEN trip both RCPs: a.Sl pumps-AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG[400 psig adverse CNMT]2..SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually start Sl pumps as necessary:
                                          -OR-Coze exit T/Cs greater than 700' AND RVLIS level (no RCPs) less than 52% [55%
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 TERMINATION CRITERIA IF ALL conditions 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).
adverse CNMT]
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 41 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONS LE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
: c. HEAT SINK Narrow range   level in all S/Gs less than 5%
EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 27 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
[25% adverse CNMT] AND total feedwater flow less than 200 gpm
-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 0 g REACTOR TRI P OR SAFETY IN JECTION 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.
: d. INTEGRITY Cold   leg temperatures decrease greater than 100'   in last 60 minutes AND RCS cold leg temperature less than 285'
4 EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 3 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open AND monitored periodically.
: e. CONTAINMENT   CNMT pressure greater than 60 psig
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).
EOP:
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: a.RCP status-ANY RCP RUNNING b.SI pumps-AT LEAST TWO RUNNING c.RCS pressure minus maximum S/G pressure-LESS THAN 175 psig[400 psig adverse CNMT]d.Stop both RCPs a.Go to Step 2.b.Go to Step 2.c.Go to Step 2.
REV: 21 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1     of 1 FOLDOUT PAGE
EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV 27 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.
: 1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
2 Identify Ruptured S/G(s): o Unexpected increase in either 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 Perform the following:
: a. Sl pumps   -AT LEAST TWO RUNNING
a.Reset SI b.Continue with Steps 10 through 16.WHEN ruptured S/G(s)identified.
: b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG [400 psig adverse CNMT]
THEN do Steps 3 through 9.-OR-o AO reports local indication of high steamline radiation-OR-o RP reports high radiation from S/G activity sample EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 steam supply valve and place in PULL STOP~S/G A, MOV-3505A~S/G B.MOV-3504A d.Verify ruptured S/G blowdown valve-CLOSED~S/G A, AOV-5738~S/G B, AOV-5737 c.Dispatch AO with locked valve key to locally isolate steam from ruptured S/G to TDAFW pump.~S/G A, V-3505~S/G B, V-3504 d.Place S/G blowdown and sample valve isolation switch to CLOSE.IF blowdown can NOT be isolated manually, THEN dispatch AO to locally isolate blowdown.~S/G A, V-5701~S/G B.V-5702 0~g 4 I EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 6 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:
2.. SI REINITIATIONCRITERIA IF EITHER condition listed below occurs, THEN manually start Sl pumps as necessary:
a.Close ruptured S/G MSIV-RUPTURED S/G MSIV CLOSED a.Perform the following:
o RCS subcooling based on core exit T/Cs - LESS THAN 0 F USING FIGURE MIN SUBCOOLING
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.b.Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)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).
                    -OR-o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMTJ
1 EOP: TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 THAN 5%[25%adverse CNMT]b.Close MDAFW pump discharge valve to ruptured S/G~S/G A, MOV-4007~S/G B, MOV-4008 a.IF ruptured S/G NOT faulted.THEN perform the following:
: 3. SI TERMINATIONCRITERIA IF ALLconditions listed below occur, THEN go to ES-1.1, Sl TERMINATION, Step 1:
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.b.Dispatch AO to locally close valve.c.Pull stop MDAFW pump for ruptured S/G d.Close TDAFW pump flow control valve to ruptured S/G~S/G A, AOV-4297~S/G B.AOV-4298 e.Verify MDAFW pump crosstie valves-CLOSED d.Dispatch AO with locked'alve key to locally close TDAFW pump manual feedwater isolation valve to ruptured S/G.~S/G AD V-4005~S/G B.V-4006 e.Manually close valves.~MOV-4000A~MOV-4000B EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 8 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Ruptured S/G Isolated: a.Check ruptured MSIV-CLOSED b.Check TDAFW pump steam supply from ruptured S/G-ISOLATED c.Ruptured S/G pressure-GREATER THAN 300 PSIG a.Ensure air ejector/gland steam supply and flange heating steam isolated.(Refer to ATTACHMENT RUPTURED S/G, part B).b.Continue efforts to isolate steam supply from ruptured S/G:~S/G A, MOV-3505A OR V-3505~S/G B, MOV-3504A OR V-3504 c.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.7 Establish Condenser Steam Dump Pressure Control: a.Verify condenser available:
: a. RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING
o Intact S/G MSIV-OPEN o Annunciator G-15.STEAM DUMP ARMED-LIT a.Adjust S/G ARV controllers to maintain intact S/G pressure in AUTO and go to Step 8.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: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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.
: b. Total feed flow to intact S/Gs - GREATER THAN 200 GPM
8 Reset SI EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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.
                    -OR-Narrow range level in at least one intact S/G - GREATER THAN 5% [25% adverse CNMT]
9 Initiate RCS Cooldown: a.Determine required core exit temperature from below table RUPTURED SG PRESSURE REQUIRED CORE EXIT TEMPERATURE
: c. RCS pressure:
('F)1100 PSIG 1000 PSIG 900 PSXG 800 PSIG 700 PSXG 600 PSIG 500 PSIG 400 PSIG 300 PSIG 525 510 500 485 465 450 425 405 375 505 adverse CNMT]490 adverse CNMT]475 adverse CNMT]460 adverse CNMT]440 adverse CNMT]420 adverse CNMT]395 adverse CNMT]370 adverse CNMT 330 adverse CNMT b.IF ruptured S/G MSIV closed, THEN initiate dumping steam to condenser from intact S/G at maximum rate c.Core exit T/Cs-LESS THAN REQUIRED TEMPERATURE d.Stop RCS cooldown and stabilize core exit T/Cs less than required temperature b.Manually or locally initiate steam dump from intact S/G at maximum rate using S/G ARV.IF no intact S/G available, THEN perform the following:
o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]
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.Continue with Step 10.WHEN core exit T/Cs less than required, THEN do Step 9d.
o STABLE OR INCREASING
EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 THAN 5%[25%%d adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT]and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in at least one S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
: d. PRZR level - GREATER THAN 5% [30% adverse CNMT]
II 4 EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 PRZR PORVs And Block Valves: a.Power to PORV block valves AVAILABLE b.PORVs-CLOSED a.Restore power to block valves unless block valve was closed to isolate an open PORV:~MOV-515, MCC D position 6C~MOV-516, MCC C position 6C b.IF PRZR pressure less than 2335 psig, THEN manually close PORVs.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.  
: 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:
: a. RCP   status - ANY RCP RUNNING         a. Go to Step 2.
: 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.
: b. Close      MDAFW pump    discharge valve      b. Dispatch     AO   to locally close to ruptured      S/G                              valve.
            ~  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
: b. PORVs    - CLOSED                            b. IF     PRZR   pressure less than 2335   psig, THEN manually close PORVs.
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.
: e. Reset both  trains of  XY relays for IA to  CNMT  AOV-5392 Verify IA to    CNMT  AOV-5392 - OPEN(
 
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


EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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 ISOLATION-EXTINGUISHED b.Perform the following:
\ ~" f W 5 ' ~
1)Reset SI.2)Depress CI reset pushbutton.
EOP:
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 14 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Monitor All AC Busses BUSSES ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses-CLOSED o 480 volt bus voltage-GREATER THAN 420 VOLTS o Emergency D/G output breakers OPEN Perform the following:
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.
a.IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.b.Perform the following as necessary:
21 Depressurize       RCS   To Minimize Break Flow And Refill PRZR:
1)Close non-safeguards bus tie 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~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.
: a. Check the following:                       a. Go to Step 22.
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).
o Ruptured S/G level - LESS THAN 90%     [80% adverse CNMT]
l EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 15 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Verify Adequate SW Flow: a.Check at least two SW pumps-RUNNING a.Manually start SW pumps as power supply permits (257 kw each).IF less than two SW pumps running, THEN: 1)Ensure SW isolation.
o Any RCP - RUNNING o   IA to CNMT - AVAILABLE
2)Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)b.Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)3)Go to Step 16.
: b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
EOP: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 16 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Establish IA to CNMT: a.Verify non-safeguards busses energized o Bus 13 normal feed-CLOSED a.Perform the following:
o   PRZR level - GREATER THAN 75%
1)Close non-safeguards bus tie breakers:-OR-o Bus 15 normal feed-CLOSED b.Verify turbine building SW isolation valves-OPEN~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Verify adequate emergency D/G capacity to run air compressors (75 kw each).IF NOT, THEN evaluate if CNMT RECIRC fans should be stopped (Refer to Attachment CNMT RECIRC FANS).b.Manually align valves.~MOV-4613 and MOV-4670~MOV-4614 and MOV-4664 c.Verify adequate air compressors
[65% adverse     CNMT]
-RUNNING d.Check IA supply: o Pressure-GREATER THAN 60 PSIG o Pressure-STABLE OR INCREASING
                          -OR-o RCS   pressure - LESS THAN SATURATION USING FIGURE MIN SUBCOOLING
, c.Manually start air compressors as power supply permits (75 kw each).IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
                          -OR-o   BOTH of the following:
d.Perform the following:
: 1) RCS   pressure - LESS THAN RUPTURED S/G PRESSURE
1)Continue attempts to restore IA (Refer to AP-IA.1.LOSS OF INSTRUMENT AIR).2)Continue with Step 16.WHEN IA restored, THEN do Steps 15e and f.e.Reset both trains of XY relays for IA to CNMT AOV-5392 Verify IA to CNMT AOV-5392-OPEN(
: 2) PRZR   level   - GREATER THAN 5%   [30%   adverse   CNMT]
EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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.
: c. Close normal     PRZR spray valves:      c. Stop associated  RCP(s).
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 THAN 250,psig[465 psig adverse CNMT]b.Stop RHR pumps and place both in AUTO a.Go to Step 17.
: 1) Adjust normal spray valve controller to 0% DEMAND
y'S&~1~I'~~~.~~''"%~I I EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 18 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Establish Charging Flow: a.Charging pumps-ANY RUNNING a.Perform the following:
: 2) Verify PRZR spray valves CLOSED
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 RWST: o LCV-112B-OPEN o LCV-112C-CLOSED c.Start charging pumps as necessary and establish 75 gpm total charging flow~Charging line flow~Seal injection b.IF LCV-112B can NOT be opened, THEN dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).IF LCV-112C can NOT be closed, THEN perform the following:
              ~ PCV-431A
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).
              ~ PCV-431B
0~I IL t Hl k$~
: d. Verify auxiliary
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 19 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If RCS Cooldown Should Be Stopped: a.Core exit T/Cs-LESS THAN REQUIRED TEMPERATURE b.Stop RCS cooldown c.Stabilize core exit T/Cs-LESS THAN REQUIRED TEMPERATURE a.Do NOT proceed until core exit T/Cs less than required temperature.
                        -
19 Check Ruptured S/G Pressure-STABLE OR INCREASING IF pressure continues to decrease 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 Core Exit T/Cs-GREATER THAN 20 F USING FIGURE MIN SUBCOOLING Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1
spray valve         d. Decrease charging speed to (AOV-296)     CLOSED                         minimum and ensure charging valve to loop B cold leg open (AOV-294).
\~" f W 5'~
: e. Go to Step   24
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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:
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: 1)Adjust normal spray valve controller to 0%DEMAND 2)Verify PRZR spray valves CLOSED~PCV-431A~PCV-431B d.Verify auxiliary spray valve (AOV-296)-CLOSED e.Go to Step 24 a.Go to Step 22.c.Stop associated RCP(s).d.Decrease charging speed to minimum and ensure charging valve to loop B cold leg open (AOV-294).
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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: a.Verify IA to CNMT-AVAILABLE b.PRZR PORVs-AT LEAST ONE AVAILABLE a.Refer to Attachment N2 PORVS to operate PORVs.b.IF auxiliary spray 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: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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 the following conditions satisfied:
o PRZR level-GREATER THAN 75%[65%adverse CNMT]-OR-o RCS pressure-LESS THAN SATURATION USING FIGURE MIN SUBCOOLING c.IF auxiliary spray available, THEN return to step 21b.1)IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 1.-OR-o BOTH of the following:
1)RCS pressure-LESS THAN RUPTURED S/G PRESSURE 2)PRZR level-GREATER THAN 5%[30%adverse CNMT]d.Close PRZR PORVs d.IF either PRZR PORV can NOT be closed, THEN close associated block valve.
!n"1 EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 23 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCS Pressure-INCREASING Close block valve for the PRZR PORV 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: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 If SI Flow Should Be Terminated:
a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.Secondary heat sink: o Total feed flow to S/G(s)GREATER THAN 200 GPM AVAILABLE-OR-a.Do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.b.IF neither condition satisfied, THEN do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED'tep 1.o Narrow range level in at least one intact S/G-GREATER THAN 5%[25%adverse CNMT]c.RCS pressure-STABLE OR INCREASING d.PRZR level-GREATER THAN 5%[30%adverse CNMT]c.Do NOT stop SI pumps.Go to ECA-3.1.SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED.Step 1.d.Do NOT stop SI pumps.Return to Step 6.
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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: b.Establish 20 gpm charging line flow~RCP A, V-300A~RCP B.V-3008 2)Ensure HCV-142 open.3)Start one charging pump.
E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 26 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*27 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.PRZR level-GREATER THAN 5%[30%adverse CNMT]a.Manually start SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.b.Control charging flow to 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: E-3 STEAM GENERATOR TUBE RUPl'URE REV: 27 PAGE 27 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check If SI ACCUMs Should Be Isolated: a.Check the following:
o RCS subcooling based on core exit T/Cs-GREATER THAN 0 F USING FIGURE MIN SUBCOOLING o PRZR level-GREATER THAN 5'/o[30%%d adverse CNMT]b.Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves~MOV-841, MCC C position 12F~MOV-865.MCC D position 12C c.Close SI ACCUM discharge valves~MOV-841~MOV-865 a.Manually operate SI pumps as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.d.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A.AOV-834A~ACCUM B.AOV-834B 2)Open HCV-945.


EOP: E-3 STEAM'GENERATOR TUBE RUPTURE REV: 27 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 RUNNING b.Verify AUX BLDG SW isolation valves-AT LEAST ONE SET OPEN a.Manually start pumps as power supply permits (257 kw each).IF less than two SW pumps can be operated, THEN go to Step 36.b.Manually align valves.~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM-EXTINGUISHED c.Dispatch'O to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.
EOP:
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 29 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Check If Normal CVCS Operation Can Be Established a.Verify IA restored: o IA to CNMT (AOV-5392)
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.
-OPEN o IA pressure-GREATER THAN 60 PSIG a.Continue with Step 36.WHEN IA restored, THEN do Steps 30 through 35.b.Verify instrument bus D-ENERGIZED c.CCW pumps-ANY RUNNING d.Charging pump-ANY RUNNING b.Energize MCC B.IF MCC B NOT available.
o  CYCLING OF THE PRZR PORV SHOULD BE MINIMIZED.
THEN perform the following:
o  THE UPPER HEAD REGION MAY VOID DURING RCS DEPRESSURIZATION IF RCPS ARE NOT RUNNING. THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
1)Verify MCC A energized.
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.
2)Place instrument bus D on maintenance supply.c.Perform the following:
o When  using  a PRZR PORV select one with  an  operable block valve.
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.Continue with Step 36.WHEN any charging pump running, THEN do Steps 31 through 35.
22  Depressurize RCS Using PRZR PORV To Minimize Break Flow And  Refill  PRZR:
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 30 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Seal Return Flow Should Be Established:
: a. Verify IA to  CNMT - AVAILABLE        a. Refer to Attachment    N2 PORVS to operate  PORVs.
a.Verify RCP gl seal outlet temperature
: b. PRZR PORVs  - AT LEAST ONE            b. IF  auxiliary spray available, AVAILABLE                                  THEN  return to Step 21b.
-LESS THAN 235 F b.Verify RCP seal outlet valves-OPEN~AOV-270A~AOV-270B a.Go to Step 32.b.Manually open valves as necessary.
IF auxiliary spray can NOT be established, THEN go to ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL. Step 1.
c.Reset both trains of XY relays for RCP seal return isolation valve MOV-313 d.Open RCP seal return isolation valve MOV-313 e.Verify RCP$1 seal leakoff flow-LESS THAN 6.0 GPM d.Perform the following:
This Step continued on the next page.
1)Place MOV-313 switch to OPEN.2)Dispatch AO with key to RMST gate to locally open MOV-313.e.Perform the following:
1)Trip the affected RCP 2)Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve f.Verify RCP tl seal leakoff flow GREATER THAN 0.8 GPM~RCP A.AOV-270A~RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 32.f.Refer to AP-RCP.l, RCP SEAL MALFUNCTION.
Ji tet fOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 31 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Verify PRZR Level-GREATER THAN 13%[40%adverse CNMT]Continue with Step 34.WHEN PRZR level increases to greater than 13%[40%adverse CNMT], THEN do Step 33.33 Establish Normal Letdown: a.Establish charging line flow to REGEN Hx-GREATER THAN 20 GPM b.Place the following switches to CLOSE:~Letdown orifice valves (AOV-200A, AOV-2008, and AOV-202)~Letdown isolation valve AOV-371~Loop B cold leg to REGEN Hx AOV-427 c.Place letdown controllers in MANUAL at 40%open~TCV-130~PCV-135 d.Reset both trains of XY relays for AOV-371 and AOV-427 e.Open AOV-371 and AOV-427 f.Open letdown orifice valves as necessary g.Place TCV-130 in AUTO at 105'F h.Place PCV-135 in AUTO at 250 psig i.Adjust charging pump speed and HCV-142 as necessary IF RCP seal return has been established.
THEN establish excess letdown as follows: o Place excess letdown divert valve, AOV-312, to NORMAL.o Ensure CCW from excess letdown open, (AOV-745).
o Open excess letdown isolation valve AOV-310.o Slowly open HCV-123 to maintain excess letdown temperature less than 195'F and pressure less than 100 psig.o Adjust charging pump speed as necessary.
IF RCP seal return NOT established, THEN consult TSC to determine if excess letdown should be placed in service.
~I\~~
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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:
1)RMW mode selector switch in AUTO 2)RMW control armed-RED LIGHT LIT c.Adjust controls as necessary.
d.Check VCT level: o Level-GREATER THAN 20%-OR-o Level-STABLE OR INCREASING d.Manually increase VCT makeup flow as follows: 1)Ensure BA transfer pumps and RMW pumps running.IF NOT, THEN reset MCC C and MCC D UV lockouts as necessary.
2)Place RMW flow control valve HCV-111 in MANUAL and increase RMW flow.3)Increase boric acid flow as necessary.
A'f~I~'4 (~wc~I~
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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 b.Verify charging pumps aligned to VCT o LCV-112C-OPEN o LCV-112B-CLOSED 2)Continue with Step 36.WHFN VCT level greater than 40%, THEN do Step 35b.b.Manually align valves as necessary.
iV, EOP: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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 LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%[40%ADVERSE CNMT]BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]o Increase charging flow o Depressurize RCS using Step 36b Depressurize RCS using Step 36b o Depressurize RCS using Step 36b o Decrease charging flow o Decrease charging flow Increase charging flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters o Increase charging flow o Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Control pressure using normal PRZR spray.if available, to obtain desired results for Step 36a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).
IF NOT, THEN use one PRZR PORV.
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 35 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 Monitor If CNMT Spray Should Be Stopped: a.CNMT spray pumps-ANY RUNNING b.Verify CNMT pressure-LESS THAN 4 PSIG c.Reset CNMT spray d.Check NaOH tank outlet valves CLOSED~AOV-836A~AOV-836B a.Go to Step 38 b.Continue with Step 38.WHEN CNMT pressure less than 4 psig.THEN do Steps 37c through f.d.Place NaOH tank outlet valve controllers to MANUAL and close valves.e.Stop CNMT spray pumps and place in AUTO f.Close CNMT spray pump discharge valves~MOV-860A~MOV-860B~MOV-860C~MOV-860D


EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 36 of 41 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN a.Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).o AC emergency bus voltage GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)39 Minimize Secondary System Contamination:
~ e ~ & '4 ~ 4 ~ '' ll k "e II I. 'h '
a.Isolate reject from hotwell to CST: o Place hotwell level controller (LC-107)in MANUAL at 50/o a.IF hotwell level increasing.
EOP:
THEN direct RP to sample hotwells for activity.o Verify hotwell level-STABLE b.Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
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)
~i I~-4.'5 k EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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: a.Check CCW to RCPs: 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:
: c. Open one PRZR PORV      until ANY of c. IF auxiliary spray available, the following conditions                  THEN return to step 21b.
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: E-3 TITLE: STEAM GENERATOR TUBE RUPTURE REV: 27 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.
satisfied:
42 Check RCP Status: a.RCPs-AT LEAST ONE RUNNING b.Stop all but one RCP a.Perform the following:
: 1) IF auxiliary spray  can NOT be o PRZR  level   - GREATER THAN 75%         established,  THEN go to
l)Try to start one RCP: a)Ensure conditions for starting an RCP.o Bus llA or llB energized.
[65% adverse   CNMT]                   ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL,
o Refer to Attachment RCP START.')IF RVLIS level (no RCPs)less than 95%.THEN perform the following:
                          -OR-                           Step 1.
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 RCS  pressure  - LESS THAN SATURATION 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.
                          -OR-o   BOTH  of the following:
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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.
: 1) RCS pressure - LESS THAN RUPTURED S/G PRESSURE
43 Check If Source Range Detectors Should Be Energized:
: 2) PRZR    level  - GREATER THAN 5%  [30%  adverse CNMT]
a.Source range channels DEENERGIZED a.Go to Step 43e.b.Check intermediate range flux EITHER CHANNEL LESS THAN 10 10 AMPS b.Perform the following:
: d. Close  PRZR PORVs                    d. IF  either  PRZR PORV can  NOT be closed, THEN close associated block valve.
1)IF neither intermediate range channel is decreasing.
THEN initiate boration.c.Check the following:
o Both intermediate range channels-LESS THAN 10 10 AMPS 2)Continue with Step 44.WHEN flux is LESS THAN 10 10 amps on any operable channel, THEN do Steps 43c through e.c.Continue with Step 44.WHEN either condition met, THEN do Steps 43d and e.-OR-o Greater than 20 minutes since reactor trip d.Verify source range detectors ENERGIZED d.Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).e.Transfer Rk-45 recorder to one source range and one intermediate range channel IF source ranges can NOT be restored.THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 44.
EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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 rod shroud fan-RUNNING 2)Verify one Rx compartment cooling fan-RUNNING 1)Manually start one fan as power supply permits (45 kw)2)Perform the following:
o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)d.Verify Attachment SD-1-COMPLETE EOP: E-3 STEAM GENERATOR TUBE RUPTURE REV 27 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: STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 1 E-3 APPENDIX LIST TITLE 1)RED PATH  
! 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]
: b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves
          ~ 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.
: f. Verify RCP  tl seal GREATER THAN    0.8 leakoff flow  f. Refer to AP-RCP.l,    RCP SEAL GPM              MALFUNCTION.
 
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
: d. Check VCT  level:                    d. Manually increase    VCT makeup flow as  follows:
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).
: a. Check  CCW to  RCPs:
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==
==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  
: 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


E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 PAGE 1 of 1 RED PATH  
REV: 27 E-3                 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH  


==SUMMARY==
==SUMMARY==
a~b.C.d.e.SUBCRXTXCALITY
 
-Nuclear power greater than 5%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]HEAT SINK-Narrow range level in all S/Gs less than 5-:[25%adverse CNMT]AND total feedwater flow less than 200 gpm INTEGRITY-Cold leg temperatures decrease greater than 100'in last 60 minutes AND RCS cold leg temperature less than 285'CONTAINMENT
a ~   SUBCRXTXCALITY Nuclear power   greater than 5%
-CNMT pressure greater than 60 psig E-3 STEAM GENERATOR TUBE RUPTURE REV: 27 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.
: b. CORE COOLING   Core exit T/Cs greater than 1200'
OR 2.o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMT].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.3.4.5.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.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).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.}}
                                        -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.}}

Revision as of 17:47, 29 October 2019

Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index
ML17265A515
Person / Time
Site: Ginna Constellation icon.png
Issue date: 01/14/1999
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17265A517 List:
References
PROC-990114, NUDOCS 9901220067
Download: ML17265A515 (159)
v • d • e


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
b. Sump pump activity increases in containment, the AUX BLDG@ or INT BLDG@ 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:

a. Check Sump A indication a. IF the SW leak is NOT in the CNMT, THEN go to Step 6.

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
c. Direct RP to establish conditions for CNMT entry

V

& 4 r-

EOP: TITLE:

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.
b. Intact SW loop header pressure b. Dispatch AO to perform the GREATER THAN 45 PSIG following:
1) Split A and B SW headers:

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)
2) ATTACHMENT SW LOADS IN CNMT (ATT-2.3)

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.

b. SI sequencing - BOTH TRAINS b. Manually actuate SI and CI.

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:
1) Ensure SI pump suction supply open from RWST.
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

  • 7 Verify CNMT Spray Not Verify CNMT spray initiated.

Required:

IF CNMT spray NOT initiated, THEN o Annunciator A-27. CNMT SPRAY- perform the following:

EXTINGUISHED

a. Depress manual CNMT spray o CNMT pressure - LESS THAN 28 PSIG pushbuttons (2 of 2).
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.
b. Check CNMT pressure - LESS THAN b ~ Ensure BOTH MSIVs closed and go 18 PSIG 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:

a. MFW pumps - TRIPPED a. Manually close MFW pump discharge valves and trip MFW pumps.
b. MFW flow control valves - CLOSED b. Place A and B S/G MFW regulating valve and bypass valve

~ 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:

a. MDAFW pumps - RUNNING a. Manually start MDAFW pumps.
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

a. Ensure one SW pump running on each energized screenhouse AC emergency bus:

~ 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)
b. AFW flow from each MDAFW pump-LESS THAN 230 GPM

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:
a. RCP status - ANY RCP RUNNING a. Go to Step 23

'.

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

b. CNMT pressure - LESS THAN 0.5 PSIG
c. CNMT sump B level - LESS THAN 8 INCHES
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

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 27.

o Pressure - GREATER THAN 1625 PSIG o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN O' Step 27.

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.
e. Go to ES-l.l. SI TERMINATION.

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.

e. Reset both trains of XY relays for IA to CNMT AOV-5392
f. Verify IA to CNMT AOV-5392 - OPEN

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:
1) Pressure - GREATER THAN 1) Go to E-l, LOSS OF REACTOR OR 250 PSIG SECONDARY COOLANT, Step 1.
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
b. RCS pressure minus maximum S/G pressure LESS THAN 175 PSIG

[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.
g. ECA-1.2, LOCA OUTSIDE CONTAINMENT, when a LOCA outside containment is isolated.
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:

a. RCP status - ANY RCP RUNNING a. Go to Step 2.
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

b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

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.

e. Reset both trains of XY relays for IA to CNMT AOV-5392
f. Verify IA to CNMT AOV-5392 - OPEN

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

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 13.

o Pressure - GREATER THAN 1625 psig [1825 psig adverse CNMT]

o Pressure - STABLE OR INCREASING

b. RCS subcooling based on core b. Do NOT stop SI pumps. Go to exit T/Cs - GREATER THAN O' Step 13.

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.
e. Go to ES-l.l, SI TERMINATION, Step l.

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

2) RCS pressure - STABLE OR 2) Go to Step 15.

INCREASING

b. Stop RHR pumps and place in AUTO 15 Check RCS And S/G Pressures
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.
c. Check RCS pressure - STABLE OR c. Return to Step l.

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:

a. Check RHR and CCW systems: a. Restore power to at least one train of emergency AC busses.
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

2) RHR pumps and valves OPERABLE
3) CCW pumps and Hx - OPERABLE
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 boron

~ RCS activity

~ CNMT hydrogen

~ CNMT sump boron

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.
b. Go to ES-1.2. POST LOCA COOLDOWN AND DEPRESSURIZATION. Step 1

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

2) Verify total SW flow to CCW 2) Perform the following:

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.

b. Manually open CCW valves to RHR b. Dispatch AO to locally open Hxs valves.

~ 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

1. RCP TRIP CRITERIA IF BOTH conditions listed below occur, THEN trip both RCPs:
a. Sl pumps -AT LEAST TWO RUNNING
b. RCS pressure minus maximum S/G pressure - LESS THAN 175 PSIG [400 psig adverse CNMT]

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:
a. RCP status - ANY RCP RUNNING a. Go to Step 2.
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.

b. Close MDAFW pump discharge valve b. Dispatch AO to locally close to ruptured S/G valve.

~ 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

b. PORVs - CLOSED b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.

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.

e. Reset both trains of XY relays for IA to CNMT AOV-5392 Verify IA to CNMT AOV-5392 - OPEN(

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:

a. Verify IA to CNMT - AVAILABLE a. Refer to Attachment N2 PORVS to operate PORVs.
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]
d. Close PRZR PORVs d. IF either PRZR PORV can NOT be closed, THEN close associated block valve.

! 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]

b. Dispatch AO with locked valve key to locally close breakers for SI ACCUM discharge valves

~ 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.

f. Verify RCP tl seal GREATER THAN 0.8 leakoff flow f. Refer to AP-RCP.l, RCP SEAL GPM MALFUNCTION.

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
d. Check VCT level: d. Manually increase VCT makeup flow as follows:

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).

a. Check CCW to RCPs:

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.
Retrieved from "https://kanterella.com/w/index.php?title=ML17265A515&oldid=1996793"