ML17263A197: 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)
 
(6 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 03/24/1993
| issue date = 03/24/1993
| title = Rev 11 to EOP E-1, Loss of Reactor or Secondary Coolant.
| title = Rev 11 to EOP E-1, Loss of Reactor or Secondary Coolant.
| author name = MARLOW T A
| author name = Marlow T
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:EOP:
E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV  ll PAGE 1 of 16 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE l v>>
PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY  1.0 REVIEWED BY:
  ,9304080163 930330 05000244
"." PDR      ADOCK P  .."
PDR
 
P 1
g  'f
 
EOP:
E-1 TLTLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV  ll PAGE 2  of 16 A. PURPOSE    This  procedure provides actions to recover from a loss of reactor or secondary coolant.
B. ENTRY CONDITIONS/SYMPTOMS
: l. ENTRY CONDITIONS  This        procedure  is entered  from:
: a. E-O, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV  is  stuck open and  its  block valve can not be closed.
: b. E-O, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure,      or high containment recirculation    sump  level.
c ~                                    I E 0 g REACTOR TRI P OR SAFETY NJECTION g ECA 2 1 g UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS    pressure  is less than the shutoff    head pressure of the  RHR pumps  or is decreasing.
: d. ES-1.1, SI TERMINATION, and FR-I.2, RESPONSE TO          LOW PRESSURIZER LEVEL,      if SI has to be reinitiated.
: e. E-2,  FAULTED STEAM GENERATOR ISOLATION,        after identification    and  isolation of  a  faulted  S/G.
f    ECA 0 ~ 2 g LOSS OF ALL AC POWER RECOVERY WITH S      I REQUIRED I after  normal  injection  mode  conditions are established.
: 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    r established.
: i. FR-H.1,    RESPONSE pressure is less than TO LOSS OF SECONDARY HEAT all SINK,  if non-faulted S/G(s) pressure.
RCS
: j. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs  are close.
 
EOP:            TITLE:
REV: 11 E-1              'LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3  of 16 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%,      THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING      ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP 1.
NOTE '      FOLDOUT    page should be open AND monitored  periodically.
o  Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.),
o  Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0,    GINNA STATION EVENT EVALUATION AND CLASSIFICATION).,
o  Adverse    CNMT values should be used whenever CNMT pressure is greater than    4 psig or CNMT radiation is greater than 10+    R/hr.
* 1 Monitor      RCP    Trip Criteria:
: 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 I E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV:  ll PAGE 4  of 16 STEP        ACTION/EXPECTED RESPONSE                ~
RESPONSE NOT OBTAINED 2  Check  If S/G Is Intact:
Secondary Side            IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized,        THEN o  Pressure    in both  S/Gs - STABLE        verify faulted    S/G  isolated unless OR INCREASING                              needed for RCS    cooldown:
o  Pressure    in both  S/Gs - GREATER      ~  Steamlines THAN 100 PSIG                              ~  Feedlines IF  NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step        l.
CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS  WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
NOTE:    TDAFW pump    flow control valves  fail open  on loss  of IA.
* 3 Monitor Intact S/G Levels:
: a. Narrow range level -      GREATER          a. Maintain    total  feed flow greater THAN 58 [258 adverse      CNMT]                than 200  gpm  until  narrow range level greater than 58 [258 adverse CNMT] in at least one S/G.
: b. Control feed flow to maintain              b. IF narrow range level in any S/G narrow range level between 178                  continues to increase in an
[258 adverse      CNMT] and 508                uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE,  Step  l.
 
W 1
N
 
EOP!
REV    11 E-1            LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5    of 16 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 4  Check Secondary Radiation                IF steamline radiation monitors NOT Levels    NORMAL                        available, THEN dispatch AO to locally check steamline radiation.
o  Steamline radiation monitor (R-31 and R-32)                        IF abnormal radiation levels detected in any S/G,    THEN go to o  Request  HP sample S/Gs  for          E-3,  STEAM GENERATOR TUBE RUPTURE, activity                              Step  l.
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
* 5 Monitor      PRZR PORV    Status:
: a. Power to  PORV  block valves-          a. Restore power to block valves AVAILABLE                                  unless block valve was closed to isolate  an open PORV:
                                                      ~ MOV-515,  MCC C  position 6C
                                                      ~ MOV-516,  MCC D  position 6C
: 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 C  position  6C
                                                      ~ MOV-516,  MCC D  position  6C
: c. Block valves -  AT LEAST ONE OPEN    c. Open one block valve unless      it was closed to isolate an open PORV.
 
K EOP!
E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV  ll PAGE 6  of 16
  ,STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED CAUTION IF OFFSITE    POWER  IS LOST AFTER SI RESET,  THEN SELECTED SW PUMPS AND ONE CCW PUMP  WILL AUTO START    ON EMERGENCY  D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
6  Reset    SZ 7  Reset CI:
: a. Depress CI reset pushbutton b., Verify annunciator A-26,    CNMT        b. Perform the following:
ISOLATION - EXTINGUISHED
: 1) Reset SI.
: 2) Depress CI reset pushbutton.
8 .Verify Adequate        SW  Flow:
: a. Check at least two    SW  pumps          a. Manually  start  SW pumps as power RUNNING                                    supply permits  (258 kw each).
IF less than two SW pumps running, THEN perform the following:
: 1) Ensure  SW  isolation.
: 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
: 3)  Go to Step 10.
: b. Dispatch    AO to establish normal shutdown alignment (Refer to Attachment SD-1)
 
EOP I REV: 11 E-1            LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7    of  16 STEP      ACTION/EXPECTED RESPONSE              RESPONSE    NOT OBTAINED 9  Establish IA to      CNMT:
: a. Verify non-safeguards    busses        a. Perform the      following:
energized from  offsite  power
: 1) Close non-safeguards      bus  tie o  Bus 13 normal  feed -  CLOSED              breakers:
                        -OR-                                ~ Bus 13  to Bus 14  tie
                                                          '  Bus 15  to Bus 16  tie o  Bus 15 normal  feed -  CLOSED
: 2)  Verify adequate    emergency D/G capacity to run    air compressors    (75 kw each).
IF  NOT, THEN  evaluate  if CNMT fans should be stopped    'ECIRC (Refer to Attachment CNMT RECIRC FANS).
: 3)  WHEN  bus 15 restored, THEN reset control room lighting.
b, Verify turbine building    SW          b. Manually align valves.
isolation valves - OPEN
            ~ MOV-4613 and MOV-4670
            ~ MOV-4614 and MOV-4664
: c. Verify at least two  air              c. Manually      start air compressors compressors  - RUNNING                    as power supply      permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
: d. Check IA supply:                      d. Perform the      following:
o  Pressure  - GREATER THAN                1) Continue attempts to restore 60 PSIG                                      IA (Refer to AP-IA.1,      LOSS OF INSTRUMENT AIR).
o  Pressure  - STABLE  OR INCREASING                              2) Continue    with Step 10. WHEN IA restored,    THEN do  Steps 9e and  f.
: e. Reset both  trains of  XY  relays for IA to CNMT AOV-5392
: f. Verify IA to CNMT AOV-5392      - OPEN
 
f)
REV: 11 E-l.            LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8  of 16 STEP      ACTION/EXPECTED RESPONSE        RESPONSE NOT OBTAINED 10  Check Normal Power      Available    Verify adequate emergency D/G To Charging Pumps:                    capacity to run charging  pumps (75 kw each).
o  Bus 14 normal  feed breaker-
      'CLOSED                            IF NOT, THEN evaluate  if CNMT RECIRC fans can be stopped (Refer o  Bus 16 normal feed  breaker-      to Attachment CNMT RECIRC FANS)..
CLOSED
 
EOP:
REV  11 E-1            LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9  of 16 STEP      ACTION/EXPECTED RESPONSE        RESPONSE  NOT OBTAINED ll Check    If Charging Been Established:
Flow Has
: a. Charging pumps -  ANY RUNNING    a. Perform the    following:
: 1) IF  CCW  flow is lost to any
                                                    .RCP  thermal barrier OR any RCP  ¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal in)ection needle valve(s) to affected  RCP:
                                                    ~  V-300A  for  RCP A
                                                    ~  V-300B  for  RCP B
: 2) Ensure HCV-142 open, demand at  0%.
: b. Charging  pump suction aligned to b. Manually align valves as RWST'                                necessary.
LCV-112B - OPEN                    IF  LCV-112B can NOT be opened, THEN  perform the following:
o  LCV-112C - CLOSED
: 1)  Verify charging    pump A NOT running and place      in PULL STOP.
: 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging    pump  room).
: 3)  WHEN  V-358 open, THEN    direct AO  to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
: c. Start charging pumps as necessary and adjust charging flow to restore  PRZR  level
 
lp ', ~
EOP:            T1TLE:
REV    11 E-1                LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10    of 16 STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED 12  Check  If Terminated:
SI Should      Be
: a. RCS  pressure:                      a. Do NOT  stop SI pumps. Go to Step 14.
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 14.
USING FIGURE MIN SUBCOOLING
: c. Secondary heat sink:                c. IF neither condition satisfied, THEN do NOT stop SI pumps.        Go o  Total feed flow to intact            to Step 14.
S/Gs - GREATER THAN 200      GPM
                          -OR-o  Narrow range    level in at least    one  intact S/G-GREATER THAN 5%    [25% adverse CNMT]
: d. PRZR  level  - GREATER THAN  5%    d;  Do NOT  stop SI  pumps'erform
[30%  adverse    CNMT]                  the following:
: 1)  IF normal    PRZR spray available,    THEN try to stabilize    RCS pressure with PRZR  spray.
: 2)  Go to Step 14.
 
EOP s E-1              LOSS OF REACTOR OR SECONDARY COOLANT REV:  ll PAGE 11    of 16 STEP      ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED 13  Go To    ES-1.1, SI TERMINATION/
Step  1
*14    Monitor Be If CNMT Spray Stopped:
Should
: a. CNMT  spray pumps -  RUNNING      a. Go  to Step 15.
: b. Check the following:              b. Continue with Step 15. WHEN BOTH  conditions satisfied,  THEN o  CNMT  pressure  - LESS THAN        do 'Steps  14c through f.
4 PSIG o  Sodium hydroxide tank    level-LESS THAN 55%
: c. Reset  CNMT  spray
: d. Check  NaOH  tank outlet valves-  d; Place    NaOH tank outlet valve CLOSED                                controllers to  MANUAL and close valves.
            ~ AOV-836A
            ~ AOV-836B
: e. Stop  CNMT  spray pumps and place in AUTO
: f. Close  CNMT  spray pump discharge valves
            ~ MOV-860A
            ~ MOV-860B
            ~ MOV-860C
            ~ MOV~860D
 
C EOP:              TITLE.
REV: 11 E-1              LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12  of 16 STEP        ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED
                                              ,  CAUTION o  IF OFFSITE    POWER  IS LOST AFTER SI RESET,    THEN SELECTED SW PUMPS AND ONE CCW PUMP    WILL AUTO START  ON EMERGENCY    D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
o  RCS PRESSURE    SHOULD BE MONITORED.      IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR          PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
*15    Monitor
      .Be Stopped:
If RHR    Pumps  Should
: a. Check    RCS  pressure:
: 1) Pressure      - GREATER THAN                  1)  Go to Step 17.
250  psig [465 psig adverse CNMT]
: 2)  RCS  pressure  - STABLE OR                2)  Go to Step 16.
              ~ INCREASING
: b. Stop  RHR pumps    and place  in    AUTO 16  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 100 PSIG                            pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.
: c. Check    RCS  pressure  - STABLE OR          c. Return to Step  l.
DECREASING
 
EOP:              TLTLE:
REV: 11 E-1                LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13    of 16 STEP        ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED 17  Check    If Emergency Should Be Stopped:
D/Gs
: a. Verify AC    emergency busses        a. Perform the following:
energized by    offsite power:
: 1) Close non-safeguards      bus  tie o  Emergency D/G    output breakers        breakers as necessary:
OPEN
                                                          ~ Bus 13  to  Bus 14  tie o  AC emergency  bus voltage                ~ Bus 15  to  Bus 16  tie GREATER THAN  420 VOLTS
: 2) Place the    following pumps in o  AC  emergency bus normal feed            PULL STOP' breakers -  CLOSED EH pumps
                                                          ~ Turning gear oil pump
                                                          ~ HP seal oil backup pump
: 3) Ensure condenser      steam dump mode  control in  MANUAL.
: 4) Restore power to MCCs:
                                                          ~ A  from  Bus  13
                                                          ~ B  from  Bus  15
                                                          ~ E from  Bus  15 F from  Bus  15
: 5)  WHEN  bus 15 restored, THEN reset control room lighting breaker.
: 6) Refer to Attachment SI/UV        for other equipment lost with loss of offsite power.
: 7) Try to    restore offsite    power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
: b. Stop any unloaded emergency D/G
          ~
and place in standby (Refer to Attachment D/G STOP)
 
EOP REV'1 E-1            LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14  of 16 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 18  Verify CNMT    Sump Recirculation Capability:
: a. Check  RHR  system:                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    1.
ENERGIZED o  MCC C  - ENERGIZED o  Bus 16 and bus  17-ENERGIZED o  MCC D  - ENERGIZED
: 2)  RHR pumps  and valves 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        be evaluated and    isolated if key may'be required)                  necessary.
 
II REV    11 E-1              LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15  of 16 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 19  Evaluate Plant Status:
: a. Check  auxiliary building          a. Notify HP  and  refer to radiation - NORMAL                      appropriate  AR-RMS  procedure.
        ~  Plant vent iodine (R-10B)            IF the cause is a loss of RCS
        ~  Plant vent particulate (R-13)        inventory outside CNMT, THEN go
        ~  Plant vent gas (R-14)                to .ECA-1.2, LOCA OUTSIDE CONTAINMENT,    Step 1.
        ~ CCW  liquid monitor (R-17)
        ~ LTDN  line monitor (R-9)
        ~ CHG  pump room  (R-4)
: b. Direct  HP  to obtain following samples:
        ~ RCS  boron
        ~ RCS  activity
        ~ CNMT  hydrogen
        ~ CNMT sump boron
        ~ BASTs,boron
: c. Verify adequate  Rx head  cooling:
: 1) Check IA to  CNMT -  AVAILABLE      1)  Go  to Step 20.
: 2)  Verify at least  one  control      2) Manually start one fan as rod shroud fan  - RUNNING              power supply permits (45 kw)
: 3) Verify,one  Rx compartment          3) Perform the    following:
cooling fan  - RUNNING o  Dispatch  AO to reset UV relays at  MCC C and MCC D o  Manually start one fan as power supply permits
                                                      '(23 kw)
 
EOP:
REV    11 E-1              LOSS OF REACTOR OR SECONDARY COOLANT PAGE 16  of 16 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED 20  Check  If  RCS  Cooldown And Depressurization Is Required:
: a. RCS  pressure  - GREATER THAN            a. IF  RHR pump flow greater than 250  psig [465 psig adverse  CNMT]          475 gpm, THEN go to Step 21,
: b. Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1 21  Check If Transfer To Cold          Leg Recirculation Is Required:
: a. RWST  level  - LESS THAN 28%            a. Return to Step 18.
: b. Go to ES-1;3, TRANSFER TO COLD LEG RECIRCULATION, Step 1
                                              -END-
 
I EOP:
REV: 11 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1  of 1 E-1 APPENDIX LIST TITIZ                          PAGES
: 1) RED PATH
 
==SUMMARY==
: 2) FIGURE MIN SUBCOOLING
: 3) ATTACHMENT CNMT RECIRC
: 4) ATTACHMENT D/G STOP
: 5) ATTACHMENT SD-1
: 6) ATTACHMENT SI/UV
: 7) ATTACHMENT MIN SW
: 8) ATTACHMENT AUX BLDG SW
: 9) ATTACHMENT SW LOADS IN CNMT
: 10) FOLDOUT
 
EOP s E-1 T1TLE0 LOSS OF REACTOR OR SECONDARY COOLANT REV  ll PAGE 1 of 1 RED PATH
 
==SUMMARY==
: a. SUBCRITICALITY - Nuclear power      greater than 54
: b. CORE COOLING      Core exit T/Cs greater than 1200'F
                                              -OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than'34 [464 adverse  CNMT]
: c. HEAT SINK  Narrow    range  level in all  S/Gs  less than 54
[254 adverse  CNMT] AND  total feedwater flow less than  200 gpm
: d. INTEGRITY  Cold    leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F
: e. CONTAINMENT  CNMT    pressure greater than  60  psig
 
EOP.
E-1 TITLE:
LOSS OF REACTOR OR SECONDARY COOLANT REV  ll PAGE 1  of  1 FIGURE MIN SUBCOOLING NOTE:      Subcooling Margin = Saturation Temperature From Figure Below  [-] Core Exit  T/C  Indication RC S  PRESSURE  (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300                            REGION 1200 1100 1000 900 800 700                                                                  INADEQUATE SUBCOOLING 600                                                                    REGION ADVERS E CNMT 500 400 300 200                                            NORMAL CNMT                  TEMPERATURE INCREMENTS 10' 100 0
200        250      300      350      400      450    500  550      600    650    700 CORE  EXIT SATURATION TEMPERATURE ('F)
 
EOP:
REV  11 E-1          LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1  of  1 FOLDOUT PAGE
: 1. SI REINITIATION CRITERIA IF EITHER  condition listed below occurs,    THEN  manually operate SI pumps as necessary:
o RCS subcooling based on core    exit  T/Cs  - LESS THAN  O'F USING FIGURE MIN SUBCOOLING OR-o  PRZR  level  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%
[30% adverse CNMT]
2 ~  SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:
: a. RCS subcooling based on core exit T/Cs  GREATER THAN 0 F        USING FIGURE MIN SUBCOOLING
: b. Total feed flow to intact S/Gs    GREATER THAN 200 GPM OR-Narrow range level in  at least one  intact  S/G  GREATER THAN 5% [25% adverse CNMT]
: c. RCS  pressure:
o GREATER THAN 1625 PSIG [1825  psig adverse    CNMT]
o STABLE OR INCREASING
: d. PRZR  level  GREATER THAN 5% [30%  adverse  CNMT]
: 3. SECONDARY INTEGRITY  CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
: 4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST  level decreases to less than  28%, THEN go    to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION,    Step .l.
: 5. AFW SUPPLY SWITCHOVER CRITERION IF CST 'evel decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).
: 6. E-3 TRANSITION CRITERIA IF any S/G 'level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.
 
EOP:        TITLE:
REV: 15 E-3                STEAM GENERATOR TUBE RUPTURE PAGE 1  of 38 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW 1
PORC REVIEW DATE k'LANT SUPERINTENDENT EFFECTIV      DATE CATEGORY 1.0 REVIEWED BY:
 
0 f IC K
c A aJ
*t pP,
 
EOP:            JITLE:
REV: 15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 2  of 38 A. PURPOSE      This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a  fault in the other        S/G.
B. ENTRY CONDITIONS/SYMPTOMS
: l. ENTRY CONDITIONS  This        procedure  is entered from:
: a. E-O, REACTOR TRIP      OR SAFETY  INJECTION, when condenser    air ejector radiation or  blowdown radiation is abnormal, or b  ~  E 0 g REACTOR TRIP OR SAFETY INJECTION/
E 1 / LOSS OF REACTOR OR SECONDARY COOLANT g E-2,  FAULTED STEAM GENERATOR ISOLATION, and FR  HE 3    RESPONSE TO STEAM GENERATOR HIGH LEVELS when secondary      radiation is abnormal, or
: c. E-O, REACTOR TRIP      OR SAFETY INJECTION/
E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g ES 1 ~ 2 g POST LOCA COOLDOWN AND DEPRESSURI ZATIONg ECA 3 ~ 3 g SGTR WITHOUT PRESSURI ZER PRESSURE CONTROLS when an intact S/G narrow range      level increases in an uncontrolled manner.
d      ECA 3 3~  ~  SGTR WITHOUT PRESSURI ZER PRESSURE  CONTROL/
when  pressurizer pressure control is restored.
: e. E-1 series FOLDOUT page 'whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.
 
  ~A
$  r a.a
 
EOP:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 3  of 38 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED NOTE:  o  FOLDOUT page  should be open AND monitored periodically.
o  Critical Safety Function Status Trees    should be monitored (Refer to Appendix 1 for Red Path Summary).
o  Personnel should be available  for sampling during this procedure.
o  Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o  Adverse  CNMT values should be used whenever CNMT pressure is
            , greater than  4 psig or CNMT radiation is greater than 10+    R/hr.
* 1  Monitor    RCP  Trip Criteria:
: 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    CNMTj
: d. Stop both    RCPs
 
\
EOP:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 4  of 38 STEP      ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED 2  Identify    Ruptured S/G(s):            Continue with Steps 6 through 11.
WHEN  ruptured S/G(s) identified, o  Unexpected increase in    either    THEN do Steps 3, 4 and 5.
S/G narrow range level
                      -OR-o  High radiation    indication on main steamline    radiation monitor
          ~  R-31 for  S/G A
          ~  R-32 for  S/G B
                      -OR-o  AO  reports local indication of high steamline radiation
                      -OR-o  RP  reports high radiation from S/G  activity  sample
 
4 WJ
 
EOP:              TITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 5    of 38 STEP        ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED
  ************                x **** *% *******************
x CAUTION o  IF THE TDAFW PUMP .IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
o  AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.
3  Isolate      Flow From Ruptured S/G  (s):
: a. Adjust ruptured S/G    ARV controller to'050 psig in    AUTO
: b. Check ruptured S/G    ARV - CLOSED      b. WHEN  ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed. IF NOT closed, THEN place controller in MANUAL and close S/G ARV.
IF  S/G ARV can NOT be  closed, THEN  dispatch  AO to *locally isolate.
: c. Close ruptured S/G TDAFW pump            c. IF at least one MDAFW pump steam supply valve and place in            running, THEN dispatch AO with PULL STOP                                  locked valve key to locally isolate steam from ruptured S/G
            ~  S/G A, MOV-3505A                        to  TDAFW pump.
            ~  S/G B, MOV-3504A
                                                        ~  S/G A, V-3505
                                                        ~  S/G B, V-3504
: d. Verify ruptured    S/G blowdown          d. Place S/G blowdown and sample valve    - CLOSED                          valve isolation switch to      CLOSE.
            ~  S/G A, AOV-5738                          IF blowdown can  NOT be  isolated
            ~  S/G B, AOV-5737                        manually,  THEN  dispatch  AO  to locally isolate blowdown..
                                                        ~  S/G A, V-5701
                                                        ~  S/G B, V-5702
 
a1 IllI il't U
 
EOP:              TITLE:
REV    15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 6    of 38 STEP        ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED 4  Complete Ruptured S/G Isolation:
: a. Close ruptured S/G MSIV-            a. Perform the following:
RUPTURED S/G MSIV CLOSED
: 1) Close  intact S/G MSIV.
: 2) Place  intact S/G ARV controller at 1005 psig in AUTO.
: 3) Place condenser  steam dump mode selector  switch to MANUAL.
: 4) Adjust condenser    steam dump controller to  1050  psig in AUTO.
: 5) Adjust reheat steam supply controller  cam to close reheat steam supply valves.
: 6) Ensure  turbine stop valves CLOSED.
: 7) Dispatch  AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).
IF the ruptured  S/G can NOT be isolated from the intact    S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step  1
: b. Dispatch    AO to complete ruptured S/G  isolation (Refer to Attachment  RUPTURED S/G part A)
 
L~
Qt J>;
 
EOP:            TITLE:
REV    15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 7    of 38 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE  NOT OBTAINED
  **********              x  * ***
a        x x x x % *x x****************
CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.
5  Check Ruptured S/G Level:
: a. Narrow range      level  - GREATER        a. IF ruptured S/G NOT faulted, THAN 5%    [25%  adverse    CNMT)              THEN perform the following:
l)  Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT).
: 2) Continue    with Step 6. WHEN ruptured  S/G level greater than  5%  [25% adverse CNMT],
THEN do  Steps 5b through e.
: b. Close  MDAFW pump    discharge valv'e      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 valve valve to ruptured      S/G                    key to locally close TDAFW pump manual feedwater    isolation valve
          ~  S/G A, AOV-4297                              to ruptured S/G.
          ~  S/G B, AOV-4298
                                                          ~  S/G A, V-4005
                                                          ~  S/G B, V-4006
: e. Verify MDAFW    pump  crosstie            e. Manually close valves.
valves  - CLOSED
          ~  MOV-4000A
          ~  MOV-4000B
 
U~W ~p*~ga t,
r.
g'1
 
EOP:            ijiLE:
REV    15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 8    of 38 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED
  **********              x ******* *******************
x    %
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 6B).
  **************                    P ***  x 0  x *0  ***x **************
* 6  Monitor    PRZR PORVs And      Block Valves:
: a. Power to    PORV  block valves          a. Restore power to block valves AVAILABLE                                    unless block valve was closed to isolate  an open PORV:
                                                        ~ MOV-515,  MCC C position  6C
                                                        ~ MOV-516,  MCC D position  6C
: 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.
 
P'>
fg
 
EOP:              TITLE:
REV: 15 E-3                        STEAM GENERATOR TUBE RUPTURE PAGE 9  of 38 STEP        ACTION/EXPECTED RESPONSE                    RESPONSE  NOT OBTAINED 7  Check    If S/G Is Intact:
Secondary Side            IF any S/G pressure decreasing in an  uncontrolled manner OR completely depressurized, THEN o  Pressure    in both  S/Gs - STABLE        verify faulted    S/G  isolated unless OR INCREASING                              needed for RCS    cooldown:
o  Pressure    in both  S/Gs - GREATER        ~  Steamlines THAN 100 PSIG                                ~  Feedlines IF faulted S/G NOT isolated, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
  **********                  x% ** x%    x x x x  ** x *****************
CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS  WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
  ********          x    4 *  %  x
* x **x**% ******************
NOTE:    TDAFW pump      flow control valves    fail open  on loss  of IA.
* 8  Monitor Intact          S/G  Level:
: a. Narrow range      level  - GREATER          a. Maintain    total feed flow greater THAN 5%    [25%  adverse  CNMT)                than 200  gpm  until  narrow range level greater than 5% [25%
adverse CNMT) in at least one S/G.
: b. Control feed flow to maintain                b. IF narrow range level in, the narrow range level between 17%                    intact S/G continues to increase
[25% adverse CNMT) and 50%                        in an  uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step    l.
 
%tk Cg gt
 
EOP:              TITLE:
REV: 15 E-3                        STEAM GENERATOR TUBE RUPTURE PAGE 10  of 38 STEP          ACTION/EXPECTED RESPONSE                    RESPONSE  NOT OBTAINED
  ********              x*  x  ~  *% x '.
* x x
* a CAUTION
                                                        *x  x**xx***x *********
IF OFFSITE    POWER IS LOST AFTER SI RESET, THEN, SELECTED SW PUMPS AND ONE CCW PUMP  WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
  ********** **              x x x      x x
* x  ***x *****************
9  Reset SI 10    Reset CI:
: a. Depress CI reset pushbutton
: b. Verify annunciator A-26,      CNMT          b. Perform the following:
ISOLATION - EXTINGUISHED
: 1) Reset SI.
: 2) Depress  CI reset pushbutton.
  **************                      x x  **  x x x CAUTION RCS  PRESSURE    SHOULD BE MONITORED.      IF  RCS PRESSURE  DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT), THEN THE RHR              PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
  **********%                  *****xx**x******************
11  Check Stopped:
If RHR      Pumps    Should  Be
: a. Check    RCS  pressure:                      a. Go  to Step 12.
o  Pressure    - GREATER THAN 250  psig [465 psig adverse CNMTj o  Pressure    - STABLE OR INCREASING
: b. Stop    RHR pumps    and place both    in AUTO
 
fA
~m f
+J g
~ 'k
 
EOP:            TITLE:
REV    15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 11    of 38 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE  NOT OBTAINED NOTE:    If ruptured    S/G needed  for cooldown, isolation is not necessary.
12  Verify Ruptured        S/G  Isolated:
: a. Check ruptured MSIV      - CLOSED          a. IF only  intact  S/G MSIV can be closed,  THEN  ensure  air ejector/gland  steam supply and flange heating steam isolated.
(Refer to  ATTACHMENT RUPTURED S/G,  part B).
IF neither S/G MSIV can be closed THEN go to ECA-3.1,    SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step  1
: b. Ruptured S/G pressure      - GREATER      b. Go to ECA-3.1, SGTR WITH LOSS OF THAN 300 PSIG                                  REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
13  Establish Condenser Steam Dump Pressure Control:
: a. Verify condenser available:                a. Adjust S/G  ARV controllers to maintain intact S/G pressure in o  Intact    S/G MSIV - OPEN                  AUTO and go to Step 14.
o  Annunciator G-15,      STEAM DUMP ARMED - LIT
: b. Adjust condenser      steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
: c. Place steam dump mode selector switch to MANUAL
 
    ~ s
  'I
~l I
c
~i~
g V
W
 
EOP:            TITLE:
REV  15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 12  of 38 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED NOTE:    Following    initiation of controlled cooldown    or depressurization,    RCP trip criteria is no longer applicable.
14  Initiate      RCS  Cooldown:
: a. Determine required core exit temperature from below table RUPTURED        REQUIRED CORE EXIT SG  PRESSURE        TEMPERATURE ('F) 1100  PSIG      525  [505  adverse  CNMT) 1000  PSIG      510  [490  adverse  CNMT) 900 PSIG      500  [475  adverse  CNMT]
800 PSIG      485  [460  adverse  CNMT) 700 PSIG      465  [440  adverse  CNMT) 600 PSIG      450  [420  adverse  CNMT) 500 PSIG      425  [395  adverse  CNMT]
400 PSIG      405  [370  adverse  CNMT) 300 PSIG      375  [330  adverse  CNMT)
: b. Initiate    dumping steam to              b. Manually or    locally initiate condenser    from  intact  S/G at            steam dump from    intact S/G at maximum  rate                                maximum  rate using    S/G ARV.
IF  no  intact  S/G  available,  THEN perform the following:
o  Use  faulted  S/G.
                                                                      -OR-o  IF both S/Gs ruptured, THEN go  to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step  1
: c. Core  exit  T/Cs - LESS THAN            c. Continue with Step 15. WHEN REQUIRED TEMPERATURE                          core exit T/Cs less than required,  THEN do  Step 14d.
: d. Stop  RCS  cooldown and maintain core  exit  T/Cs less than required temperature
 
+k
~ f
 
EOP:          TtTLE:
REV    15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 13      of 38 STEP      ACTION/EXPECTED RESPONSE        RESPONSE    NOT OBTAINED
*15  Monitor    All AC  Busses            Perform the following:
BUSSES  ENERGIZED BY OFFSITE POWER                                a. IF any    AC emergency bus normal feed breaker open, THEN ensure o  Normal feed breakers to  all 480      associated D/G breaker closed.
volt busses - CLOSED
: b. Perform the following as o  480 volt bus voltage  - GREATER      necessary:
THAN 420 VOLTS
: 1) Close non-safeguards        bus  tie o  Emergency D/G output breakers            breakers:
OPEN
                                                    ~  Bus 13    to  Bus 14  tie
                                                    ~  Bus 15    to  Bus 16  tie
: 2) Place the      following    pumps  in PULL STOP:
                                                    ~  EH  pumps
                                                    ~  Turning gear oil pump
                                                    ~  HP seal oil backup pump
: 3) Restore power to MCCs.
                                                    ~  A  from  Bus  13
                                                  ~  B  from  Bus  15
                                                    ~  E  from  Bus  15
                                                  ~  F  from  Bus  15
: 4)  Start    CNMT RECIRC    fans as necessary.
: 5) WHEN    bus 15 restored, THEN reset control room lighting.
: c. Try to restore        offsite  power to all    AC busses    (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
 
pffft'Illp%
~I 4,
r l    ~
 
EOP:
REV'5 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 14  of 38 STEP      ACTION/EXPECTED RESPONSE        RESPONSE  NOT OBTAINED 16  Verify Adequate      SW  Flow:
: a. Check  at least two SW  pumps      a. Manually    start SW  pumps as power RUNNING                                supply permits (258 kw each).
IF less than two    SW pumps running, THEN:
: 1) Ensure  SW isolation.
: 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
: 3) Go  to Step 18.
: b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
 
<<I EOP:              TITLE:
REV: 15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 15      of 38 STEP      ACTION/EXPECTED RESPONSE              RESPONSE    NOT OBTAINED 17  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        if  CNMT RECIRC fans should be        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 at least two air                  c. Manually    start air compressors compressors - RUNNING                        as power supply    permits (75 kw each). IF air compressors can NOT  be started, THEN dispatch        AO to locally reset compressors        as necessary.
: d. Check IA supply:                          d. Perform the    following:
o  Pressure    - GREATER THAN              1) Continue attempts      to restore 60 PSIG                                    IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).
o  Pressure    - STABLE OR INCREASING                              2) Continue    with Step 18.      WHEN IA restored,    THEN do  Steps 17e and    f.
: e. Reset both      trains of  XY relays for IA to    CNMT  AOV-5392
: f. Verify    IA to    CNMT  AOV-5392  - OPEN
 
I'4
* 4 -'p'il I %P bl QI Cal
 
EOP:            LITLE:
REV    15 STEAM GENERATOR TUBE RUPTURE PAGE 16    of 38 STEP      ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED 18  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  &#xb9;1 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
: 2) Ensure HCV-142 demand    at  0%.
: b. Align charging  pump suction to    b. IF LCV-112B can NOT be opened, RWST:                                  THEN perform the following:
o  LCV-112B - OPEN                      1) Verify charging    pump A NOT running and place in    PULL o  LCV-112C - CLOSED                      STOP.
: 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
: 3) WHEN  V-358 open,  THEN  direct AO  to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
: c. Start charging pumps as necessary and establish  75 gpm total charging flow
          ~ Charging line flow
          ~ Seal inj ection
 
)%%
41 e'
 
EOP:            TITLE:
REV  15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 17  of 38 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
  ************x*x**x**x*%                CAUTION
                                                    ******x**********
RCS COOLDOWN  IN  STEP 14 SHOULD BE COMPLETED BEFORE CONTINUING TO STEP  19.
  **********x****x                    x x x**x x**x**x**********
x 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  l.
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
 
k
 
EOP:              TITLE:
REV  15 E-3                          STEAM GENERATOR TUBE RUPTURE PAGE 18  of 38 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%      [85%  adverse  CNMTj 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 RCPs.
: 1)  Adjust normal spray valve controller to 0% DEMAND
: 2)  Verify    RCS    pressure INCREASING
: 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
 
re% 4 ',r, f '
 
EOP:              TITLE:
REV    15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 19    of '38 STEP        ACTION/EXPECTED RESPONSE                  RESPONSE  NOT OBTAINED
  ***********                  4  ** x ~ x x x x x x CAUTION
* x**x**************
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.
  ******* ** ***    x %      x        4 x
* x x  4 ******************
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.
 
~ A 4
 
EOP:
REV: 15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 20  of 38 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
                        -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.
 
J g~
~ '
 
EOP:
REV: 15 E-3                STEAM GENERATOR TUBE RUPTURE PAGE 21  of 38 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 to increase.
: b. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
 
Cl J
1 C
,C
 
EOP:              T I l'LE:
REV  15 E-3                        STEAM GENERATOR TUBE RUPTURE PAGE 22  of 38 STEP      ACTION/EXPECTED RESPONSE                    RESPONSE    NOT OBTAINED
  **************                      0
* x x  w *** ****************
CAUTION x  %
SI MUST BE TERMINATED WHEN TERMINATION CRITERIA ARE SATISFIED TO PREVENT
    'OVERFILLING OF THE RUPTURED S/G.
  ***********                    x*x  x  **x 0
* x **x **x x *x******x***
24    Check  If Terminated:
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, Step 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  l.
: d. PRZR  level    - GREATER THAN 5%            d. Do NOT stop SI pumps. Return to
[30%  adverse      CNMT)                          Step 12.
 
I'I EOP:            TITLE:
REV: 15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 23 of 38 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  41  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-300B
: 2) Ensure HCV-142 open.
: 3) Start  one  charging pump.
: b. Establish 20    gpm  charging line flow
*27  Monitor SI Reinitiation Criteria:
: a. RCS  subcooling based on core        a. Manually operate 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    l..
: b. PRZR  level  - GREATER THAN 5%      b. Manually,.operate SI pumps as
[30%  adverse  CNMTj                    necessary.
IF PRZR level can NOT be maintained, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step    l.
 
yg'-u
                'I
~ fE
      'tI l
ht
 
EOP:
REV  15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 24  of 38 STEP      ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED
*28  Monitor    If CNMT Spray      Should Be  Stopped:
: a. CNMT  spray pumps  - ANY RUNNING    a. Go to Step 29.
: b. Verify  CNMT pressure  - LESS THAN b. Continue'with Step 29. WHEN 4 PSIG                                  CNMT pressure less than 4 psig, THEN do Steps 28c 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
 
  &q. II I
 
EOP:          LITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 25 of 38 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 29  Check  If SI Isolated:
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 O'        COOLANT - SUBCOOLED RECOVERY USING FIGURE MIN SUBCOOLING          DESIRED, Step  l.
o  PRZR  level  - GREATER THAN 5%
[30%  adverse  CNMTj
: 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
 
f.
+tk    >,1 $y 4s 4
hPW jf-Qy
'"9,,
t 4
'X;i
 
EOP:
REV  15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 26  of 38 STEP      ACTION/EXPECTED RESPONSE          RESPONSE  NOT OBTAINED 30  Verify Adequate      SW  Flow To CCW  Hx:
: a. Verify at least three  SW pumps  a. Manually  start pumps as power RUNNING                                supply permits (258 kw each).
IF less than two SW pumps can be operated, THEN go to Step 37.
: b. Verify AUX BLDG  SW isolation      b. Establish SW to AUX BLDG (Refer valves  - AT LEAST ONE SET OPEN        to Attachment AUX BLDG SW).
          ~ MOV-4615 and MOV-4734
          ~ MOV-4616 and MOV-4735
: c. Verify CNMT RECIRC  fan            c. Dispatch  AO to locally throttle annunciator C-2,  HIGH                flow to  CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED      5000 gpm  and 6000 gpm total flow.
 
4 I
P
 
EOP:            TITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 27    of 38 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 31  Check  If Normal Operation CVCS Can Be Established
: a. Verify IA restored:                  a. Continue with Step 37. WHEN IA restored, THEN do Steps 31 o  IA to  CNMT  (AOV-5392) - OPEN      through 36.
o  IA pressure    - GREATER THAN 60 PSIG
: b. Verify instrument bus    D          b. Energize    MCC  B. IF MCC B NOT ENERGIZED                                available,  THEN  perform the following:
: 1)  Verify MCC  A  energized.
: 2) Place instrument bus      D on maintenance    supply.
: c. CCW  pumps  - ANY RUNNING            c. Perform the following:
: 1) IF any  RCP  tl  seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected      RCP(s).
                                                        ~ RCP A, MOV-749A    and MOV-759A
                                                        ~ RCP B, MOV-749B    and MOV-759B
: 2) Manually    start  one  CCW pump.
: d. Charging pump    - ANY RUNNING        d. Continue with Step 37.        WHEN  any charging  pump  running,    THEN do Steps 32  through 36.
 
I '1
    'r I V I
IWg
 
EOP:            JIZLE:
REV: 15 E-3                        STEAM GENERATOR TUBE RUPTURE PAGE 28    of 38 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 32  Check Should IfBe Seal    Return Flow Established:
: a. Verify RCP &#xb9;1 seal outlet                a. Go  to Step 33.
temperature      - LESS THAN  235'F
: b. Verify  RCP    seal outlet valves      b. Manually open valves as OPEN                                        necessary.
          ~ AOV-270A
          ~ AOV-270B
: c. Reset both trains of XY relays for RCP seal return isolation valve  MOV-313
: d. Open  RCP    seal return isolation      d. Perform the    following:
valve  MOV-313
: 1) Place MOV-313 switch to OPEN.
: 2) Dispatch  AO with key to  RWST gate to  locally open MOV-313.
: e. Verify RCP &#xb9;1 seal leakoff flow          e. IF any  RCP seal leakoff flow LESS THAN      5.5  GPM                    greater than 5.5 gpm, THEN:
o  Close the affected  RCP seal discharge valve
                                                            ~ RCP A, AOV-270A
                                                            ~ RCP B, AOV-270B o  Trip the affected  RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.
: f. Verify RCP      &#xb9;1 seal leakoff flow      f. Refer to AP-RCP.1,  RCP SEAL GREATER THAN      0.25 GPM              MALFUNCTION.
 
      ~I ~ .
I.'
4 Al tg
~Ck
 
EOP:            TITLE:
REV: 15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 29  of 38 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 33  Verify    PRZR Level  GREATER                Continue with Step 35. WHEN PRZR THAN 13% [40: adverse CNMT]                  level increases to greater than 13%
[40% adverse CNMT], THEN do Step 34.
34  Establish Normal Letdown:                    IF RCP seal return has been established, THEN establish excess
: a. Establish charging      line flow to      letdown as follows:
REGEN Hx - GREATER THAN 20 GPM o  Place excess  letdown  divert
: b. Place the following switches to                valve, AOV-312, to    NORMAL.
CLOSE:
o  Ensure CCW from excess    letdown
          ~ Letdown    orifice valves                  open, (AOV-745).
(AOV-200A, AOV-200B, and AOV-202)                                o  Open excess  letdown  isolation
          ~  Letdown    isolation valve    AOV-371      valve AOV-310.
          ~  Loop B cold    leg to  REGEN Hx AOV-427                                o  Slowly open HCV-123 to maintain excess letdown temperature less
: c. Place letdown controllers in                  than 195'F and pressure less MANUAL at 40% open                            than 100 psig.
          ~  TCV-130                                o  Adjust charging    pump speed  as
          ~  PCV-135                                    necessary.
: d. Reset both    trains of  XY  relays    IF RCP seal return NOT established, for  AOV-371 and AOV-427                  THEN consult TSC to determine      if excess  letdown should be placed in
: e. Open AOV-371 and AOV-427                  service.
: f. Open  letdown    orifice valves      as necessary
: g. Place TCV-130      in  AUTO  at 105'F
: h. Place PCV-135 in      AUTO  at  250  psig
: i. Adjust charging      pump speed    and HCV-142 as necessary
 
A h
 
EOP:
REV  15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 30  of 38 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 35  Check VCT Makeup System:
: a. Adjust boric acid flow control valve in  AUTO to 9.5  gpm
: b. Verify the following:              b. Adjust controls as necessary.
: 1) RMW mode  selector switch in AUTO
: 2) RMW control  armed - RED LIGHT LIT
: c. Check VCT  level:                  c. 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.
 
I>  ~ M t~,
M.lt Cg~a
~ I~ 4P h
~4
 
EOP:
REV: 15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 31  of 38 STEP      ACTION/EXPECTED RESPONSE        RESPONSE  NOT OBTAINED 36  Check Charging Pump Suction Aligned To    VCT:
: a. VCT level - GREATER THAN 20%      a. IF VCT    level  can NOT  be maintained greater than    5%, THEN perform the following:
: 1) Ensure charging pump suction aligned to  RWST o  LCV-112B open o    LCV-112C  closed
: 2) Continue    with Step 37. WHEN VCT level greater    than 40%,
THEN do Step 36b.
: b. Verify charging pumps aligned to  b. Manually align valves as VCT                                  necessary.
o  LCV-112C - OPEN o  LCV-112B - CLOSED
 
Pp
<<4.
ig
%1EP
 
EOP:              TITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 32  of 38 STEP        ACTION/EXPECTED RESPONSE                RESPONSE    NOT OBTAINED
  **************                    x  ** *x    x x x CAUTION RCS AND RUPTURED    S/G PRESSURES  MUST BE MAINTAINED LESS THAN        1050 PSIG.
  ***xx*******xxxxxxx*xx*x*xx****x*****
*37    Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary      Leakage:
: a. Perform appropriate action(s) from table:
PRZR                    RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING        DECREASING        OFFSCALE HIGH LESS THAN 13%          o Increase    RCS      Increase    RCS o  Increase  RCS
[40% ADVERSE CNMTJ      makeup  flow        makeup  flow      makeup  flow o Depressurize RCS                      o  Maintain RCS and using Step 37b                          ruptured S/G pressure equal BETWEEN 13%              Depressurize RCS      Energize          Maintain RCS and
[40% ADVERSE CNMT)      using Step 37b        PRZR              ruptured S/G AND 50%                                        heaters            pressure equal BETWEEN 50% AND 75% o    Depressurize RCS      Energize          Maintain RCS and
[65% ADVERSE CNMTj      using Step 37b        PRZR              ruptured S/G heaters            pressure equal o Decrease    RCS makeup  flow GREATER THAN 75%      o  Decrease    RCS      Energize          Maintain  RCS and
[65% ADVERSE CNMT]      makeup  flow        PRZR              ruptured  S/G heaters            pressure equal
: b. Control pressure using normal              b. IF letdown    is in service, THEN PRZR spray,  if available, to                use  auxiliary spray (AOV-296).
obtain desired results for                    IF  NOT, THEN use one PRZR PORV.
Step 37a
 
I')~4 N
1g
            '0'1I+
S
 
EOP:              TITLE:
REV    15 E-3                      STEAM GENERATOR TUBE RUPTURE PAGE 33  of 38 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 38  Check Should IfBe Emergency    D/Gs Stopped:
: a. Verify AC    emergency busses        a. Try to restore  offsite  power energized by    offsite power:          (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
o  Emergency D/G    output breakers OPEN o  AC emergency    bus voltage GREATER THAN    420 VOLTS o  AC  emergency bus normal feed breakers    - CLOSED
: b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP).
Minimize Secondary System 50'.
39 Contamination:
: a. Isolate reject from hotwell to            IF hotwell level increasing, CST:                                    THEN  direct RP to sample hotwells for activity.
o  Place hotwell level controller    (LC-107) in  MANUAL at o  Verify hotwell level      - STABLE
: b. Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)
 
l I h
 
EOP:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 34 of 38 STEP      ACTION/EXPECTED'ESPONSE            RESPONSE NOT OBTAINED 40  Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41  Check RCP Cooling:                      Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
: 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
 
EOP:            TITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 35    of 38 STEP      ACTION/EXPECTED RESPONSE            RESPONSE    NOT OBTAINED
  ******xx            x*0 xxxxx%xx'xx%'*x4***x****x*******
CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
  ************4 *4                  x x w * ~ ***********                *'* * * * * * * *
* 42    Check RCP    Status:
: a. RCPs  - AT LEAST ONE RUNNING          a. Perform the      following:
: 1) Try to    start  one RCP:
a) Ensure conditions        for starting    an RCP.
o    Bus  llA or  11B energized.
o    Refer to Attachment      RCP START.
b) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:
o    Increase  PRZR  level to greater than    65%  (80%
adverse CNMTj.
o    Dump  steam to establish RCS  subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.
c) Start one      RCP.
: 2) IF an    RCP  can  NOT  be  started, THEN  verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT  be  verified,    THEN increase dumping steam.
: b. Stop  all  but one RCP
 
J ig$ V ~w II
'gl e
 
EOP:            TITLE:
REV: 15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 36  of 38 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED NOTE:    Adverse  CNMT  conditions or loss of forced air cooling    may result in failure of  NIS  detectors.
43  Check    If Source Detectors Should Range Be Energized:
: a. Source range channels                  a. Go  to Step 43e.
DEENERGIZED
: b. Check intermediate range    flux      b. Perform the following:
EITHER CHANNEL LESS THAN 10 10 AMPS                                  1)  IF neither intermediate range channel is decreasing,  THEN initiate boration.
: 2) Continue  with Step 44. WHEN flux is  LESS THAN 10    amps on any operable channel,  THEN do Steps 43c through e.
: c. Check the following:                    c. Continue with Step 44. WHEN either condition met, THEN do o  Both intermediate range                  Steps 43d and e.
channels - LESS THAN 10 10 AMPS
                      -OR-o  Greater than  20 minutes since reactor  trip
: d. Verify source range detectors          d. Manually energize source range ENERGIZED                                  detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can'OT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.
: e. Transfer Rk-45 recorder to one source range and one intermediate range channel
 
I 4Q  A~
 
EOP:              TITLE:
REV: 15 E-3                        STEAM GENERATOR TUBE RUPTURE PAGE 37  of 38 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 44  Establish Normal Shutdown Alignment:
: a. Check condenser      - AVAILABLE        a. Dispatch  AO to perform Attachment SD-2.
: b. Perform the following:
i o    Open  generator disconnects
                ~ 1G13A71
                ~ 9X13A73 o    Place voltage regulator to      OFF o  Open  turbine drain valves o  Rotate reheater steam supply controller cam to close valves o  Place reheater dump valve switches to HAND o  Stop  all  but  one condensate pump
: c. Verify adequate Rx head cooling:
: 1) Check IA to      CNMT -  AVAILABLE        1) Go  to Step 45.
: 2) Verify at least      one  control        2) Manually start one fan as rod shroud fan      - RUNNING                power supply permits (45 kw)
: 3) Verify    one Rx compartment            3) Perform the  following:
cooling fan      - RUNNING o  Dispatch  AO to reset UV relays at  MCC C and MCC D.
o  Manually start one fan as power supply permits (23 kw)
: d. Verify Attachment      SD COMPLETE
 
~m ,~
      ~l
~l,
 
EOP:          LITLE:
REV  15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 38 of 38 STEP    ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED 45  Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:
o Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1
                    -OR-o Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1
                    -OR-o Go to ES-'3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1
                                          -END-
 
    ~ lt 4
elhi 7
X
 
EOP:
REV  15 E-3              STEAM GENERATOR TUBE RUPTURE PAGE 1  of 1 E-3 APPENDIX LIST TITLE                        PAGES
: 1) RED PATH
 
==SUMMARY==
: 2) FIGURE MIN SUBCOOLING
: 3) ATTACHMENT CNMT RECIRC FANS
: 4) ATTACHMENT D/G STOP
: 5) ATTACHMENT N2 PORVS
: 6) ATTACHMENT NC
: 7) ATTACHMENT SEAL COOLING
: 8) ATTACHMENT RCP START
: 9) ATTACHMENT RUPTURED S/G
: 10) ATTACHMENT SD-1
: 11) ATTACHMENT SD-2
: 12) ATTACHMENT AUX BLDG SW
: 13) FOLDOUT
 
4 EOP:
REV  15 E-3                STEAM GENERATOR TUBE RUPTURE PAGE 1  of 1 RED PATH
 
==SUMMARY==
: a. SUBCRITICALITY  Nuclear power greater than    5~
: b. CORE COOLING  Core  exit  T/Cs greater than 1200'F
                                              -OR-Core  exit  T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43~~ [464 adverse  CNMT]
: c. HEAT SINK  Narrow range    level in all  S/Gs  less than 54
[25< adverse  CNMT] AND  total feedwater flow less than    200 gpm
: d. INTEGRITY  Cold  leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F
: e. CONTAINMENT  CNMT    pressure greater than  60  psig
 
'p V'
        ,II Ijf r'-
Il+
~" I
'~    f c
I, I
~ 4
 
EOP:              TITLE:
REV  15 E-3                    STEAM GENERATOR TUBE RUPTURE PAGE 1  of  1 FIGURE MIN SUBCOOLING NOTE:      Subcooling Margin      =  Saturation Temperature From Figure Below t'-] Core Exit T/C Indication RC S  PRESSURE    (PSIG) 2500 2400 2300            RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1400 SUBCOOLED 1300                            REGION 1200 1100 1000 900 800 700                                                                  INADEQUATE SUBCOOLING 600                                                                    REGION DV ERS E C 500 400 300 200                                          NORMAL CNMT                    TEMPERATURE 100                                                                        INCREMENTS 10'F 0
200        250        300  350      400    450    500    550      600    650    700 CORE  EXIT SATURATION TEMPERATURE  (')
 
J'-
EOP:
REV: 15 E-3                  STEAM GENERATOR TUBE RUPTURE PAGE 1  of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR          WITH LOSS OF REACTOR COOLANT  SUBCOOLED RECOVERY DESIRED,        Step 1:
o  RCS  subcooling based on core exit T/Cs      LESS THAN 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR o  PRZR  level    CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%  [304 adverse CNMT).
2 4    SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
3 ~    COLD LEG RECIRCULATION SWITCHOVER CRITERION IF  RWST    level decreases to less than 284, THEN go    to ES-1.3,    TRANSFER TO COLD LEG RECIRCULATION, Step    l.
: 4.      AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
: 5.      MULTIPLE    S G TUBE RUPTURE  CRITERIA IF any    intact  S/G  level increases in in  an uncontrolled manner  OR  IF any intact  S/G has abnormal  radiation,  THEN go  to ECA-3.1,    SGTR WITH LOSS OF REACTOR COOLANT  SUBCOOLED RECOVERY DESIRED,      Step 1.
 
tel 5t
 
EOP:          T1TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 '                          GENERATORS              PAGE 1  of 31 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RES 0 SIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY
 
EOP:          TLTLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA 1                          GENERATORS                  PAGE 2  of 31 A. PURPOSE    This  procedure provides actions to mitigate and minimize a    loss of secondary coolant from both steam generators.
B. ENTRY CONDITIONS/SYMPTOMS 1-  ENTRY CONDITIONS  This    procedure  is entered from:
: a. E-2, FAULTED STEAM GENERATOR ISOLATION, when an uncontrolled depressurization of both steam generators occurs.
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATZON OF BOTH STEAM ECA-2.1                                    GENERATORS                      PAGE 3  of 31 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.
NOTE:  o  FOLDOUT    page should be open AND monitored    periodically.
o  Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
o  Adverse    CNMT  values should be used whenever CNMT pressure is greater than      4 psig or CNMT radiation is greater than 10+    R/hr.
1  Check Secondary        Pressure              Manually close valves one loop at a Boundary:                                    time.
o MSIVs - CLOSED                            IF valves can NOT be closed, THEN dispatch AO to locally isolate o MFW  flow control valves      - CLOSED    flowpaths, as necessary, one loop at a time.
          ~ MFW  regulating valves
          ~ MFW  bypass valves o MFW  pump    discharge valves CLOSED V
o  S/G blowdown and sample      valves CLOSED o TDAFW pump    steam supply valves PULL STOP o TDAFW pump      flow control valves CLOSED o S/G ARVs - CLOSED o Dispatch AO to locally isolate S/Gs (Refer to Attachment FAULTED S/G)
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                GENERATORS                    PAGE 4  of 31 STEP        ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED CAUTION A MINIMUM FEED FLOW OF 50 GPM MUST BE MAINTAINED TO EACH S/G WITH A NARROW RANGE LEVEL LESS THAN 5% [25% ADVERSE CNMT].
2  Control Feed Flow        To  Minimize RCS  Cooldown:
: a. Check cooldown rate in RCS cold        a. Decrease feed flow to 50 gpm to legs -'ESS THAN 100'F/HR                  each S/G and go to Step 2c.
: b. Check narrow range level in both        b. Control feed flow to maintain S/Gs - LESS THAN 50%                      narrow range level less than 50%
in both S/Gs.
: c. Check    RCS hot leg temperatures      c. Control feed flow or dump steam STABLE OR DECREASING                      to stabilize RCS hot leg temperatures.
3  Check Stopped:
If RCPs    Should Be
: a. RCP  status -  ANY RCP RUNNING        a. Go  to Step 4.
: b. SI pumps -    AT LEAST TWO RUNNING    b. Go  to Step 4.
: c. RCS  pressure minus maximum S/G          Go  to Step 4.
pressure - LESS THAN 175 psig
[400 psig adverse    CNMT]
: d. Stop both    RCPs
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                  GENERATORS PAGE 5    of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 4  Check CST Level  GREATER                  'witch    to alternate AFW suction THAN 5 FEET                                  supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).
* 5  Monitor    PRZR PORVs And        Block Valves:
: a. Power  to  PORV  block valves          a. Restore power to block valves AVAILABLE                                    unless block valve was closed to isolate  an open PORV:
                                                        ~ MOV-515,  MCC C  position  6C
                                                        ~ MOV-516,  MCC D  position  6C
: 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 C position  6C
                                                        ~ MOV-516,    MCC D position  6C
: c. Block valves      - AT LEAST ONE OPEN    c.'Open one block valve unless      it was closed to isolate an open PORV.
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                              GENERATORS                        PAGE 6  of 31 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 6  Check Secondary Radiation                  Go to E-3,  STEAM GENERATOR TUBE Levels    NORMAL                        RUPTURE,  Step l.
o  Steamline radiation monitor (R-31 and R-32) o  Dispatch AO to locally check steamline radiation o  Request  RP sample S/Gs for activity CAUTION IF OFFSITE  POWER IS LOST AFTER SI RESET,  THEN SELECTED SW PUMPS AND ONE CCW PUMP  WILL AUTO START ON EMERGENCY  D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.
7  Reset SI
 
EOP:            TITLE:
REV  12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1                                GENERATORS                        PAGE 7  of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED CAUTION RCS PRESSURE  SHOULD BE MONITORED. IF .RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG    ADVERSE  CNMT],  THEN  THE RHR PUMPS MUST BE MANUALLY RESTARTED TO  SUPPLY  WATER  TO THE  RCS.
* 8  Monitor Be If Stopped:
RHR Pumps    Should
: a. RHR pumps    - ANY RUNNING                a. Go to Step 9.
: b. Check  RCS  Pressure:
: 1) Pressure    - GREATER THAN                  1) Go to  E-l, LOSS OF REACTOR OR 250 psig [465 psig adverse                    SECONDARY COOLANT, Step 1.
CNMT]
: 2) Pressure    - STABLE OR                    2) Go to Step 9.
INCREASING
: c. Stop  RHR pumps    and place in  AUTO
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1                                GENERATORS                        PAGE 8    of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED
* 9 Monitor Be  Stopped:
If CNMT Spray    Should
: a. CNMT  spray pumps -  RUNNING          a. Go  to Step 10.
: b. Check the following:                    b. Continue with Step 10.      WHEN BOTH  conditions satisfied,  THEN o  CNMT  pressure  - LESS THAN            do Steps  9c through f.
4 PSIG o  Sodium hydroxide tank    level LESS THAN 55%
: c. Reset    CNMT  spray
: d. Check    NaOH  tank outlet valves        d. Place  NaOH  tank outlet valve CLOSED                                      controllers to    MANUAL and close valves.
            ~ AOV-836A
            ~ AOV-836B                                  ~  AOV-836A
                                                        ~  AOV-836B
: e. Stop  CNMT  spray pumps and place in AUTO
: f. Close  CNMT  spray pump discharge valves
            ~ MOV-860A
            ~ MOV-860B
            ~ MOV-860C
            ~ MOV-860D,
 
l~
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                  GENERATORS                        PAGE 9  of  31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 10  Check  RWST    Level  GREATER          Go to ES-1.3,  TRANSFER TO COLD LEG THAN 284                                    RECIRCULATION, Step    l.
ll Reset    CI:
: a. Depress CI reset pushbutton
: b. Verify annunciator A-26,    CNMT      b. Perform the following:
ISOLATION - EXTINGUISHED
: 1) Reset SI.
: 2) Depress CI reset pushbutton.
12  Verify Adequate        SW  Flow:
: a. Check at least two    SW  pumps        a. Manually  start  SW pumps as power RUNNING                                    supply permits (258 kw each).
IF less than two SW pumps running, THEN perform the following:
1),Ensure  SW  isolation.
: 2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
: 3) Go to Step 14.
: b. Dispatch    AO to establish normal shutdown alignment (Refer to Attachment SD-1)
 
EOP:            T!TLE:
REV: 12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1                                  GENERATORS                        PAGE 10      of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED 13  Establish IA to      CNMT:
: a. Verify non-safeguards    busses          a. Perform the following:
energized from  offsite  power
: 1) Close non-safeguards    bus  tie o  Bus 13 normal feed - CLOSED                  breakers:
                      -OR-                                ~  Bus 13  to Bus 14  tie
                                                          ~  Bus 15  to Bus 16  tie o  Bus 15 normal feed - CLOSED
: 2) Verify adequate    emergency D/G capacity to run    air compressors  (75 kw each).
IF NOT, THEN evaluate RECIRC fans should be if  CNMT stopped (Refer to Attachment    CNMT RECIRC FANS).
: 3) WHEN  bus 15 restored, THEN reset control room lighting.
: b. Verify SW isolation  valves to          b. Manually align valves.
turbine building - OPEN
          ~ MOV-4613 and MOV-4670
          ~ MOV-4614 and MOV-4664
: c. Verify at least two  air                c. Manually    start air compressors compressors  - RUNNING                      as power supply  permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
: d. Check IA supply:                        d. Perform the    following:
o  Pressure  - GREATER THAN                  1) C'ontinue attempts to restore 60 PSIG                                      IA (Refer,to AP-IA.1,      LOSS OF INSTRUMENT AIR).
o  Pressure  - STABLE  OR INCREASING                                2) Continue  with Step 14.      WHEN IA restored,  THEN do  Steps 13e and  f.
: e. Reset both  trains of  XY  relays for IA to CNMT AOV-5392
: f. Verify IA to CNMT AOV-5392      - OPEN
 
EOP:            T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 '                                    GENERATORS                        PAGE 11 of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED 14  Check  If SI Isolated:
ACCUMs    Should Be
: a. Both RCS  hot leg temperatures          a. Go to Step 15.
LESS THAN    400'F
: 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 15  Check Normal Power          Available        Verify adequate  emergency D/G To Charging Pumps:                            capacity to run charging    pumps (75 kw each).
o  Bus 14 normal    feed breaker CLOSED                                    IF NOT, THEN evaluate    if CNMT RECIRC fans can be stopped (Refer o  Bus 16 normal    feed breaker-          to.Attachment CNMT RECIRC FANS).
CLOSED
 
EOP;              T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                GENERATORS                          PAGE 12  of 31 STEP        ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED 16  Check    If  Charging Flow Has Been Established:
: a. Charging pumps - ANY    RUNNING        a. Perform the      following:
: 1) IF  CCW  flow is lost to any RCP  thermal barrier OR any RCP  &#xb9;1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected    RCP:
                                                          ~ RCP A,    V-300A
                                                          ~ RCP B,    V-300B
: 2) Ensure HCV-142 open, demand at  Oa.
: b. Align charging    pump suction to      b. IF LCV-112B can NOT be opened, RWST:                                    THEN perform the following:
o  LCV-112B - OPEN                      1) Verify charging    pump A NOT running    and place in PULL o  LCV-112C - CLOSED                        STOP.
: 2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
: 3) WHEN    V-358 open,  THEN direct AO  to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
: c. Start charging pumps as
          'ecessary and adjust charging flow to restore PRZR level
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                GENERATORS                            PAGE 13  of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
*17  Monitor SI Termination Criteria:
pumps'
: a. SI pumps -    ANY RUNNING                a. Go  to Step 19.
: b. Check  RCS  pressure:                  b. DO NOT  stop SI          ,
Perform the following:
o  Pressure  - GREATER THAN 1625  psig [1825 psig adverse            1) Energize    PRZR heaters  and CNMT]                                        operate  PRZR spray as necessary to stabilize RCS o  Pressure  - STABLE OR                      pressure greater than INCREASING                                  1625 psig [1825 psig adverse CNMT)
: 2) Return to Step 2.
: c. RCS  subcooling based on core            c. DO NOT  stop SI pumps. Return to exit T/Cs - GREATER THAN O'                  Step 2.
USING FIGURE MIN SUBCOOLING
: d. PRZR  level  - GREATER THAN 5%          d. Do NOT  stop SI pumps. Perform
[30%  adverse  CNMT)                        the following:
: 1) IF normal 'PRZR spray available,    THEN try to stabilize    RCS pressure with PRZR  spray,
: 2) Return to Step 17a.
NOTE:  Foldout Page E-2 transition    criteria does  not apply while performing steps 18 and 19.
18  Stop SI and RHR Pumps And Place In Auto
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA    2. 1                                  GENERATORS                            PAGE 14  of 31 STEP        ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED
*19  Monitor SI Reinitiation Criteria:
: a. RCS  subcooling based on core            a. Manually operate SI pumps as exit  T/Cs - GREATER THAN O'                  necessary and return to Step 2.
USING FIGURE MIN SUBCOOLING
: b. PRZR  level  - GREATER THAN  5%        b. Control charging flow to
[30%  adverse  CNMT]                        maintain PRZR level.
IF  PRZR  level  can  NOT  be maintained,    THEN  manually operate SI pumps as necessary and  return to Step 2.
20  Check    RCS    Hot Leg                        Control feed flow or dump steam to Temperatures  STABLE            OR            stabilize RCS hot leg temperatures.
DECREASING 21  Check Narrow Range Level In                    Control feed flow to maintain Both S/Gs  LESS THAN 504                      narrow range level less than 50% in both S/Gs.
22  Verify Adequate          SW  Flow To CCW    Hx:
: a. Verify at least      two  SW pumps        a. Manually    start  pumps as power RUNNING                                        supply permits      (258 kw per pump). IF less than two SW pumps can be operated, THEN      go to Step 28
: b. Verify AUX BLDG      SW  isolation            Establish SW to AUX BLDG (Refer valves - OPEN                                  to Attachment AUX BLDG SW).
            ~ MOV-4615 and MOV-4734
            ~ MOV-4616 and MOV-4735
: c. Verify CNMT RECIRC fan                    c. Dispatch AO to locally throttle annunciator C-2, HIGH                          flow to CCW Hx to between TEMPERATURE AIARM - EXTINGUISHED                5000 gpm and 6000 gpm      total flow.
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                GENERATORS                          PAGE 15    of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 23  Check    If  Normal CVCS Operation Can Be Established
: a. Verify IA restored:                    a. Continue with Step 28. WHEN IA restored, THEN do Steps 23 o  IA to    CNMT (AOV-5392) - OPEN        through 27.
o  IA pressure -    GREATER THAN 60 PSIG
: b. Verify instrument    bus D-            b. Energize  MCC  B. IF MCC B NOT ENERGIZED                                  available,  THEN perform the following:
: 1)  Verify MCC  A energized.
: 2) Place instrument bus    D on maintenance supply.
: c. CCW  pumps    - ANY RUNNING            c. Perform the following:
: 1) IF any  RCP &#xb9;1 seal outlet f
temperature of scale high, THEN isolate CCW to thermal barrier of affected    RCP(s).
                                                          ~ RCP  A, MOV-749A and MOV-759A
                                                          ~ RCP  B, MOV-749B and MOV-759B
: 2) Manually  start  one  CCW pump.
: d. Charging pump -    ANY RUNNING        d. Continue with Step 28.      WHEN  any charging pump running,    THEN do Steps 24 through 27.
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                    GENERATORS                          PAGE 16        of 31 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE  NOT OBTAINED 24  Verify    PRZR  Level  GREATER              Continue with Step 26. WHEN PRZR THAN    134 [40% adverse CNMT]                  level increases to greater than 13%
[40% adverse CNMT], THEN do Step 25.
25  Establish Normal Letdown:                      IF RCP seal return has been established, THEN establish excess
: a. Verify charging line flow to                letdown as follows:
REGEN Hx - GREATER THAN 20        GPM o  Place excess letdown    divert
: b. Place the following switches to                valve, AOV-312, to    NORMAL.
CLOSE:
o  Ensure CCW from excess    letdown
          ~ Letdown    orifice'valves                    open, (AOV-745).
(AOV-200A, AOV-200B, and AOV-202)                                  o  Open excess  letdown isolation
          ~ AOV-371, letdown isolation                          AOV-310.                    'alve valve
          ~ AOV-427, loop      B  cold leg to        o  Slowly open HCV-123 to maintain REGEN Hx                                      excess letdown temperature less than 195'F and pressure less
: c. Place letdown controllers in                    than 100 psig.
MANUAL  at  40%  open o  Adjust charging    pump speed  as
          ~ TCV-130                                      necessary.
          ~ PCV-135 IF  RCP seal  return  NOT established,
: d. Reset both    trains of  XY  relays      THEN consult TSC    to determine  if for  AOV-371 and AOV-427                    excess letdown should be placed in service.
: e. Open AOV-371 and AOV-427
: f. Open  letdown    orifice valves    as necessary
: g. Place TCV-130      in  AUTO at 105'F
: h. Place PCV-135 in      AUTO at  250  psig
: i. Adjust charging      pump speed    and HCV-142 as necessary
 
EOP:            T1TLE REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                GENERATORS                        PAGE 17    of 31 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 26  Check VCT Makeup System:
: a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
: b. Adjust RMW flow control valve in AUTO to 40 gpm
: c. Verify the following:                  c. Adjust controls as necessary.
: 1) RMW  mode  selector switch in AUTO
: 2) RMW  control  armed - RED LIGHT LIT
: 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.
 
EOP:            TITLE:
REV    12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1                                GENERATORS                          PAGE 18  of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 27  Check Charging Pump Suction Aligned To      VCT:
: a. VCT  level  - GREATER THAN 20%        a. IF VCT    level  can NOT  be maintained greater than    5%, THEN perform the following:
: 1) Ensure charging pump suction aligned to  RWST o  LCV-112B open o  LCV-112C  closed
: 2) Continue    with Step 28. WHEN VCT  level greater than  40%,
THEN  do'tep'7b.
: b. Verify charging pumps aligned to      b. Manually align valves as VCT:                                      necessary.
o  LCV-112C - OPEN o  LCV-112B - CLOSED
 
EOP:            TITLES REV  12 UNCONTROLLED DEPRESSURXZATZON OF BOTH STEAM ECA-'2. 1                                GENERATORS                      PAGE 19  of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED 28  Check RCP Cooling:                          Establish normal cooling to RCPs
                                                  ~
(Refer to Attachment SEAL COOLING).
: a. Check  CCW  to RCPs:
o  Annunciator A-7,  RCP lA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o  Annunciator A-15,    RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED
: b. Check'RCP seal injection:
o  Labyrinth seal D/Ps    - GREATER THAN 15 INCHES OF WATER
                        -OR-o  RCP  seal injection  flov to each  RCP - GREATER THAN 6 GPM
 
EOP:              T1TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                    GENERATORS                        PAGE 20    of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 29  Check    If  Seal Return Flow Should Be Established:
: a. Verify RCP &#xb9;1 seal outlet                a. Go to Step 30.
temperature      - LESS THAN 235'F
: b. Verify    RCP  seal outlet valves        b. Manually open valves as OPEN                                          necessary.
            ~ AOV-270A
            ~ AOV-270B
: c. Reset both trains of XY relays for RCP seal return isolation valve  MOV-313
: d. Open    RCP  seal return isolation        d. Perform the    following:
valve  MOV-313
: 1) Place MOV-313 switch to OPEN.
: 2) Dispatch  AO  with key to  RWST gate to  locally  open MOV-313.
: e. Verify RCP &#xb9;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 30.
: f. Verify RCP &#xb9;1      seal leakoff flow      f. Refer to AP-RCP.1,    RCP SEAL GREATER    THAN 0.8 GPM                    MALFUNCTION.
 
EOP:          TITLE:
UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM                REV: 12 ECA-2. 1                              GENERATORS PAGE 21  of 31 STEP    ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE:  o  If auxiliary spray  is in use, spray flow may be increased by closing  normal  charging valve AOV-294 and normal PRZR spray valves.
o  When  using  PRZR PORV,  select one with  an operable block valve.
30  Energize Heaters And Operate              IF normal'pray NOT available and Normal Spray As Necessary To              letdown is in service, THEN use Maintain  RCS  Pressure Stable          auxiliary spray valve (AOV-296).
IF  PRZR spray NOT'vailable', THEN use one PRZR PORV.
IF IA NOT available,  THEN refer to Attachment N2 PORVS.
 
C EOP:
ECA-2.1'1ILE:
UNCONTROLLED                                                  REV    12 DEPRESSURIZATION OF BOTH STEAM GENERATORS PAGE 22    of 31 STEP    ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 31 Verify All, AC Busses                  Perform the following:
ENERGIZED BY OFFSITE PONER
: a. IF any AC emergency bus normal o Normal feed breakers to  all 480        feed breaker open, THEN ensure volt busses - CLOSED                    associated    D/G  breaker closed.
o 480 bus voltage - GREATER THAN      b. Perform the following, as 420 VOLTS                                necessary:
o Emergency D/G output breakers            1) Close non-safeguards      bus  tie OPEN                                        breakers:
                                                      ~  Bus 13  to  Bus 14  tie
                                                      ~ 'Bus 15  to  Bus 16  tie
: 2) Place the    following  pumps  in PULL STOP:
                                                      ~  EH pumps
                                                      ~  Turning gear oil pump
                                                      ~  HP seal oil backup pump
: 3) Restore power to MCCs.
                                                      ~  A from  Bus  13 4 B  from  Bus  15
                                                      ~ E  from  Bus  15
                                                      ~  F from  Bus  15
: 4) WHEN  bus 15 restored, THEN reset control room lighting..
: 5) Refer to Attachment SI/UV        for other equipment lost with loss of offsite power.
: c. Try to restore      offsite  power to all  AC busses    (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
 
I EOP:            T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 1                              GENERATORS                          PAGE 23  of  31 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATIONS 32  Check RCP Status ONE RUNNING
                            'T LEAST        Try to  start  one RCP:
: a. Establish conditions    for starting  an RCP.
o  Bus 11A  or  11B energized I
o  Refer to Attachment    RCP START.
: b. Start one    RCP.
IF an  RCP  can  NOT  be started,  THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation can NOT be verified,  THEN increase feed flow or dumping steam.
 
ilk EOP:                TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1                                  GENERATORS                        PAGE 24  of 31 STEP        ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED I
NOTE:    Adverse    CNMT conditions or loss of forced air cooling    may result in failure of    NIS  detectors.
33  Check      If Source Detectors Should Range Be  Energized:
: a. Source range channels                    a. Go  to Step 33e.
DEENERGIZED
: b. Check intermediate, range      flux-      b. Perform the following:
EITHER CHANNEL LESS THAN 10 10 AMPS                                  1) IF  neither intermediate range channel  is decreasing  THEN initiate boration.
: 2) Continue  with Step 34. WHEN flux is  LESS THAN 10      amps on any operable channel,    THEN do Steps 33c, d and e.
: c. Check the following:                      c. Continue with step 34.      WHEN either condition    met,  THEN do o  Both intermediate range                Steps 33d and e.
channels - LESS THAN 10-10 AMPS
                          -OR-o  Greater than    20  minutes since reactor  trip
: d. Verify source    range detectors        d. Manually energize source 'range ENERGIZED                                  detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).
IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION and    go to Step 34.
: e. Transfer Rk-45 recorder 'to one source range and one intermediate range channel.
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                  GENERATORS                      PAGE 25  of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED 34  Check    If Emergency Should Be Stopped:
D/Gs
: a. Verify AC  emergency busses          a. Try to restore  offsite power energized by  offsite  power:            (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
o  Emergency D/G  output breakers OPEN o  AC emergency  bus voltage GREATER THAN  420 VOLTS o  AC  emergency bus normal feed breakers -  CLOSED
: b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                  GENERATORS                        PAGE 26  of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 35  Establish Normal Shutdown Alignment:
: a. Check condenser    - AVAILABLE          a. Dispatch AO to perform Attachment SD-2.
b, Perform the following:
o  Open    generator disconnects
                ~  1G13A71
                ~  9X13A73 o  Place voltage regulator to      OFF o  Open    turbine drain valves o  Rotate reheater steam supply controller cam to close valves o  Place reheater dump valve switches to HAND o  Stop    all  but one condensate pump
: c. Verify adequate    Rx head  cooling:
: 1) Verify at least      one control          1) Manually start one fan as rod shroud fan      - RUNNING                power supply permits (45 kw)
: 2) Verify one    Rx compartment              2) Perform the  following:
cooling    fan - RUNNING o  Dispatch  AO to reset UV relays at  MCC C and MCC D.
o  Manually start one fan as power supply permits (23 kw)
: d. Verify Attachment      SD COMPLETE
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1                                  GENERATORS                          PAGE 27 of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 36  Maintain Plant Conditions                  Control plant systems as necessary STABLE                                      to maintain conditions stable.
o  RCS  pressure o  PRZR  level o  RCS  temperatures
*37  Monitor SI Reinitiation Criteria:
: a. RCS  subcooling based on core          a. Manually operate SI pumps as exit T/Cs - GREATER THAN O'                necessary. Return to Step 2.
USING FIGURE MIN SUBCOOLING
: b. PRZR  level  - GREATER THAN 5%        b. Control charging flow to
[30%  adverse  CNMT)                    maintain PRZR level.
IF  PRZR  level  can  NOT  be maintained,    THEN  manually operate  SI  pumps as necessary.
Return  to  Step 2 ~
 
'I
  '4
 
EOP:              T1TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1                                    GENERATORS                      PAGE 28 of 31 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 38  Check Isolated:
If SI    ACCUMs    Should  Be
: a. Check the    following:                  a. Go to Step 39.
o  RCS  subcooling based on core exit  T/Cs -    GREATER THAN  O' USING FIGURE MIN SUBCOOLING o  PRZR    level  - GREATER THAN  5%
[30% adverse    CNMT]
: 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:            T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1                              GENERATORS                        PAGE 29  of 31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 39  Check RCS Hot Leg                          Control feed flow and dump steam to Temperatures  LESS        THAN  350'F    .establish RCS cooldown rate less than 100'F/hr in RCS cold legs.
NOTE:  o  If auxiliary spray  is in  use, spray flow may be increased by AOV-294 and normal PRZR spray valves.
closing normal charging valve o  When  using  PRZR PORV, select  one with operable block valve.
40  Check  RCS    Pressure    LESS            Use normal PRZR  spray.
THAN 400 PSIG      [300 PSIG adverse CNMT]                  e            IF normal spray NOT available and letdown is in service, THEN use auxiliary spray.
IF  NOT, THEN use one PRZR PORV.
IF IA  NOT available,  THEN refer to Attachment  N2 PORVS.
 
EOP:              TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                      GENERATORS                          PAGE 30  of 31 STEP      ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED 41  Check Can Be IfEstablished:
RHR Normal    Cooling
: a. RCS cold leg temperature      - LESS      a. Return to Step 37 THAN  350'F RCS pressure    - LESS THAN                b. Return to Step 40.
400 psig [300 psig adverse      CNMT]
: c. Place letdown pressure controller    (PCV-135)  in  MANUAL CLOSED
: d. Check    following valves    - OPEN        d. Perform the      following:
            ~ AOV-371, letdown    isolation              1) Reset both    trains of  XY valve                                            relays for    AOV-371 and
            ~ AOV-'427, loop B cold leg to                    AOV-427 REGEN Hx                                                ')
            ~ At least one letdown orifice                    Open AOV-371 and AOV-427.
valve (AOV-200A, AOV-200B, or AOV-202)                                    3) Open one letdown      orifice valve.
: e. Verify pressure    on PI-135 - LESS        e. Return to Step 40.
THAN 400 PSIG
: f. Place  RCS  overpressure                  f. IF  RCS  overpressure    protection protection system in service                  system can    NOT  be placed  in (Refer to 0-7,    ALIGNMENT AND                service,  THEN    notify TSC  of OPERATION OF THE REACTOR VESSEL                potential  Tech Spec    violation if OVERPRESSURE PROTECTION SYSTEM)                RHR  system    is placed in service.
: g. Establish    RHR normal cooling (Refer to Attachment      RHR COOL)
 
EOP:            TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                                  GENERATORS                      PAGE 31  of  31 STEP      ACTION/EXPECTED RESPONSE              RESPONSE  NOT OBTAINED 42  Continue    RCS  Cooldown To Cold Shutdown:
: a. Maintain cooldown rate  in  RCS cold legs -  LESS THAN 100'F/HR
      ,b. Check narrow range    level in both      b. Control feed flow to maintain S/Gs - LESS THAN 50%                        narrow range level less than 50% 'n both S/Gs.
43  Check Core      Exit  T/Cs  LESS          Return to Step 42.
THAN  200'F 44  Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions
: b. Consult  TSC
                                                -END-
 
EOP:  TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS            PAGE 1  of 1 ECA-2.1 APPENDIX LIST TITLE                    PAGES
: 1)    RED PATH
 
==SUMMARY==
: 2)    FIGURE MIN SUBCOOLING
: 3)    ATTACHMENT FAULTED S/G
: 4)    ATTACHMENT CNMT RECIRC FANS
: 5)    ATTACHMENT NC 6)- ATTACHMENT RCP START
: 7)    ATTACHMENT N2 PORVS
: 8)    ATTACHMENT SEAL COOLING
: 9)    ATTACHMENT SI/UV
: 10)    ATTACHMENT D/G STOP
: 11)    ATTACHMENT SD-1
: 12)    ATTACHMENT SD-2
: 13)    ATTACHMENT RHR COOL
: 14)    ATTACHMENT AUX BLDG SW
: 15)    FOLDOUT
 
EOP:        T!TLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                        GENERATORS                  PAGE 1  of 1 RED PATH
 
==SUMMARY==
: a. SUBCRITICALITY  Nuclear power    greater than 54
: b. CORE COOLING  Core exit T/Cs greater than 1200'F
                                          -OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43% [464 adverse  CNMT]
: c. HEAT SINK  Narrow  range  level in all  S/Gs less than 54
[254 adverse  CNMT] AND  total feedwater flow less than  200 gpm
: d. INTEGRITY  Cold. leg temperatures decrease greater than 100'F 'in last 60 minutes AND RCS cold leg temperature less than 285'F
: e. CONTAINMENT  CNMT pressure. greater than,60 psig
 
EOP:                TITLE:
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1                                    GENERATORS                        PAGE 1  of  1 FIGURE MIN SUBCOOLING NOTE:    Subcooling Margin      =  Saturation Temperature      From  Figure Below  [-]  Core  Exit  T/C  Indication RC S    PRESSURE  (PSIG) 2500 2400 RCS PRESSURE 2300 INCREHENTS 20 PSIG 2200 2100 2000 1900
      '800 1700 1600 1500 1400                            SUBCOOLED 1300                              REGION 1200 1100 1000 900 800 INADEQUATE 700                                                                      SUBCOOLING 600                                                                        REGION ADVERSE CNHT 500 400 300 200                                            NORHAL CNHT                    TEHPERATURE INCREHENTS 10'F 100 0
20    0'50          300    350 EXIT 400    450 SATURATION 500 TEHPERATURE 550
('F) 600    650    700 CORE
 
EOP!          TITLE!
REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1                            GENERATORS PAGE 1  of 1 FOLDOUT PAGE
: 1. SI REINITIATION CRITERIA Manually operate SI pumps as necessary listed below occurs:
if EITHER condition o  RCS  subcooling based on core  exit TCs  LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING o  PRZR  level -  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54
[304  ADVERSE CNMT]
: 2. E-2 TRANSITION CRITERIA IF any S/G pressure increases at any time (except while performing SI termination in Steps 18 and 19), THEN go to E-2,  FAULTED STEAM GENERATOR ISOLATION,      Step 1.
: 3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. LOSS OF EMERGENCY COOLANT RECIRCULATION CRITERION IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION,    'Step 1.
: 5. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).}}

Latest revision as of 10:37, 4 February 2020

Rev 11 to EOP E-1, Loss of Reactor or Secondary Coolant.
ML17263A197
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/24/1993
From: Marlow T
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A191 List:
References
E-1, NUDOCS 9304080163
Download: ML17263A197 (194)


Text

EOP:

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 16 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE l v>>

PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

,9304080163 930330 05000244

"." PDR ADOCK P .."

PDR

P 1

g 'f

EOP:

E-1 TLTLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 2 of 16 A. PURPOSE This procedure provides actions to recover from a loss of reactor or secondary coolant.

B. ENTRY CONDITIONS/SYMPTOMS

l. ENTRY CONDITIONS This procedure is entered from:
a. E-O, REACTOR TRIP OR SAFETY INJECTION, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when a PRZR PORV is stuck open and its block valve can not be closed.
b. E-O, REACTOR TRIP OR SAFETY INJECTION, with any of the following symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.

c ~ I E 0 g REACTOR TRI P OR SAFETY NJECTION g ECA 2 1 g UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, and FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when RCS pressure is less than the shutoff head pressure of the RHR pumps or is decreasing.

d. ES-1.1, SI TERMINATION, and FR-I.2, RESPONSE TO LOW PRESSURIZER LEVEL, if SI has to be reinitiated.
e. E-2, FAULTED STEAM GENERATOR ISOLATION, after identification and isolation of a faulted S/G.

f ECA 0 ~ 2 g LOSS OF ALL AC POWER RECOVERY WITH S I REQUIRED I after normal injection mode conditions are established.

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 r established.
i. FR-H.1, RESPONSE pressure is less than TO LOSS OF SECONDARY HEAT all SINK, if non-faulted S/G(s) pressure.

RCS

j. FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, after secondary heat sink has been reestablished and all PRZR PORVs are close.

EOP: TITLE:

REV: 11 E-1 'LOSS OF REACTOR OR SECONDARY COOLANT PAGE 3 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RWST LEVEL DECREASES TO LESS THAN 28%, THEN THE SI SYSTEM SHOULD BE ALIGNED FOR COLD LEG RECIRCULATION USING ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, STEP 1.

NOTE ' FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored. (Refer to Appendix 1 for Red Path Summary.),

o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).,

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

  • 1 Monitor RCP Trip Criteria:
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 I E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 4 of 16 STEP ACTION/EXPECTED RESPONSE ~

RESPONSE NOT OBTAINED 2 Check If S/G Is Intact:

Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

o Pressure in both S/Gs - GREATER ~ Steamlines THAN 100 PSIG ~ Feedlines IF NOT, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step l.

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE: TDAFW pump flow control valves fail open on loss of IA.

  • 3 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 58 [258 adverse CNMT] than 200 gpm until narrow range level greater than 58 [258 adverse CNMT] in at least one S/G.
b. Control feed flow to maintain b. IF narrow range level in any S/G narrow range level between 178 continues to increase in an

[258 adverse CNMT] and 508 uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

W 1

N

EOP!

REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 5 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check Secondary Radiation IF steamline radiation monitors NOT Levels NORMAL available, THEN dispatch AO to locally check steamline radiation.

o Steamline radiation monitor (R-31 and R-32) IF abnormal radiation levels detected in any S/G, THEN go to o Request HP sample S/Gs for E-3, STEAM GENERATOR TUBE RUPTURE, activity Step l.

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

  • 5 Monitor PRZR PORV Status:
a. Power to PORV block valves- a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

~ MOV-515, MCC C position 6C

~ MOV-516, MCC D position 6C

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 C position 6C

~ MOV-516, MCC D position 6C

c. Block valves - AT LEAST ONE OPEN c. Open one block valve unless it was closed to isolate an open PORV.

K EOP!

E-1 TITLE LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 6 of 16

,STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

6 Reset SZ 7 Reset CI:

a. Depress CI reset pushbutton b., Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

8 .Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps running, THEN perform the following:

1) Ensure SW isolation.
2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
3) Go to Step 10.
b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)

EOP I REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 7 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR- ~ Bus 13 to Bus 14 tie

' Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT, THEN evaluate if CNMT fans should be stopped 'ECIRC (Refer to Attachment CNMT RECIRC FANS).

3) WHEN bus 15 restored, THEN reset control room lighting.

b, Verify turbine building SW b. Manually align valves.

isolation valves - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify at least two air c. Manually start air compressors compressors - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
d. Check IA supply: d. Perform the following:

o Pressure - GREATER THAN 1) Continue attempts to restore 60 PSIG IA (Refer to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 10. WHEN IA restored, THEN do Steps 9e and f.

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

f)

REV: 11 E-l. LOSS OF REACTOR OR SECONDARY COOLANT PAGE 8 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker-

'CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker- to Attachment CNMT RECIRC FANS)..

CLOSED

EOP:

REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 9 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Check If Charging Been Established:

Flow Has

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any

.RCP thermal barrier OR any RCP ¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal in)ection needle valve(s) to affected RCP:

~ V-300A for RCP A

~ V-300B for RCP B

2) Ensure HCV-142 open, demand at 0%.
b. Charging pump suction aligned to b. Manually align valves as RWST' necessary.

LCV-112B - OPEN IF LCV-112B can NOT be opened, THEN perform the following:

o LCV-112C - CLOSED

1) Verify charging pump A NOT running and place in PULL STOP.
2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
3) WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
c. Start charging pumps as necessary and adjust charging flow to restore PRZR level

lp ', ~

EOP: T1TLE:

REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 10 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If Terminated:

SI Should Be

a. RCS pressure: a. Do NOT stop SI pumps. Go to Step 14.

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 14.

USING FIGURE MIN SUBCOOLING

c. Secondary heat sink: c. IF neither condition satisfied, THEN do NOT stop SI pumps. Go o Total feed flow to intact to Step 14.

S/Gs - GREATER THAN 200 GPM

-OR-o Narrow range level in at least one intact S/G-GREATER THAN 5% [25% adverse CNMT]

d. PRZR level - GREATER THAN 5% d; Do NOT stop SI pumps'erform

[30% adverse CNMT] the following:

1) IF normal PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray.
2) Go to Step 14.

EOP s E-1 LOSS OF REACTOR OR SECONDARY COOLANT REV: ll PAGE 11 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Go To ES-1.1, SI TERMINATION/

Step 1

  • 14 Monitor Be If CNMT Spray Stopped:

Should

a. CNMT spray pumps - RUNNING a. Go to Step 15.
b. Check the following: b. Continue with Step 15. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do 'Steps 14c through f.

4 PSIG o Sodium hydroxide tank level-LESS THAN 55%

c. Reset CNMT spray
d. Check NaOH tank outlet valves- d; Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

~ AOV-836A

~ AOV-836B

e. Stop CNMT spray pumps and place in AUTO
f. Close CNMT spray pump discharge valves

~ MOV-860A

~ MOV-860B

~ MOV-860C

~ MOV~860D

C EOP: TITLE.

REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 12 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

, CAUTION o IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

o RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

  • 15 Monitor

.Be Stopped:

If RHR Pumps Should

a. Check RCS pressure:
1) Pressure - GREATER THAN 1) Go to Step 17.

250 psig [465 psig adverse CNMT]

2) RCS pressure - STABLE OR 2) Go to Step 16.

~ INCREASING

b. Stop RHR pumps and place in AUTO 16 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 100 PSIG pressure does NOT increase after faulted S/G dryout, THEN go to Step 17.
c. Check RCS pressure - STABLE OR c. Return to Step l.

DECREASING

EOP: TLTLE:

REV: 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 13 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Check If Emergency Should Be Stopped:

D/Gs

a. Verify AC emergency busses a. Perform the following:

energized by offsite power:

1) Close non-safeguards bus tie o Emergency D/G output breakers breakers as necessary:

OPEN

~ Bus 13 to Bus 14 tie o AC emergency bus voltage ~ Bus 15 to Bus 16 tie GREATER THAN 420 VOLTS

2) Place the following pumps in o AC emergency bus normal feed PULL STOP' breakers - CLOSED EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

3) Ensure condenser steam dump mode control in MANUAL.
4) Restore power to MCCs:

~ A from Bus 13

~ B from Bus 15

~ E from Bus 15 F from Bus 15

5) WHEN bus 15 restored, THEN reset control room lighting breaker.
6) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
7) Try to restore offsite power (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).
b. Stop any unloaded emergency D/G

~

and place in standby (Refer to Attachment D/G STOP)

EOP REV'1 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 14 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify CNMT Sump Recirculation Capability:

a. Check RHR system: 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 1.

ENERGIZED o MCC C - ENERGIZED o Bus 16 and bus 17-ENERGIZED o MCC D - ENERGIZED

2) RHR pumps and valves 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 be evaluated and isolated if key may'be required) necessary.

II REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 15 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Evaluate Plant Status:

a. Check auxiliary building a. Notify HP and refer to radiation - NORMAL appropriate AR-RMS procedure.

~ Plant vent iodine (R-10B) IF the cause is a loss of RCS

~ Plant vent particulate (R-13) inventory outside CNMT, THEN go

~ Plant vent gas (R-14) to .ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.

~ CCW liquid monitor (R-17)

~ LTDN line monitor (R-9)

~ CHG pump room (R-4)

b. Direct HP to obtain following samples:

~ RCS boron

~ RCS activity

~ CNMT hydrogen

~ CNMT sump boron

~ BASTs,boron

c. Verify adequate Rx head cooling:
1) Check IA to CNMT - AVAILABLE 1) Go to Step 20.
2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
3) Verify,one Rx compartment 3) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D o Manually start one fan as power supply permits

'(23 kw)

EOP:

REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 16 of 16 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If RCS Cooldown And Depressurization Is Required:

a. RCS pressure - GREATER THAN a. IF RHR pump flow greater than 250 psig [465 psig adverse CNMT] 475 gpm, THEN go to Step 21,
b. Go to ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1 21 Check If Transfer To Cold Leg Recirculation Is Required:
a. RWST level - LESS THAN 28% a. Return to Step 18.
b. Go to ES-1;3, TRANSFER TO COLD LEG RECIRCULATION, Step 1

-END-

I EOP:

REV: 11 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 E-1 APPENDIX LIST TITIZ PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) ATTACHMENT CNMT RECIRC
4) ATTACHMENT D/G STOP
5) ATTACHMENT SD-1
6) ATTACHMENT SI/UV
7) ATTACHMENT MIN SW
8) ATTACHMENT AUX BLDG SW
9) ATTACHMENT SW LOADS IN CNMT
10) FOLDOUT

EOP s E-1 T1TLE0 LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power greater than 54
b. CORE COOLING Core exit T/Cs greater than 1200'F

-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than'34 [464 adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 54

[254 adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F
e. CONTAINMENT CNMT pressure greater than 60 psig

EOP.

E-1 TITLE:

LOSS OF REACTOR OR SECONDARY COOLANT REV ll PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION ADVERS E CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10' 100 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

EOP:

REV 11 E-1 LOSS OF REACTOR OR SECONDARY COOLANT PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:

o RCS subcooling based on core exit T/Cs - LESS THAN O'F USING FIGURE MIN SUBCOOLING OR-o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%

[30% adverse CNMT]

2 ~ SI TERMINATION CRITERIA IF ALL conditions listed below occur, THEN go to ES-1.1, SI TERMINATION, Step 1:

a. RCS subcooling based on core exit T/Cs GREATER THAN 0 F USING FIGURE MIN SUBCOOLING
b. Total feed flow to intact S/Gs GREATER THAN 200 GPM OR-Narrow range level in at least one intact S/G GREATER THAN 5% [25% adverse CNMT]
c. RCS pressure:

o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]

o STABLE OR INCREASING

d. PRZR level GREATER THAN 5% [30% adverse CNMT]
3. SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
4. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step .l.
5. AFW SUPPLY SWITCHOVER CRITERION IF CST 'evel decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).
6. E-3 TRANSITION CRITERIA IF any S/G 'level increases in an uncontrolled manner or any S/G has abnormal radiation, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step l.

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 38 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW 1

PORC REVIEW DATE k'LANT SUPERINTENDENT EFFECTIV DATE CATEGORY 1.0 REVIEWED BY:

0 f IC K

c A aJ

  • t pP,

EOP: JITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 2 of 38 A. PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture (SGTR), this procedure should also be used for a SGTR in one S/G and a fault in the other S/G.

B. ENTRY CONDITIONS/SYMPTOMS

l. ENTRY CONDITIONS This procedure is entered from:
a. E-O, REACTOR TRIP OR SAFETY INJECTION, when condenser air ejector radiation or blowdown radiation is abnormal, or b ~ E 0 g REACTOR TRIP OR SAFETY INJECTION/

E 1 / LOSS OF REACTOR OR SECONDARY COOLANT g E-2, FAULTED STEAM GENERATOR ISOLATION, and FR HE 3 RESPONSE TO STEAM GENERATOR HIGH LEVELS when secondary radiation is abnormal, or

c. E-O, REACTOR TRIP OR SAFETY INJECTION/

E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g ES 1 ~ 2 g POST LOCA COOLDOWN AND DEPRESSURI ZATIONg ECA 3 ~ 3 g SGTR WITHOUT PRESSURI ZER PRESSURE CONTROLS when an intact S/G narrow range level increases in an uncontrolled manner.

d ECA 3 3~ ~ SGTR WITHOUT PRESSURI ZER PRESSURE CONTROL/

when pressurizer pressure control is restored.

e. E-1 series FOLDOUT page 'whenever either S/G level increases in an uncontrolled manner or either S/G has abnormal radiation.

~A

$ r a.a

EOP:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 3 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should be open AND monitored periodically.

o Critical Safety Function Status Trees should be monitored (Refer to Appendix 1 for Red Path Summary).

o Personnel should be available for sampling during this procedure.

o Conditions should be evaluated for Site Contingency Reporting (EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is

, greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

  • 1 Monitor RCP Trip Criteria:
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 CNMTj

d. Stop both RCPs

\

EOP:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 4 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Identify Ruptured S/G(s): Continue with Steps 6 through 11.

WHEN ruptured S/G(s) identified, o Unexpected increase in either THEN do Steps 3, 4 and 5.

S/G narrow range level

-OR-o High radiation indication on main steamline radiation monitor

~ R-31 for S/G A

~ R-32 for S/G B

-OR-o AO reports local indication of high steamline radiation

-OR-o RP reports high radiation from S/G activity sample

4 WJ

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 5 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

                        • x **** *% *******************

x CAUTION o IF THE TDAFW PUMP .IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.

o AT LEAST ONE S/G SHALL BE MAINTAINED AVAILABLE FOR RCS COOLDOWN.

3 Isolate Flow From Ruptured S/G (s):

a. Adjust ruptured S/G ARV controller to'050 psig in AUTO
b. Check ruptured S/G ARV - CLOSED b. WHEN ruptured S/G pressure less than 1050 psig, THEN verify S/G ARV closed. IF NOT closed, THEN place controller in MANUAL and close S/G ARV.

IF S/G ARV can NOT be closed, THEN dispatch AO to *locally isolate.

c. Close ruptured S/G TDAFW pump c. IF at least one MDAFW pump steam supply valve and place in running, THEN dispatch AO with PULL STOP locked valve key to locally isolate steam from ruptured S/G

~ S/G A, MOV-3505A to TDAFW pump.

~ S/G B, MOV-3504A

~ S/G A, V-3505

~ S/G B, V-3504

d. Verify ruptured S/G blowdown d. Place S/G blowdown and sample valve - CLOSED valve isolation switch to CLOSE.

~ S/G A, AOV-5738 IF blowdown can NOT be isolated

~ S/G B, AOV-5737 manually, THEN dispatch AO to locally isolate blowdown..

~ S/G A, V-5701

~ S/G B, V-5702

a1 IllI il't U

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 6 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Complete Ruptured S/G Isolation:

a. Close ruptured S/G MSIV- a. Perform the following:

RUPTURED S/G MSIV CLOSED

1) Close intact S/G MSIV.
2) Place intact S/G ARV controller at 1005 psig in AUTO.
3) Place condenser steam dump mode selector switch to MANUAL.
4) Adjust condenser steam dump controller to 1050 psig in AUTO.
5) Adjust reheat steam supply controller cam to close reheat steam supply valves.
6) Ensure turbine stop valves CLOSED.
7) Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G, parts A and B).

IF the ruptured S/G can NOT be isolated from the intact S/G, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1

b. Dispatch AO to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G part A)

L~

Qt J>;

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 7 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

                    • x * ***

a x x x x % *x x****************

CAUTION IF ANY RUPTURED S/G IS FAULTED, FEED FLOW TO THAT S/G SHOULD REMAIN ISOLATED DURING SUBSEQUENT RECOVERY ACTIONS UNLESS NEEDED FOR RCS COOLDOWN.

5 Check Ruptured S/G Level:

a. Narrow range level - GREATER a. IF ruptured S/G NOT faulted, THAN 5% [25% adverse CNMT) THEN perform the following:

l) Maintain feed flow to ruptured S/G until level greater than 5% [25% adverse CNMT).

2) Continue with Step 6. WHEN ruptured S/G level greater than 5% [25% adverse CNMT],

THEN do Steps 5b through e.

b. Close MDAFW pump discharge valv'e 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 valve valve to ruptured S/G key to locally close TDAFW pump manual feedwater isolation valve

~ S/G A, AOV-4297 to ruptured S/G.

~ S/G B, AOV-4298

~ S/G A, V-4005

~ S/G B, V-4006

e. Verify MDAFW pump crosstie e. Manually close valves.

valves - CLOSED

~ MOV-4000A

~ MOV-4000B

U~W ~p*~ga t,

r.

g'1

EOP: ijiLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 8 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

                    • x ******* *******************

x  %

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 6B).

                            • P *** x 0 x *0 ***x **************
  • 6 Monitor PRZR PORVs And Block Valves:
a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

~ MOV-515, MCC C position 6C

~ MOV-516, MCC D position 6C

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.

P'>

fg

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 9 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check If S/G Is Intact:

Secondary Side IF any S/G pressure decreasing in an uncontrolled manner OR completely depressurized, THEN o Pressure in both S/Gs - STABLE verify faulted S/G isolated unless OR INCREASING needed for RCS cooldown:

o Pressure in both S/Gs - GREATER ~ Steamlines THAN 100 PSIG ~ Feedlines IF faulted S/G NOT isolated, THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.

                    • x% ** x% x x x x ** x *****************

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

                • x 4 *  % x
  • x **x**% ******************

NOTE: TDAFW pump flow control valves fail open on loss of IA.

  • 8 Monitor Intact S/G Level:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5% [25% adverse CNMT) than 200 gpm until narrow range level greater than 5% [25%

adverse CNMT) in at least one S/G.

b. Control feed flow to maintain b. IF narrow range level in, the narrow range level between 17% intact S/G continues to increase

[25% adverse CNMT) and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

%tk Cg gt

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 10 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

                • x* x ~ *% x '.
  • x x
  • a CAUTION
  • x x**xx***x *********

IF OFFSITE POWER IS LOST AFTER SI RESET, THEN, SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

                    • ** x x x x x
  • x ***x *****************

9 Reset SI 10 Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.
                            • x x ** x x x CAUTION RCS PRESSURE SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT), THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
                    • % *****xx**x******************

11 Check Stopped:

If RHR Pumps Should Be

a. Check RCS pressure: a. Go to Step 12.

o Pressure - GREATER THAN 250 psig [465 psig adverse CNMTj o Pressure - STABLE OR INCREASING

b. Stop RHR pumps and place both in AUTO

fA

~m f

+J g

~ 'k

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 11 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If ruptured S/G needed for cooldown, isolation is not necessary.

12 Verify Ruptured S/G Isolated:

a. Check ruptured MSIV - CLOSED a. IF only intact S/G MSIV can be closed, THEN ensure air ejector/gland steam supply and flange heating steam isolated.

(Refer to ATTACHMENT RUPTURED S/G, part B).

IF neither S/G MSIV can be closed THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1

b. Ruptured S/G pressure - GREATER b. Go to ECA-3.1, SGTR WITH LOSS OF THAN 300 PSIG REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

13 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Adjust S/G ARV controllers to maintain intact S/G pressure in o Intact S/G MSIV - OPEN AUTO and go to Step 14.

o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Adjust condenser steam dump controller HC-484 to maintain intact S/G pressure and verify in AUTO
c. Place steam dump mode selector switch to MANUAL

~ s

'I

~l I

c

~i~

g V

W

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 12 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Following initiation of controlled cooldown or depressurization, RCP trip criteria is no longer applicable.

14 Initiate RCS Cooldown:

a. Determine required core exit temperature from below table RUPTURED REQUIRED CORE EXIT SG PRESSURE TEMPERATURE ('F) 1100 PSIG 525 [505 adverse CNMT) 1000 PSIG 510 [490 adverse CNMT) 900 PSIG 500 [475 adverse CNMT]

800 PSIG 485 [460 adverse CNMT) 700 PSIG 465 [440 adverse CNMT) 600 PSIG 450 [420 adverse CNMT) 500 PSIG 425 [395 adverse CNMT]

400 PSIG 405 [370 adverse CNMT) 300 PSIG 375 [330 adverse CNMT)

b. Initiate dumping steam to b. Manually or locally initiate condenser from intact S/G at steam dump from intact S/G at maximum rate maximum rate using S/G ARV.

IF no intact S/G available, THEN perform the following:

o Use faulted S/G.

-OR-o IF both S/Gs ruptured, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1

c. Core exit T/Cs - LESS THAN c. Continue with Step 15. WHEN REQUIRED TEMPERATURE core exit T/Cs less than required, THEN do Step 14d.
d. Stop RCS cooldown and maintain core exit T/Cs less than required temperature

+k

~ f

EOP: TtTLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 13 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 15 Monitor All AC Busses Perform the following:

BUSSES ENERGIZED BY OFFSITE POWER a. IF any AC emergency bus normal feed breaker open, THEN ensure o Normal feed breakers to all 480 associated D/G breaker closed.

volt busses - CLOSED

b. Perform the following as o 480 volt bus voltage - GREATER necessary:

THAN 420 VOLTS

1) Close non-safeguards bus tie o Emergency D/G output breakers breakers:

OPEN

~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:

~ EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

3) Restore power to MCCs.

~ A from Bus 13

~ B from Bus 15

~ E from Bus 15

~ F from Bus 15

4) Start CNMT RECIRC fans as necessary.
5) WHEN bus 15 restored, THEN reset control room lighting.
c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

pffft'Illp%

~I 4,

r l ~

EOP:

REV'5 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 14 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps running, THEN:

1) Ensure SW isolation.
2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
3) Go to Step 18.
b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)

<,1 $y 4s 4

hPW jf-Qy

'"9,,

t 4

'X;i

EOP:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 26 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 Verify Adequate SW Flow To CCW Hx:

a. Verify at least three SW pumps a. Manually start pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps can be operated, THEN go to Step 37.

b. Verify AUX BLDG SW isolation b. Establish SW to AUX BLDG (Refer valves - AT LEAST ONE SET OPEN to Attachment AUX BLDG SW).

~ MOV-4615 and MOV-4734

~ MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

4 I

P

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 27 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Check If Normal Operation CVCS Can Be Established

a. Verify IA restored: a. Continue with Step 37. WHEN IA restored, THEN do Steps 31 o IA to CNMT (AOV-5392) - OPEN through 36.

o IA pressure - GREATER THAN 60 PSIG

b. Verify instrument bus D b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:
1) Verify MCC A energized.
2) Place instrument bus D on maintenance supply.
c. CCW pumps - ANY RUNNING c. Perform the following:
1) IF any RCP tl seal outlet temperature offscale high, THEN isolate CCW to thermal barrier of affected RCP(s).

~ RCP A, MOV-749A and MOV-759A

~ RCP B, MOV-749B and MOV-759B

2) Manually start one CCW pump.
d. Charging pump - ANY RUNNING d. Continue with Step 37. WHEN any charging pump running, THEN do Steps 32 through 36.

I '1

'r I V I

IWg

EOP: JIZLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 28 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 Check Should IfBe Seal Return Flow Established:

a. Verify RCP ¹1 seal outlet a. Go to Step 33.

temperature - LESS THAN 235'F

b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.

~ AOV-270A

~ AOV-270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
d. Open RCP seal return isolation d. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.
2) Dispatch AO with key to RWST gate to locally open MOV-313.
e. Verify RCP ¹1 seal leakoff flow e. IF any RCP seal leakoff flow LESS THAN 5.5 GPM greater than 5.5 gpm, THEN:

o Close the affected RCP seal discharge valve

~ RCP A, AOV-270A

~ RCP B, AOV-270B o Trip the affected RCP IF both RCP seal discharge valves are shut, THEN go to Step 33.

f. Verify RCP ¹1 seal leakoff flow f. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.25 GPM MALFUNCTION.

~I ~ .

I.'

4 Al tg

~Ck

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 29 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 33 Verify PRZR Level GREATER Continue with Step 35. WHEN PRZR THAN 13% [40: adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Step 34.

34 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Establish charging line flow to letdown as follows:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Place the following switches to valve, AOV-312, to NORMAL.

CLOSE:

o Ensure CCW from excess letdown

~ Letdown orifice valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) o Open excess letdown isolation

~ Letdown isolation valve AOV-371 valve AOV-310.

~ Loop B cold leg to REGEN Hx AOV-427 o Slowly open HCV-123 to maintain excess letdown temperature less

c. Place letdown controllers in than 195'F and pressure less MANUAL at 40% open than 100 psig.

~ TCV-130 o Adjust charging pump speed as

~ PCV-135 necessary.

d. Reset both trains of XY relays IF RCP seal return NOT established, for AOV-371 and AOV-427 THEN consult TSC to determine if excess letdown should be placed in
e. Open AOV-371 and AOV-427 service.
f. Open letdown orifice valves as necessary
g. Place TCV-130 in AUTO at 105'F
h. Place PCV-135 in AUTO at 250 psig
i. Adjust charging pump speed and HCV-142 as necessary

A h

EOP:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 30 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
b. Verify the following: b. Adjust controls as necessary.
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
c. Check VCT level: c. 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.

I> ~ M t~,

M.lt Cg~a

~ I~ 4P h

~4

EOP:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 31 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 37. WHEN VCT level greater than 40%,

THEN do Step 36b.

b. Verify charging pumps aligned to b. Manually align valves as VCT necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED

Pp

<<4.

ig

%1EP

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 32 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

                            • x ** *x x x x CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
      • xx*******xxxxxxx*xx*x*xx****x*****
  • 37 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage:
a. Perform appropriate action(s) from table:

PRZR RUPTURED S/G NARROW RANGE LEVEL LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13% o Increase RCS Increase RCS o Increase RCS

[40% ADVERSE CNMTJ makeup flow makeup flow makeup flow o Depressurize RCS o Maintain RCS and using Step 37b ruptured S/G pressure equal BETWEEN 13% Depressurize RCS Energize Maintain RCS and

[40% ADVERSE CNMT) using Step 37b PRZR ruptured S/G AND 50% heaters pressure equal BETWEEN 50% AND 75% o Depressurize RCS Energize Maintain RCS and

[65% ADVERSE CNMTj using Step 37b PRZR ruptured S/G heaters pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS and

[65% ADVERSE CNMT] makeup flow PRZR ruptured S/G heaters pressure equal

b. Control pressure using normal b. IF letdown is in service, THEN PRZR spray, if available, to use auxiliary spray (AOV-296).

obtain desired results for IF NOT, THEN use one PRZR PORV.

Step 37a

I')~4 N

1g

'0'1I+

S

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 33 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check Should IfBe Emergency D/Gs Stopped:

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

o Emergency D/G output breakers OPEN o AC emergency bus voltage GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP).

Minimize Secondary System 50'.

39 Contamination:

a. Isolate reject from hotwell to IF hotwell level increasing, CST: THEN direct RP to sample hotwells for activity.

o Place hotwell level controller (LC-107) in MANUAL at o Verify hotwell level - STABLE

b. Check status of local actions to complete ruptured S/G isolation (Refer to Attachment RUPTURED S/G)

l I h

EOP:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 34 of 38 STEP ACTION/EXPECTED'ESPONSE RESPONSE NOT OBTAINED 40 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 41 Check RCP Cooling: Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).

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

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 35 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

            • xx x*0 xxxxx%xx'xx%'*x4***x****x*******

CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.

                        • 4 *4 x x w * ~ *********** *'* * * * * * * *
  • 42 Check RCP Status:
a. RCPs - AT LEAST ONE RUNNING a. Perform the following:
1) Try to start one RCP:

a) Ensure conditions for starting an RCP.

o Bus llA or 11B energized.

o Refer to Attachment RCP START.

b) IF RVLIS level (no RCPs) less than 95%, THEN perform the following:

o Increase PRZR level to greater than 65% (80%

adverse CNMTj.

o Dump steam to establish RCS subcooling based on core exit T/Cs to greater than 20'F using Figure MIN SUBCOOLING.

c) Start one RCP.

2) IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation can NOT be verified, THEN increase dumping steam.

b. Stop all but one RCP

J ig$ V ~w II

'gl e

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 36 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

43 Check If Source Detectors Should Range Be Energized:

a. Source range channels a. Go to Step 43e.

DEENERGIZED

b. Check intermediate range flux b. Perform the following:

EITHER CHANNEL LESS THAN 10 10 AMPS 1) IF neither intermediate range channel is decreasing, THEN initiate boration.

2) Continue with Step 44. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 43c through e.
c. Check the following: c. Continue with Step 44. WHEN either condition met, THEN do o Both intermediate range Steps 43d and e.

channels - LESS THAN 10 10 AMPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can'OT be restored, THEN refer to ER-NIS.1, SR MALFUNCTION and go to Step 44.

e. Transfer Rk-45 recorder to one source range and one intermediate range channel

I 4Q A~

EOP: TITLE:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 37 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 44 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.
b. Perform the following:

i o Open generator disconnects

~ 1G13A71

~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump

c. Verify adequate Rx head cooling:
1) Check IA to CNMT - AVAILABLE 1) Go to Step 45.
2) Verify at least one control 2) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
3) Verify one Rx compartment 3) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD COMPLETE

~m ,~

~l

~l,

EOP: LITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 38 of 38 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 45 Consult TSC To Determine Appropriate Post-SGTR Cooldown Procedure:

o Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1

-OR-o Go to ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1

-OR-o Go to ES-'3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1

-END-

~ lt 4

elhi 7

X

EOP:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 E-3 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) ATTACHMENT CNMT RECIRC FANS
4) ATTACHMENT D/G STOP
5) ATTACHMENT N2 PORVS
6) ATTACHMENT NC
7) ATTACHMENT SEAL COOLING
8) ATTACHMENT RCP START
9) ATTACHMENT RUPTURED S/G
10) ATTACHMENT SD-1
11) ATTACHMENT SD-2
12) ATTACHMENT AUX BLDG SW
13) FOLDOUT

4 EOP:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY Nuclear power greater than 5~
b. CORE COOLING Core exit T/Cs greater than 1200'F

-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43~~ [464 adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 54

[25< adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F
e. CONTAINMENT CNMT pressure greater than 60 psig

'p V'

,II Ijf r'-

Il+

~" I

'~ f c

I, I

~ 4

EOP: TITLE:

REV 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below t'-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 2300 RCS PRESSURE INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION DV ERS E C 500 400 300 200 NORMAL CNMT TEMPERATURE 100 INCREMENTS 10'F 0

200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE (')

J'-

EOP:

REV: 15 E-3 STEAM GENERATOR TUBE RUPTURE PAGE 1 of 1 FOLDOUT PAGE SI REINITIATION CRITERIA IF either condition listed below occurs, THEN operate SI pumps manually as necessary and go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1:

o RCS subcooling based on core exit T/Cs LESS THAN 0 F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [304 adverse CNMT).

2 4 SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.

3 ~ COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step l.

4. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
5. MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

tel 5t

EOP: T1TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ' GENERATORS PAGE 1 of 31 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RES 0 SIBLE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY

EOP: TLTLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA 1 GENERATORS PAGE 2 of 31 A. PURPOSE This procedure provides actions to mitigate and minimize a loss of secondary coolant from both steam generators.

B. ENTRY CONDITIONS/SYMPTOMS 1- ENTRY CONDITIONS This procedure is entered from:

a. E-2, FAULTED STEAM GENERATOR ISOLATION, when an uncontrolled depressurization of both steam generators occurs.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATZON OF BOTH STEAM ECA-2.1 GENERATORS PAGE 3 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF THE TDAFW PUMP IS THE ONLY AVAILABLE SOURCE OF FEED FLOW, THEN STEAM SUPPLY TO THE TDAFW PUMP MUST BE MAINTAINED FROM ONE S/G.

NOTE: o FOLDOUT page should be open AND monitored periodically.

o Conditions should be evaluated for Site Contingency Reporting (Refer to EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+ R/hr.

1 Check Secondary Pressure Manually close valves one loop at a Boundary: time.

o MSIVs - CLOSED IF valves can NOT be closed, THEN dispatch AO to locally isolate o MFW flow control valves - CLOSED flowpaths, as necessary, one loop at a time.

~ MFW regulating valves

~ MFW bypass valves o MFW pump discharge valves CLOSED V

o S/G blowdown and sample valves CLOSED o TDAFW pump steam supply valves PULL STOP o TDAFW pump flow control valves CLOSED o S/G ARVs - CLOSED o Dispatch AO to locally isolate S/Gs (Refer to Attachment FAULTED S/G)

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 4 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION A MINIMUM FEED FLOW OF 50 GPM MUST BE MAINTAINED TO EACH S/G WITH A NARROW RANGE LEVEL LESS THAN 5% [25% ADVERSE CNMT].

2 Control Feed Flow To Minimize RCS Cooldown:

a. Check cooldown rate in RCS cold a. Decrease feed flow to 50 gpm to legs -'ESS THAN 100'F/HR each S/G and go to Step 2c.
b. Check narrow range level in both b. Control feed flow to maintain S/Gs - LESS THAN 50% narrow range level less than 50%

in both S/Gs.

c. Check RCS hot leg temperatures c. Control feed flow or dump steam STABLE OR DECREASING to stabilize RCS hot leg temperatures.

3 Check Stopped:

If RCPs Should Be

a. RCP status - ANY RCP RUNNING a. Go to Step 4.
b. SI pumps - AT LEAST TWO RUNNING b. Go to Step 4.
c. RCS pressure minus maximum S/G Go to Step 4.

pressure - LESS THAN 175 psig

[400 psig adverse CNMT]

d. Stop both RCPs

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 5 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check CST Level GREATER 'witch to alternate AFW suction THAN 5 FEET supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

CAUTION IF ANY PRZR PORV OPENS BECAUSE OF HIGH PRZR PRESSURE, IT SHOULD BE CLOSED AFTER PRESSURE DECREASES TO LESS THAN 2335 PSIG (REFER TO STEP 5B).

  • 5 Monitor PRZR PORVs And Block Valves:
a. Power to PORV block valves a. Restore power to block valves AVAILABLE unless block valve was closed to isolate an open PORV:

~ MOV-515, MCC C position 6C

~ MOV-516, MCC D position 6C

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 C position 6C

~ MOV-516, MCC D position 6C

c. Block valves - AT LEAST ONE OPEN c.'Open one block valve unless it was closed to isolate an open PORV.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 6 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Secondary Radiation Go to E-3, STEAM GENERATOR TUBE Levels NORMAL RUPTURE, Step l.

o Steamline radiation monitor (R-31 and R-32) o Dispatch AO to locally check steamline radiation o Request RP sample S/Gs for activity CAUTION IF OFFSITE POWER IS LOST AFTER SI RESET, THEN SELECTED SW PUMPS AND ONE CCW PUMP WILL AUTO START ON EMERGENCY D/G. MANUAL ACTION WILL BE REQUIRED TO RESTART SAFEGUARDS EQUIPMENT.

7 Reset SI

EOP: TITLE:

REV 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 7 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS PRESSURE SHOULD BE MONITORED. IF .RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THEN THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.

  • 8 Monitor Be If Stopped:

RHR Pumps Should

a. RHR pumps - ANY RUNNING a. Go to Step 9.
b. Check RCS Pressure:
1) Pressure - GREATER THAN 1) Go to E-l, LOSS OF REACTOR OR 250 psig [465 psig adverse SECONDARY COOLANT, Step 1.

CNMT]

2) Pressure - STABLE OR 2) Go to Step 9.

INCREASING

c. Stop RHR pumps and place in AUTO

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 8 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 9 Monitor Be Stopped:

If CNMT Spray Should

a. CNMT spray pumps - RUNNING a. Go to Step 10.
b. Check the following: b. Continue with Step 10. WHEN BOTH conditions satisfied, THEN o CNMT pressure - LESS THAN do Steps 9c through f.

4 PSIG o Sodium hydroxide tank level LESS THAN 55%

c. Reset CNMT spray
d. Check NaOH tank outlet valves d. Place NaOH tank outlet valve CLOSED controllers to MANUAL and close valves.

~ AOV-836A

~ AOV-836B ~ AOV-836A

~ AOV-836B

e. Stop CNMT spray pumps and place in AUTO
f. Close CNMT spray pump discharge valves

~ MOV-860A

~ MOV-860B

~ MOV-860C

~ MOV-860D,

l~

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 9 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Check RWST Level GREATER Go to ES-1.3, TRANSFER TO COLD LEG THAN 284 RECIRCULATION, Step l.

ll Reset CI:

a. Depress CI reset pushbutton
b. Verify annunciator A-26, CNMT b. Perform the following:

ISOLATION - EXTINGUISHED

1) Reset SI.
2) Depress CI reset pushbutton.

12 Verify Adequate SW Flow:

a. Check at least two SW pumps a. Manually start SW pumps as power RUNNING supply permits (258 kw each).

IF less than two SW pumps running, THEN perform the following:

1),Ensure SW isolation.

2) Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)
3) Go to Step 14.
b. Dispatch AO to establish normal shutdown alignment (Refer to Attachment SD-1)

EOP: T!TLE:

REV: 12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 10 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Establish IA to CNMT:

a. Verify non-safeguards busses a. Perform the following:

energized from offsite power

1) Close non-safeguards bus tie o Bus 13 normal feed - CLOSED breakers:

-OR- ~ Bus 13 to Bus 14 tie

~ Bus 15 to Bus 16 tie o Bus 15 normal feed - CLOSED

2) Verify adequate emergency D/G capacity to run air compressors (75 kw each).

IF NOT, THEN evaluate RECIRC fans should be if CNMT stopped (Refer to Attachment CNMT RECIRC FANS).

3) WHEN bus 15 restored, THEN reset control room lighting.
b. Verify SW isolation valves to b. Manually align valves.

turbine building - OPEN

~ MOV-4613 and MOV-4670

~ MOV-4614 and MOV-4664

c. Verify at least two air c. Manually start air compressors compressors - RUNNING as power supply permits (75 kw each). IF air compressors can NOT be started, THEN dispatch AO to locally reset compressors as necessary.
d. Check IA supply: d. Perform the following:

o Pressure - GREATER THAN 1) C'ontinue attempts to restore 60 PSIG IA (Refer,to AP-IA.1, LOSS OF INSTRUMENT AIR).

o Pressure - STABLE OR INCREASING 2) Continue with Step 14. WHEN IA restored, THEN do Steps 13e and f.

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

EOP: T!TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ' GENERATORS PAGE 11 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If SI Isolated:

ACCUMs Should Be

a. Both RCS hot leg temperatures a. Go to Step 15.

LESS THAN 400'F

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 15 Check Normal Power Available Verify adequate emergency D/G To Charging Pumps: capacity to run charging pumps (75 kw each).

o Bus 14 normal feed breaker CLOSED IF NOT, THEN evaluate if CNMT RECIRC fans can be stopped (Refer o Bus 16 normal feed breaker- to.Attachment CNMT RECIRC FANS).

CLOSED

EOP; T!TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 12 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Charging Flow Has Been Established:

a. Charging pumps - ANY RUNNING a. Perform the following:
1) IF CCW flow is lost to any RCP thermal barrier OR any RCP ¹1 seal outlet temperature offscale high, THEN dispatch AO with key to RWST gate to close seal injection needle valve(s) to affected RCP:

~ RCP A, V-300A

~ RCP B, V-300B

2) Ensure HCV-142 open, demand at Oa.
b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST: THEN perform the following:

o LCV-112B - OPEN 1) Verify charging pump A NOT running and place in PULL o LCV-112C - CLOSED STOP.

2) Dispatch AO to locally open manual charging pump suction from RWST (V-358 located in charging pump room).
3) WHEN V-358 open, THEN direct AO to close V-268 to isolate charging pumps B and C from VCT (V-268 located in charging pump room).
c. Start charging pumps as

'ecessary and adjust charging flow to restore PRZR level

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 13 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 17 Monitor SI Termination Criteria:

pumps'

a. SI pumps - ANY RUNNING a. Go to Step 19.
b. Check RCS pressure: b. DO NOT stop SI ,

Perform the following:

o Pressure - GREATER THAN 1625 psig [1825 psig adverse 1) Energize PRZR heaters and CNMT] operate PRZR spray as necessary to stabilize RCS o Pressure - STABLE OR pressure greater than INCREASING 1625 psig [1825 psig adverse CNMT)

2) Return to Step 2.
c. RCS subcooling based on core c. DO NOT stop SI pumps. Return to exit T/Cs - GREATER THAN O' Step 2.

USING FIGURE MIN SUBCOOLING

d. PRZR level - GREATER THAN 5% d. Do NOT stop SI pumps. Perform

[30% adverse CNMT) the following:

1) IF normal 'PRZR spray available, THEN try to stabilize RCS pressure with PRZR spray,
2) Return to Step 17a.

NOTE: Foldout Page E-2 transition criteria does not apply while performing steps 18 and 19.

18 Stop SI and RHR Pumps And Place In Auto

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA 2. 1 GENERATORS PAGE 14 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 19 Monitor SI Reinitiation Criteria:
a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary and return to Step 2.

USING FIGURE MIN SUBCOOLING

b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT] maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually operate SI pumps as necessary and return to Step 2.

20 Check RCS Hot Leg Control feed flow or dump steam to Temperatures STABLE OR stabilize RCS hot leg temperatures.

DECREASING 21 Check Narrow Range Level In Control feed flow to maintain Both S/Gs LESS THAN 504 narrow range level less than 50% in both S/Gs.

22 Verify Adequate SW Flow To CCW Hx:

a. Verify at least two SW pumps a. Manually start pumps as power RUNNING supply permits (258 kw per pump). IF less than two SW pumps can be operated, THEN go to Step 28
b. Verify AUX BLDG SW isolation Establish SW to AUX BLDG (Refer valves - OPEN to Attachment AUX BLDG SW).

~ MOV-4615 and MOV-4734

~ MOV-4616 and MOV-4735

c. Verify CNMT RECIRC fan c. Dispatch AO to locally throttle annunciator C-2, HIGH flow to CCW Hx to between TEMPERATURE AIARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 15 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check If Normal CVCS Operation Can Be Established

a. Verify IA restored: a. Continue with Step 28. WHEN IA restored, THEN do Steps 23 o IA to CNMT (AOV-5392) - OPEN through 27.

o IA pressure - GREATER THAN 60 PSIG

b. Verify instrument bus D- b. Energize MCC B. IF MCC B NOT ENERGIZED available, THEN perform the following:
1) Verify MCC A energized.
2) Place instrument bus D on maintenance supply.
c. CCW pumps - ANY RUNNING c. Perform the following:
1) IF any RCP ¹1 seal outlet f

temperature of scale high, THEN isolate CCW to thermal barrier of affected RCP(s).

~ RCP A, MOV-749A and MOV-759A

~ RCP B, MOV-749B and MOV-759B

2) Manually start one CCW pump.
d. Charging pump - ANY RUNNING d. Continue with Step 28. WHEN any charging pump running, THEN do Steps 24 through 27.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 16 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Verify PRZR Level GREATER Continue with Step 26. WHEN PRZR THAN 134 [40% adverse CNMT] level increases to greater than 13%

[40% adverse CNMT], THEN do Step 25.

25 Establish Normal Letdown: IF RCP seal return has been established, THEN establish excess

a. Verify charging line flow to letdown as follows:

REGEN Hx - GREATER THAN 20 GPM o Place excess letdown divert

b. Place the following switches to valve, AOV-312, to NORMAL.

CLOSE:

o Ensure CCW from excess letdown

~ Letdown orifice'valves open, (AOV-745).

(AOV-200A, AOV-200B, and AOV-202) o Open excess letdown isolation

~ AOV-371, letdown isolation AOV-310. 'alve valve

~ AOV-427, loop B cold leg to o Slowly open HCV-123 to maintain REGEN Hx excess letdown temperature less than 195'F and pressure less

c. Place letdown controllers in than 100 psig.

MANUAL at 40% open o Adjust charging pump speed as

~ TCV-130 necessary.

~ PCV-135 IF RCP seal return NOT established,

d. Reset both trains of XY relays THEN consult TSC to determine if for AOV-371 and AOV-427 excess letdown should be placed in service.
e. Open AOV-371 and AOV-427
f. Open letdown orifice valves as necessary
g. Place TCV-130 in AUTO at 105'F
h. Place PCV-135 in AUTO at 250 psig
i. Adjust charging pump speed and HCV-142 as necessary

EOP: T1TLE REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 17 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Check VCT Makeup System:

a. Adjust boric acid flow control valve in AUTO to 9.5 gpm
b. Adjust RMW flow control valve in AUTO to 40 gpm
c. Verify the following: c. Adjust controls as necessary.
1) RMW mode selector switch in AUTO
2) RMW control armed - RED LIGHT LIT
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.

EOP: TITLE:

REV 12 UNCONTROLLED DEPRESSURXZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 18 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check Charging Pump Suction Aligned To VCT:

a. VCT level - GREATER THAN 20% a. IF VCT level can NOT be maintained greater than 5%, THEN perform the following:
1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed
2) Continue with Step 28. WHEN VCT level greater than 40%,

THEN do'tep'7b.

b. Verify charging pumps aligned to b. Manually align valves as VCT: necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED

EOP: TITLES REV 12 UNCONTROLLED DEPRESSURXZATZON OF BOTH STEAM ECA-'2. 1 GENERATORS PAGE 19 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 28 Check RCP Cooling: Establish normal cooling to RCPs

~

(Refer to Attachment SEAL COOLING).

a. Check CCW to RCPs:

o Annunciator A-7, RCP lA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED

b. Check'RCP seal injection:

o Labyrinth seal D/Ps - GREATER THAN 15 INCHES OF WATER

-OR-o RCP seal injection flov to each RCP - GREATER THAN 6 GPM

EOP: T1TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 20 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 Check If Seal Return Flow Should Be Established:

a. Verify RCP ¹1 seal outlet a. Go to Step 30.

temperature - LESS THAN 235'F

b. Verify RCP seal outlet valves b. Manually open valves as OPEN necessary.

~ AOV-270A

~ AOV-270B

c. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
d. Open RCP seal return isolation d. Perform the following:

valve MOV-313

1) Place MOV-313 switch to OPEN.
2) Dispatch AO with key to RWST gate to locally open MOV-313.
e. Verify RCP ¹1 seal leakoff flow e. Perform the following:

LESS THAN 6.0 GPM

1) Trip the affected RCP
2) Allow 4 minutes for pump coast down, THEN close the affected RCP seal discharge valve

~ RCP A, AOV-270A

~ RCP B, AOV-270B IF both RCP seal discharge valves are shut, THEN go to Step 30.

f. Verify RCP ¹1 seal leakoff flow f. Refer to AP-RCP.1, RCP SEAL GREATER THAN 0.8 GPM MALFUNCTION.

EOP: TITLE:

UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM REV: 12 ECA-2. 1 GENERATORS PAGE 21 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.

o When using PRZR PORV, select one with an operable block valve.

30 Energize Heaters And Operate IF normal'pray NOT available and Normal Spray As Necessary To letdown is in service, THEN use Maintain RCS Pressure Stable auxiliary spray valve (AOV-296).

IF PRZR spray NOT'vailable', THEN use one PRZR PORV.

IF IA NOT available, THEN refer to Attachment N2 PORVS.

C EOP:

ECA-2.1'1ILE:

UNCONTROLLED REV 12 DEPRESSURIZATION OF BOTH STEAM GENERATORS PAGE 22 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 Verify All, AC Busses Perform the following:

ENERGIZED BY OFFSITE PONER

a. IF any AC emergency bus normal o Normal feed breakers to all 480 feed breaker open, THEN ensure volt busses - CLOSED associated D/G breaker closed.

o 480 bus voltage - GREATER THAN b. Perform the following, as 420 VOLTS necessary:

o Emergency D/G output breakers 1) Close non-safeguards bus tie OPEN breakers:

~ Bus 13 to Bus 14 tie

~ 'Bus 15 to Bus 16 tie

2) Place the following pumps in PULL STOP:

~ EH pumps

~ Turning gear oil pump

~ HP seal oil backup pump

3) Restore power to MCCs.

~ A from Bus 13 4 B from Bus 15

~ E from Bus 15

~ F from Bus 15

4) WHEN bus 15 restored, THEN reset control room lighting..
5) Refer to Attachment SI/UV for other equipment lost with loss of offsite power.
c. Try to restore offsite power to all AC busses (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

I EOP: T!TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 1 GENERATORS PAGE 23 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATIONS 32 Check RCP Status ONE RUNNING

'T LEAST Try to start one RCP:

a. Establish conditions for starting an RCP.

o Bus 11A or 11B energized I

o Refer to Attachment RCP START.

b. Start one RCP.

IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).

IF natural circulation can NOT be verified, THEN increase feed flow or dumping steam.

ilk EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 24 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

33 Check If Source Detectors Should Range Be Energized:

a. Source range channels a. Go to Step 33e.

DEENERGIZED

b. Check intermediate, range flux- b. Perform the following:

EITHER CHANNEL LESS THAN 10 10 AMPS 1) IF neither intermediate range channel is decreasing THEN initiate boration.

2) Continue with Step 34. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 33c, d and e.
c. Check the following: c. Continue with step 34. WHEN either condition met, THEN do o Both intermediate range Steps 33d and e.

channels - LESS THAN 10-10 AMPS

-OR-o Greater than 20 minutes since reactor trip

d. Verify source range detectors d. Manually energize source 'range ENERGIZED detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).

IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 34.

e. Transfer Rk-45 recorder 'to one source range and one intermediate range channel.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 25 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check If Emergency Should Be Stopped:

D/Gs

a. Verify AC emergency busses a. Try to restore offsite power energized by offsite power: (Refer to ER-ELEC.1, RESTORATION OF OFFSITE POWER).

o Emergency D/G output breakers OPEN o AC emergency bus voltage GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers - CLOSED

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 26 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 Establish Normal Shutdown Alignment:

a. Check condenser - AVAILABLE a. Dispatch AO to perform Attachment SD-2.

b, Perform the following:

o Open generator disconnects

~ 1G13A71

~ 9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cam to close valves o Place reheater dump valve switches to HAND o Stop all but one condensate pump

c. Verify adequate Rx head cooling:
1) Verify at least one control 1) Manually start one fan as rod shroud fan - RUNNING power supply permits (45 kw)
2) Verify one Rx compartment 2) Perform the following:

cooling fan - RUNNING o Dispatch AO to reset UV relays at MCC C and MCC D.

o Manually start one fan as power supply permits (23 kw)

d. Verify Attachment SD COMPLETE

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1 GENERATORS PAGE 27 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 Maintain Plant Conditions Control plant systems as necessary STABLE to maintain conditions stable.

o RCS pressure o PRZR level o RCS temperatures

  • 37 Monitor SI Reinitiation Criteria:
a. RCS subcooling based on core a. Manually operate SI pumps as exit T/Cs - GREATER THAN O' necessary. Return to Step 2.

USING FIGURE MIN SUBCOOLING

b. PRZR level - GREATER THAN 5% b. Control charging flow to

[30% adverse CNMT) maintain PRZR level.

IF PRZR level can NOT be maintained, THEN manually operate SI pumps as necessary.

Return to Step 2 ~

'I

'4

EOP: T1TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-F 1 GENERATORS PAGE 28 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 Check Isolated:

If SI ACCUMs Should Be

a. Check the following: a. Go to Step 39.

o RCS subcooling based on core exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5%

[30% adverse CNMT]

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: T!TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2 ~ 1 GENERATORS PAGE 29 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 Check RCS Hot Leg Control feed flow and dump steam to Temperatures LESS THAN 350'F .establish RCS cooldown rate less than 100'F/hr in RCS cold legs.

NOTE: o If auxiliary spray is in use, spray flow may be increased by AOV-294 and normal PRZR spray valves.

closing normal charging valve o When using PRZR PORV, select one with operable block valve.

40 Check RCS Pressure LESS Use normal PRZR spray.

THAN 400 PSIG [300 PSIG adverse CNMT] e IF normal spray NOT available and letdown is in service, THEN use auxiliary spray.

IF NOT, THEN use one PRZR PORV.

IF IA NOT available, THEN refer to Attachment N2 PORVS.

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 30 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 41 Check Can Be IfEstablished:

RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Return to Step 37 THAN 350'F RCS pressure - LESS THAN b. Return to Step 40.

400 psig [300 psig adverse CNMT]

c. Place letdown pressure controller (PCV-135) in MANUAL CLOSED
d. Check following valves - OPEN d. Perform the following:

~ AOV-371, letdown isolation 1) Reset both trains of XY valve relays for AOV-371 and

~ AOV-'427, loop B cold leg to AOV-427 REGEN Hx ')

~ At least one letdown orifice Open AOV-371 and AOV-427.

valve (AOV-200A, AOV-200B, or AOV-202) 3) Open one letdown orifice valve.

e. Verify pressure on PI-135 - LESS e. Return to Step 40.

THAN 400 PSIG

f. Place RCS overpressure f. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PROTECTION SYSTEM) RHR system is placed in service.
g. Establish RHR normal cooling (Refer to Attachment RHR COOL)

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 31 of 31 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 42 Continue RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR

,b. Check narrow range level in both b. Control feed flow to maintain S/Gs - LESS THAN 50% narrow range level less than 50% 'n both S/Gs.

43 Check Core Exit T/Cs LESS Return to Step 42.

THAN 200'F 44 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions
b. Consult TSC

-END-

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS PAGE 1 of 1 ECA-2.1 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) ATTACHMENT FAULTED S/G
4) ATTACHMENT CNMT RECIRC FANS
5) ATTACHMENT NC 6)- ATTACHMENT RCP START
7) ATTACHMENT N2 PORVS
8) ATTACHMENT SEAL COOLING
9) ATTACHMENT SI/UV
10) ATTACHMENT D/G STOP
11) ATTACHMENT SD-1
12) ATTACHMENT SD-2
13) ATTACHMENT RHR COOL
14) ATTACHMENT AUX BLDG SW
15) FOLDOUT

EOP: T!TLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 1 of 1 RED PATH

SUMMARY

a. SUBCRITICALITY Nuclear power greater than 54
b. CORE COOLING Core exit T/Cs greater than 1200'F

-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43% [464 adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 54

[254 adverse CNMT] AND total feedwater flow less than 200 gpm

d. INTEGRITY Cold. leg temperatures decrease greater than 100'F 'in last 60 minutes AND RCS cold leg temperature less than 285'F
e. CONTAINMENT CNMT pressure. greater than,60 psig

EOP: TITLE:

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2.1 GENERATORS PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREHENTS 20 PSIG 2200 2100 2000 1900

'800 1700 1600 1500 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION ADVERSE CNHT 500 400 300 200 NORHAL CNHT TEHPERATURE INCREHENTS 10'F 100 0

20 0'50 300 350 EXIT 400 450 SATURATION 500 TEHPERATURE 550

('F) 600 650 700 CORE

EOP! TITLE!

REV: 12 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM ECA-2. 1 GENERATORS PAGE 1 of 1 FOLDOUT PAGE

1. SI REINITIATION CRITERIA Manually operate SI pumps as necessary listed below occurs:

if EITHER condition o RCS subcooling based on core exit TCs LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54

[304 ADVERSE CNMT]

2. E-2 TRANSITION CRITERIA IF any S/G pressure increases at any time (except while performing SI termination in Steps 18 and 19), THEN go to E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
3. COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4. LOSS OF EMERGENCY COOLANT RECIRCULATION CRITERION IF emergency coolant recirculation is established and subsequently lost, THEN go to ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, 'Step 1.
5. AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.l, ALTERNATE WATER SUPPLY TO AFW PUMPS).