ML17262A349: Difference between revisions

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


=Text=
=Text=
{{#Wiki_filter:ECP: AP-RCS.3 TITLE: HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 1 of 5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 40 P T SUPER NT NDENT-cgQ-9b EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY: 9i0207008i 9i020i l PDR ADDCK 050002m<PDR  
{{#Wiki_filter:ECP:           TITLE:                                        REV: 5 AP-RCS.3             HIGH REACTOR COOLANT ACTIVITY PAGE 1 of 5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE       40 P   T SUPER NT NDENT
/P Q'1II t 1~k EOP,: AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 2 of 5 A.PURPOSE-This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.B.ENTRY CONDITIONS/SYMPTOMS 1.SYMPTOMS-The symptoms of HIGH REACTOR COOLANT ACTIVITY are;a.Unexplained increase in letdown line monitor, R-9, or b.Sampling indicates I-131 equivalent GREATER THAN 0.2 uCi/gm, or c.Sampling indicates gross degassed activity GREATER THAN 20 uCi/gm, or d.Sampling indicates that total specific activity exceeds 84/E.  
                                          - cgQ-9b EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
~'g(,""
9i0207008i 9i020i PDR l         ADDCK 050002m<
AP-RCS.3 TITLE: HIGH REACTOR COOLANT ACTIVITY REV 5 PAGE 3 of 5 STEP ACTION/BXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************
PDR
CAUTION IF LETDOWN PLOW EXCEEDS 60 GPM WHEN USING AOV-202, D/P ACROSS THE CVCS DBMINERALIZERS SHOULD BE MONITORED TO VERIPY THAT FLOW IS CONTINUING THROUGH THE DI'S.HOWEVER, FLOW THROUGH THE DI'S SHOULD NOT EXCEED 90 GPM.1 Verify RCS Activity: a.Direct HP-TO SAMPLE RCS FOR ACTIVITY b.RCS activity-GREATER THAN NORMAL (Check with HP Department for normal activity)b.IP normal activity verified, THEN direct I8C to check operability of R-9, letdown line monitor, AND return to normal operations.
 
2 Increase Letdown Flow To 60 GPM a.Verify deborating DI i'solated-DIVERT VLV CATION DEBOR DI AOV-244 IN BYPASS POSITION b.Place PCV-135 to manual AND ad)ust as necessary-TO CONTROL LETDOWN PRESSURE a.Place AOV-244 in bypass position.c.Change orifices-CLOSE 40 GPM ORIPICE AND OPEN 60 GPM LTDN ORIFICE AOV-202 IMMBDIATELY d.Ad)ust letdown pressure-TO APPROXIMATELY 250 PSIG e.Return PCV-135-TO AUTO, IF DBSIRBD  
            /
+4 4 t, (,~V aa EOP.: AP-RCS.3 LITLE: HIGH REACTOR COOLANT ACTIVITY REV'PAGE 4 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
P Q '1 II t
3 Check Area Monitor R9 Letdown Line-LESS THAN 200 MR/HR ABOVE BACKGROUND Refer to EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION.
1 ~
*****************************************CAUTION WHEN A NEW DI IS VALVED IN, THERE MAY BE A PLUS OR MINUS REACTIVITY ADDITION DUE TO A BORON CHANGE.(REFER TO S-3.2B TO PREVENT A REACTIVITY CHANGE.)4 Verify Proper Operation Of Letdown DI-DECONTAMINATION FACTOR GREATER THAN 10 IF DI efficiency is NOT acceptable, THEN place a new mixed bed in service.(Refer to S-4.5.7A, A LETDOWN MIXED BED DI RESIN REPLACEMENT, OR S-4.5.7B, B LETDOWN MIXED BED DI RESIN REPLACEMENT).
k
5.Check Sampling Requirements REFER TO TECHNICAL SPECIFICATION TABLE 4.1-4 6 Check If Continued Plant Power Operation Allowed: o Continued plant power operation-ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION 3.1.4 IF shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
 
8 lk'V$it EOP: AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY REV: 5 PAGE 5 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Aux Bldg For Increased Radiation Levels: a.Notify HP Department
EOP,:
-TO SURVEY AUX BLDG b.Aux Bldg radiation levels-NORMAL (Check with HP for normal readings)b.IF Aux Bldg radiation levels indicate above normal, THEN have HP Department establish controls for the higher radiation areas.8 Complete-NOTIFICATION TO HIGHER SUPERVISION AND THE REACTOR ENGINEER 9 Check Conditions For Offsite Reporting:
REV: 5 AP-RCS.3           HIGH REACTOR COOLANT ACTIVITY PAGE 2 of 5 A. PURPOSE This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.
o Refer to-EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION-END-I~8 h 0 P4 h EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 4P/7~PLANT SUPERINTENDENT 4-/1-5'8 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:  
B. ENTRY CONDITIONS/SYMPTOMS
: 1. SYMPTOMS   The symptoms of HIGH REACTOR COOLANT ACTIVITY are;
: a. Unexplained increase in letdown   line monitor, R-9, or
: b. Sampling indicates I-131 equivalent   GREATER THAN 0.2 uCi/gm, or
: c. Sampling indicates gross degassed   activity GREATER THAN 20 uCi/gm, or
: d. Sampling indicates   that total specific activity exceeds 84/E.
 
  ~
    'g(,"
"
 
TITLE:                                                      REV    5 AP-RCS.3               HIGH REACTOR COOLANT ACTIVITY PAGE 3   of 5 STEP       ACTION/BXPECTED RESPONSE               RESPONSE NOT OBTAINED
**********************************     CAUTION IF LETDOWN PLOW EXCEEDS 60 GPM WHEN USING AOV-202, D/P ACROSS THE CVCS DBMINERALIZERS SHOULD BE MONITORED TO VERIPY THAT FLOW IS CONTINUING THROUGH THE DI'S. HOWEVER, FLOW THROUGH THE   DI'S SHOULD NOT EXCEED 90 GPM.
1 Verify RCS Activity:
: a. Direct HP - TO SAMPLE RCS FOR ACTIVITY
: b. RCS activity   - GREATER THAN           b. IP normal activity verified, NORMAL  (Check with HP                      THEN direct I8C to check Department for normal  activity)          operability of R-9, letdown line monitor, AND return to normal operations.
2   Increase Letdown Flow To 60 GPM
: a. Verify deborating DI i'solated-         a. Place AOV-244 in bypass DIVERT VLV CATION DEBOR   DI               position.
AOV-244 IN BYPASS POSITION
: b. Place PCV-135 to manual AND ad)ust as necessary - TO CONTROL LETDOWN PRESSURE
: c. Change   orifices - CLOSE 40 GPM ORIPICE AND OPEN 60 GPM LTDN ORIFICE AOV-202 IMMBDIATELY
: d. Ad)ust letdown pressure   - TO APPROXIMATELY 250 PSIG
: e. Return PCV-135 -   TO AUTO, IF DBSIRBD
 
t, 4
+4
(,
  ~ V aa
 
EOP.:             LITLE:                                                    REV' AP-RCS.3                 HIGH REACTOR COOLANT ACTIVITY PAGE 4   of 5 STEP       ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED NOTE:     Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
3   Check Area Monitor R9                   Refer to EPIP 1-0,   GINNA STATION Letdown Line  LESS THAN                EVENT EVALUATION AND 200 MR/HR ABOVE BACKGROUND              CLASSIFICATION.
  *****************************************
CAUTION WHEN A NEW   DI IS VALVED IN, THERE MAY BE A PLUS OR MINUS REACTIVITY ADDITION DUE TO A BORON CHANGE.   (REFER TO S-3.2B TO PREVENT A REACTIVITY CHANGE.)
4 Verify Proper     Operation   Of         IF DI efficiency is NOT Letdown DI      DECONTAMINATION        acceptable, THEN place a new mixed FACTOR GREATER THAN 10                  bed in service. (Refer to S-4.5.7A, A LETDOWN MIXED BED   DI RESIN REPLACEMENT,   OR S-4.5.7B, B LETDOWN MIXED BED   DI RESIN REPLACEMENT).
: 5. Check Sampling Requirements REFER TO TECHNICAL SPECIFICATION TABLE     4.1-4 6   Check   If Continued Plant Power Operation Allowed:
IF shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN     TO HOT SHUTDOWN.
o  Continued plant power operation
            - ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION  3.1.4
 
8 lk
'V$
it
 
EOP:
REV: 5 AP-RCS.3               HIGH REACTOR COOLANT ACTIVITY PAGE 5 of 5 STEP     ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 7 Check Aux Bldg For Increased Radiation Levels:
: a. Notify HP Department - TO SURVEY AUX BLDG
: b. Aux Bldg radiation   levels-       b. IF Aux Bldg   radiation levels NORMAL (Check with  HP  for            indicate above normal, THEN normal readings)                      have HP Department establish controls for the higher radiation areas.
8 Complete   NOTIFICATION TO HIGHER SUPERVISION AND THE REACTOR ENGINEER 9 Check Conditions For Offsite Reporting:
o Refer to - EPIP 1-0,   GINNA STATION EVENT EVALUATION AND CLASSIFICATION
                                      -END-
 
I
~8 h
0 P4 h
 
EOP:
REV: 5 ES-0 '             NATURAL CIRCULATION COOLDOWN PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE   4P / 7~
PLANT SUPERINTENDENT 4-/1-5'8 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
 
T!TLE REV: 5 ES-0.2                NATURAL CIRCULATION COOLDOWN PAGE 2 of  17 A. PURPOSE    - This procedure provides actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation.
B. SYMPTOMS AND OR ENTRY CONDITIONS This procedure    is entered  from:
: 1) ES-0.1, REACTOR TRIP RESPONSE, that    a when natural circulation cooldown it has been determined is required.
: 2) ECA-0 when
                ', has been ALL it  LOSS OF      AC  POWER RECOVERY WITHOUT determined    that a SI REQUIRED/
natural circulation cooldown is required.
: 3) Other normal    operating procedures    'when a natural circulation cooldown    is required.
 
'r EOP:            T1TLE:
REV: 5 ES-0  '                NATURAL CIRCULATION COOLDOWN PAGE 3  of 17 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
  *****************************************
CAUTION o  IF SI ACTUATION OCCURS DURING THIS PROCEDURE,    E-O, REACTOR TRIP OR SAFETY INJECTION,  SHOULD BE PERFORMED.
o  IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
NOTE:    Foldout page should be open and monitored periodically.
* 1 Monitor Conditions For RCP Restart:
: a. Establish conditions for                a. Go to Step 2.
starting an RCP:
o  Bus 11A  or 11B energiz.ed o  Refer to Attachment    RCP START
: b. Start one    RCP
: c. Any RCP - RUNNING                      c. Go to Step 2.
: d. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION


ES-0.2 T!TLE NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 2 of 17 A.PURPOSE-This procedure provides actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation.
B.SYMPTOMS AND OR ENTRY CONDITIONS This procedure is entered from: 1)ES-0.1, REACTOR TRIP RESPONSE, when it has been determined that a natural circulation cooldown is required.2)ECA-0', LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED/when it has been determined that a natural circulation cooldown is required.3)Other normal operating procedures
'when a natural circulation cooldown is required.
'r EOP: ES-0'T1TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 3 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o IF SI ACTUATION OCCURS DURING THIS PROCEDURE, E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.
o IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
NOTE: Foldout page should be open and monitored periodically.
*1 Monitor Conditions For RCP Restart: a.Establish conditions for starting an RCP: o Bus 11A or 11B energiz.ed o Refer to Attachment RCP START b.Start one RCP c.Any RCP-RUNNING d.Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION a.Go to Step 2.c.Go to Step 2.
.
.
EOP s ES-0'T!TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 4 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check VCT Makeup System: a.Verify the following:
EOP s           T!TLE:
l)Boric acid flow control valve-SET FOR REQUIRED CSD CONCENTRATION 2)RMW mode selector switch in AUTO 3)RMW control armed-RED LIGHT LIT b.Check VCT level o Level-GREATER THAN 20$-OR-o Level-STABLE OR INCREASING b.Manually increase VCT makeup flow as follows: 1)Ensure BA transfer pumps and RMW pumps running.2)Place RMW,flow control valve HCV-ill in MANUAL and increase RNW flow.3)Increase boric acid flow as necessary.  
REV: 5 ES-0 '                 NATURAL CIRCULATION COOLDOWN PAGE 4 of 17 STEP     ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 2 Check VCT Makeup System:
: a. Verify the following:
l) Boric acid flow control valve - SET FOR REQUIRED   CSD CONCENTRATION
: 2) RMW mode selector switch in AUTO
: 3) RMW control   armed - RED LIGHT LIT
: b. Check VCT level                   b. Manually increase   VCT makeup flow as follows:
o  Level -  GREATER THAN 20$
: 1) Ensure BA   transfer pumps and
                        -OR-                        RMW pumps running.
o  Level -  STABLE OR INCREASING      2) Place RMW,flow   control valve HCV-ill in   MANUAL and increase   RNW flow.
: 3) Increase   boric acid flow  as necessary.
 
EOP:
REV' ES-0 '                  NATURAL CIRCULATION  COOLDOWN PAGE 5  of 17 STEP      ACTION/EXPECTED RESPONSE        RESPONSE NOT OBTAINED 3  Check Charging Pump Suction Aligned To    VCT:
: a. Check  VCT  level:                  a. IF VCT  level  can NOT  be maintained greater than    5%, THEN o  Level -  GREATER THAN 20%          perform the following:
o  VCT makeup  system - AVAILABLE    1) Ensure charging pump suction aligned to  RWST o  LCV-112B open o  LCV-112C  closed
: 2) Continue    with Step 4. WHEN VCT level greater    than 40$ ,
THEN do Step 3b.
: b. Verify the following:              b. Manually align valves as necessary.
o  LCV-112C - OPEN o  LCV-112B - CLOSED 4  Borate  RCS To Cold Shutdown Boron Concentration (Refer to Figure  SDM) 5  Establish    Maximum Rx    Vessel    Start fans  as necessary.
Head  Cooling:
o  Check  control rod shroud fans (45,kw) -  BOTH RUNNING o  Check one Rx compartment  cooling fan (23 kw)- RUNNING
 
EOP:
REV: 5 ES-0 '                NATURAL CIRCULATION COOLDOWN PAGE 6 of 17 STEP      ACTION/EXPECTED RESPONSE        RESPONSE NOT OBTAINED 6  Verify Adequate    Shutdown Margin
: a. Direct  HP to sample the RCS  for boron concentration
          ~ RCS  loop A
          ~ RCS  loop B
          ~ PRZR
: b. Verify boron concentration-      b. Perform the following:
GREATER -THAN REQUIREMENTS OF FIGURE SDM                          1) Maintain  RCS average temperature greater than 500'F until adequate SDM established.
: 2) Continue to borate as necessary.
 
'I I
  ~ x~ ~
 
EOP:            T]ILE:
REV: 5 ES-0.2                NATURAL CIRCULATION COOLDOWN PAGE 7  of 17 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
  *****************************************
CAUTION o  IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW WILL BE NECESSARY (REFER TO ER-AFW.1) ALTERNATE WATER SUPPLY TO AFW PUMPS).
o  SI MUST BE BLOCKED BEFORE S/G PRESSURE    DECREASES TO  514 PSIG.
o  THE hT BETWEEN PRZR LIQUID AND THE HOT LEG TEMPERATURE SHOULD NOT BE PERMITTED TO EXCEED 200'F. IF THIS LIMIT IS EXCEEDED, THEN NOTIFY TECHNICAL ENGINEERING OF THE MAXIMUM hT OBSERVED.
7  Initiate    RCS  Cooldown To Cold Shutdown:
: a. Dump steam to condenser                a. Manually or  locally dump steam using S/G ARVs.
: b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
: c. Maintain S/G narrow range level        c. Control feed flow as necessary.
BETWEEN 17$ AND 39%
: d. Plot RCS  cold leg temperatures and PRZR temperature  twice per hour (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN,  for plot paper) 8  Check:RCS Hot Leg                          Return to Step 7.
Temperatures  LESS      THAN  550'F
 
I H
    - I
 
EOP t          TlTLE:
REV: 5 ES-0.2                NATURAL CIRCULATION      COOLDOWN PAGE 8  of 17 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED NOTE:  o  If charging  line to PRZR vapor hT exceeds 320'F, then plant    staff should be  consulted  before using auxiliary spray.
o  WHEN  using  a PRZR PORV, THEN  select  one with  an operable  block valve.
o  If auxiliary spray    is in use, spray flow may  be increased by AOV-294 and normal PRZR spray valves.
closing normal charging valve 9 Depressurize    RCS  To 1950 PSIG:
: a. Check letdown - IN SERVICE              a. Try to establish letdown (Refer to Attachment LETDOWN).
IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 10.
: b. Depressurize RCS using auxiliary        b. IF auxiliary spray valve    NOT spray valve (AOV-296)                      available,  THEN  use one PRZR PORV.
 
FOP:              T!TLE.
REV: 5 ES-0 '                      NATURAL CIRCULATION COOLDONN PAGE 9  of  17 STEP      ACTION/EXPECTED RESPONSE                    RESPONSE NOT OBTAINED
  * * * * * * * * * * * * * * * * * * * * * * * * *
* 4'            *************
CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLYUNBLOCK IF          PRZR PRESSURE  INCREASES TO GREATER THAN      1992 PSIG.
  *****************************************
*10    Monitor SI Block Criteria:
: a. Check the following:                        a. Return to Step 9.
o  PRZR  pressure    - LESS THAN 1950 PSIG
                            -OR-o  LOW PRZR PRESS      BLOCK SAF INJEC    status  light  - LIT h
: b. Place SI block switches to        BLOCK
          ~ Train    A
          ~ Train    B
: c. Verify    SAFETY INJECTION BLOCKED          c. Maintain PRZR pressure greater status    light    - LIT                        than 1750 psig and S/G pressure greater than 514 psig until SI blocked.
11  Determine RCS Pressure And Temperature Limits-.
: a. Check control rod shroud        fans-        a. Perform the following:
BOTH RUNNING
: 1) Maintain  RCS pressure within limits of Figure  NAT CIRC C/D WITHOUT SHROUD FANS.
: 2) Go  to Step 12.
: b. Maintain      RCS  pressure - WITHIN LIMITS OF FIGURE NAT CIRC C/D WITH SHROUD FANS
 
l O' T1TLE!
REV  5 ES-0.2                    NATURAL CIRCULATION COOLDOWN PAGE 10 of 17 STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED
*12  Maintain      PRZR    Level Between 204 And 304
*13  Monitor RCS Cooldown:
o Core exit T/Cs - DECREASING o  RCS hot leg temperatures-DECREASING o  RCS  subcooling based on core exit  T/Cs - INCREASING o  Cooldown    rate in  RCS cold legs-LESS THAN    25'F/HR
 
EOP $              TITLE$
REV: 5 ES-0.2                    NATURAL CIRCULATION COOLDOWN PAGE 11  of 17 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED
    *****************************************
CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.          THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE:    o  If at    any time it is determined that a natural circulation cooldown and depressurization must be performed at a rate that may form a steam void in the vessel, then procedure ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAN VOID IN VESSEL, should be used.
o  If charging    line to PRZR vapor AT exceeds 320'F, then plant    staff should be consulted before using auxiliary spray.
o  WHEN    using a  PRZR PORV, THEN  select  one with  an operable block valve.
o  If auxiliary spray    is in  use, spray flow may be increased by AOV-294 and normal PRZR spray valves, closing normal charging valve 14    Initiate    RCS    Depressurization:
: a. Check letdown - IN SERVICE                a. Try to establish letdown (Refer to Attachment LETDOWN).
IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 15.
: b. Depressurize RCS using auxiliary          b. IF auxiliary spray valve    NOT spray valve (AOV-296)                        available,  THEN use one PRZR PORV.
: c. Plot:" RCS temperature and pressure on curve selected      in Step 11 hourly


EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV'PAGE 5 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check Charging Pump Suction Aligned To VCT: a.Check VCT level: o Level-GREATER THAN 20%o VCT makeup system-AVAILABLE a.IF VCT level can NOT be maintained greater than 5%, THEN perform the following:
EOP:
1)Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed 2)Continue with Step 4.WHEN VCT level greater than 40$, THEN do Step 3b.b.Verify the following:
REV: 5 ES-0 '                   NATURAL CIRCULATION COOLDOWN PAGE 12  of 17 STEP     ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED 15  Continue Cooldown And Depressurization:
o LCV-112C-OPEN o LCV-112B-CLOSED b.Manually align valves as necessary.
: a. Check RCS  cold leg temperature-   a. Stabilize RCS temperature and go GREATER THAN   335'F                  to Step 15c.
4 Borate RCS To Cold Shutdown Boron Concentration (Refer to Figure SDM)5 Establish Maximum Rx Vessel Head Cooling: o Check control rod shroud fans (45,kw)-BOTH RUNNING o Check one Rx compartment cooling fan (23 kw)-RUNNING Start fans as necessary.  
: b. Maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
: c. Maintain RCS temperature and        c. Control    RCS  pressure as pressure within limits of Figure        neces'sary  to restore pressure/
determined previously                  temperature relationship to within limits of approprite Figure.
16  Establish Required        RCS Hydrogen Concentration         (Refer to S-3.3C,    H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 17  Check For Steam Void In                Repressurize    RCS within allowable Reactor Vessel:                       limits  and continue cooldown.
o PRZR  level  -  NO UNEXPECTED LARGE IF RCS depressurization must VARIATIONS                          continue, THEN go to ES-0.3, NATURAL CIRCULATION COOLDOWN WITH o RVLIS  level  (no RCPs) - GREATER  STEAM VOID    IN VESSEL.
THAN 95%


EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Adequate Shutdown Margin a.Direct HP to sample the RCS for boron concentration
C I,
~RCS loop A~RCS loop B~PRZR b.Verify boron concentration-GREATER-THAN REQUIREMENTS OF FIGURE SDM b.Perform the following:
V l
1)Maintain RCS average temperature greater than 500'F until adequate SDM established.
t 4
2)Continue to borate as necessary.
l
'I I~x~~
EOP: ES-0.2 T]ILE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 7 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW WILL BE NECESSARY (REFER TO ER-AFW.1)ALTERNATE WATER SUPPLY TO AFW PUMPS).o SI MUST BE BLOCKED BEFORE S/G PRESSURE DECREASES TO 514 PSIG.o THE hT BETWEEN PRZR LIQUID AND THE HOT LEG TEMPERATURE SHOULD NOT BE PERMITTED TO EXCEED 200'F.IF THIS LIMIT IS EXCEEDED, THEN NOTIFY TECHNICAL ENGINEERING OF THE MAXIMUM hT OBSERVED.7 Initiate RCS Cooldown To Cold Shutdown: a.Dump steam to condenser b.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 25'F/HR c.Maintain S/G narrow range level BETWEEN 17$AND 39%a.Manually or locally dump steam using S/G ARVs.c.Control feed flow as necessary.
d.Plot RCS cold leg temperatures and PRZR temperature twice per hour (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, for plot paper)8 Check:RCS Hot Leg Temperatures
-LESS THAN 550'F Return to Step 7.
I H-I EOP t ES-0.2 TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 8 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If charging line to PRZR vapor hT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.9 Depressurize RCS To 1950 PSIG: a.Check letdown-IN SERVICE a.Try to establish letdown (Refer to Attachment LETDOWN).b.Depressurize RCS using auxiliary spray valve (AOV-296)IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 10.b.IF auxiliary spray valve NOT available, THEN use one PRZR PORV.


FOP: ES-0'T!TLE.NATURAL CIRCULATION COOLDONN REV: 5 PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**************************4'*************CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLY UNBLOCK IF PRZR PRESSURE INCREASES TO GREATER THAN 1992 PSIG.******************************************10 Monitor SI Block Criteria: a.Check the following:
EOP t REV: 5 ES-0   '                 NATURAL CIRCULATION COOLDONN PAGE 13  of 17 STEP       ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 18  Check    If SI Isolated:
o PRZR pressure-LESS THAN 1950 PSIG a.Return to Step 9.-OR-o LOW PRZR PRESS BLOCK SAF INJEC status light-LIT h b.Place SI block switches to BLOCK~Train A~Train B c.Verify SAFETY INJECTION BLOCKED status light-LIT c.Maintain PRZR pressure greater than 1750 psig and S/G pressure greater than 514 psig until SI blocked.11 Determine RCS Pressure And Temperature Limits-.a.Check control rod shroud fans-BOTH RUNNING b.Maintain RCS pressure-WITHIN LIMITS OF FIGURE NAT CIRC C/D WITH SHROUD FANS a.Perform the following:
ACCUMs  Should Be
1)Maintain RCS pressure within limits of Figure NAT CIRC C/D WITHOUT SHROUD FANS.2)Go to Step 12.
: a. RCS  pressure - LESS THAN         a. Continue with Step 19. WHEN RCS 1500 PSIG                              pressure is less than 1500 psig, THEN do Steps 18b through d.
l O' ES-0.2 T1TLE!NATURAL CIRCULATION COOLDOWN REV 5 PAGE 10 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*12 Maintain PRZR Level Between 204 And 304*13 Monitor RCS Cooldown: o Core exit T/Cs-DECREASING o RCS hot leg temperatures-DECREASING o RCS subcooling based on core exit T/Cs-INCREASING o Cooldown rate in RCS cold legs-LESS THAN 25'F/HR
: 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. IF any valve can NOT be closed, THEN perform the following:
            ~ ACCUM  A) MOV-841
            ~ ACCUM  B, MOV-865                  1) Dispatch personnel to    locally close valves, as necessary.
: 2) Maintain   RCS  pressure greater than 1000  psig until both SI ACCUMs  isolated.
IF any SI ACCUM can NOT be isolated AND RCS depressurization to less than 1000 psig is required, THEN;
: 1) Open vent valves    for unisolated SI    ACCUMs,
                                                        ~ ACCUM  A, AOV-834A
                                                        ~ ACCUM  B, AOV-834B
: 2) Open HCV-945.
: 3) Maintain   RCS pressure greater than SI  ACCUM pressure.
: d. Locally open breakers    for MOV-841 and MOV-865


EOP$ES-0.2 TITLE$NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 11 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.
EOP:
THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o If at any time it is determined that a natural circulation cooldown and depressurization must be performed at a rate that may form a steam void in the vessel, then procedure ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAN VOID IN VESSEL, should be used.o If charging line to PRZR vapor AT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves, 14 Initiate RCS Depressurization:
REV: 5 ES-0.2                 NATURAL CIRCULATION COOLDOWN PAGE 14  of 17 STEP       ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED
a.Check letdown-IN SERVICE b.Depressurize RCS using auxiliary spray valve (AOV-296)c.Plot:" RCS temperature and pressure on curve selected in Step 11 hourly a.Try to establish letdown (Refer to Attachment LETDOWN).IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 15.b.IF auxiliary spray valve NOT available, THEN use one PRZR PORV.
*19    Maintain Letdown Flow:
: a. Open letdown orifice valves  as necessary
: b. Adjust low pressure letdown control valve setpoint as necessary
*20    Maintain Required      RCP Seal      Perform the following:
Injection  Flow And Labyrinth Seal D/P:                            o   Adjust charging flow to   REGEN Hx (HCV-142) as necessary.
o Labyrinth seal  D/P to each RCP-GREATER THAN 15 INCHES OF WATER                  -OR-o  Seal injection flow to each  RCP  o  Dispatch  AO to adjust seal
            - GREATER THAN 6 GPM                  injection needle valves  if necessary.
                                                  ~ RCP  A, V-300A
                                                  ~ RCP  B, V-300B


EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Continue Cooldown And Depressurization:
4 EOP:
a.Check RCS cold leg temperature-GREATER THAN 335'F b.Maintain cooldown rate in RCS cold legs-LESS THAN 25'F/HR c.Maintain RCS temperature and pressure within limits of Figure determined previously a.Stabilize RCS temperature and go to Step 15c.c.Control RCS pressure as neces'sary to restore pressure/temperature relationship to within limits of approprite Figure.16 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)17 Check For Steam Void In Reactor Vessel: Repressurize RCS within allowable limits and continue cooldown.o PRZR level-NO UNEXPECTED LARGE VARIATIONS o RVLIS level (no RCPs)-GREATER THAN 95%IF RCS depressurization must continue, THEN go to ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL.
REV' ES-0 '                     NATURAL CIRCULATION COOLDOWN PAGE 15  of 17 STEP       ACTION/EXPECTED RESPONSE             RESPONSE NOT OBTAINED 21    Check    If  SI System Normal Shutdown Alignment Should Be Established:
C I, V l t 4 l EOP t ES-0'NATURAL CIRCULATION COOLDONN REV: 5 PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If SI ACCUMs Should Be Isolated: a.RCS pressure-LESS THAN 1500 PSIG 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~ACCUM A)MOV-841~ACCUM B, MOV-865 a.Continue with Step 19.WHEN RCS pressure is less than 1500 psig, THEN do Steps 18b through d.c.IF any valve can NOT be closed, THEN perform the following:
: a. RCS   cold leg temperature -   LESS    a. Return to Step 15.
1)Dispatch personnel to locally close valves, as necessary.
THAN   350'F b, RCS   pressure -   LESS THAN           b. Stabilize RCS temperature and 1500 PSIG                                  return to Step 14.
2)Maintain RCS pressure greater than 1000 psig until both SI ACCUMs isolated.IF any SI ACCUM can NOT be isolated AND RCS depressurization to less than 1000 psig is required, THEN;1)Open vent valves for unisolated SI ACCUMs,~ACCUM A, AOV-834A~ACCUM B, AOV-834B d.Locally open breakers for MOV-841 and MOV-865 2)Open HCV-945.3)Maintain RCS pressure greater than SI ACCUM pressure.
: c. Lock out SI system as follows:
: 1) Place    all  SI pump switches  in PULL STOP
: 2) Locally close breakers     for SI .
pump  discharge valves to cold legs
                ~ MOV-878B, MCC D position 8C
                ~ MOV-878D, MCC D position 8F
: 3) Close SI pump discharge to cold legs
                ~ MOV-878B
                ~ MOV-878D
: 4) Locally open breakers     for MOV-878B and MOV-878D


EOP: ES-0.2 NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 14 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*19 Maintain Letdown Flow: a.Open letdown orifice valves as necessary b.Adjust low pressure letdown control valve setpoint as necessary*20 Maintain Required RCP Seal Injection Flow And Labyrinth Seal D/P: o Labyrinth seal D/P to each RCP-GREATER THAN 15 INCHES OF WATER Perform the following:
P t
o Adjust charging flow to REGEN Hx (HCV-142)as necessary.-OR-o Seal injection flow to each RCP-GREATER THAN 6 GPM o Dispatch AO to adjust seal injection needle valves if necessary.
~RCP A, V-300A~RCP B, V-300B 4
EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV'PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If SI System Normal Shutdown Alignment Should Be Established:
a.RCS cold leg temperature
-LESS THAN 350'F a.Return to Step 15.b, RCS pressure-LESS THAN 1500 PSIG c.Lock out SI system as follows: 1)Place all SI pump switches in PULL STOP b.Stabilize RCS temperature and return to Step 14.2)Locally close breakers for SI.pump discharge valves to cold legs~MOV-878B, MCC D position 8C~MOV-878D, MCC D position 8F 3)Close SI pump discharge to cold legs~MOV-878B~MOV-878D 4)Locally open breakers for MOV-878B and MOV-878D Pt EOPt ES-0.2 TITLE: NATURAL CIRCULATION COOLDOWN REV 5 PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check If RHR Normal Cooling Can Be Established:
a.RCS pressure-LESS THAN 400 PSIG b.Verify all SI pump switches in PULL STOP a.Stabilize RCS temperature and return.to Step 14.b.Return to Step 21.c.Sample the RHR system to ensure adequate boron concentration (Refer to Attachment RHR SAMPLE)d.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)e.Establish RHR normal cooling (Refer to Attachment RHR COOL)d.IF RCS overpressure protection system can NOT be placed in service, THEN consult Plant staff to determine if RHR normal cooling should be established and go to Step 23.23 Continue RCS Cooldown To Cold.Shutdown*****************************************CAUTION DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS IS LESS THAN 200'F MAY RESULT IN ADDITIONAL VOID FORMATION IN THE RCS.24 Continue Cooldown Of Inactive Portion Of RCS: a.Cool upper head region using control rod shroud fans b.Cool S/G U-tubes by dumping steam from all S/Gs


EOP: ES-O.'T1TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 17 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION IF LESS THAN TWO CONTROL ROD SHROUD FANS ARE RUNNING, THE UPPER HEAD REGION MAY REMAIN ABOVE 200'F FOR UP TO 29 HOURS AFTER REACHING CSD.25 Determine If RCS Depressurization Is Permitted:
EOPt              TITLE:
a.Entire RCS-LESS THAN 200'F~Core exit T/Cs~Upper head T/Cs~RCS hot leg temperature
REV    5 ES-0.2                    NATURAL CIRCULATION COOLDOWN PAGE 16  of 17 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 22  Check Can Be IfEstablished:
~RCS cold leg temperature b.Check control rod shroud fan status-BOTH RUNNING DURING COOLDOWN c.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD SHUTDOWN)a.Do NOT depressurize RCS.Return to Step 23.b.Consult Plant staff to determine wait period for upper head cooling.-END-I EOP;ES-0'T1TLE NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 ES-0.2 APPENDIX LIST TITLE PAGES 1)RED PATH  
RHR Normal      Cooling
: a. RCS  pressure -  LESS THAN 400 PSIG      a. Stabilize    RCS  temperature and return  .to Step 14.
: b. Verify    all  SI pump  switches in        b. Return to Step 21.
PULL STOP
: c. Sample the RHR system to ensure adequate boron concentration (Refer to Attachment RHR SAMPLE)
: d. Place  RCS  overpressure                d. IF RCS overpressure protection protection system in service                  system can NOT be placed in (Refer to 0-7, ALIGNMENT AND                  service, THEN consult Plant OPERATION OF THE REACTOR VESSEL              staff to determine    if  RHR normal OVERPRESSURE PROTECTION SYSTEM)              cooling should be established and go to Step 23.
: e. Establish    RHR normal cooling (Refer to Attachment      RHR COOL) 23    Continue    RCS  Cooldown To Cold.
Shutdown
  *****************************************
CAUTION DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS        IS LESS THAN    200'F MAY RESULT  IN ADDITIONAL VOID FORMATION IN THE RCS.
24    Continue Cooldown Of Inactive Portion Of      RCS:
: a. Cool upper head region using control rod shroud fans
: b. Cool S/G U-tubes by dumping steam from all S/Gs
 
EOP:             T1TLE:
REV: 5 ES-O.'                   NATURAL CIRCULATION COOLDOWN PAGE 17 of 17 STEP     ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED
  *****************************************
CAUTION IF LESS THAN TWO CONTROL ROD SHROUD FANS ARE RUNNING, THE UPPER HEAD REGION MAY REMAIN ABOVE     200'F FOR UP TO 29 HOURS AFTER REACHING CSD.
25   Determine       If RCS Depressurization Is Permitted:
: a. Entire   RCS   - LESS THAN 200'F         a. Do NOT depressurize RCS.
          ~ Core exit T/Cs                             Return to Step 23.
          ~ Upper head T/Cs
          ~ RCS   hot leg temperature
          ~ RCS   cold leg temperature
: b. Check control rod shroud fan             b. Consult Plant staff to determine status -     BOTH RUNNING DURING             wait period for upper head COOLDOWN                                     cooling.
: c. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD SHUTDOWN)
                                            -END-
 
I EOP;         T1TLE REV: 5 ES-0 '             NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 ES-0.2 APPENDIX LIST TITLE                           PAGES
: 1)   RED PATH  


==SUMMARY==
==SUMMARY==
2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)FIGURE NAT CIRC C/D WITHOUT SHROUD FANS 5)FIGURE NAT CIRC C/D WITH SHROUD FANS 6)ATTACHMENT RCP START 7)ATTACHMENT LETDOWN 8)ATTACHMENT RHR COOL 9)ATTACHMENT RHR SAMPLE 10)FOLDOUT  
: 2)   FIGURE MIN SUBCOOLING
: 3)   FIGURE SDM
: 4)   FIGURE NAT CIRC C/D WITHOUT SHROUD FANS
: 5)   FIGURE NAT CIRC C/D WITH SHROUD FANS
: 6)   ATTACHMENT RCP START
: 7)   ATTACHMENT LETDOWN
: 8)   ATTACHMENT RHR COOL
: 9)   ATTACHMENT RHR SAMPLE
: 10)   FOLDOUT


EOP: ES-0'NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 RED PATH  
EOP:
REV: 5 ES-0 '               NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 RED PATH  


==SUMMARY==
==SUMMARY==
a.SUBCRITICALITY
: a. SUBCRITICALITY Nuclear power   greater than 5%
-Nuclear power greater than 5%b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 43%[46%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT
: b. CORE COOLING   Core exit T/Cs greater than 1200'F
-CNMT pressure greater than 60 psig
                                            -OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43% [46%
adverse CNMT]
: c. HEAT SINK - Narrow range   level in all S/Gs less than 5%
[25% adverse   CNMT] AND total feedwater flow less than 200 gpm
: d. INTEGRITY Cold leg temperatures decrease greater than 100'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: 5 ES-0  '              NATURAL CIRCULATION      COOLDOWN 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 OI woo                          SUBCOOLED 1300                          REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOL ING 600      ADVERSE CNMT                                               REGION 500 400 300 200                                        NORMAL CNMT                  TEMPERATURE INCREMENTS 10'F 100 0
200      250      300    350    400    450    500    550      600      650    700 CORE EXIT SATURATION TEMPERATURE ('F)
 
EOP:            T!TLE:
REV    5 ES-0.2                  NATURAL CIRCULATION    COOLDOWN PAGE 1  of  1 FIGURE SDM BORON CONCENTRATION  (PPH) 1800 BORON INCREHENTS 20 PPH 1600 1400 ADEQUATE SDH 1200                                                    100 PPH CONS ERVATISH INCLUDED 1000 8OO 600 400 BORATE 200                                                                      BURNUP INCREHENTS 100 HWD/HTU 0    1000    2000    3000  4000  5000  6000    7000    8000  9000  10000  11000 CYCLE 22 BURNUP (HWD/HTU)
NOTE: To    obtain core burnup, use    PPCS  turn  on code BURNUP.
 
h, A"
 
EOP0              T!TLE:
REV: 5 ES-0 '                    NATURAL CIRCULATION COOLDOWN PAGE 1  of 1 FIGURE NAT CIRC      C D  WITHOUT SHROUD FANS RCS PRESSURE      (PSIG) 2500 2400      RCS    PRESSURE                                                NORHAL INCREHENTS                                RCS  temp        RANGE 2300            20 PSIG                              for  S/G SI 2200 (514 psig) 2100 SI  UNBLOCK 2000 1900 1800 1700 1600 1500                                                              [1] Wait 11 hrs before decreasing RCS pressure 1400                                                                less than 1600 psig 1300 1200 1100 1000 900 800 700          [2] Wait 29 hrs before decreasing RCS pressure 600              less than 350 psig to prevent boiling in 500                upper head 400 300 200 TEHPERATURE 100                                                                        INCREHENTS 10'F 0  50      100    150  '200    250  300  350    400    450    500  550  600  650  700 RCS COLD LEG TEHPERATURE    ('F)
 
EOP:          TlTLE:
REV: 5 ES-0.2              NATURAL CIRCULATION COOLDOWN PAGE 1  of I FIGURE NAT CIRC C D WITH SHROUD FANS RCS PRESSURE  (PSIG) 2500 2400 RCS PRESSURE INCREMENTS RCS  temp 2300                                            for  S/G SI 20 PSIG 2200 (514 psig) 2100 SI  UNBLOCK 2000 1900 1800 A
1700                                            .V 0
1600 I
D 1500 1400 NORMAL 1300 RANGE 1200 1100 1000 900 800 700 600 500 400 300 200 TEMPERATURE ioo                                                                  INCREMENTS 10'F 0  50  100    150 200    250  300  350    400    450    500  550  600  650  700 RCS COLD LEG TEMPERATURE      ('F)
 
EOP:          TlTLE:
REV: 5 ES-0  '                NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FOLDOUT PAGE 1~    RC    T  I  CR TERIA IF  BOTH  conditions listed below occur,  THEN  trip both RCPs:
: a. SI pumps    - AT LEAST TWO RUNNING
: b. RCS  pressure minus  maximum S/G  pressure   LESS THAN 175 PSIG 2 ~  SI  PUMP AUTO SWITCHOVER CRITERION WHEN BAST    level decreases to 104,  THEN  ensure SI pump automatic switchover to RWST.
3 ~  SI  ACTUATION CRITERIA IF  EITHER  condition listed below occurs,    THEN  actuate SI and go  to  E-O, REACTOR TRIP  OR  SAFETY INJECTION, Step 1.
o    RCS  subcooling based on core  exit  T/Cs  LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING OR-o    PRZR  level  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 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).
 
"Sy EOP:          TITLE:
REV: 10 ES-1.2        POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1  of 23 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0    .
REVIEWED BY:
 
P EOP:          TITLE:
REV  10 ES-1.2        POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 2  of 23 A. PURPOSE    This  procedure provides actions to cool down and depressurize      the RCS to cold shutdown conditions following    a loss of reactor coolant inventory.
B. ENTRY CONDITIONS/SYMPTOMS
: 1. ENTRY CONDITIONS  This    procedure  is entered from:
E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g when    RCS pressure is greater than the shutoff head pressure of the RHR pumps.


EOP!ES-0'TiTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 OI woo 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOL ING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE
EOP:            TITLE:
('F)  
REV  10 ES-1s2          POST. LOCA COOLDOWN AND DEPRESSURIZATION PAGE 3  of 23 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED
  *****************************************
CAUTION o  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    l.
o  IF PRZR LEVEL IS LESS THAN 50% OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.
o  RCS PRESSURE   SHOULD BE MONITORED. IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG [465 PSIG ADVERSE CNMT], THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.
NOTE:  o  Foldout page should be open and monitored periodically.
1 o  Adverse  CNMT values should be used whenever CNMT pressure is greater than    4 psig or CNMT radiation is greater than 10+    R/hr.
* I Monitor Be If RHR Stopped:
Pumps  Should
: a. Check  RCS  pressure:                    a. Go to Step 2.
: 1) Pressure    - GREATER THAN 250 psig  [465 psig adverse CNMT]
: 2) Pressure    - STABLE  OR INCREASING
: b. Stop  RHR pumps    and place AUTO


EOP: ES-0.2 T!TLE: NATURAL CIRCULATION COOLDOWN REV 5 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREHENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONS ERVATISH INCLUDED8OO 600 400 BORATE 200 BURNUP INCREHENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.
EOP:
h, A" EOP0 ES-0'T!TLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 RCS 2500 PRESSURE (PSIG)FIGURE NAT CIRC C D WITHOUT SHROUD FANS 2400 2300 2200 2100 2000 1900 1800 1700 1600 RCS PRESSURE INCREHENTS 20 PSIG RCS temp for S/G SI (514 psig)SI UNBLOCK NORHAL RANGE 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200100[2]Wait 29 hrs before decreasing RCS pressure less than 350 psig to prevent boiling in upper head[1]Wait 11 hrs before decreasing RCS pressure less than 1600 psig TEHPERATURE INCREHENTS 10'F 0 50 100 150'200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEHPERATURE
REV: 10 ES-1.2         POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 4  of 23 STEP      ACTION/EXPECTED RESPONSE        RESPONSE  NOT OBTAINED
('F)  
* 2  Monitor  All  AC Busses-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 bus voltage - GREATER THAN      necessary:
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)  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).


EOP: ES-0.2 TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of I RCS PRESSURE (PSIG)2500 FIGURE NAT CIRC C D WITH SHROUD FANS 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200ioo RCS PRESSURE INCREMENTS 20 PSIG RCS temp for S/G SI (514 psig)SI UNBLOCK A.V 0 I D NORMAL RANGE TEMPERATURE INCREMENTS 10'F 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE
EOP:
('F)  
REV  10 ES-1 '          POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 5  of 23 STEP      ACTION/EXPECTED RESPONSE        RESPONSE  NOT OBTAINED 3  Establish    75 GPM Charging Flaw:
: 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 RWST area key to locally isolate seal injection to affected RCP' V-300A  for RCP A
                                                    ~  V-300B  for RCP B
: 2) Ensure HCV-142 open, demand at  0%.
: b. Align charging  pump  suction to  b. IF LCV-112B can NOT be opened, RWST'                                THEN perform the following:
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 (75 kw each) and establish 75 gpm total charging flow
            ~ Charging line flow
            ~ Seal injection flow


EOP: ES-0'TlTLE: NATURAL CIRCULATION COOLDOWN REV: 5 PAGE 1 of 1 1~2~FOLDOUT PAGE RC T I CR TERIA IF BOTH conditions listed below occur, THEN trip both RCPs: a.SI pumps-AT LEAST TWO RUNNING b.RCS pressure minus maximum S/G pressure-LESS THAN 175 PSIG SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST level decreases to 104, THEN ensure SI pump automatic switchover to RWST.3~SI ACTUATION CRITERIA IF EITHER condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1.o RCS subcooling based on core exit T/Cs-LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
EOP!            TITLE!
"Sy EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 23 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0.REVIEWED BY:
REV  10 ES-1.2          POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 6  of 23 STEP      ACTION/EXPECTED RESPONSE                RESPONSE  NOT OBTAINED 4  Establish Condenser Steam Dump Pressure Control:
P EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 2 of 23 A.PURPOSE-This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory.
: a. Verify condenser available:              a. Place S/G   ARV controllers in AUTO  at desired pressure and   go o  Any MSIV -  OPEN                        to Step 5.
B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
o   Annunciator G-15,    STEAM DUMP ARMED - LIT
-This procedure is entered from: E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g when RCS pressure is greater than the shutoff head pressure of the RHR pumps.  
: b. Ad)ust condenser steam dump controller HC-484 to desired pressure and verify in AUTO
: c. Place steam    dump mode  selector switch to    MANUAL
  *****************************************
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.
* 5 Monitor Intact S/G Levels:
: a. Narrow range level -     GREATER          a. Maintain  total  feed flow greater THAN 5S [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 any S/G narrow range level between 17%                continues to increase in an
[25% adverse CNMT] and 50%                  uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE,  Step 1.


EOP: ES-1s2 TITLE: POST.LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 3 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o 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 l.o IF PRZR LEVEL IS LESS THAN 50%OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.o RCS PRESSURE SHOULD BE MONITORED.
EOP:
IF RCS PRESSURE DECREASES TO LESS THAN 250 PSIG[465 PSIG ADVERSE CNMT], THE RHR PUMPS MUST BE MANUALLY RESTARTED TO SUPPLY WATER TO THE RCS.NOTE: o Foldout page should be open and monitored periodically.
REV  10 ES-1.2            POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 7  of 23 STEP       ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED NOTE:    Shutdown margin should be monitored during  RCS cooldown (Refer to Figure    SDM).
1 o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+R/hr.*I Monitor If RHR Pumps Should Be Stopped: a.Check RCS pressure: 1)Pressure-GREATER THAN 250 psig[465 psig adverse CNMT]2)Pressure-STABLE OR INCREASING a.Go to Step 2.b.Stop RHR pumps and place AUTO
6  Initiate      RCS   Cooldown To Cold Shutdown:
: a. Establish and maintain cooldown rate in    RCS cold legs - LESS THAN   100'F/HR
: b. Use  RHR   system  if in service
: c. Dump  steam to condenser  from      c. Manually or locally dump steam intact    S/G(s)                        using intact S/Gs ARV.
7  Check RCS Subcooling'ased On              Manually operate SI pumps as Core Exit T/Cs - GREATER THAN             necessary and go to Step 19.
O'F USING FIGURE MIN SUBCOOLING 8  Check SI and        RHR Pump  Status:  Go to Step 15.
o  SI pumps -    ANY RUNNING
                        -OR-o  RHR pumps     - ANY RUNNING IN INJECTION    MODE 9  Place    PRZR    Heater Switches In The  Following Positions:
o  PRZR'eater control group      - PULL STOP' PRZR  heater backup group -    OFF


EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 4 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*2 Monitor All AC Busses-BUSSES ENERGIZED BY OFFSITE POWER o Normal feed breakers to all 480 volt busses-CLOSED o 480 bus voltage-GREATER THAN 420 VOLTS o Emergency D/G output breakers OPEN a.IF any AC emergency bus normal feed breaker open, THEN ensure associated D/G breaker closed.b.Perform the following, as necessary:
"i EOP:             TLTLE:
1)Close non-safeguards bus tie breakers:~Bus 13 to Bus 14 tie~Bus 15 to Bus 16 tie 2)Place the following pumps in PULL STOP'EH pumps~Turning gear oil pump~HP seal oil backup pump 3)Restore power to MCCs.~A from Bus 13~B from Bus 15~E from Bus 15~F from Bus 15 4)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).
REV    10 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 8    of 23 STEP     ACTION/EXPECTED RESPONSE                 RESPONSE NOT OBTAINED
  *****************************************
CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.        THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE:  o WHEN  using a  PRZR PORV, THEN  select  one with  an operable  block valve.
o   If auxiliary spray    is in use, spray flow may    be increased by closing normal charging valve      AOV-294 and normal PRZR spray valves.
10  Depressurize      RCS  To  Refill PRZR:
: a. Depressurize    using  normal PRZR        a. Depressurize  using one  PRZR spray  if available                          PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.
IF no PORV  available,   THEN use auxiliary spray valve    (AOV-296).
: b. PRZR  level  - GREATER THAN  13%        b. Continue with Step    ll. WHEN
[40$ adverse    CNMT]                        level greater than  13%  [40$
adverse  CNMTJ, THEN stop  RCS depressurization.
: c. Stop  RCS  depressurization


EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 5 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish 75 GPM Charging Flaw: a.Charging pumps-ANY RUNNING a.Perform the following:
4 EOP:               T1TLE:
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 RWST area key to locally isolate seal injection to affected RCP'V-300A for RCP A~V-300B for RCP B 2)Ensure HCV-142 open, demand at 0%.b.Align charging pump suction to RWST'LCV-112B-OPEN o LCV-112C-CLOSED b.IF LCV-112B can NOT be opened, THEN perform the following:
REV: 10 ES-1.2            POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 9  of 23 STEP       ACTION/EXPECTED RESPONSE                   RESPONSE NOT OBTAINED
1)Verify charging pump A NOT running and place in PULL STOP.c.Start charging pumps as necessary (75 kw each)and establish 75 gpm total charging flow 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).~Charging line flow~Seal injection flow
  *****************************************
CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
  *****************************************
11  Check Started:
If An RCP      Should Be
: a. Both    RCPs    - STOPPED                    a. Stop all but'one  RCP and go to Step 12.
: b. RCS  subcooling based on core              b. Go  to Step 19, exit  T/Cs -    GREATER THAN O' USING FIGURE MIN SUBCOOLING
: c. PRZR    level -   GREATER THAN 13%         c. Return to Step 10.
[40$ adverse      CNMT]
: d. Try to   start  an  RCP                  d. IF IA to CNMT available, THEN ensure at least one control rod
: 1) Establish conditions      for              shroud fan running (45 kw each).
starting an RCP o    Bus 11A  or  11B energized o    Refer to Attachment    RCP START
: 2) Start    one RCP


EOP!ES-1.2 TITLE!POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 6 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Establish Condenser Steam Dump Pressure Control: a.Verify condenser available:
I I EOP:
o Any MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Place S/G ARV controllers in AUTO at desired pressure and go to Step 5.b.Ad)ust condenser steam dump controller HC-484 to desired pressure and verify in AUTO c.Place steam dump mode selector switch to MANUAL*****************************************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.*5 Monitor Intact S/G Levels: a.Narrow range level-GREATER THAN 5S[25$adverse CNMT)b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT]and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in at least one S/G.b.IF narrow range level in any S/G continues to increase in an uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.  
REV: 10 ES-1.2         POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 10   of 23 STEP       ACTION/EXPECTED RESPONSE       RESPONSE NOT OBTAINED 12  Check Pumps If  One Of Three SI Should Be Stopped:
: a. Three SI pumps -   RUNNING        a. Go to Step 13.
: b. RCS  subcooling based on core    b. IF RCS hot leg temperatures exit  T/Cs - GREATER THAN 35'F        greater than 325'F [270'F
[90'F adverse CNMT] USING FIGURE      adverse CNMT] OR IF RHR normal MIN SUBCOOLING                        cooling in service, THEN go to Step 19.
IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F
[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection  mode and go to Step 12c. IF no RHR pump can be operated  in injection mode, THEN go to Step 19.
: c. Check  PRZR  level - GREATER THAN c. Do NOT  stop SI pump. Return to 13%  [40% adverse  CNMT]              Step 10.
: d. Stop one SI pump


EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 7 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).6 Initiate RCS Cooldown To Cold Shutdown: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR system if in service c.Dump steam to condenser from intact S/G(s)c.Manually or locally dump steam using intact S/Gs ARV.7 Check RCS Subcooling'ased On Core Exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING Manually operate SI pumps as necessary and go to Step 19.8 Check SI and RHR Pump Status: o SI pumps-ANY RUNNING-OR-Go to Step 15.o RHR pumps-ANY RUNNING IN INJECTION MODE 9 Place PRZR Heater Switches In The Following Positions:
EOP!              TlTLE~
o PRZR'eater control group-PULL STOP'PRZR heater backup group-OFF "i
REV  10 ES-1.2             POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 11  of 23 STEP       ACTION/EXPECTED RESPONSE             RESPONSE NOT OBTAINED 13  Check    If    One Of Two SI Pumps Should Be Stopped:
EOP: ES-1.2 TLTLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 8 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.
: a. Two  SI pumps -   RUNNING               a. Go to Step 14.
THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.10 Depressurize RCS To Refill PRZR: a.Depressurize using normal PRZR spray if available a.Depressurize using one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.b.PRZR level-GREATER THAN 13%[40$adverse CNMT]c.Stop RCS depressurization IF no PORV available, THEN use auxiliary spray valve (AOV-296).
: b. Determine required RCS subcooling from table:
b.Continue with Step ll.WHEN level greater than 13%[40$adverse CNMTJ, THEN stop RCS depressurization.
Charging Pump              RCS Subcooling Criteria Availability NONE              120'F [200'F adverse CNMT]
4 EOP: ES-1.2 T1TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 9 of 23 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 EVALUATION.
ONE              115'F [190'F adverse CNMT]
*****************************************11 Check If An RCP Should Be Started: a.Both RCPs-STOPPED b.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Stop all but'one RCP and go to Step 12.b.Go to Step 19, c.PRZR level-GREATER THAN 13%[40$adverse CNMT]c.Return to Step 10.d.Try to start an RCP 1)Establish conditions for starting an RCP o Bus 11A or 11B energized o Refer to Attachment RCP START d.IF IA to CNMT available, THEN ensure at least one control rod shroud fan running (45 kw each).2)Start one RCP I I EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If One Of Three SI Pumps Should Be Stopped: a.Three SI pumps-RUNNING b.RCS subcooling based on core exit T/Cs-GREATER THAN 35'F[90'F adverse CNMT]USING FIGURE MIN SUBCOOLING c.Check PRZR level-GREATER THAN 13%[40%adverse CNMT]d.Stop one SI pump a.Go to Step 13.b.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c.IF no RHR pump can be operated in injection mode, THEN go to Step 19.c.Do NOT stop SI pump.Return to Step 10.  
105'F [180'F adverse CNMT]
THREE            100'F [175'F adverse CNMT)
: c. RCS subcooling based on core           c. IF  RCS hot leg temperatures exit T/Cs -   GREATER THAN VALUE          greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE              adverse CNMT] OR IF RHR normal MIN SUBCOOLING                              cooling in service, THEN go to Step 19.
IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F
[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13d. IF no RHR pump can be operated in injection mode, THEN go to Step 19.
: d. PRZR  level  - GREATER THAN 13%        d. Do NOT stop SI pump. Return to
[40%  adverse  CNMT]                      Step 10.
: e. Stop one SI pump


EOP!ES-1.2 TlTLE~POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 11 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check If One Of Two SI Pumps Should Be Stopped: a.Two SI pumps-RUNNING b.Determine required RCS subcooling from table: a.Go to Step 14.Charging Pump Availability NONE ONE THREE RCS Subcooling Criteria 120'F[200'F adverse CNMT]115'F[190'F adverse CNMT]105'F[180'F adverse CNMT]100'F[175'F adverse CNMT)c.RCS subcooling based on core exit T/Cs-GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING c.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.d.PRZR level-GREATER THAN 13%[40%adverse CNMT]e.Stop one SI pump IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13d.IF no RHR pump can be operated in injection mode, THEN go to Step 19.d.Do NOT stop SI pump.Return to Step 10.
1 TITLEt EOP:
1 EOP: ES-1.2 TITLEt POST LOCA COOLDOWN AND DEPRESSURIZATION REV'0 PAGE 12 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If Last SI Pump Should Be Stopped: a.One SI pump-RUNNING b.Determine required RCS subcooling from table: a.'F any RHR pump running in injection mode, THEN go to Step 19.IF NOT, THEN go to Step 15.Charging Pump Availability NONE ONE TWO THREE RCS Subcooling Criteria Insufficient subcooling to stop SI pump.255'F[295'F adverse CNMT]235'F[285'F adverse CNMT]210'F[270'F adverse CNMT]c.RCS subcooling based on core exit T/Cs-GREATER THAN VALUE FROM TABLE ABOVE USING FIGURE MIN SUBCOOLING c.IF RCS hot leg temperatures greater than 325'F[270'F adverse CNMT]OR IF RHR normal cooling in service, THEN go to Step 19.IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F[270'F adverse CNMT], THEN ,ensure at least one RHR pump running in injection mode and go to Step 14d.IF no RHR pump can be operated in injection mode, THEN go to Step 19.d.PRZR level-GREATER THAN 13%[40%adverse CNMT]e.Stop running SI pump d.Do NOT stop SI pump.Return to Step 10.  
REV'0 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 12   of 23 STEP       ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED 14   Check Be If Last Stopped:
SI   Pump Should
: a. One SI pump - RUNNING                 a.'F   any RHR pump running in injection mode, THEN go to Step 19. IF NOT, THEN go to Step 15.
: b. Determine required RCS subcooling from table:
Charging Pump               RCS Subcooling Criteria Availability NONE              Insufficient subcooling to stop SI pump.
ONE              255'F [295'F adverse CNMT]
TWO              235'F [285'F adverse CNMT]
THREE            210'F [270'F adverse CNMT]
: c. RCS subcooling based on core           c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE             greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE              adverse CNMT] OR IF RHR normal MIN SUBCOOLING                              cooling in service,   THEN go to Step 19.
IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F
[270'F adverse CNMT], THEN
                                                        ,ensure at least one RHR pump running in injection mode and go to Step 14d. IF no RHR pump can be operated in injection mode, THEN go to Step 19.
: d. PRZR level   - GREATER THAN   13%       d. Do NOT stop SI pump. Return to
[40%  adverse  CNMT]                        Step 10.
: e. Stop running SI pump


EOP: ES-1'TITLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If Charging Flow Should Be Controlled To Maintain PRZR Level: a.Check RHR pumps-RUNNING IN INJECTION MODE b.Go to Step 19 a.Start charging pump and control charging flow to maintain PRZR level and go to Step 16.*****************************************CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
EOP:             TITLE$
16 Check RCP Status: a.RCPs-AT LEAST ONE RUNNING a.Perform the following:
REV    10 ES-1 '           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 13   of 23 STEP     ACTION/EXPECTED RESPONSE                 RESPONSE NOT OBTAINED 15   Check   If Charging Maintain Be Controlled To Flow Should PRZR Level:
1)Establish conditions for starting an RCP: o Verify Bus 11A or 11B energized.
: a. Check   RHR pumps   - RUNNING IN         a. Start charging pump and control INJECTION    MODE                            charging flow to maintain     PRZR level and go   to Step 16.
o Refer to Attachment RCP START.2)Start one RCP.IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).IF natural circulation NOT verified, THEN increase dumping steam.b.Stop all but one RCP-w EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 14 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.
: b. Go  to Step    19
THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.o If auxiliary spray is in use, spray flow may be increased by closing normal charging valve AOV-294 and normal PRZR spray valves.17 Depressurize RCS To Minimize RCS Subcooling:
  *****************************************
a.Depressurize using normal PRZR spray if available a.IF normal spray NOT available, THEN use one PRZR PORV.IF IA NOT available, THEN refer to Attachment N2 PORVS.b.Energize PRZR heaters as necessary c.Depressurize RCS until EITHER of the following conditions satisfied:
CAUTION IF RCP SEAL COOLING HAD PREVIOUSLY BEEN LOST, THEN THE AFFECTED RCP SHOULD NOT BE STARTED PRIOR TO A STATUS EVALUATION.
16   Check RCP       Status:
: a. RCPs   - AT LEAST   ONE RUNNING         a. Perform the following:
: 1) Establish conditions for starting an RCP:
o Verify Bus   11A or 11B energized.
o Refer to Attachment     RCP START.
: 2) Start one RCP.
IF an RCP can NOT be started, THEN verify natural circulation (Refer to Attachment NC).
IF natural circulation     NOT verified,   THEN increase dumping steam.
: b. Stop all   but one RCP-
 
w EOP:
REV: 10 ES-1 '         POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 14   of 23 STEP     ACTION/EXPECTED RESPONSE                   RESPONSE NOT OBTAINED
  *****************************************
CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION.           THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.
NOTE:   o WHEN   using a PRZR PORV, THEN   select   one with an operable block valve.
o If auxiliary spray     is in use, spray flow may     be increased by AOV-294 and normal PRZR spray valves.
closing normal charging valve 17   Depressurize RCS To Minimize RCS Subcooling:
: a. Depressurize using normal     PRZR         a. IF normal spray NOT available, spray  if available                            THEN use one PRZR PORV.
NOT available, THEN IF IA refer to Attachment N2 PORVS.
IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).
IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).
o RCS subcooling based on core exit T/Cs-LESS THAN 10'F USING FIGURE MIN SUBCOOLING-OR-o PRZR level-GREATER THAN.75%[65%adverse CNMT]  
: b. Energize  PRZR  heaters as necessary
: c. Depressurize RCS until EITHER of the following conditions satisfied:
o RCS   subcooling based on core exit   T/Cs - LESS THAN 10'F USING FIGURE MIN SUBCOOLING
                        -OR-o PRZR   level   - GREATER THAN. 75%
[65% adverse   CNMT]


EOP: ES-1.2 T!TLE POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate Shutdown Margin a.Direct HP to sample RCS for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.
EOP:             T!TLE REV  10 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 15 of 23 STEP       ACTION/EXPECTED RESPONSE       RESPONSE NOT OBTAINED 18   Verify Adequate       Shutdown Margin
*19 Monitor SI Reinitiation Criteria: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Manually operate SI pumps as necessary and go to Step 20.b, PRZR level-GREATER THAN 5%[30%adverse CNMT]b.Manually operate SI pumps as necessary and return to Step 10.  
: a. Direct   HP to sample RCS for boron concentration
: b. Verify boron concentration-       b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM
*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 go to Step 20.
USING FIGURE MIN SUBCOOLING b, PRZR level   - GREATER THAN 5%   b. Manually operate SI pumps as
[30%  adverse  CNMT]                necessary and return to Step 10.


EOP$ES-1.2.T1TLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 16 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If SI ACCUMs Should Be Isolated: a.RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING b.PRZR level-GREATER THAN 5%[30%adverse CNMT]c.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 d.Close SI ACCUM discharge valves~ACCUM A, MOV-841~ACCUM B, MOV-865 e.Locally reopen breakers for MOV-841 and MOV-865 a.IF both RCS hot leg temperatures less than 400'F, THEN go to Step 20c.IF NOT, THEN go to Step 21.b.Return to Step 10.d.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.  
EOP $             T1TLE$
REV    10 ES-1. 2 .       POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 16   of 23 STEP       ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED 20 Check Isolated:
If SI     ACCUMs   Should Be
: a. RCS subcooling based on core       a. IF both  RCS hot leg temperatures exit T/Cs - GREATER THAN O'           less than 400'F, THEN go to USING FIGURE MIN SUBCOOLING             Step 20c.
IF  NOT, THEN go  to Step 21.
: b. PRZR   level   - GREATER THAN 5%   b. Return to Step 10.
[30% adverse     CNMT]
: c. 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
: d. Close SI       ACCUM discharge valves d. Vent any unisolated    ACCUMs:
            ~ ACCUM   A, MOV-841                   1) Open vent valves for
            ~ ACCUM   B, MOV-865                       unisolated SI ACCUMs.
                                                        ~ ACCUM  A, AOV-834A
                                                        ~ ACCUM  B, AOV-834B
: 2) Open HCV-945.
: e. Locally reopen breakers       for MOV-841 and MOV-865
 
EOP:
REV: 10 ES-1.2          POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 17  of 23 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 21  Check  If Emergency Should Be Stopped:
D/Gs
: a. Verify AC  emergency busses        a. Try to restore offsite power energized by  offsite power:          (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).
o  Emergency D/G output breakers OPEN o  AC emergency  bus voltage-GREATER THAN  420 VOLTS o  AC  emergency bus normal feed breakers -  CLOSED
: b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 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 23.
: b. Verify AUX BLDG  SW  isolation    b. 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 ALARM    - EXTINGUISHED    5000 gpm and 6000 gpm  total flow.


EOP: ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 17 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Emergency D/Gs Should Be Stopped: a.Verify AC emergency busses energized by offsite power: o Emergency D/G output breakers OPEN a.Try to restore offsite power (Refer to ER-ELEC.l, RESTORATION OF OFFSITE POWER).o AC emergency bus voltage-GREATER THAN 420 VOLTS o AC emergency bus normal feed breakers-CLOSED b.Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP)22 Verify Adequate SW Flow To CCW Hx: a.Verify at least two SW pumps-RUNNING b.Verify AUX BLDG SW isolation valves-OPEN~MOV-4615 and MOV-4734~MOV-4616 and MOV-4735 c.Verify CNMT RECIRC fan annunciator C-2, HIGH TEMPERATURE ALARM-EXTINGUISHED a.Manually start pumps as power supply permits (258 kw per pump).IF less than two SW pumps can be operated, THEN go to Step 23.b.Establish SW to AUX BLDG (Refer to Attachment AUX BLDG SW).c.Dispatch AO to locally throttle flow to CCW Hx to between 5000 gpm and 6000 gpm total flow.
'
'
EOP: ES-1.2 T!TLE0 POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 18 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 Check RCP Cooling a.Check CCW to RCPs Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).o Annunciator A-7, RCP lA CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED o Annunciator A-15, RCP 1B CCW RETURN HIGH TEMP OR LOW FLOW EXTINGUISHED b.Check RCP seal in)ection o Labyrinth seal D/Ps-GREATER THAN 15 INCHES WATER-OR-o RCP seal injection flov to each RCP-GREATER THAN 6 GPM 3 It EOP: ES-1'POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 19 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Check If Seal Return Flow Should Be Established:
EOP:             T!TLE0 REV  10 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 18 of 23 STEP     ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED 23   Check RCP Cooling                       Establish normal cooling to RCPs (Refer to Attachment SEAL COOLING).
a.Verify instrument bus D-ENERGIZED b.Verify RCP&#xb9;1 seal outlet temperature
: 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
-LESS THAN 235'F c.Verify RCP seal outlet valves OPEN~AOV-270A~AOV-270B a.Restore power to instrument bus D from MCC B or MCC A (maintenance supply).b.Go to Step 25.c.Manually open valves as necessary.
: b. Check   RCP seal in)ection o Labyrinth seal D/Ps     - GREATER THAN 15 INCHES WATER
d.Reset both trains of XY relays for RCP seal return isolation valve MOV-313 e.Open RCP seal return isolation valve MOV-313 f.Verify RCP&#xb9;1 seal leakoff flow-LESS THAN 5.5 GPM g.Verify RCP&#xb9;1 seal leakoff flow GREATER THAN 0.25 GPM e.Perform the following:
                        -OR-o RCP   seal injection   flov to each   RCP   - GREATER THAN 6 GPM
1)Place MOV-313 switch to OPEN, 2)Dispatch AO with key to RWST gate to locally open MOV-313.f.IF any RCP seal leakoff flow greater than 5.5 gpm, THEN perform the following:
 
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 25'.Refer to AP-RCP.l, RCP SEAL MALFUNCTION.  
3 It
 
EOP:
REV    10 ES-1 '         POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 19   of 23 STEP     ACTION/EXPECTED RESPONSE         RESPONSE   NOT OBTAINED 24   Check   If   Seal Return Flow Should Be Established:
: a. Verify instrument   bus D-       a. Restore power to instrument bus ENERGIZED                             D from MCC B or MCC A (maintenance supply).
: b. Verify RCP &#xb9;1 seal outlet         b. Go  to Step 25.
temperature - LESS THAN 235'F
: c. Verify RCP seal outlet valves     c. Manually open valves as OPEN                                 necessary.
          ~ AOV-270A
          ~ AOV-270B
: d. Reset both   trains of XY relays for RCP seal return isolation valve MOV-313
: e. Open RCP seal return isolation e. 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.
: f. Verify RCP  &#xb9;1 seal leakoff flow f. IF any RCP seal leakoff flow
          - LESS THAN 5.5    GPM                greater than 5.5 gpm, THEN perform the following:
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 25
                                                          '.
: g. Verify RCP &#xb9;1 seal leakoff flow      Refer to AP-RCP.l,   RCP SEAL GREATER THAN    0.25 GPM            MALFUNCTION.


EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 20 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.
EOP:             TITLE:
25 Check Xf Source Range Detectors Should Be Energized:
REV  10 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 20   of 23 STEP       ACTION/EXPECTED RESPONSE             RESPONSE NOT OBTAINED NOTE:   Adverse   CNMT conditions or loss of forced   air cooling may result in failure of   NIS detectors.
a.Source range channels DEENERGIZED a.Go to Step 25e.b, Check intermediate range flux-EITHER CHANNEL LESS THAN 10 10 AMPS b.Perform the following:
25   Check Xf Source Range Detectors Should         Be Energized:
1)IF neither intermediate range channel is decreasing, THEN initiate boration.2)Continue with Step 26.WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 25c, d and e.c.Check the following:
: a. Source range channels                   a. Go to Step 25e.
o Both intermediate range channels-LESS THAN 10 AMPS c.Continue with Step 26.WHEN either condition met, THEN do Steps 25d and e.-OR-o Greater than 20 minutes since reactor trip d.Verify source range detectors-ENERGIZED d.Manually energize source range detectors by depressing P-6 permissive defeat pushbuttons (2 of 2).IF source ranges can NOT be restored, THEN refer to ER-NIS.l, SR MALFUNCTION and go to Step 25.e.Transfer Rk-45 recorder to one source range and one intermediate range channel  
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 26. WHEN flux is LESS THAN 10     amps on any operable channel,   THEN do Steps 25c, d and e.
: c. Check the following:                   c. Continue with Step 26.     WHEN either condition met,   THEN do o  Both intermediate range                Steps 25d and e.
channels - LESS THAN 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 25.
: e. Transfer Rk-45 recorder to one source range and one intermediate range channel


EOP$ES-1'TITLE$POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 21 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 Establish Normal Shutdown.Alignment:
EOP$             TITLE$
a.Check condenser-AVAILABLE a.Dispatch AO to perform Attachment SD-2.b.Perform the following:
REV    10 ES-1 '           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 21   of 23 STEP     ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED 26   Establish Normal Shutdown
o Open generator disconnects
      . Alignment:
~1G13A71~9X13A73 o Place voltage regulator to OFF o Open turbine drain valves o Rotate reheater steam supply controller cern 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 26d.2)Verify at least one control rod shroud fan-RUNNING 3)Verify one Rx compartment cooling fan-RUNNING 2)Manually start one fan as power supply permits (45 kw)3)Perform the following:
: a. Check condenser     - AVAILABLE         a. Dispatch AO to perform Attachment SD-2.
o Dispatch AO to reset UV relays at MCC C and MCC D.o Manually start one fan as power supply permits (23 kw)d.Verify Attachment SD-1-COMPLETE  
: 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 cern 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 26d.
: 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


EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 22 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check If RCPs Must Be Stopped: a.RCPs-ANY RUNNING b.Check the following:
EOP:             TITLE:
o RCP&#xb9;1 seal D/P-LESS THAN 220 PSID a.Go to Step 28.b.Go to Step 28.-OR-o RCP&#xb9;1 seal leakoff-LESS THAN 0.25 GPM c.Stop affected RCP(s)28 Check Condenser Steam Dump Available-CONDENSER VACUUM GREATER THAN 20 INCHES HG Use intact S/G'ARV for RCS temperature control.29 Check If RHR Normal Cooling Can Be Established:
REV: 10 ES-1.2             POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 22 of 23 STEP       ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED 27   Check   If RCPs   Must Be Stopped:
a.RCS cold leg temperature
: a. RCPs   - ANY RUNNING                 a. Go to Step 28.
-LESS THAN 350'F a.Return to Step 1.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL b.Go to Step 30.
: b. Check the following:                 b. Go to Step 28.
o   RCP &#xb9;1 seal   D/P - LESS THAN 220 PSID
                          -OR-o   RCP &#xb9;1 seal   leakoff - LESS THAN 0.25 GPM
: c. Stop affected RCP(s) 28   Check Condenser Steam Dump               Use intact S/G 'ARV for RCS Available        CONDENSER VACUUM        temperature control.
GREATER THAN 20 INCHES HG 29   Check Can Be IfEstablished:
RHR Normal     Cooling
: a. RCS cold leg temperature -   LESS a. Return to Step 1.
THAN  350'F
: b. RCS pressure -   LESS THAN         b. Go to Step 30.
400 psig [300 psig adverse   CNMT]
: c. Place   RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
: d. Consult TSC to determine     if RHR normal cooling should be established using Attachment RHR COOL


EOP:, ES-1.2 T!TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 23 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 30.30 Check CNMT Hydrogen Concentration:
EOP:,           T!TLE:
a.Direct HP to start CNMT hydrogen monitors as necessary)b.Hydrogen concentration
REV  10 ES-1.2           POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 23 of 23 STEP       ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED NOTE:   This procedure should be continued while obtaining       CNMT hydrogen sample in Step 30.
-LESS THAN 0.5%b.Consult TSC to determine if hydrogen recombiners should be placed in service.31 Check Core Exit T/Cs-LESS THAN 200'F Return to Step l.32 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions b.Consult TSC-END-  
30   Check CNMT   Hydrogen Concentration:
: a. Direct HP to start CNMT hydrogen monitors as necessary
      )
: b. Hydrogen concentration -   LESS         b. Consult   TSC to determine if THAN 0.5%                                  hydrogen recombiners should be placed in service.
31   Check Core     Exit T/Cs - LESS           Return to Step   l.
THAN  200'F 32   Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions
: b. Consult   TSC
                                              -END-


EOP ES-1.2 T!TLEI POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 1 of 1 ES-1.2 APPENDIX LIST TITLE 1)RED PATH  
EOP           T!TLEI REV  10 ES-1.2       POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 ES-1.2 APPENDIX LIST TITLE                               PAGES
: 1) RED PATH  


==SUMMARY==
==SUMMARY==
2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT SEAL COOLING 5)ATTACHMENT RCP START 6)ATTACHMENT NC 7)ATTACHMENT D/G STOP 8)ATTACHMENT SD-1 9)ATTACHMENT SD-2 10)ATTACHMENT SI/UV 11)ATTACHMENT N2 PORVS 12)ATTACHMENT RHR COOL 13)ATTACHMENT AUX BLDG SW 14)FOLDOUT PAGES
: 2) FIGURE MIN SUBCOOLING
: 3) FIGURE SDM
: 4) ATTACHMENT SEAL COOLING
: 5) ATTACHMENT RCP START
: 6) ATTACHMENT NC
: 7) ATTACHMENT D/G STOP
: 8) ATTACHMENT SD-1
: 9) ATTACHMENT SD-2
: 10) ATTACHMENT   SI/UV
: 11) ATTACHMENT N2 PORVS
: 12) ATTACHMENT RHR COOL
: 13) ATTACHMENT AUX BLDG SW
: 14) FOLDOUT
 
EOP:        TITLE!
REV: 10 ES-1.2      POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1  of 1 RED PATH SUMhG&Y
: 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% [46%
adverse  CNMT]
: c. HEAT SINK  Narrow  range level  in all  S/Gs  less than 5%
[25% adverse CNMT]  AND  total feedwater flow less than 200 gpm
: d. INTEGRITY  Cold  leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F
: e. CONTAINMENT  -  CNMT pressure greater than  60  psig
 
EOP:            T!TLE:
REV: 10 ES-1.2        POST LOCA COOLDOWN AND DEPRESSURIZATION 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 INADEQUATE 700 SUBCOOLING 600      ADVERSE CNMT                                                REGION 500 400 300 200                                        NORMAL CNMT                  TEMPERATURE INCREMENTS 10'F 100 0
200      250    300      350    400      450    500    550      600    650    700 CORE  EXIT SATURATION TEMPERATURE ('F)
 
1t EOP:            TITLE:
REV    10 ES-1.2          POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1    of  1 FIGURE SDM BORON CONCENTRATION  (PPM) 1800 BORON INCREMENTS 20  PPM 1600 1400 ADEQUATE SDM 1200                                                    100  PPM CONSERVATISM INCLUDED 1000 800 600 400 BORATE 200                                                                    BURNUP INCREMENTS 100 MWD/MTU 0    1000    2000  3000  4000  5000  6000    7000    8000  9000  10000  11000 CYCLE 22 BURNUP (MWD/HTU)
NOTE: To    obtain core burnup, use    PPCS  turn  on code BURNUP.
 
8 EOP:            T!TLE0 REV: 10 ES-1.2          POST LOCA COOLDOWN AND DEPRESSURIZATION 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 54
[304  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 O'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 54 [254 adverse CNMT]
: c. RCS  pressure:
o GREATER THAN 1625 PSIG [1825    psig adverse  CNMT]
o STABLE OR INCREASING
: d. PRZR  level  GREATER THAN 54  [304 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. COL  LEG    CIRCULATION SWITCHOVER CRITERION IF  RpST  level decreases to less than  284, THEN go  to ES-1.3, TRANSFER TO COLD LEG 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.1, 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 1.
 
EOPo          TITLE:
REV: 6 ES-3 ~ 1          POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC'EVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE
  'ATEGORY  1.0 REVIEWED BY:
 
ps-REV  6 ES-3.1          POST-SGTR COOLDOWN USING BACKFILL PAGE 2 of 9 A. PURPOSE  This  procedure provides actions to cool down and depressurize  the  plant to cold shutdown conditions following a SGTR. This recovery    method depressurizes the ruptured S/G by draining  it through  the  ruptured S/G tubes into the RCS.
B. ENTRY CONDITIONS/SYMPTOMS
: 1. ENTRY CONDITIONS    -  This procedure  is entered from:
: a. E-3 STEAM  GENERATOR TUBE RUPTURE&,
staff selects backfill method.
if plant
: b. ES-3.2,  POST-SGTR COOLDOWN USING BLOWDOWNg when blowdown    is not available and plant staff selects backfill. method.
 
V I i
l 4
 
EOP:            T!TLE0 REV: 6 ES-3.1              POST-SGTR COOLDOWN USING BACKFILL PAGE 3  of 9 STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED
  *****************************************
CAUTION INADVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.
J NOTE:  o  FOLDOUT  page should be open AND monitored  periodically.
o  Adverse  CNMT values should be used whenever CNMT pressure is greater than  4 psig or CNMT radiation is greater than 10+O R/hr.
1  Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure.
 
J 8
  ~
I
 
EOP              TITLE:
REV: 6 ES-3.1-              POST-SGTR COOLDOWN USING BACKFILL PAGE 4  of 9 STEP      ACTION/EXPECTED RESPONSE          RESPONSE NOT OBTAINED 2  Check Isolated:
If SI    ACCUMs    Should Be
: a. Check the    following:              a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o  RCS  subcooling based on core        RECOVERY DESIRED, Step 1.
exit  T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o  PRZR  level  - GREATER THAN 5S
[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  outlet valves    c. Vent any unisolated  ACCUMs:
            ~ ACCUM  A, MOV-841                    1) Open vent valves  for
            ~ ACCUM  B, 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
 
I t EOP:            TlTLE:
REV: 6 ES-F 1              POST-SGTR COOLDOWN USING BACKFILL E
PAGE 5  of  9 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED NOTE:  Leakage from ruptured S/G    into RCS will dilute  RCS boron concentration.
3  Verify Adequate      Shutdown Margin
: a. Direct  HP to sample RCS and ruptured S/G for boron concentration
: b. Verify boron concentration-              b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM
  *****************************************
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.
* 4 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 the intact 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.


EOP: ES-1.2 TITLE!POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 RED PATH SUMhG&Y a.SUBCRITICALITY
S
-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%[46%adverse CNMT]c.HEAT SINK-Narrow range level in all S/Gs less than 5%[25%adverse CNMT]AND total feedwater flow less than 200 gpm d.INTEGRITY-Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.CONTAINMENT
-r
-CNMT pressure greater than 60 psig


EOP: ES-1.2 T!TLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core.Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE
EOP:             T1TLE!
('F) 1t EOP: ES-1.2 TITLE: POST LOCA COOLDOWN AND DEPRESSURIZATION REV 10 PAGE 1 of 1 BORON CONCENTRATION (PPM)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPM 1400 1200 1000 ADEQUATE SDM 100 PPM CONSERVATISM INCLUDED800 600 400 BORATE 200 BURNUP INCREMENTS 100 MWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.
REV: 6 ES-3.1               POST-SGTR COOLDOWN USING BACKFILL PAGE 6    of 9 STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED NOTE:   Since ruptured S/G may continue to depressurize to less than the minimum  RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.
8 EOP: ES-1.2 T!TLE0 POST LOCA COOLDOWN AND DEPRESSURIZATION REV: 10 PAGE 1 of 1 FOLDOUT PAGE 1.SI REINITIATION CRITERIA IF EITHER condition listed below occurs, THEN manually operate SI pumps as necessary:
5  Initiate    RCS Cooldown To Cold Shutdown:
o RCS subcooling based on core exit T/Cs-LESS THAN O'F USING FIGURE MIN SUBCOOLING
: a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
-OR-o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[304 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 O'F USING FIGURE MIN SUBCOOLING b.Total feed flow to intact-S/Gs
: b. Use  RHR  system if in service
-GREATER THAN 200 GPM-OR-Narrow range level in at least one intact S/G-GREATER THAN 54[254 adverse CNMT]c.RCS pressure: o GREATER THAN 1625 PSIG[1825 psig adverse CNMT]o STABLE OR INCREASING d.PRZR level-GREATER THAN 54[304 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.COL LEG CIRCULATION SWITCHOVER CRITERION IF RpST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG 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.1, 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 1.  
: c. Dump  steam to condenser  from        c. Manually or locally dump steam intact  S/G                              using intact S/G ARV.
IF no  intact  S/G  available  and RHR  system  NOT  in service,   THEN perform the following:
o Use  faulted  S/G.
                                                                    -OR-o   Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
* 6 Monitor Ruptured S/G Narrow                 Refill ruptured    S/G to 67% [55%
Range Level  LEVEL GREATER               adverse   CNMT] using feed flow.
THAN 174    [254 adverse   CNMT]
IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:
o  Ruptured S/G pressure decreases in an uncontrolled manner.
                                                                -OR-o  Ruptured S/G pressure      increases to 1020  psig.


EOPo ES-3~1 TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC'EVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE'ATEGORY 1.0 REVIEWED BY:
g l
ps-ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV 6 PAGE 2 of 9 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by draining it through the ruptured S/G tubes into the RCS.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE&, if plant staff selects backfill method.b.ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWNg when blowdown is not available and plant staff selects backfill.method.
V I i l 4 EOP: ES-3.1 T!TLE0 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION INADVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.J NOTE: o FOLDOUT page should be open AND monitored periodically.
o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+O R/hr.1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure.
J~8 I EOP ES-3.1-TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:
o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.o PRZR level-GREATER THAN 5S[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 outlet valves~ACCUM A, MOV-841~ACCUM B, MOV-865 d.Locally reopen breakers for MOV-841 and MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.
I t EOP: ES-F 1 E TlTLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.
3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.
*****************************************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.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%adverse CNMT)and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in the intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.
S-r EOP: ES-3.1 T1TLE!POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To Cold Shutdown: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR system if in service c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV.IF no intact S/G available and RHR system NOT in service, THEN perform the following:
o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.*6 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.
g l EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*7 Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR level-LESS THAN 75%[65%adverse CNMT]a.Increase RCS makeup flow as.necessary and go to Step 8.b.Decrease RCS makeup flow to'ecrease level and go to Step 10.NOTE: The upper head region may void during RCS depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*8 Depressurize RCS To Backfill From Ruptured S/G: a.Depressurize using normal PRZR spray a.IF letdown is in service, THEN depressurize using auxiliary spray valve (AOV-296), IF NOT, THEN use one PRZR PORV.b.Maintain PRZR level-BETWEEN 13%AND 75%[BETWEEN 40%AND 65%adverse CNMT]c.Check ruptured S/G level-GREATER THAN 5$[25%adverse CNMT]d.Energize PRZR heaters as necessary e.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING c.Stop RCS depressurization.
**
EOP: ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish Recpxired RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)10 Check If RHR Normal Cooling Can Be Established:
a.RCS cold leg temperature
-LESS THAN, 350'F b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)a.Go to Step 11.b.Go to Step 11, c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.*ll'onitor RCP Operation:
a.RCPs-ANY RUNNING b.Check the folloving:
o RCP&#xb9;1 seal D/P-LESS THAN 220 PSID a.Go to Step 12.b.Go to Step 12.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)


EOP: ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 3.13 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC'END-
EOP:
REV: 6 ES-3 '              POST-SGTR COOLDOWN USING BACKFILL PAGE 7            of 9 STEP     ACTION/EXPECTED RESPONSE                 RESPONSE NOT OBTAINED
* 7 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
: a. PRZR  level -  GREATER THAN 13%          a. Increase  RCS makeup  flow as
[40%  adverse  CNMT]                        .necessary  and go to Step 8.
: b. PRZR  level  - LESS THAN   75%  [65%    b. Decrease  RCS makeup  flow to adverse  CNMT]                                        level and go  to Step 10.
                                                                                        'ecrease NOTE:  The upper head    region  may void during RCS depressurization    if RCPs are not running.      This  may result in a rapidly increasing PRZR level.
* 8 Depressurize        RCS To    Backfill From Ruptured S/G:
: a. Depressurize using normal      PRZR      a. IF letdown  is in service,  THEN spray                                        depressurize using auxiliary spray valve (AOV-296), IF NOT, THEN  use one PRZR PORV.
: b. Maintain  PRZR  level  - BETWEEN 13% AND 75% [BETWEEN 40% AND 65%
adverse CNMT]
: c. Check ruptured S/G    level-            c. Stop  RCS depressurization.
GREATER THAN 5$    [25%  adverse CNMT]
: d. Energize  PRZR  heaters as necessary
: e. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING


EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV',PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE 1)RED PATH  
*
* EOP:
REV: 6 ES-3.1                POST-SGTR COOLDOWN USING BACKFILL PAGE 8  of  9 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED 9  Establish      Recpxired  RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 10  Check Can Be IfEstablished:
RHR Normal      Cooling
: a. RCS cold leg    temperature  - LESS  a. Go  to Step 11.
THAN, 350'F
: b. RCS  pressure -    LESS THAN          b. Go  to Step 11, 400  psig [300 psig adverse    CNMT]
: c. Place  RCS  overpressure            c. 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.
: d. Establish    RHR  normal cooling (Refer to Attachment      RHR COOL)
*ll'onitor        RCP  Operation:
: a. RCPs  - ANY RUNNING                  a. Go  to Step 12.
: b. Check the folloving:                  b. Go  to Step 12.
o  RCP  &#xb9;1 seal D/P -    LESS THAN 220 PSID
                        -OR-o  Check  RCP seal leakage -  LESS THAN  0.25  GPM
: c. Stop affected RCP(s)
 
EOP:
REV: 6 ES-3.1              POST-SGTR COOLDOWN USING BACKFILL PAGE 9 of 9 STEP      ACTION/EXPECTED RESPONSE        RESPONSE NOT OBTAINED 12  Check Core    Exit  T/Cs  LESS      Return to Step 3.
THAN  200'F 13  Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
: b. Consult TSC '
END-
 
EOP:
REV' ES-3 '        POST-SGTR COOLDOWN USING BACKFILL
                                                      ,PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE                             PAGES
: 1) RED PATH  


==SUMMARY==
==SUMMARY==
2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES I a,g EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV 6 PAGE 1 of 1 RED PATH  
: 2) FIGURE MIN SUBCOOLING
: 3) FIGURE SDM
: 4) ATTACHMENT RHR COOL
: 5) FOLDOUT
 
I a,g
 
EOP:
REV  6 ES-3 '           POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 RED PATH  


==SUMMARY==
==SUMMARY==
a.SUBCRITICALITY
: a. SUBCRITICALITY Nuclear power   greater than 54
-Nuclear power greater than 54 b.CORE COOLING-Core exit T/Cs greater than 1200'F-OR-'ore exit T/Cs greater than 700'F AND RVLIS level (no RCPs)less than 434[46%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
: b. CORE COOLING   Core exit T/Cs greater than 1200'F exit T/Cs greater than 700'F AND
-CNMT pressure greater than 60 psig I'
                                            -OR-'ore RVLIS level (no RCPs) less than 434 [46%
EOP: ES-3'POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNHT NORMAL CNHT INADEQUATE SUBCOOL ING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE
adverse CNMT]
('F) l'~~~tl EOP t ES-F 1 T1TLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPM 1400 1200 1000 ADEQUATE SDH 100 PPH CONSERVATISM INCLUDED80O 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn on code BURNUP.  
: 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
 
I' EOP:
REV: 6 ES-3 '             POST-SGTR COOLDOWN USING BACKFILL 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 INADEQUATE 700 SUBCOOL ING 600     ADVERSE CNHT                                              REGION 500 400 300 200                                       NORMAL CNHT                   TEMPERATURE INCREMENTS 10'F 100 0
200     250     300     350     400     450     500   550     600     650   700 CORE EXIT SATURATION TEMPERATURE ('F)
 
l'~
~ ~
tl
 
EOP t           T1TLE:
REV: 6 ES-F 1             POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION   (PPH) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDH 1200                                                      100 PPH CONSERVATISM INCLUDED 1000 80O 600 400 BORATE 200                                                                       BURNUP INCREMENTS 100 HWD/MTU 0     1000     2000   3000   4000   5000   6000   7000   8000 9000   10000 11000 CYCLE 22 BURNUP (HWD/HTU)
NOTE: To     obtain core burnup, use     PPCS turn   on code BURNUP.
 
EOP!            TITLE:
REV: 6 ES-3 ~ 1              POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FOLDOUT PAGE 1~    SI REINITIATION CRITERI 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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR o  PRZR    level  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 [30% adverse    CNMT].
2 ~    SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
: 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 ~  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    '<  SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
 
i' EOP:
ES-3  '        POST-SGTR COOLDOWN USING BLOWDOWN
                                                    'EV:      7 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LANT SUPERINTENDENT 4-i0-9G EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
 
l
  ~i
 
F.OP REV: 7 ES-3. 2          POST-SGTR COOLDOWN USING BLOWDOWN PAGE 2 of 10 A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by draining via  S/G blowdown.
B. ENTRY CONDITIONS/SYMPTOMS
: 1. ENTRY CONDITIONS  - This procedure is entered from:
: a. E-3 STEAM  GENERATOR TUBE RUPTURE, selects the blowdown method.
if plant  staff
 
E
~ as
 
EOP              T1TLE:
REV: 7 ES-3  '            POST-SGTR COOLDOWN USING BLOWDOWN PAGE 3  of 10 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE:    o  FOLDOUT  page should. be open  AND monitored periodically.
o  Adverse  CNMT  values should be used whenever    CNMT  pressure is greater than  4 psig or  CNMT  radiation is greater than    10+    R/hr.
1  Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 2  Check Isolated:
If SI  ACCUMs  Should Be
: a. Check the following:                      a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o  RCS  subcooling based on core              RECOVERY DESIRED, Step 1.
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  outlet valves            c. Vent any unisolated    ACCUMs:
            ~ ACCUM  A, MOV-841                          1) Open vent valves    for
            ~ ACCUM  B) 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
 
    % ~
    'I e ~
 
EOP:              T1TLE:
REV: 7 ES-3  '                POST-SGTR COOLDOWN USING BLOWDOWN PAGE 4  of  10 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE:  Leakage from ruptured S/G        into RCS will dilute  RCS boron concentration.
3  Verify Adequate        Shutdown Margin
: a. Direct    HP to sample RCS and ruptured S/G for boron concentration
: b. Verify boron concentration-                b. Borate as necessary.
GREATER THAN REQUIREMENTS OF FIGURE SDM
  *****************************************
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.
* 4 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 intact S/G.
: b. Control feed flow to maintain              b. IF narrow range level in the narrow, range    level between  17%          intact S/G continues to increase
[25%,. adverse  CNMT]  and 50%                in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1,
 
a 4 EOP!            T!TLK:
REV: 7 ES-3  '              POST-SGTR COOLDOWN USING BLOWDOWN PAGE 5  of  10 STEP      ACTION/EXPECTED RESPONSE            RESPONSE  NOT OBTAINED NOTE:  Since ruptured S/G may continue to depressurize to less than the minimum  RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.
5  Initiate    RCS  Cooldown To 350'F:
: a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
: b. Dump steam to condenser  from        b. Manually or locally dump steam intact  S/G                          ~
from intact S/G using S/G ARV.
IF no  intact  S/G  available, THEN perform the following:
o  Use  faulted  S/G.
                                                                  -OR-o  Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step  l.
 
P 0
 
T1TLE:
REV: 7 ES-3 2
      ~                POST-SGTR COOLDOWN USING BLOWDOWN PAGE 6 of 10 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
*****************************************
CAUTION RCS AND RUPTURED S/G PRESSURES    MUST BE MAINTAINED LESS THAN    1050 PSIG.
* 6 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 CNMT]      makeup  flow    makeup  flow    makeup  flow o Depressurize                  o  Maintain RCS RCS  using                        and ruptured Step 6b,                          S/G pressure equal BETWEEN 13%            Depressurize    Energize        Maintain RCS
[40% ADVERSE CNMT]      RCS  using      PRZR            and ruptured AND 50%                  Step 6b.        heaters          S/G pressure equal.
BETWEEN 50% AND 75% o Depressurize      Energize        Maintain RCS
[65% ADVERSE CNMT]      RCS using        PRZR            and ruptured Step 6b.        heaters          S/G pressure equal o Decrease  RCS makeup  flow GREATER THAN 75%      o Decrease  RCS  Energize        Maintain RCS
[65% ADVERSE CNMT]      makeup  flow    PRZR            and ruptured heaters          S/G  pressure equal
: b. Use normal PRZR spray to obtain          b. IF letdown is in service, THEN desired results for Step 6a                  use auxiliary spray (AOV-296).
IF  NOT, THEN use one PRZR PORV.
 
EOP:              TITLE:
REV: 7 ES-3  '              POST-SGTR COOLDOWN USING BLOWDOWN PAGE 7  of 10 STEP        ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED 7  Establish Required          RCS Hydrogen Concentration (Refer to S-3.3C,      H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8  Check Be If Stopped:
RCS  Cooldown Should
: a. RCS  cold leg temperatures    - LESS    a. Return to Step 3.
THAN  350'F
: b. Stop  RCS  cooldown
: c. Maintain    RCS  cold leg temperature -    LESS THAN  350'F
* 9  Monitor Ruptured S/G Narrow                  Refill ruptured    S/G to 67%  [55%
Range Level - LEVEL GREATER                  adverse  CNMT]  using feed flow.
THAN 174      [254 adverse      CNMT]
IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:
o  Ruptured S/G pressure decreases in an  uncontrolled manner.
                                                                    -OR-o  Ruptured S/G pressure increases to 1020  psig.
NOTE:    Blowdown from    ruptured S/G may be stopped when RHR system    is placed in service.
10  Consult TSC To Determine                      IF blowdown can NOT be initiated, Appropriate Procedure To                      THEN go  to alternate post-SGTR Establish      Blowdown From                cooldown procedure,    ES-3.1, Ruptured S/G                                  POST-SGTR COOLDOWN USING BACKFILL, Step 1, OR ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.


EOP!ES-3~1 TITLE: POST-SGTR COOLDOWN USING BACKFILL REV: 6 PAGE 1 of 1 1~SI REINITIATION CRITERI FOLDOUT PAGE 2~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 O'USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
EOPs              TITLE~
OR o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[30%adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3.COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5.IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go'tO,.ECA-3
REV: 7 ES-3. 2               POST-SGTR COOLDOWN USING BLOWDOWN PAGE 8  of 10 STEP       ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED
'<SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
*11    Control      RCS  Makeup Flow And Letdown      To Maintain    PRZR Level:
i' EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN'EV: 7 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LANT SUPERINTENDENT 4-i0-9G EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
: a. PRZR level   - GREATER THAN   13%     a. Increase  RCS  makeup flow as
l~i F.OP ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 2 of 10 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by draining via S/G blowdown.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
[40% adverse   CNMT]                       necessary  and go to Step 12.
-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects the blowdown method.
: b. PRZR  level    - LESS THAN 75%   [65%   b. Decreases  RCS  makeup flow to adverse   CNMT]                             decrease  level  and go to Step 13.
E~as EOP ES-3'T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should.be open AND monitored periodically.
NOTE:     The upper head    region may void during depressurization    if RCPs are not running. This may result in a rapidly increasing PRZR level.
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 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:
*12    Depressurize        RCS To Minimize RCS-To-Secondarjj Leakage:
o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.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 outlet valves~ACCUM A, MOV-841~ACCUM B)MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.d.Locally reopen breakers for MOV-841 and MOV-865~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.  
: a. Depressurize     using normal   PRZR     a. IF letdown   is in service,   TBEN spray                                        depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV ~
%~'I e~
: b. Energize    PRZR  heaters as necessary
EOP: ES-3'T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.
: c. Maintain    RCS  pressure at ruptured    S/G  pressure
3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.
: d. Maintain    RCS  subcooling based on core  exit  T/Cs -  GREATER THAN O'F USING FIGURE MIN      SUBCOOLING
*****************************************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.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow, range level between 17%[25%,.adverse CNMT]and 50%a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1, a 4 EOP!ES-3'T!TLK: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To 350'F: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser from intact S/G b.Manually or locally dump steam~from intact S/G using S/G ARV.IF no intact S/G available, THEN perform the following:
o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step l.
P0 ES-3~2 T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.*6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage: a.Perform appropriate action(s)from table: PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13%[40%ADVERSE CNMT]o Increase RCS makeup flow o Depressurize RCS using Step 6b, Increase RCS o Increase RCS makeup flow makeup flow o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]Depressurize RCS using Step 6b.o Depressurize RCS using Step 6b.o Decrease RCS makeup flow o Decrease RCS makeup flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal.Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Use normal PRZR spray to obtain desired results for Step 6a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).
IF NOT, THEN use one PRZR PORV.  


EOP: ES-3'TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT)8 Check If RCS Cooldown Should Be Stopped: a.RCS cold leg temperatures
EOP:             T!TLE:
-LESS THAN 350'F a.Return to Step 3.b.Stop RCS cooldown c.Maintain RCS cold leg temperature
REV: 7 ES-3   '               POST-SGTR COOLDOWN USING BLOWDOWN PAGE 9  of 10 STEP       ACTION/EXPECTED RESPONSE           RESPONSE NOT OBTAINED
-LESS THAN 350'F*9 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.NOTE: Blowdown from ruptured S/G may be stopped when RHR system is placed in service.10 Consult TSC To Determine Appropriate Procedure To Establish Blowdown From Ruptured S/G IF blowdown can NOT be initiated, THEN go to alternate post-SGTR cooldown procedure, ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1, OR ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.  
*13    Monitor      RCP  Operation:
: a. RCPs  - ANY RUNNING                  a. Go  to Step 14.
: b. Check the following:                  b. Go  to Step 14.
o  RCP  &#xb9;1 seal D/P -   LESS THAN 220 PSID
                          -OR-o  Check  RCP  seal leakage  - LESS THAN  0.25  GPM
: c. Stop affected RCP(s) 14  Check Can Be IfEstablished:
RHR Normal      Cooling
: a. RCS cold leg temperature -     LESS a. Return to Step 9.
THAN 350'F
: b. RCS  pressure    - LESS THAN         b. Return to Step 9.
400  psig [300 psig adverse     CNMT]
: c. Place    RCS  overpressure            c. 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.
: d. Establish    RHR  normal cooling (Refer to Attachment      RHR COOL)


EOPs ES-3.2 TITLE~POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*11 Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR level-LESS THAN 75%[65%adverse CNMT]a.Increase RCS makeup flow as necessary and go to Step 12.b.Decreases RCS makeup flow to decrease level and go to Step 13.NOTE: The upper head region may void during depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*12 Depressurize RCS To Minimize RCS-To-Secondarjj Leakage: a.Depressurize using normal PRZR spray a.IF letdown is in service, TBEN depressurize using auxiliary spray valve (AOV-296).
I' EOP:              TITLE:
IF NOT, THEN use one PRZR PORV~b.Energize PRZR heaters as necessary c.Maintain RCS pressure at ruptured S/G pressure d.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING
REV: 7 ES-3 ~ 2               POST-SGTR COOLDOWN USING BLOWDOWN PAGE 10  of 10 STEP       ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED
                          'I 15  Continue      RCS     Cooldown To Cold Shutdown:
: a. Maintain cooldown rate        in  RCS cold legs -     LESS THAN 100'F/HR
: b. Use    RHR  System
: c. Dump  steam  to condenser from          c. Manually or locally dump steam intact  S/G                                using intact S/G ARV.
IF no intact    S/G  available and RHR system  NOT  in service, THEN perform the following:
o  Use  faulted  S/G.
                                                                        -OR-o  Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOIANT-SUBCOOLED RECOVERY DESIRED, Step  l.
16  Check Core        Exit    T/Cs   LESS        Return to Step 9.
THAN   200'F 17  Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions - (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
: b. Consult    TSC
                                                -END-


EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*13 Monitor RCP Operation:
I; EOP:
a.RCPs-ANY RUNNING b.Check the following:
REV: 7 ES-3 '         POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 ES-3.2 APPENDIX LIST TITLE                             PAGES
o RCP&#xb9;1 seal D/P-LESS THAN 220 PSID a.Go to Step 14.b.Go to Step 14.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)14 Check If RHR Normal Cooling Can Be Established:
: 1) RED PATH  
a.RCS cold leg temperature
-LESS THAN 350'F a.Return to Step 9.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMT]c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)b.Return to Step 9.c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.
I' EOP: ES-3~2 TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED'I 15 Continue RCS Cooldown To Cold Shutdown: a.Maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR System c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV.IF no intact S/G available and RHR system NOT in service, THEN perform the following:
o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOIANT-SUBCOOLED RECOVERY DESIRED, Step l.16 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 9.17 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions
-(Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC-END-I; EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 ES-3.2 APPENDIX LIST TITLE 1)RED PATH  


==SUMMARY==
==SUMMARY==
2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES I.
: 2) FIGURE MIN SUBCOOLING
EOP: ES-3'POST-SGTR COOLDOWN USING BLOWDOWN.REV: 7 PAGE 1 of 1 RED PATH  
: 3) FIGURE SDM
: 4) ATTACHMENT RHR COOL
: 5) FOLDOUT
 
I.
EOP:
REV: 7 ES-3 '           POST-SGTR COOLDOWN USING BLOWDOWN.
PAGE 1 of 1 RED PATH  


==SUMMARY==
==SUMMARY==
a.SUBCRITICALITY
: a. SUBCRITICALITY - Nuclear power   greater than 54
-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 434[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 temper'ature less than 285'F e.CONTAINMENT
: b. CORE COOLING   Core exit T/Cs greater than 1200'F
-CNMT pressure greater than 60 psig  
                                          -OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 434 [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 temper'ature less than 285'F
: e. CONTAINMENT - CNMT pressure greater than 60 psig
 
EOP:            TITLE:
REV: 7 ES-3.2                POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1  of  1 FIGURE MIN SUBCOOLING NOTE:    Subcooling Margin = Saturation Temperature            Fro'm 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 1400 SUBCOOLED 1300                            REGION 1200 1100 1000 900 800 700                                                                INADEQUATE SUBCOOLING 600                                                                  REGION ADVERSE GNAT 500 400 300 200                                          NORNL CNNT                  TEMPERATURE INCREMENTS 10'F 100 0
200      250      300      350      400    450      500  550      600    650    700 CORE  EXIT SATURATION TEMPERATURE ('F)
 
I
~
 
EOP:            T1TLE:
REV: 7 ES-3.2              POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1  of  1 FIGURE SDM BORON CONCENTRATION  (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 1000'DEQUATE SDH 1200                                                      100 PPM CONSERVATISM INCLUDED SOO 600 400 BORATE 200                                                                        BURNUP INCREMENTS 100 HWD/HTU 0    1000    2000  3000  4000  5000  6000    7000    8000    9000  10000 11000 CYCLE 22 BURNUP (HWD/HTU)
NOTE: To    obtain core burnup, use      PPCS  turn'n      code BURNUP.
 
l' EOP:            TiTLE:
REV: 7 ES-3  '              POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1  of 1 FOLDOUT PAGE 1~    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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
OR o  PRZR    level -  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 [304 adverse    CNMT].
2 ~    SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
: 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 ~  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 ~O IF any intact S/G has abnormal radiation,'HEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT  SUBCOOLED RECOVERY DESIRED, Step 1.
 
k /~V EOP:          T!TLE$
REV: 7 ES-3.3            POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:


EOP: ES-3.2 TITLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin=Saturation Temperature Fro'm Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700'1600 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE GNAT NORNL CNNT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE
EOP:         TITLE:
('F)
REV: 7 ES-3.3            POST-SGTR COOLDOWN USING STEAM DUMP PAGE 2 of 12 A. PURPOSE    - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by dumping steam.
~I EOP: ES-3.2 T1TLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000'DEQUATE SDH 100 PPM CONSERVATISM INCLUDEDSOO 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)NOTE: To obtain core burnup, use PPCS turn'n code BURNUP.
B. ENTRY CONDITIONS/SYMPTOMS
l' EOP: ES-3'TiTLE: POST-SGTR COOLDOWN USING BLOWDOWN REV: 7 PAGE 1 of 1 FOLDOUT PAGE 1~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 O'USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
: 1. ENTRY CONDITIONS      - This procedure  is entered from:
OR 2~o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54[304 adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3.COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5~IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner~O IF any intact S/G has abnormal radiation,'HEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.
: a. E-3 STEAM staff selects GENERATOR TUBE RUPTURE, steam dump method.
k/~V EOP: ES-3.3 T!TLE$POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
if plant b  ~   ES 3 ~ 2  POST SGTR COOLDOWN US ING BLOWDOWNg plant staff g
when blowdown    is not available  and selects steam    dump method.


EOP: ES-3.3 TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 2 of 12 A.PURPOSE-This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.This recovery method depressurizes the ruptured S/G by dumping steam.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
~ 4
-This procedure is entered from: a.E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects steam dump method.b~ES 3~2 g POST SGTR COOLDOWN US ING BLOWDOWN g when blowdown is not available and plant staff selects steam dump method.
* P ~ I EOP:           T!TLE!
~4*P~I EOP: ES-3'T!TLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.
REV: 7 ES-3 '             POST-SGTR COOLDOWN USING STEAM DUMP PAGE 3   of 12 STEP     ACTION/EXPECTED RESPONSE               RESPONSE NOT OBTAINED
o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.
  *****************************************
NOTE: o FOLDOUT page should be open AND monitored periodically.
CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G     IF WATER MAY EXIST IN ITS STEAMLINE.
o Adverse CNMT value's should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+R/hr.1 Energy.ze PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure  
o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.
NOTE:   o FOLDOUT   page should be open AND monitored   periodically.
o Adverse   CNMT value's should be used whenever CNMT pressure is greater than 4 psig or   CNMT radiation is greater than   10+   R/hr.
1 Energy.ze PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure


EOP: ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check If SI ACCUMs Should Be Isolated: a.Check the following:
EOP:
o RCS subcooling based on core exit T/Cs-GREATER THAN O'USING FIGURE MIN SUBCOOLING a.Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.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 outlet valves~ACCUM A, MOV-841~ACCUM B, MOV-865 d.Locally reopen breakers for MOV-841 and MOV-865 c.Vent any unisolated ACCUMs: 1)Open vent valves for unisolated SI ACCUMs.~ACCUM A, AOV-834A~ACCUM B, AOV-834B 2)Open HCV-945.  
REV: 7 ES-3.3             POST-SGTR COOLDOWN USING STEAM DUMP PAGE 4 of 12 STEP     ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 2 Check Isolated:
If SI ACCUMs Should       Be
: a. Check the following:               a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o  RCS  subcooling based on core      RECOVERY DESIRED, Step l.
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 outlet valves   c. Vent any unisolated  ACCUMs:
          ~ ACCUM   A, MOV-841                   1) Open vent valves for
          ~ ACCUM   B, 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: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.
EOP:             T!TLE:
=3 Verify Adequate Shutdown Margin a.Direct HP to sample RCS and ruptured S/G for boron concentration b.Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM b.Borate as necessary.
REV: 7 ES-3   '             POST-SGTR COOLDOWN USING STEAM DUMP PAGE 5   of 12 STEP     ACTION/EXPECTED RESPONSE               RESPONSE   NOT OBTAINED NOTE:   Leakage from ruptured S/G     into RCS will dilute   RCS boron concentration.
****************************************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.*4 Monitor Intact S/G Level: a.Narrow range level-GREATER THAN 5%[25%adverse CNMT]b.Control feed flow to maintain narrow range level between 17%[25%'dverse CNMT]and 50$a.Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%[25%adverse CNMT]in intact S/G.b.IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.  
  = 3 Verify Adequate       Shutdown Margin
.t=,~
: a. Direct HP to sample RCS and ruptured S/G for boron concentration
EOP: ES-3'POST-SGTR COOLDOWN USING STEAM'UMP REV: 7 PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.5 Initiate RCS Cooldown To 350'F: a.Establish and maintain cooldown rate in RCS cold legs-LESS THAN 100'F/HR b.Dump steam to condenser from intact S/G b.Manually or locally dump steam from intact S/G using S/G ARV.IF no intact S/G available, THEN perform the following:
: b. Verify boron concentration-             b. Borate as necessary.
o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.
GREATER THAN REQUIREMENTS OF FIGURE SDM
4 EOP$ES-3'ZLTLE$POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 7 of 12-STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.*6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage: a.Perform appropriate action(s)from table: PRZR LEVEL RUPTURED S/G NARROW RANGE LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 13$[40%ADVERSE CNMT]o Increase RCS makeup flow o Depressurize RCS using Step 6b.Increase RCS o Increase RCS makeup flow makeup flow o Maintain RCS and ruptured S/G pressure equal BETWEEN 13%[40%ADVERSE CNMT]AND 50%BETWEEN 50%AND 75%[65%ADVERSE CNMT]GREATER THAN 75%[65%ADVERSE CNMT]Depressurize RCS using Step 6b.o Depressurize RCS using Step 6b.o Decrease RCS makeup flow o Decrease RCS makeup flow Energize PRZR heaters Energize PRZR heaters Energize PRZR heaters Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal Maintain RCS and ruptured S/G pressure equal b.Use normal PRZR spray to obtain desired results for Step 6a b.IF letdown is in service, THEN use auxiliary spray (AOV-296).
  ****************************************
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.
* 4 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 intact 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%'dverse CNMT] and 50$                  in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step     l.
 
      .
t =, ~
 
EOP:
REV: 7 ES-3   '             POST-SGTR COOLDOWN USING STEAM'UMP PAGE 6 of 12 STEP       ACTION/EXPECTED RESPONSE             RESPONSE   NOT OBTAINED NOTE:   Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.
5 Initiate     RCS   Cooldown To 350'F:
: a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
: b. Dump steam to condenser   from       b. Manually or locally dump steam intact  S/G                              from intact S/G using S/G ARV.
IF no   intact S/G available, THEN perform the following:
o Use   faulted   S/G.
                                                                    -OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.
 
4 EOP$             ZLTLE$
REV: 7 ES-3   '               POST-SGTR COOLDOWN USING STEAM DUMP PAGE 7 of 12-STEP       ACTION/EXPECTED RESPONSE                 RESPONSE NOT OBTAINED
  *****************************************
CAUTION RCS AND RUPTURED     S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
* 6 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 CNMT]       makeup   flow   makeup flow     makeup flow o Depressurize                  o  Maintain RCS RCS using                        and ruptured Step 6b.                          S/G pressure equal BETWEEN 13%               Depressurize    Energize        Maintain RCS
[40% ADVERSE CNMT]       RCS using        PRZR            and ruptured AND 50%                   Step 6b.        heaters          S/G  pressure equal BETWEEN 50% AND 75% o Depressurize          Energize        Maintain RCS
[65% ADVERSE CNMT]       RCS using       PRZR            and ruptured Step 6b.         heaters          S/G pressure equal o Decrease   RCS makeup   flow GREATER THAN 75%        o Decrease   RCS   Energize        Maintain RCS
[65% ADVERSE CNMT]        makeup   flow   PRZR             and ruptured heaters          S/G pressure equal
: b. Use normal PRZR spray to obtain             b. IF letdown is in service, THEN desired results for Step 6a                    use auxiliary spray (AOV-296).
IF NOT, THEN use one PRER PORV.
IF NOT, THEN use one PRER PORV.
1 EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY.BURPING VCT)8 Check If RCS Cooldown Should Be Stopped: a.RCS cold leg temperatures
-LESS THAN 350'F a.Return to Step 3, b.Stop RCS cooldown c.Maintain RCS cold leg temperature
-LESS THAN 350'F*9 Monitor Ruptured S/G Narrow Range Level-LEVEL GREATER THAN 174[254 adverse CNMT]Refill ruptured S/G to 67%[55%adverse CNMT]using feed flow.IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G: o Ruptured S/G pressure decreases in an uncontrolled manner.-OR-o Ruptured S/G pressure increases to 1020 psig.
C EOP!ES-3'TITLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.NOTE: Steam release from ruptured S/G may be stopped when RHR System is in service.10 Initiate Cooldown Of Ruptured S/G: a.Verify condenser available:
o Intact S/G MSIV-OPEN o Annunciator G-15, STEAM DUMP ARMED-LIT a.Manually or locally dump steam using ruptured S/G ARV and go to Step 11.b.Dispatch AO to locally open ruptured S/G MSIV bypass valve c.Dump steam to condenser using steam dump pressure controller
*ll Control RCS Makeup Flow And Letdown To Maintain PRZR Level: a.PRZR level-GREATER THAN 13%[40%adverse CNMT]b.PRZR4~level
-LESS THAN 75%[65%adverse'CNMT]
a.Increase RCS makeup flow as necessary and go to Step 12.b.Decrease RCS makeup flow to decrease level and go to Step 13.
'I~
EOP ES-3'TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The upper head region may void during depressurization if RCPs are not running.This may result in a rapidly increasing PRZR level.*12 Depressurize RCS To Minimize RCS-To-Secondary Leakage: a.Depressurize using normal PRZR spray associated with running RCP a.IF letdown is in service, THEN depressurize using auxiliary spray valve (AOV-296).
IF NOT, THEN use one PRZR PORV.b, Energize PRZR heaters as necessary c.Maintain RCS pressure at ruptured S/G pressure d.Maintain RCS subcooling based on core exit T/Cs-GREATER THAN O'F USING FIGURE MIN SUBCOOLING
*13 Monitor RCP Operation:
a.RCPs-ANY RUNNING b.Check the following:
o RCP&#xb9;1 seal D/P-LESS THAN 220 PSID a.Go to Step 14.b.Go to Step 14.-OR-o Check RCP seal leakage-LESS THAN 0.25 GPM c.Stop affected RCP(s)


EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If RHR Normal Cooling Can Be Established a.RCS cold leg temperature
1 EOP:               T!TLE:
-LESS THAN 350'F a.Return to Step 9.b.RCS pressure-LESS THAN 400 psig[300 psig adverse CNMTj c.Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)d.Establish RHR normal cooling (Refer to Attachment RHR COOL)b.Return to Step 9.c.IF RCS overpressure protection system can NOT be placed in service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.15 Continue RCS Cooldown To Cold Shutdown: a.Maintain co'oldown rate in RCS cold legs-LESS THAN 100'F/HR b.Use RHR System c.Dump steam to condenser from intact S/G c.Manually or locally dump steam using intact S/G ARV IF no intact S/G available and RHR system NOT in service, THEN perform the following:
REV: 7 ES-3   '             POST-SGTR COOLDOWN USING STEAM DUMP PAGE 8  of 12 STEP         ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 7  Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY
o Use faulted S/G.-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.  
      . BURPING VCT) 8  Check Be If Stopped:
RCS  Cooldown Should
: a. RCS cold leg temperatures  - LESS a. Return to Step 3, THAN  350'F
: b. Stop  RCS  cooldown
: c. Maintain RCS cold leg temperature - LESS THAN 350'F
* 9 Monitor Ruptured S/G Narrow                Refill ruptured    S/G to 67% [55%
Range Level - LEVEL GREATER            adverse   CNMT] using feed flow.
THAN 174      [254 adverse  CNMT]
IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:
o  Ruptured S/G pressure decreases in an  uncontrolled manner.
                                                              -OR-o  Ruptured S/G pressure increases to 1020  psig.
 
C EOP!              TITLE!
REV: 7 ES-3  '              POST-SGTR COOLDOWN USING STEAM DUMP PAGE 9 of  12 STEP        ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED
  *****************************************
CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM          IS RELEASED.
NOTE:    Steam  release from ruptured  S/G may be stopped when RHR System      is in service.
10  Initiate      Cooldown Of Ruptured S/G:
: a. Verify condenser available:              a. Manually or     locally dump steam using ruptured    S/G ARV and go  to o  Intact    S/G MSIV - OPEN                Step 11.
o  Annunciator G-15,    STEAM DUMP ARMED    - LIT
: b. Dispatch AO to locally open ruptured S/G MSIV bypass valve
: c. Dump  steam to condenser using steam dump pressure controller
*ll    Control      RCS    Makeup Flow And Letdown      To  Maintain  PRZR Level:
: a. PRZR  level    - GREATER THAN 13%        a. Increase    RCS  makeup flow as
[40%  adverse    CNMT]                        necessary  and go  to Step 12.
: b. PRZR4~level -    LESS THAN 75% [65%      b. Decrease    RCS  makeup flow to adverse'CNMT]                                decrease  level  and go  to Step 13.
 
'I ~
EOP              TITLE:
REV: 7 ES-3  '              POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10    of 12 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE:  The upper head    region may void during depressurization    if  RCPs are level.
not running. This may result in a rapidly increasing    PRZR
  *12  Depressurize        RCS  To Minimize RCS-To-Secondary          Leakage:
: a. Depressurize using normal PRZR            a. IF letdown  is in service,   THEN spray associated with running RCP            depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN  use one PRZR PORV.
b, Energize    PRZR  heaters as necessary
: c. Maintain RCS pressure at ruptured S/G pressure
: d. Maintain    RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING
*13    Monitor    RCP  Operation:
: a. RCPs  - ANY RUNNING                      a. Go  to Step 14.
: b. Check the following:                     b. Go  to Step 14.
o RCP  &#xb9;1 seal    D/P - LESS THAN 220 PSID
                          -OR-o Check  RCP  seal leakage - LESS THAN  0.25  GPM
: c. Stop affected RCP(s)


ES-3'TLTLE0 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check Core Exit T/Cs-LESS THAN 200'F Return to Step 9.17 Evaluate Long Term Plant Status: a.Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)b.Consult TSC-END-e EOP!ES-3'TITLE!POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE 1)RED PATH  
EOP:            T!TLE:
REV: 7 ES-3 '             POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11  of 12 STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED 14  Check Can Be IfEstablished RHR Normal      Cooling
: a. RCS  cold leg temperature -      LESS  a. Return to Step 9.
THAN  350'F
: b. RCS  pressure -  LESS THAN            b. Return to Step 9.
400  psig [300 psig adverse      CNMTj
: c. Place  RCS  overpressure              c. 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.
: d. Establish    RHR normal cooling (Refer to Attachment      RHR COOL) 15  Continue    RCS  Cooldown To Cold Shutdown:
: a. Maintain co'oldown rate    in  RCS cold legs -    LESS THAN  100'F/HR
: b. Use  RHR  System
: c. Dump  steam to condenser    from      c. Manually or locally dump steam intact  S/G                              using intact S/G ARV IF  no  intact  S/G  available and RHR  system  NOT  in service, THEN perform the following:
o  Use  faulted  S/G.
                                                                    -OR-o  Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.
 
TLTLE0 REV: 7 ES-3 '            POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12 STEP     ACTION/EXPECTED RESPONSE         RESPONSE NOT OBTAINED 16 Check Core     Exit T/Cs   LESS       Return to Step 9.
THAN  200'F 17 Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
: b. Consult   TSC
                                    -END-
 
e EOP!         TITLE!
REV: 7 ES-3 '           POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE                               PAGES
: 1) RED PATH  


==SUMMARY==
==SUMMARY==
2)FIGURE MIN SUBCOOLING 3)FIGURE SDM 4)ATTACHMENT RHR COOL 5)FOLDOUT PAGES
: 2) FIGURE MIN SUBCOOLING
: 3) FIGURE SDM
: 4) ATTACHMENT RHR COOL
: 5) FOLDOUT
 
REV: 7 ES-3.3        POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 RED PATH SUMl6&Y
: 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 434 [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
 
Cl EOP:            T!TLE:
REV: 7 ES-3  '            POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1  of  1 FIGURE MIN SUBCOOLING NOTE:    Suhcooling 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 INADEQUATE 700 SUBCOOLING 600                                                                  REGION ADVERSE CNMT 500 400 300 200                                        NORMAL CNMT                  TEMPERATURE INCREMENTS 10'F 100 0
200      250    300      350    400      450    500    550      600    650    700 CORE  EXIT. SATURATION TEMPERATURE ('F)


ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 RED PATH SUMl6&Y a.SUBCRITICALITY
EOP!
-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 434[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
REV: 7 ES-3.3           POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION  (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 ADEQUATE SDH 1200                                                   100 PPH CONSERVATISM INCLUDED 1000 800 600 400 BORATE 200                                                                     BURNUP INCREMENTS 100 HWD/HTU 0   1000  2000    3000  4000  5000  6000    7000    8000  9000  10000 11000 CYCLE 22 BURNUP (MWD/HTU)
-CNMT pressure greater than 60 psig Cl EOP: ES-3'T!TLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Suhcooling Margin=Saturation Temperature From Figure Below[-]Core Exit T/C Indication RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0 S PRESSURE (PSIG)RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION ADVERSE CNMT NORMAL CNMT INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT.SATURATION TEMPERATURE
NOTE: To  obtain- core burnup, use    PPCS  turn  on code BURNUP.
('F)


EOP!ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 BORON CONCENTRATION (PPH)1800 FIGURE SDM 1600 BORON INCREMENTS 20 PPH 1400 1200 1000 ADEQUATE SDH 100 PPH CONSERVATISM INCLUDED800 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)NOTE: To obtain-core burnup, use PPCS turn on code BURNUP.  
EOP:            TITLE:
REV: 7 ES-3 '              POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FOLDOUT PAGE 1~    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 O' USING RE{}UIREMENTS OF FIGURE MIN SUBCOOLING.
OR o    PRZR    level  CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%  [30%  adverse CNMT].
2 ~    SECONDARY INTEGRITY      CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has.not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
3 ~  COLD LEG RECIRCULATION SWITCHOVER CRITERION IF  RWST    level decreases to less than 28%, THEN go to ES-1.3,      TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4 ~  AFW SUPPLY SWITCHOVER CRITERION IF  CST    level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
: 5. MULTIPLE      S G TUBE RUPTURE  CRITERIA IF any intact S/G level increases in in an uncontrolled maniier ~O 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.


EOP: ES-3'TITLE: POST-SGTR COOLDOWN USING STEAM DUMP REV: 7 PAGE 1 of 1 FOLDOUT PAGE 1~2~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 O'USING RE{}UIREMENTS OF FIGURE MIN SUBCOOLING.
    , jL P t
OR o PRZR level-CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5%[30%adverse CNMT].SECONDARY INTEGRITY CRITERIA IF any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has.not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.3~COLD LEG RECIRCULATION SWITCHOVER CRITERION 4~5.IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled maniier~O 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.
        ~ ~}}
, jL P t~~}}

Revision as of 18:43, 29 October 2019

Rev 5 to High Reactor Coolant Activity.
ML17262A349
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/20/1990
From: Widay J
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A347 List:
References
AP-RCS.3, NUDOCS 9102070081
Download: ML17262A349 (206)
v • d • e


Text

ECP: TITLE: REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 1 of 5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 40 P T SUPER NT NDENT

- cgQ-9b EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

9i0207008i 9i020i PDR l ADDCK 050002m<

PDR

/

P Q '1 II t

1 ~

k

EOP,:

REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 2 of 5 A. PURPOSE This procedure provides guidance necessary to operate the plant with indication of high reactor coolant activity.

B. ENTRY CONDITIONS/SYMPTOMS

1. SYMPTOMS The symptoms of HIGH REACTOR COOLANT ACTIVITY are;
a. Unexplained increase in letdown line monitor, R-9, or
b. Sampling indicates I-131 equivalent GREATER THAN 0.2 uCi/gm, or
c. Sampling indicates gross degassed activity GREATER THAN 20 uCi/gm, or
d. Sampling indicates that total specific activity exceeds 84/E.

~

'g(,"

"

TITLE: REV 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 3 of 5 STEP ACTION/BXPECTED RESPONSE RESPONSE NOT OBTAINED

                                                                    • CAUTION IF LETDOWN PLOW EXCEEDS 60 GPM WHEN USING AOV-202, D/P ACROSS THE CVCS DBMINERALIZERS SHOULD BE MONITORED TO VERIPY THAT FLOW IS CONTINUING THROUGH THE DI'S. HOWEVER, FLOW THROUGH THE DI'S SHOULD NOT EXCEED 90 GPM.

1 Verify RCS Activity:

a. Direct HP - TO SAMPLE RCS FOR ACTIVITY
b. RCS activity - GREATER THAN b. IP normal activity verified, NORMAL (Check with HP THEN direct I8C to check Department for normal activity) operability of R-9, letdown line monitor, AND return to normal operations.

2 Increase Letdown Flow To 60 GPM

a. Verify deborating DI i'solated- a. Place AOV-244 in bypass DIVERT VLV CATION DEBOR DI position.

AOV-244 IN BYPASS POSITION

b. Place PCV-135 to manual AND ad)ust as necessary - TO CONTROL LETDOWN PRESSURE
c. Change orifices - CLOSE 40 GPM ORIPICE AND OPEN 60 GPM LTDN ORIFICE AOV-202 IMMBDIATELY
d. Ad)ust letdown pressure - TO APPROXIMATELY 250 PSIG
e. Return PCV-135 - TO AUTO, IF DBSIRBD

t, 4

+4

(,

~ V aa

EOP.: LITLE: REV' AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 4 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.

3 Check Area Monitor R9 Refer to EPIP 1-0, GINNA STATION Letdown Line LESS THAN EVENT EVALUATION AND 200 MR/HR ABOVE BACKGROUND CLASSIFICATION.

CAUTION WHEN A NEW DI IS VALVED IN, THERE MAY BE A PLUS OR MINUS REACTIVITY ADDITION DUE TO A BORON CHANGE. (REFER TO S-3.2B TO PREVENT A REACTIVITY CHANGE.)

4 Verify Proper Operation Of IF DI efficiency is NOT Letdown DI DECONTAMINATION acceptable, THEN place a new mixed FACTOR GREATER THAN 10 bed in service. (Refer to S-4.5.7A, A LETDOWN MIXED BED DI RESIN REPLACEMENT, OR S-4.5.7B, B LETDOWN MIXED BED DI RESIN REPLACEMENT).

5. Check Sampling Requirements REFER TO TECHNICAL SPECIFICATION TABLE 4.1-4 6 Check If Continued Plant Power Operation Allowed:

IF shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.

o Continued plant power operation

- ALLOWED, REFER TO TECHNICAL SPECIFICATION SECTION 3.1.4

8 lk

'V$

it

EOP:

REV: 5 AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY PAGE 5 of 5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Aux Bldg For Increased Radiation Levels:

a. Notify HP Department - TO SURVEY AUX BLDG
b. Aux Bldg radiation levels- b. IF Aux Bldg radiation levels NORMAL (Check with HP for indicate above normal, THEN normal readings) have HP Department establish controls for the higher radiation areas.

8 Complete NOTIFICATION TO HIGHER SUPERVISION AND THE REACTOR ENGINEER 9 Check Conditions For Offsite Reporting:

o Refer to - EPIP 1-0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION

-END-

I

~8 h

0 P4 h

EOP:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 17 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 4P / 7~

PLANT SUPERINTENDENT 4-/1-5'8 EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

T!TLE REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 2 of 17 A. PURPOSE - This procedure provides actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under requirements that will preclude any upper head void formation.

B. SYMPTOMS AND OR ENTRY CONDITIONS This procedure is entered from:

1) ES-0.1, REACTOR TRIP RESPONSE, that a when natural circulation cooldown it has been determined is required.
2) ECA-0 when

', has been ALL it LOSS OF AC POWER RECOVERY WITHOUT determined that a SI REQUIRED/

natural circulation cooldown is required.

3) Other normal operating procedures 'when a natural circulation cooldown is required.

'r EOP: T1TLE:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 3 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION o IF SI ACTUATION OCCURS DURING THIS PROCEDURE, E-O, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.

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

NOTE: Foldout page should be open and monitored periodically.

  • 1 Monitor Conditions For RCP Restart:
a. Establish conditions for a. Go to Step 2.

starting an RCP:

o Bus 11A or 11B energiz.ed o Refer to Attachment RCP START

b. Start one RCP
c. Any RCP - RUNNING c. Go to Step 2.
d. Go to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITION

.

EOP s T!TLE:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 4 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check VCT Makeup System:

a. Verify the following:

l) Boric acid flow control valve - SET FOR REQUIRED CSD CONCENTRATION

2) RMW mode selector switch in AUTO
3) RMW control armed - RED LIGHT LIT
b. Check VCT level b. Manually increase VCT makeup flow as follows:

o Level - GREATER THAN 20$

1) Ensure BA transfer pumps and

-OR- RMW pumps running.

o Level - STABLE OR INCREASING 2) Place RMW,flow control valve HCV-ill in MANUAL and increase RNW flow.

3) Increase boric acid flow as necessary.

EOP:

REV' ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 5 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check Charging Pump Suction Aligned To VCT:

a. Check VCT level: a. IF VCT level can NOT be maintained greater than 5%, THEN o Level - GREATER THAN 20% perform the following:

o VCT makeup system - AVAILABLE 1) Ensure charging pump suction aligned to RWST o LCV-112B open o LCV-112C closed

2) Continue with Step 4. WHEN VCT level greater than 40$ ,

THEN do Step 3b.

b. Verify the following: b. Manually align valves as necessary.

o LCV-112C - OPEN o LCV-112B - CLOSED 4 Borate RCS To Cold Shutdown Boron Concentration (Refer to Figure SDM) 5 Establish Maximum Rx Vessel Start fans as necessary.

Head Cooling:

o Check control rod shroud fans (45,kw) - BOTH RUNNING o Check one Rx compartment cooling fan (23 kw)- RUNNING

EOP:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 6 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Adequate Shutdown Margin

a. Direct HP to sample the RCS for boron concentration

~ RCS loop A

~ RCS loop B

~ PRZR

b. Verify boron concentration- b. Perform the following:

GREATER -THAN REQUIREMENTS OF FIGURE SDM 1) Maintain RCS average temperature greater than 500'F until adequate SDM established.

2) Continue to borate as necessary.

'I I

~ x~ ~

EOP: T]ILE:

REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 7 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

o SI MUST BE BLOCKED BEFORE S/G PRESSURE DECREASES TO 514 PSIG.

o THE hT BETWEEN PRZR LIQUID AND THE HOT LEG TEMPERATURE SHOULD NOT BE PERMITTED TO EXCEED 200'F. IF THIS LIMIT IS EXCEEDED, THEN NOTIFY TECHNICAL ENGINEERING OF THE MAXIMUM hT OBSERVED.

7 Initiate RCS Cooldown To Cold Shutdown:

a. Dump steam to condenser a. Manually or locally dump steam using S/G ARVs.
b. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
c. Maintain S/G narrow range level c. Control feed flow as necessary.

BETWEEN 17$ AND 39%

d. Plot RCS cold leg temperatures and PRZR temperature twice per hour (Refer to 0-2.2, PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN, for plot paper) 8 Check:RCS Hot Leg Return to Step 7.

Temperatures LESS THAN 550'F

I H

- I

EOP t TlTLE:

REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 8 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o If charging line to PRZR vapor hT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.

o WHEN using a PRZR PORV, THEN select one with an operable block valve.

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

closing normal charging valve 9 Depressurize RCS To 1950 PSIG:

a. Check letdown - IN SERVICE a. Try to establish letdown (Refer to Attachment LETDOWN).

IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 10.

b. Depressurize RCS using auxiliary b. IF auxiliary spray valve NOT spray valve (AOV-296) available, THEN use one PRZR PORV.

FOP: T!TLE.

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDONN PAGE 9 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • * * * * * * * * * * * * * * * * * * * * * * * *
  • 4' *************

CAUTION SI ACTUATION CIRCUITS WILL AUTOMATICALLYUNBLOCK IF PRZR PRESSURE INCREASES TO GREATER THAN 1992 PSIG.

  • 10 Monitor SI Block Criteria:
a. Check the following: a. Return to Step 9.

o PRZR pressure - LESS THAN 1950 PSIG

-OR-o LOW PRZR PRESS BLOCK SAF INJEC status light - LIT h

b. Place SI block switches to BLOCK

~ Train A

~ Train B

c. Verify SAFETY INJECTION BLOCKED c. Maintain PRZR pressure greater status light - LIT than 1750 psig and S/G pressure greater than 514 psig until SI blocked.

11 Determine RCS Pressure And Temperature Limits-.

a. Check control rod shroud fans- a. Perform the following:

BOTH RUNNING

1) Maintain RCS pressure within limits of Figure NAT CIRC C/D WITHOUT SHROUD FANS.
2) Go to Step 12.
b. Maintain RCS pressure - WITHIN LIMITS OF FIGURE NAT CIRC C/D WITH SHROUD FANS

l O' T1TLE!

REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 10 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 12 Maintain PRZR Level Between 204 And 304
  • 13 Monitor RCS Cooldown:

o Core exit T/Cs - DECREASING o RCS hot leg temperatures-DECREASING o RCS subcooling based on core exit T/Cs - INCREASING o Cooldown rate in RCS cold legs-LESS THAN 25'F/HR

EOP $ TITLE$

REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 11 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o If at any time it is determined that a natural circulation cooldown and depressurization must be performed at a rate that may form a steam void in the vessel, then procedure ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAN VOID IN VESSEL, should be used.

o If charging line to PRZR vapor AT exceeds 320'F, then plant staff should be consulted before using auxiliary spray.

o WHEN using a PRZR PORV, THEN select one with an operable block valve.

o If auxiliary spray is in use, spray flow may be increased by AOV-294 and normal PRZR spray valves, closing normal charging valve 14 Initiate RCS Depressurization:

a. Check letdown - IN SERVICE a. Try to establish letdown (Refer to Attachment LETDOWN).

IF letdown can NOT be established, THEN depressurize RCS using one PRZR PORV and go to Step 15.

b. Depressurize RCS using auxiliary b. IF auxiliary spray valve NOT spray valve (AOV-296) available, THEN use one PRZR PORV.
c. Plot:" RCS temperature and pressure on curve selected in Step 11 hourly

EOP:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 12 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Continue Cooldown And Depressurization:

a. Check RCS cold leg temperature- a. Stabilize RCS temperature and go GREATER THAN 335'F to Step 15c.
b. Maintain cooldown rate in RCS cold legs - LESS THAN 25'F/HR
c. Maintain RCS temperature and c. Control RCS pressure as pressure within limits of Figure neces'sary to restore pressure/

determined previously temperature relationship to within limits of approprite Figure.

16 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 17 Check For Steam Void In Repressurize RCS within allowable Reactor Vessel: limits and continue cooldown.

o PRZR level - NO UNEXPECTED LARGE IF RCS depressurization must VARIATIONS continue, THEN go to ES-0.3, NATURAL CIRCULATION COOLDOWN WITH o RVLIS level (no RCPs) - GREATER STEAM VOID IN VESSEL.

THAN 95%

C I,

V l

t 4

l

EOP t REV: 5 ES-0 ' NATURAL CIRCULATION COOLDONN PAGE 13 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check If SI Isolated:

ACCUMs Should Be

a. RCS pressure - LESS THAN a. Continue with Step 19. WHEN RCS 1500 PSIG pressure is less than 1500 psig, THEN do Steps 18b through d.
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. IF any valve can NOT be closed, THEN perform the following:

~ ACCUM A) MOV-841

~ ACCUM B, MOV-865 1) Dispatch personnel to locally close valves, as necessary.

2) Maintain RCS pressure greater than 1000 psig until both SI ACCUMs isolated.

IF any SI ACCUM can NOT be isolated AND RCS depressurization to less than 1000 psig is required, THEN;

1) Open vent valves for unisolated SI ACCUMs,

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.
3) Maintain RCS pressure greater than SI ACCUM pressure.
d. Locally open breakers for MOV-841 and MOV-865

EOP:

REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 14 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 19 Maintain Letdown Flow:
a. Open letdown orifice valves as necessary
b. Adjust low pressure letdown control valve setpoint as necessary
  • 20 Maintain Required RCP Seal Perform the following:

Injection Flow And Labyrinth Seal D/P: o Adjust charging flow to REGEN Hx (HCV-142) as necessary.

o Labyrinth seal D/P to each RCP-GREATER THAN 15 INCHES OF WATER -OR-o Seal injection flow to each RCP o Dispatch AO to adjust seal

- GREATER THAN 6 GPM injection needle valves if necessary.

~ RCP A, V-300A

~ RCP B, V-300B

4 EOP:

REV' ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 15 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If SI System Normal Shutdown Alignment Should Be Established:

a. RCS cold leg temperature - LESS a. Return to Step 15.

THAN 350'F b, RCS pressure - LESS THAN b. Stabilize RCS temperature and 1500 PSIG return to Step 14.

c. Lock out SI system as follows:
1) Place all SI pump switches in PULL STOP
2) Locally close breakers for SI .

pump discharge valves to cold legs

~ MOV-878B, MCC D position 8C

~ MOV-878D, MCC D position 8F

3) Close SI pump discharge to cold legs

~ MOV-878B

~ MOV-878D

4) Locally open breakers for MOV-878B and MOV-878D

P t

EOPt TITLE:

REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 16 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 Check Can Be IfEstablished:

RHR Normal Cooling

a. RCS pressure - LESS THAN 400 PSIG a. Stabilize RCS temperature and return .to Step 14.
b. Verify all SI pump switches in b. Return to Step 21.

PULL STOP

c. Sample the RHR system to ensure adequate boron concentration (Refer to Attachment RHR SAMPLE)
d. Place RCS overpressure d. IF RCS overpressure protection protection system in service system can NOT be placed in (Refer to 0-7, ALIGNMENT AND service, THEN consult Plant OPERATION OF THE REACTOR VESSEL staff to determine if RHR normal OVERPRESSURE PROTECTION SYSTEM) cooling should be established and go to Step 23.
e. Establish RHR normal cooling (Refer to Attachment RHR COOL) 23 Continue RCS Cooldown To Cold.

Shutdown

CAUTION DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS IS LESS THAN 200'F MAY RESULT IN ADDITIONAL VOID FORMATION IN THE RCS.

24 Continue Cooldown Of Inactive Portion Of RCS:

a. Cool upper head region using control rod shroud fans
b. Cool S/G U-tubes by dumping steam from all S/Gs

EOP: T1TLE:

REV: 5 ES-O.' NATURAL CIRCULATION COOLDOWN PAGE 17 of 17 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION IF LESS THAN TWO CONTROL ROD SHROUD FANS ARE RUNNING, THE UPPER HEAD REGION MAY REMAIN ABOVE 200'F FOR UP TO 29 HOURS AFTER REACHING CSD.

25 Determine If RCS Depressurization Is Permitted:

a. Entire RCS - LESS THAN 200'F a. Do NOT depressurize RCS.

~ Core exit T/Cs Return to Step 23.

~ Upper head T/Cs

~ RCS hot leg temperature

~ RCS cold leg temperature

b. Check control rod shroud fan b. Consult Plant staff to determine status - BOTH RUNNING DURING wait period for upper head COOLDOWN cooling.
c. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD SHUTDOWN)

-END-

I EOP; T1TLE REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 ES-0.2 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) FIGURE SDM
4) FIGURE NAT CIRC C/D WITHOUT SHROUD FANS
5) FIGURE NAT CIRC C/D WITH SHROUD FANS
6) ATTACHMENT RCP START
7) ATTACHMENT LETDOWN
8) ATTACHMENT RHR COOL
9) ATTACHMENT RHR SAMPLE
10) FOLDOUT

EOP:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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% [46%

adverse CNMT]

c. HEAT SINK - Narrow range level in all S/Gs less than 5%

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

d. INTEGRITY Cold leg temperatures decrease greater than 100'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: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN 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 OI woo SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOL ING 600 ADVERSE CNMT REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

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

EOP: T!TLE:

REV 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREHENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONS ERVATISH INCLUDED 1000 8OO 600 400 BORATE 200 BURNUP INCREHENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)

NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

h, A"

EOP0 T!TLE:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FIGURE NAT CIRC C D WITHOUT SHROUD FANS RCS PRESSURE (PSIG) 2500 2400 RCS PRESSURE NORHAL INCREHENTS RCS temp RANGE 2300 20 PSIG for S/G SI 2200 (514 psig) 2100 SI UNBLOCK 2000 1900 1800 1700 1600 1500 [1] Wait 11 hrs before decreasing RCS pressure 1400 less than 1600 psig 1300 1200 1100 1000 900 800 700 [2] Wait 29 hrs before decreasing RCS pressure 600 less than 350 psig to prevent boiling in 500 upper head 400 300 200 TEHPERATURE 100 INCREHENTS 10'F 0 50 100 150 '200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEHPERATURE ('F)

EOP: TlTLE:

REV: 5 ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 1 of I FIGURE NAT CIRC C D WITH SHROUD FANS RCS PRESSURE (PSIG) 2500 2400 RCS PRESSURE INCREMENTS RCS temp 2300 for S/G SI 20 PSIG 2200 (514 psig) 2100 SI UNBLOCK 2000 1900 1800 A

1700 .V 0

1600 I

D 1500 1400 NORMAL 1300 RANGE 1200 1100 1000 900 800 700 600 500 400 300 200 TEMPERATURE ioo INCREMENTS 10'F 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 RCS COLD LEG TEMPERATURE ('F)

EOP: TlTLE:

REV: 5 ES-0 ' NATURAL CIRCULATION COOLDOWN PAGE 1 of 1 FOLDOUT PAGE 1~ RC T I CR TERIA IF BOTH conditions listed below occur, THEN trip both RCPs:

a. SI pumps - AT LEAST TWO RUNNING
b. RCS pressure minus maximum S/G pressure LESS THAN 175 PSIG 2 ~ SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST level decreases to 104, THEN ensure SI pump automatic switchover to RWST.

3 ~ SI ACTUATION CRITERIA IF EITHER condition listed below occurs, THEN actuate SI and go to E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1.

o RCS subcooling based on core exit T/Cs LESS THAN O'F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING OR-o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 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).

"Sy EOP: TITLE:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 23 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 .

REVIEWED BY:

P EOP: TITLE:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 2 of 23 A. PURPOSE This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS This procedure is entered from:

E 1 g LOSS OF REACTOR OR SECONDARY COOLANT g when RCS pressure is greater than the shutoff head pressure of the RHR pumps.

EOP: TITLE:

REV 10 ES-1s2 POST. LOCA COOLDOWN AND DEPRESSURIZATION PAGE 3 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION o 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 l.

o IF PRZR LEVEL IS LESS THAN 50% OR IF ADVERSE CNMT CONDITIONS EXIST, THEN PRZR HEATERS SHOULD NOT BE ENERGIZED UNTIL PRZR LEVEL IS EVALUATED BY THE TSC.

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

NOTE: o Foldout page should be open and monitored periodically.

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

  • I Monitor Be If RHR Stopped:

Pumps Should

a. Check RCS pressure: a. Go to Step 2.
1) Pressure - GREATER THAN 250 psig [465 psig adverse CNMT]
2) Pressure - STABLE OR INCREASING
b. Stop RHR pumps and place AUTO

EOP:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 4 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 2 Monitor All AC Busses-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 bus voltage - GREATER THAN necessary:

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) 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).

EOP:

REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 5 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Establish 75 GPM Charging Flaw:

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 RWST area key to locally isolate seal injection to affected RCP' V-300A for RCP A

~ V-300B for RCP B

2) Ensure HCV-142 open, demand at 0%.
b. Align charging pump suction to b. IF LCV-112B can NOT be opened, RWST' THEN perform the following:

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 (75 kw each) and establish 75 gpm total charging flow

~ Charging line flow

~ Seal injection flow

EOP! TITLE!

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 6 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Establish Condenser Steam Dump Pressure Control:

a. Verify condenser available: a. Place S/G ARV controllers in AUTO at desired pressure and go o Any MSIV - OPEN to Step 5.

o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Ad)ust condenser steam dump controller HC-484 to desired pressure and verify in AUTO
c. Place steam dump mode selector switch to MANUAL

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.

  • 5 Monitor Intact S/G Levels:
a. Narrow range level - GREATER a. Maintain total feed flow greater THAN 5S [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 any S/G narrow range level between 17% continues to increase in an

[25% adverse CNMT] and 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

EOP:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 7 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Shutdown margin should be monitored during RCS cooldown (Refer to Figure SDM).

6 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Use RHR system if in service
c. Dump steam to condenser from c. Manually or locally dump steam intact S/G(s) using intact S/Gs ARV.

7 Check RCS Subcooling'ased On Manually operate SI pumps as Core Exit T/Cs - GREATER THAN necessary and go to Step 19.

O'F USING FIGURE MIN SUBCOOLING 8 Check SI and RHR Pump Status: Go to Step 15.

o SI pumps - ANY RUNNING

-OR-o RHR pumps - ANY RUNNING IN INJECTION MODE 9 Place PRZR Heater Switches In The Following Positions:

o PRZR'eater control group - PULL STOP' PRZR heater backup group - OFF

"i EOP: TLTLE:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 8 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

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

10 Depressurize RCS To Refill PRZR:

a. Depressurize using normal PRZR a. Depressurize using one PRZR spray if available PORV. IF IA NOT available, THEN refer to Attachment N2 PORVS.

IF no PORV available, THEN use auxiliary spray valve (AOV-296).

b. PRZR level - GREATER THAN 13% b. Continue with Step ll. WHEN

[40$ adverse CNMT] level greater than 13% [40$

adverse CNMTJ, THEN stop RCS depressurization.

c. Stop RCS depressurization

4 EOP: T1TLE:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 9 of 23 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 EVALUATION.

11 Check Started:

If An RCP Should Be

a. Both RCPs - STOPPED a. Stop all but'one RCP and go to Step 12.
b. RCS subcooling based on core b. Go to Step 19, exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING
c. PRZR level - GREATER THAN 13% c. Return to Step 10.

[40$ adverse CNMT]

d. Try to start an RCP d. IF IA to CNMT available, THEN ensure at least one control rod
1) Establish conditions for shroud fan running (45 kw each).

starting an RCP o Bus 11A or 11B energized o Refer to Attachment RCP START

2) Start one RCP

I I EOP:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 10 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Pumps If One Of Three SI Should Be Stopped:

a. Three SI pumps - RUNNING a. Go to Step 13.
b. RCS subcooling based on core b. IF RCS hot leg temperatures exit T/Cs - GREATER THAN 35'F greater than 325'F [270'F

[90'F adverse CNMT] USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 12c. IF no RHR pump can be operated in injection mode, THEN go to Step 19.

c. Check PRZR level - GREATER THAN c. Do NOT stop SI pump. Return to 13% [40% adverse CNMT] Step 10.
d. Stop one SI pump

EOP! TlTLE~

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 11 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check If One Of Two SI Pumps Should Be Stopped:

a. Two SI pumps - RUNNING a. Go to Step 14.
b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE 120'F [200'F adverse CNMT]

ONE 115'F [190'F adverse CNMT]

105'F [180'F adverse CNMT]

THREE 100'F [175'F adverse CNMT)

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN ensure at least one RHR pump running in injection mode and go to Step 13d. IF no RHR pump can be operated in injection mode, THEN go to Step 19.

d. PRZR level - GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

e. Stop one SI pump

1 TITLEt EOP:

REV'0 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 12 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Be If Last Stopped:

SI Pump Should

a. One SI pump - RUNNING a.'F any RHR pump running in injection mode, THEN go to Step 19. IF NOT, THEN go to Step 15.
b. Determine required RCS subcooling from table:

Charging Pump RCS Subcooling Criteria Availability NONE Insufficient subcooling to stop SI pump.

ONE 255'F [295'F adverse CNMT]

TWO 235'F [285'F adverse CNMT]

THREE 210'F [270'F adverse CNMT]

c. RCS subcooling based on core c. IF RCS hot leg temperatures exit T/Cs - GREATER THAN VALUE greater than 325'F [270'F FROM TABLE ABOVE USING FIGURE adverse CNMT] OR IF RHR normal MIN SUBCOOLING cooling in service, THEN go to Step 19.

IF RHR normal cooling NOT in service AND RCS hot leg temperatures less than 325'F

[270'F adverse CNMT], THEN

,ensure at least one RHR pump running in injection mode and go to Step 14d. IF no RHR pump can be operated in injection mode, THEN go to Step 19.

d. PRZR level - GREATER THAN 13% d. Do NOT stop SI pump. Return to

[40% adverse CNMT] Step 10.

e. Stop running SI pump

EOP: TITLE$

REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If Charging Maintain Be Controlled To Flow Should PRZR Level:

a. Check RHR pumps - RUNNING IN a. Start charging pump and control INJECTION MODE charging flow to maintain PRZR level and go to Step 16.
b. Go to Step 19

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

16 Check RCP Status:

a. RCPs - AT LEAST ONE RUNNING a. Perform the following:
1) Establish conditions for starting an RCP:

o Verify Bus 11A or 11B energized.

o Refer to Attachment RCP START.

2) Start one RCP.

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

IF natural circulation NOT verified, THEN increase dumping steam.

b. Stop all but one RCP-

w EOP:

REV: 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 14 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION VOIDING MAY OCCUR IN THE RCS DURING RCS DEPRESSURIZATION. THIS WILL RESULT IN A RAPIDLY INCREASING PRZR LEVEL.

NOTE: o WHEN using a PRZR PORV, THEN select one with an operable block valve.

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

closing normal charging valve 17 Depressurize RCS To Minimize RCS Subcooling:

a. Depressurize using normal PRZR a. IF normal spray NOT available, spray if available THEN use one PRZR PORV.

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

IF no PRZR PORV available, THEN use auxiliary spray valve (AOV-296).

b. Energize PRZR heaters as necessary
c. Depressurize RCS until EITHER of the following conditions satisfied:

o RCS subcooling based on core exit T/Cs - LESS THAN 10'F USING FIGURE MIN SUBCOOLING

-OR-o PRZR level - GREATER THAN. 75%

[65% adverse CNMT]

EOP: T!TLE REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 15 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS for boron concentration
b. Verify boron concentration- b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

  • 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 go to Step 20.

USING FIGURE MIN SUBCOOLING b, PRZR level - GREATER THAN 5% b. Manually operate SI pumps as

[30% adverse CNMT] necessary and return to Step 10.

EOP $ T1TLE$

REV 10 ES-1. 2 . POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 16 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check Isolated:

If SI ACCUMs Should Be

a. RCS subcooling based on core a. IF both RCS hot leg temperatures exit T/Cs - GREATER THAN O' less than 400'F, THEN go to USING FIGURE MIN SUBCOOLING Step 20c.

IF NOT, THEN go to Step 21.

b. PRZR level - GREATER THAN 5% b. Return to Step 10.

[30% adverse CNMT]

c. 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

d. Close SI ACCUM discharge valves d. Vent any unisolated ACCUMs:

~ ACCUM A, MOV-841 1) Open vent valves for

~ ACCUM B, MOV-865 unisolated SI ACCUMs.

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.
e. Locally reopen breakers for MOV-841 and MOV-865

EOP:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 17 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Emergency Should Be Stopped:

D/Gs

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

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

b. Stop any unloaded emergency D/G and place in standby (Refer to Attachment D/G STOP) 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 23.
b. Verify AUX BLDG SW isolation b. 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 ALARM - EXTINGUISHED 5000 gpm and 6000 gpm total flow.

'

EOP: T!TLE0 REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 18 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 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 in)ection o Labyrinth seal D/Ps - GREATER THAN 15 INCHES WATER

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

3 It

EOP:

REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 19 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 Check If Seal Return Flow Should Be Established:

a. Verify instrument bus D- a. Restore power to instrument bus ENERGIZED D from MCC B or MCC A (maintenance supply).
b. Verify RCP ¹1 seal outlet b. Go to Step 25.

temperature - LESS THAN 235'F

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

~ AOV-270A

~ AOV-270B

d. Reset both trains of XY relays for RCP seal return isolation valve MOV-313
e. Open RCP seal return isolation e. 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.
f. Verify RCP ¹1 seal leakoff flow f. IF any RCP seal leakoff flow

- LESS THAN 5.5 GPM greater than 5.5 gpm, THEN perform the following:

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 25

'.

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

EOP: TITLE:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 20 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Adverse CNMT conditions or loss of forced air cooling may result in failure of NIS detectors.

25 Check Xf Source Range Detectors Should Be Energized:

a. Source range channels a. Go to Step 25e.

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 26. WHEN flux is LESS THAN 10 amps on any operable channel, THEN do Steps 25c, d and e.
c. Check the following: c. Continue with Step 26. WHEN either condition met, THEN do o Both intermediate range Steps 25d and e.

channels - LESS THAN 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 25.

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

EOP$ TITLE$

REV 10 ES-1 ' POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 21 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 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 cern 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 26d.
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

EOP: TITLE:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 22 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 Check If RCPs Must Be Stopped:

a. RCPs - ANY RUNNING a. Go to Step 28.
b. Check the following: b. Go to Step 28.

o RCP ¹1 seal D/P - LESS THAN 220 PSID

-OR-o RCP ¹1 seal leakoff - LESS THAN 0.25 GPM

c. Stop affected RCP(s) 28 Check Condenser Steam Dump Use intact S/G 'ARV for RCS Available CONDENSER VACUUM temperature control.

GREATER THAN 20 INCHES HG 29 Check Can Be IfEstablished:

RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Return to Step 1.

THAN 350'F

b. RCS pressure - LESS THAN b. Go to Step 30.

400 psig [300 psig adverse CNMT]

c. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
d. Consult TSC to determine if RHR normal cooling should be established using Attachment RHR COOL

EOP:, T!TLE:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 23 of 23 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: This procedure should be continued while obtaining CNMT hydrogen sample in Step 30.

30 Check CNMT Hydrogen Concentration:

a. Direct HP to start CNMT hydrogen monitors as necessary

)

b. Hydrogen concentration - LESS b. Consult TSC to determine if THAN 0.5% hydrogen recombiners should be placed in service.

31 Check Core Exit T/Cs - LESS Return to Step l.

THAN 200'F 32 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions
b. Consult TSC

-END-

EOP T!TLEI REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 ES-1.2 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

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

EOP: TITLE!

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 RED PATH SUMhG&Y

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% [46%

adverse CNMT]

c. HEAT SINK Narrow range level in all S/Gs less than 5%

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

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

EOP: T!TLE:

REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 INADEQUATE 700 SUBCOOLING 600 ADVERSE CNMT REGION 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

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

1t EOP: TITLE:

REV 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPM) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDM 1200 100 PPM CONSERVATISM INCLUDED 1000 800 600 400 BORATE 200 BURNUP INCREMENTS 100 MWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)

NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

8 EOP: T!TLE0 REV: 10 ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 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 54

[304 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 O'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 54 [254 adverse CNMT]
c. RCS pressure:

o GREATER THAN 1625 PSIG [1825 psig adverse CNMT]

o STABLE OR INCREASING

d. PRZR level GREATER THAN 54 [304 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. COL LEG CIRCULATION SWITCHOVER CRITERION IF RpST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG 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.1, 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 1.

EOPo TITLE:

REV: 6 ES-3 ~ 1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC'EVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE

'ATEGORY 1.0 REVIEWED BY:

ps-REV 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 2 of 9 A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by draining it through the ruptured S/G tubes into the RCS.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-3 STEAM GENERATOR TUBE RUPTURE&,

staff selects backfill method.

if plant

b. ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWNg when blowdown is not available and plant staff selects backfill. method.

V I i

l 4

EOP: T!TLE0 REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION INADVERTANT CRITICALITY MAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

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

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

1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure.

J 8

~

I

EOP TITLE:

REV: 6 ES-3.1- POST-SGTR COOLDOWN USING BACKFILL PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Isolated:

If SI ACCUMs Should Be

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step 1.

exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING o PRZR level - GREATER THAN 5S

[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 outlet valves c. Vent any unisolated ACCUMs:

~ ACCUM A, MOV-841 1) Open vent valves for

~ ACCUM B, 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

I t EOP: TlTLE:

REV: 6 ES-F 1 POST-SGTR COOLDOWN USING BACKFILL E

PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration- b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

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.

  • 4 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 the intact 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.

S

-r

EOP: T1TLE!

REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Use RHR system if in service
c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV.

IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

  • 6 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%

Range Level LEVEL GREATER adverse CNMT] using feed flow.

THAN 174 [254 adverse CNMT]

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:

o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR-o Ruptured S/G pressure increases to 1020 psig.

g l

EOP:

REV: 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 7 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
a. PRZR level - GREATER THAN 13% a. Increase RCS makeup flow as

[40% adverse CNMT] .necessary and go to Step 8.

b. PRZR level - LESS THAN 75% [65% b. Decrease RCS makeup flow to adverse CNMT] level and go to Step 10.

'ecrease NOTE: The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

  • 8 Depressurize RCS To Backfill From Ruptured S/G:
a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray depressurize using auxiliary spray valve (AOV-296), IF NOT, THEN use one PRZR PORV.
b. Maintain PRZR level - BETWEEN 13% AND 75% [BETWEEN 40% AND 65%

adverse CNMT]

c. Check ruptured S/G level- c. Stop RCS depressurization.

GREATER THAN 5$ [25% adverse CNMT]

d. Energize PRZR heaters as necessary
e. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING
  • EOP:

REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Establish Recpxired RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 10 Check Can Be IfEstablished:

RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Go to Step 11.

THAN, 350'F

b. RCS pressure - LESS THAN b. Go to Step 11, 400 psig [300 psig adverse CNMT]
c. Place RCS overpressure c. 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.
d. Establish RHR normal cooling (Refer to Attachment RHR COOL)
  • ll'onitor RCP Operation:
a. RCPs - ANY RUNNING a. Go to Step 12.
b. Check the folloving: b. Go to Step 12.

o RCP ¹1 seal D/P - LESS THAN 220 PSID

-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM

c. Stop affected RCP(s)

EOP:

REV: 6 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Core Exit T/Cs LESS Return to Step 3.

THAN 200'F 13 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
b. Consult TSC '

END-

EOP:

REV' ES-3 ' POST-SGTR COOLDOWN USING BACKFILL

,PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) FIGURE SDM
4) ATTACHMENT RHR COOL
5) FOLDOUT

I a,g

EOP:

REV 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 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 exit T/Cs greater than 700'F AND

-OR-'ore RVLIS level (no RCPs) less than 434 [46%

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

I' EOP:

REV: 6 ES-3 ' POST-SGTR COOLDOWN USING BACKFILL 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 INADEQUATE 700 SUBCOOL ING 600 ADVERSE CNHT REGION 500 400 300 200 NORMAL CNHT TEMPERATURE INCREMENTS 10'F 100 0

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

l'~

~ ~

tl

EOP t T1TLE:

REV: 6 ES-F 1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPM 1600 1400 ADEQUATE SDH 1200 100 PPH CONSERVATISM INCLUDED 1000 80O 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/MTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)

NOTE: To obtain core burnup, use PPCS turn on code BURNUP.

EOP! TITLE:

REV: 6 ES-3 ~ 1 POST-SGTR COOLDOWN USING BACKFILL PAGE 1 of 1 FOLDOUT PAGE 1~ SI REINITIATION CRITERI 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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 [30% adverse CNMT].

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

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 ~ 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 '< SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.

i' EOP:

ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN

'EV: 7 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE LANT SUPERINTENDENT 4-i0-9G EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

l

~i

F.OP REV: 7 ES-3. 2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 2 of 10 A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by draining via S/G blowdown.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-3 STEAM GENERATOR TUBE RUPTURE, selects the blowdown method.

if plant staff

E

~ as

EOP T1TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: o FOLDOUT page should. be open AND monitored periodically.

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

1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure 2 Check Isolated:

If SI ACCUMs Should Be

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step 1.

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 outlet valves c. Vent any unisolated ACCUMs:

~ ACCUM A, MOV-841 1) Open vent valves for

~ ACCUM B) 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

% ~

'I e ~

EOP: T1TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration- b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

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.

  • 4 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 intact S/G.

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

[25%,. adverse CNMT] and 50% in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1,

a 4 EOP! T!TLK:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To 350'F:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Dump steam to condenser from b. Manually or locally dump steam intact S/G ~

from intact S/G using S/G ARV.

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

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step l.

P 0

T1TLE:

REV: 7 ES-3 2

~ POST-SGTR COOLDOWN USING BLOWDOWN PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

  • 6 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 CNMT] makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b, S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS

[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal.

BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS

[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS

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

b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).

IF NOT, THEN use one PRZR PORV.

EOP: TITLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8 Check Be If Stopped:

RCS Cooldown Should

a. RCS cold leg temperatures - LESS a. Return to Step 3.

THAN 350'F

b. Stop RCS cooldown
c. Maintain RCS cold leg temperature - LESS THAN 350'F
  • 9 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%

Range Level - LEVEL GREATER adverse CNMT] using feed flow.

THAN 174 [254 adverse CNMT]

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:

o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR-o Ruptured S/G pressure increases to 1020 psig.

NOTE: Blowdown from ruptured S/G may be stopped when RHR system is placed in service.

10 Consult TSC To Determine IF blowdown can NOT be initiated, Appropriate Procedure To THEN go to alternate post-SGTR Establish Blowdown From cooldown procedure, ES-3.1, Ruptured S/G POST-SGTR COOLDOWN USING BACKFILL, Step 1, OR ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1.

EOPs TITLE~

REV: 7 ES-3. 2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 11 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
a. PRZR level - GREATER THAN 13% a. Increase RCS makeup flow as

[40% adverse CNMT] necessary and go to Step 12.

b. PRZR level - LESS THAN 75% [65% b. Decreases RCS makeup flow to adverse CNMT] decrease level and go to Step 13.

NOTE: The upper head region may void during depressurization if RCPs are not running. This may result in a rapidly increasing PRZR level.

  • 12 Depressurize RCS To Minimize RCS-To-Secondarjj Leakage:
a. Depressurize using normal PRZR a. IF letdown is in service, TBEN spray depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV ~
b. Energize PRZR heaters as necessary
c. Maintain RCS pressure at ruptured S/G pressure
d. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING

EOP: T!TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • 13 Monitor RCP Operation:
a. RCPs - ANY RUNNING a. Go to Step 14.
b. Check the following: b. Go to Step 14.

o RCP ¹1 seal D/P - LESS THAN 220 PSID

-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM

c. Stop affected RCP(s) 14 Check Can Be IfEstablished:

RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Return to Step 9.

THAN 350'F

b. RCS pressure - LESS THAN b. Return to Step 9.

400 psig [300 psig adverse CNMT]

c. Place RCS overpressure c. 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.
d. Establish RHR normal cooling (Refer to Attachment RHR COOL)

I' EOP: TITLE:

REV: 7 ES-3 ~ 2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

'I 15 Continue RCS Cooldown To Cold Shutdown:

a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Use RHR System
c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV.

IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOIANT-SUBCOOLED RECOVERY DESIRED, Step l.

16 Check Core Exit T/Cs LESS Return to Step 9.

THAN 200'F 17 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions - (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
b. Consult TSC

-END-

I; EOP:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 ES-3.2 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) FIGURE SDM
4) ATTACHMENT RHR COOL
5) FOLDOUT

I.

EOP:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN.

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 434 [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 temper'ature less than 285'F
e. CONTAINMENT - CNMT pressure greater than 60 psig

EOP: TITLE:

REV: 7 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature Fro'm 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 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 700 INADEQUATE SUBCOOLING 600 REGION ADVERSE GNAT 500 400 300 200 NORNL CNNT TEMPERATURE INCREMENTS 10'F 100 0

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

I

~

EOP: T1TLE:

REV: 7 ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 1000'DEQUATE SDH 1200 100 PPM CONSERVATISM INCLUDED SOO 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (HWD/HTU)

NOTE: To obtain core burnup, use PPCS turn'n code BURNUP.

l' EOP: TiTLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING BLOWDOWN PAGE 1 of 1 FOLDOUT PAGE 1~ 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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54 [304 adverse CNMT].

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

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 ~ 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 ~O IF any intact S/G has abnormal radiation,'HEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

k /~V EOP: T!TLE$

REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 2 of 12 A. PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR. This recovery method depressurizes the ruptured S/G by dumping steam.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:
a. E-3 STEAM staff selects GENERATOR TUBE RUPTURE, steam dump method.

if plant b ~ ES 3 ~ 2 POST SGTR COOLDOWN US ING BLOWDOWNg plant staff g

when blowdown is not available and selects steam dump method.

~ 4

  • P ~ I EOP: T!TLE!

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION o STEAM SHOULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN ITS STEAMLINE.

o AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS PROCEDURE.

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

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

1 Energy.ze PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

EOP:

REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Isolated:

If SI ACCUMs Should Be

a. Check the following: a. Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED o RCS subcooling based on core RECOVERY DESIRED, Step l.

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 outlet valves c. Vent any unisolated ACCUMs:

~ ACCUM A, MOV-841 1) Open vent valves for

~ ACCUM B, 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: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

= 3 Verify Adequate Shutdown Margin

a. Direct HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration- b. Borate as necessary.

GREATER THAN REQUIREMENTS OF FIGURE SDM

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.

  • 4 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 intact 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%'dverse CNMT] and 50$ in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step l.

.

t =, ~

EOP:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM'UMP PAGE 6 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Since ruptured S/G may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.

5 Initiate RCS Cooldown To 350'F:

a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Dump steam to condenser from b. Manually or locally dump steam intact S/G from intact S/G using S/G ARV.

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

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step l.

4 EOP$ ZLTLE$

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 7 of 12-STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION RCS AND RUPTURED S/G PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.

  • 6 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 CNMT] makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured Step 6b. S/G pressure equal BETWEEN 13% Depressurize Energize Maintain RCS

[40% ADVERSE CNMT] RCS using PRZR and ruptured AND 50% Step 6b. heaters S/G pressure equal BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS

[65% ADVERSE CNMT] RCS using PRZR and ruptured Step 6b. heaters S/G pressure equal o Decrease RCS makeup flow GREATER THAN 75% o Decrease RCS Energize Maintain RCS

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

b. Use normal PRZR spray to obtain b. IF letdown is in service, THEN desired results for Step 6a use auxiliary spray (AOV-296).

IF NOT, THEN use one PRER PORV.

1 EOP: T!TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR 02 REMOVAL FROM PRIMARY SYSTEM BY

. BURPING VCT) 8 Check Be If Stopped:

RCS Cooldown Should

a. RCS cold leg temperatures - LESS a. Return to Step 3, THAN 350'F
b. Stop RCS cooldown
c. Maintain RCS cold leg temperature - LESS THAN 350'F
  • 9 Monitor Ruptured S/G Narrow Refill ruptured S/G to 67% [55%

Range Level - LEVEL GREATER adverse CNMT] using feed flow.

THAN 174 [254 adverse CNMT]

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:

o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR-o Ruptured S/G pressure increases to 1020 psig.

C EOP! TITLE!

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

CAUTION RUPTURED S/G PRESSURE MAY DECREASE RAPIDLY WHEN STEAM IS RELEASED.

NOTE: Steam release from ruptured S/G may be stopped when RHR System is in service.

10 Initiate Cooldown Of Ruptured S/G:

a. Verify condenser available: a. Manually or locally dump steam using ruptured S/G ARV and go to o Intact S/G MSIV - OPEN Step 11.

o Annunciator G-15, STEAM DUMP ARMED - LIT

b. Dispatch AO to locally open ruptured S/G MSIV bypass valve
c. Dump steam to condenser using steam dump pressure controller
  • ll Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
a. PRZR level - GREATER THAN 13% a. Increase RCS makeup flow as

[40% adverse CNMT] necessary and go to Step 12.

b. PRZR4~level - LESS THAN 75% [65% b. Decrease RCS makeup flow to adverse'CNMT] decrease level and go to Step 13.

'I ~

EOP TITLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: The upper head region may void during depressurization if RCPs are level.

not running. This may result in a rapidly increasing PRZR

  • 12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:
a. Depressurize using normal PRZR a. IF letdown is in service, THEN spray associated with running RCP depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.

b, Energize PRZR heaters as necessary

c. Maintain RCS pressure at ruptured S/G pressure
d. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O'F USING FIGURE MIN SUBCOOLING
  • 13 Monitor RCP Operation:
a. RCPs - ANY RUNNING a. Go to Step 14.
b. Check the following: b. Go to Step 14.

o RCP ¹1 seal D/P - LESS THAN 220 PSID

-OR-o Check RCP seal leakage - LESS THAN 0.25 GPM

c. Stop affected RCP(s)

EOP: T!TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check Can Be IfEstablished RHR Normal Cooling

a. RCS cold leg temperature - LESS a. Return to Step 9.

THAN 350'F

b. RCS pressure - LESS THAN b. Return to Step 9.

400 psig [300 psig adverse CNMTj

c. Place RCS overpressure c. 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.
d. Establish RHR normal cooling (Refer to Attachment RHR COOL) 15 Continue RCS Cooldown To Cold Shutdown:
a. Maintain co'oldown rate in RCS cold legs - LESS THAN 100'F/HR
b. Use RHR System
c. Dump steam to condenser from c. Manually or locally dump steam intact S/G using intact S/G ARV IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

TLTLE0 REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check Core Exit T/Cs LESS Return to Step 9.

THAN 200'F 17 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
b. Consult TSC

-END-

e EOP! TITLE!

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 ES-3.3 APPENDIX LIST TITLE PAGES

1) RED PATH

SUMMARY

2) FIGURE MIN SUBCOOLING
3) FIGURE SDM
4) ATTACHMENT RHR COOL
5) FOLDOUT

REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 RED PATH SUMl6&Y

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 434 [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

Cl EOP: T!TLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Suhcooling 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 INADEQUATE 700 SUBCOOLING 600 REGION ADVERSE CNMT 500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0

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

EOP!

REV: 7 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FIGURE SDM BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 ADEQUATE SDH 1200 100 PPH CONSERVATISM INCLUDED 1000 800 600 400 BORATE 200 BURNUP INCREMENTS 100 HWD/HTU 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 22 BURNUP (MWD/HTU)

NOTE: To obtain- core burnup, use PPCS turn on code BURNUP.

EOP: TITLE:

REV: 7 ES-3 ' POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FOLDOUT PAGE 1~ 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 O' USING RE{}UIREMENTS OF FIGURE MIN SUBCOOLING.

OR o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% [30% adverse CNMT].

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

3 ~ COLD LEG RECIRCULATION SWITCHOVER CRITERION IF RWST level decreases to less than 28%, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

4 ~ AFW SUPPLY SWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

5. MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled maniier ~O 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.

, jL P t

~ ~

Retrieved from "https://kanterella.com/w/index.php?title=ML17262A349&oldid=1998050"