NL-08-154, Supplement to Reply to Request for Additional Information Regarding Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance: Difference between revisions

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=Text=
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{{#Wiki_filter:Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 SEntergy                                                          Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 R Walpole Manager, Licensing October 3, 2008 Re:  Indian Point Units 2 Docket Nos. 50-247 NL-08-1 54 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
{{#Wiki_filter:}}
 
==SUBJECT:==
Supplement to Reply to Request for Additional Information Regarding Indian Point Unit 2 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance (TAC NO.MD9214)
 
==References:==
: 1. Entergy letter NL-08-139 dated September 29, 2008 regarding "Reply to Request for Additional Information Regarding Indian Point Unit 2 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance (TAC NO.MD9214)"
 
==Dear Sir or Madam:==
 
Entergy Nuclear Operations, Inc (Entergy) provided additional information in Reference 1 regarding proposed changes to Indian Point 2 Technical Specifications regarding Diesel Generator endurance test surveillance. The procedures in Enclosure 1 were not the correct version of the procedures that Entergy intended to send. Please replace the  to Reference 1 with the attached Enclosure 1 to correct this error.
There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. R. Walpole, Manager, Licensing at (914) 734-6710.
R. Walpoe" Manager, Licensing Indian Point Energy cc (next page)
                                                                                                  ~fL-
 
NL-08-154 Docket 50-247 Page 2 of 2
 
==Enclosure:==
: 1. Copy of Emergency Operating Procedures (EOP) referenced in Load Studies Provided in Response to Question 8 in NL-08-139 cc:    Mr. John P. Boska, Senior Project Manager, NRC NRR Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Senior Resident Inspectors Office Mr. Paul Eddy, New York State Dept. of Public Service vi
 
Enclosure 1 TO NL-08-154 Copy of Emergency Operating Procedures (EOP)
Referenced in Load Studies Provided in Response to Question 8 in NL-08-139 List of Procedures included in Enclosure 1 EOP Number                              EOP Title                    Revision No.
2-E-0          Reactor Trip or Safety Injection                            0 2-ES-0.0      Rediagnosis                                                  0 2-ES-0.1      Reactor Trip Response                                        1 2-ES-0.2      Natural Circulation Cooldown                                0 2-ES-0.3      Natural Circulation Cooldown with Steam Void in Vessel      0 (with RVLIS) 2-ES-0.4      Natural Circulation Cooldown with Steam Void in Vessel      0 (without RVLIS) 2-E-1          Loss of Reactor or Secondary Coolant                        0 2-ES-1.1      SI Termination                                              1 2-ES-1.2      Post LOCA Cooldown and Depressurization                      0 2-ES-1.3      Transfer to Cold Leg Recirculation                          .1 2-ES-1.4      Transfer to Hot Leg Recirculation                            1 2-E-2          Faulted Steam Generator Isolation                            0 2-E-3          Steam Generator Tube Rupture                                0 2-ES-3.1      Post SGTR Cooldown Using Backfill                            0 2-ES-3.2      Post SGTR Cooldown Using Blowdown                            0 2-ES-3.3      Post SGTR Cooldown Using Steam Dump                          0 2-ECA-0.0      Loss of all AC Power                                        2 2-ECA-0.1      Loss of all AC Power Recovery without SI Required            0 2-ECA-0.2      Loss of all AC Power Recovery with SI Required              0 2-ECA-1.1      Loss of Emergency Coolant Recirculation                      0 ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET No. 50-247
 
Procedure Use Is: Control Copy:
SEntergy                  0 Continuous Nuclear Northeast      0 Reference      Effective Date: __/_/_
: r.
* TM, .  :.
O3 Information 2-E-0, Revision: 0 REACTOR TRIP          *=R*AEETY INJECTION Approved By:
Proced e Sponsor, RPO/ Dg Team P Procedure Owner
 
A. PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure.
B. SYMPTOMS AND ENTRY CONDITIONS
: 1) The following are symptoms that require a reactor trip, if    one has not occurred:.
REACTOR TRIP                              LOGIC                SETPOINT Overtemperature AT                        (2/4)                Variable Overpower AT                              (2/4)                Variable High pressurizer pressure                  (2/3)                2362 psig Low pressurizer pressure                  (2/4, P-7)            1930 psig High pressurizer level                    (2/3, P-7)            89%
Low flow or RCP breaker open              (2/4. P-7) (1/4, P-8) N/A RCP bus undervoltage                      (2/4, P-7)            75%
RCP bus underfrequency/RCP bkr open        (2/4, P-7) (1/4, P-8) 57.5 hz Source range high flux                    (1/2, P-1O and P-6)  2.3E5 CPS Intermediate range high flux              (1/2, P-10)          3.8E-5 amps Power range high flux low level trip      (2/4, P-10)          25%
Power range high flux high level trip      (2/4)                108%
Low SG level                              (1/8)                9%
and low feedwater flow          (mi! smatch of)            1.15 E6 lbs/hr Low low steam generator level              (2/3)                9%
Low RCS temperature                        (2/3)                385°F Turbine trip signal                        (P-7, P-8)            N/A
: 2)  The following are symptoms of a reactortrip:
o Reactor first out annunciator alarm.
o Turbine first out annunciator alarm.
o Rapid decrease in neutron level indicated by nuclear instrumentation.
o All shutdown and control rods are fully inserted.
o Rod bottom lights-are lit.
o Rapid decrease in SG level.
This Step Continued on the next page.
1 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
LNumber:
2-E-O
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION Revision Number:
REV. 0
: 3) The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
REACTOR TRIP AND SAFETY IN JECTION        LOGIC            SETPOINT Low pressurizer pressure                  (2/3)            1840 psig High steamline AP                        (1/4)            155 psid (less than two other loops)
High steamline flow                      (2/4)            1.3 E6 lbs/hr and TAVE                          (2/4)            5420 F or low steamline press ure        (2/4)            570 psig High containment pressure                (2/3)            2 psig High High containment pres sure          (2/2) of (2/3)  24 psig
: 4) The following are symptoms of a reactor trip and safety injection:
0 Reactor first out annunciator alarm.
0 SI first out annunciator alarm.
0  FW isolation.
0  Safeguards equipment sequence signal start.
0  Phase A isolation.
0 Steamline isolation.
: 5) This procedure should also be entered anytime a manual reactor trip or safety injection is actuated.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if      either of the following conditions exist:
o Containment radiation levels greater than iE5 R/hr.
                                - OR -
o Containment pressure greater than 4 psig.
2 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
: 1. Verify Reactor Trip:                  Manually trip reactor.
o Reactor trip breakers - OPEN        IF reactor will NOT trip, THEN go to 2-FR-S.1, RESPONSE TO NUCLEAR o Neutron flux - DECREASING          POWER GENERATION/ATWS, Step 1.
o Rod bottom lights - LIT o Rod position indicators - ALL RODS LESS THAN 7.5 INCHES
: 2. Verify Turbine Trip:
: a. All turbine stop valves -        a. Manually trip turbine. IF CLOSED                                turbine will NOT trip, THEN close MSIVs.
IF MSIVs can NOT be closed, THEN manually run back turbine.
3 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (30 0 F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-O                      REACTOR TRIP OR SAFETY INJECTION                    REV. 0
: 3. Verify Power To 480V Busses:
: a. 480V busses - AT LEAST ONE          a. Go to 2-ECA-O.O, LOSS OF ALL ENERGIZED:                            AC POWER, Step 1.
o 2A AND 3A OR -
o 5A
                        - OR -
o 6A
: b. 480V busses  - ALL ENERGIZED      b. Continue with Step 4. WHEN time permits, THEN try to restore power to deenergized 480V busses per:
o 2-AOP-480V-1,  LOSS OF NORMAL POWER TO ANY 480V BUS
                                                                - OR o 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6 4 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
I  2-E-O Number          Tirtle:
REACTOR TRIP OR SAFETY INJECTION.                          REV. 0 Revision Number: 1
: 4. Check SI Status:
: a. Check if  SI is  actuated:            a. Check if  SI is  required:'
o SI annunciator    -  LIT                o Containment pressure greater than 2 psig
                        - OR  -
OR  -
o SI system pumps    -  RUNNING o PRZR pressure less than 1840 psig OR-o PRZR level less than 14%
OR -
o Steamline AP greater than 155 psid OR  -
o High steamline flow with either TAVE less than 542 0 F OR steamlin.e pressure less than 570 psig IF SI is required, THEN manually actuate.
IF SI is NOT required,      THEN perform the following:
: 1) Verify AFW pump(s) running as necessary to establish total feed flow greater than. 760 gpm.
                                                          .2) Maintain total feed flow greater than 760 gpm.
: 3) GO To 2-ES-0.1, REACTOR TRIP RESPONSE, Step 1.
This Step continued on the next page.
5 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA; IF BOTH conditions listed below occur. trip all RCPs:
: a. SI pumps -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit ICs  - LESS THAN 231F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CSTIevel decreases to less than 2 ft. switch to city water supply.
: b. Both trains of SI  - ACTUATED:      b. IF one train is actuated AND safeguards pumps are running.
THEN go to Step 5.
IF NEITHER train is actuated, THEN manually actuate both trains of SI AND verify manual relay(s):
o Train A master relay'SIM-1 (above rack E) o Train B master relay SIM-2 (above rack F)
: 5. Perform ATTACHMENT 1 While Continuing With This Procedure
: 6. Verify AFW Pumps Running:
: a. Motor-driven pumps    RUNNING      a. Manually start pumps.
: b. Turbine-driven pump  -  RUNNING    b. Perform the following:
IF NECESSARY
: 1) Manually open steam supply.
regulator valve:
o PCV-1139
: 2)  Open turbine-driven AFW pump FCVs as necessary.
: 3) Adjust turbine speed control valve as necessary:
o HCV-1118 6 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 7. Verify Total AFW Flow - GREATER      IF SG narrow range level greater THAN 400 GPM                          than 10% (27% FOR ADVERSE CONTAINMENT) in any SG, THEN control feed flow to maintain narrow range level.
IF narrow range level less than 10% (27% for ADVERSE CONTAINMENT) in all SGs, THEN perform the following:
: a. Manually start pumps AND) align valves as necessary.
: b. IF AFW flow greater than 400 gpm can NOT be established, THEN go to 2-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. Step 1.
7 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 23-F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
"                                  CAUTION
"  RCS pressure should be monitored. IF RCS pressure decreases in an
"  uncontrolled manner to less than 320 psig (340 psig FOR ADVERSE
* CONTAINMENT), any RHR pump placed in PULLOUT must be manually restarted    *
* to supply water to the RCS. This pump should ONLY be restarted when the    *
* running RHR pump has loop flow indicated.
: 8. Verify SI System Flow:
: a. RCS pressure - LESS THAN          a. Place one RHR pump in PULLOUT.
1660 PSIG (1690 PSIG FOR            Go to Step 9.
ADVERSE CONTAINMENT)
: b. SI pump flow - FLOW INDICATED      b. Manually start pumps and align valves.
: c. RCS pressure - LESS THAN          c. Place one RHR pump in PULLOUT.
320 PSIG (340 PSIG FOR ADVERSE        Go to Step 9.
CONTAINMENT)
: d. RHR pump flow - FLOW INDICATED    d. PERFORM the following:
: 1) IF NO RHR pumps are running, THEN align valves and manually start ONE pump.
a)  IF RHR loop flow is indicated, THEN start second RHR pump.
: 2)  IF BOTH RHR pumps are running AND NO RHR lop flow is indicated, THEN place ONE RHR pump in PULLOUT.
8 of 35
 
FOLDOUT PAGE FOR 2-E--O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-O                          REACTOR TRIP OR SAFETY INJECTION                    REV. 0 STP        ATONEPCEDRSOSERSOS                                NO  OT    INE
: 9. Check RCP Seal Cooling:
: a. Three CCW pumps - RUNNING            a. Manually start CCW pumps on busses supplied by offsite power.
IF NO CCW pumps can be started, THEN refer to 2-SOP-4.1.2 COMPONENT COOLING SYSTEM OPERATION to establish backup cooling to:
o Charging pumps o RHR pumps 0 SI pumps This Step continued on the next page.
9 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-O                    REACTOR TRIP OR SAFETY INJECTION                      REV. 0
: b. CCW flow to RCP thermal            b. IF CCW to RCPs is lost, THEN:
barriers - NORMAL:
: 1) Stop all RCPs.
o RCP Thermal Barrier CCW alarms - CLEARED                    2)  IF NO charging pump running, THEN:
a) Verify adequate power available to run one charging pump. If necessary, shed sufficient non-essential loads.
b)  Start one charging pump in MANUAL at maximum speed for pump cooling.
: c. Check service water system    -    c. Locally close the following ALIGNED FOR THREE HEADER              valves:
OPERATION o Service water valve pit:
o  FCV-1111 o  FCV-1112 o  SWN-6 o  SWN-7 WHEN valves are closed,      THEN do Steps 9d and 9e.
Go to Step 10.      OBSERVE CAUTION PRIOR TO STEP 10.
: d. Locally verify following valves in zurn strainer pit    -
CLOSED:
o SWN-4 o SWN-5
: e. Start one service water pump on NON-essential header on bus supplied by offsite power in preferred order:
o 22, 23. 21 if  1-2-3 header NON-essential
                      - OR -
o 25, 26, 24 if  4-5-6 header NON-essential 10 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (30OF FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
IINumber :            ITitle:                                                                  Revision Number:
2-E-0                            REACTOR TRIP OR SAFETY INJECTION                              REV. 0
          *
* a  *  * *
* a
* a * * *  * * *
* a  * * *  *
* a * *
* a
* a a
* a a
* a a  *
* a a
CAUTION a
* IF adverse containment conditions exist, use wide range cold leg                                  a
* temperatures to determine RCS temperature.                                                        a a a  a  a  a a  a a  a a a
* a a a a  a a  a a a
* a  a a a  a
* a  a a
* a *
* a  a a  a a
      *10.        Check RCS Temperatures:                    IF temperature less than 5470F and decreasing, THEN:
o RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 547 0 F IF ANY        a. Stop dumping steam.
RCP RUNNING
: b. IF cooldown continues, THEN
                                - OR -                            control feed flow.        Maintain total feed flow greater than o RCS COLD LEG TEMPERATURES                      400 gpm until narrow range STABLE AT OR TRENDING TO 5470F                level greater than 10% (27%
IF NO RCP RUNNING                              FOR ADVERSE CONTAINMENT) in at least one SG.
: c. IF cooldown continues. THEN close MSIVs. IF valves can NOT be closed, THEN locally close MSIVs per 2-SOP-ESP-OO1, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS.
IF temperature greater than 5470F and increasing,        THEN:
o Dump steam to condenser.
                                                                            -  OR -
o Dump steam using SG atmospheric steam dumps.
11 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs -'LESS  THAN 230 F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 11. Check PRZR PORVs And Spray Valves:
: a. PORVs - CLOSED                    a. IF PRZR pressure less than 2335 psig, THEN manually close PORVs.
IF any PORV can NOT be closed, THEN manually close its block valve. IF block valve can NOT be closed, THEN go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
: b. Normal PRZR spray valves -        b. IF PRZR pressure less than CLOSED                              2210 psig, THEN manually close valves.
IF valves can NOT be closed, THEN stop ANY RCP(s) required to stop spray flow.
: c. Auxiliary spray valve - CLOSED    c. Manually close auxiliary spray valve.
IF valve can NOT be closed, THEN locally energize AND close charging line isolation valves:
o MOV-205 (At MCC 26AA)
                                                      - OR -
o MOV.-226 (At MCC 26BB) AND MOV-227 (At MCC 26AA) 12 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions. listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30OF FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[  2-E-O Number:
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION                REV. 0 Revision Number: 1
: 12. Check If    RCPs Should Be Stopped:
: a. SI pumps - AT LEAST ONE RUNNING    a. Go to Step 13.
: b. RCS subcooling based on core        b. Go to Step 13.
exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: c. Stop all RCPs
: 13. Check If Any SG Is Faulted:
: a. Check pressures in all SGs:        a. Go to Step 14.
o ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
                        - OR -
o ANY SG COMPLETELY DEPRESSURIZED
: b. Go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1
: 14. Check If    SG Tubes Are Intact:        Go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
o Main steamline radiation recorder (R-28, R-29, R-30,    and R-31) - NORMAL o Condenser air ejector radiation recorder (R-45) - NORMAL o SG blowdown radiation recorder (R-49) - NORMAL o NO SG LEVEL INCREASING IN AN UNCONTROLLED MANNER 13 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AF* SUPPLY SWITCHOVER CRITERION; IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:      ITitle:                                                        Revision Number:
2-E-O                    REACTOR TRIP OR SAFETY INJECTION                    REV. 0
: 15. Check If  RCS Is Intact:                Go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
o Containment sump level    -  NORMAL o Recirculation sump level    -
NORMAL o Reactor cavity sump level      -
NORMAL o Containment pressure - NORMAL o Gaseous particulate radiation recorder (R-41, R-42)      NORMAL o Containment radiation (R-25, R-26) - NORMAL o Containment area radiation NORMAL:
o Area Monitor High Radiation alarm - CLEARED OR -
o Containment area radiation (R-2, R-7) - NORMAL 14 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
  ,b. RCS subcooling based on core exit TCs  - LESS THAN 230F (309F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
[
N b2Ti 2--
t1 e:                          S REACTOR TRIP OR SAFETY INJECTIONI Revision Number:
REV. 0
: 16. Check If SI Flow Should Be Terminated:
: a. RCS subcooling based on core          a. Go to Step 17.
exit TCs - GREATER THAN 190 F
: b. Secondary heat sink:                  b. IF neither condition satisfied, THEN go to Step 17.
o Total feed flow to SGs    -
GREATER THAN 400 GPM OR  -
o Narrow range level in at least one SG - GREATER THAN 10%
: c. RCS pressure:                        c. Go to Step 17.
o Pressure - GREATER THAN 1660 PSIG o Pressure - STABLE OR INCREASING
: d. PRZR level  -  GREATER THAN 14%      d. Try to stabilize RCS pressure with normal PRZR spray. Go to Step 17.
: e. Go to 2-ES-1.1, SI TERMINATION, Step 1
: 17. Check ATTACHMENT I    - COMPLETE          FRPs should NOT be implemented prior to completion of Automatic Action Verification steps.
: 18. Initiate MonitorinQ Of Critical Safety Function Status Trees 15 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:            JTitle:                                                                  Revision Number:
2-E-O                            REACTOR TRIP OR SAFETY INJECTION                              REV. 0 CAUTION o If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
o Overriding breaker anti-pump/lockout may require placing control switches to TRIP or may require Containment Spray Reset o Placing key switches to DEFEAT will prevent auto SI actuation.
1 *
* R
* s * *  * * * * * *.  * *
* a *  * *
* a *
* a  * * * *  * * * .*  *  *  * *  *
: 19.      Reset SI:
: a. Check all CCW pumps - RUNNING            a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1 o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2):
o Train A o Train B
: e. Verify Train A AND B    -  RESET        e. Verify relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o  SIA-1 o  SIM-1 o  SIA-2 o  SIM-2 16 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions* listed below occur, trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:              fTitle:                                                                      Revision Number:,
2-E-O                                  REACTOR TRIP OR SAFETY INJECTION                              REV. 0
        *  *  *  *    *    *  * * * * *
* a *  *  * * *  * * *  *
* a  *
* a  * * * * * * *  *
* a  *  *
* Q Q
CAUTION RCS pressure should be monitored. IF RCS pressure decreases in an t
uncontrolled manner to less than 320 psig. the RHR pumps must be manually
* Ill restarted to supply water to the RCS.
020.          Check If          RHR Pumps Should Be StoDDed:
: a. Check RCS pressure:
: 1) Pressure - GREATER THAN                      1) Go to 2-E-1. LOSS OF 320 PSIG                                      REACTOR OR SECONDARY COOLANT, Step 1.
: 2) Pressure - STABLE OR                          2) Go to Step 21.
INCREASING
: b. Stop RHR pumps and place in AUTO 021.          Check SG Levels:
: a. Narrow range level      -  GREATER      a. Maintain total feed flow THAN 10%                                        greater than 400 gpm until narrow range level greater than 10% in at least one SG.
: b. Control feed flow to maintain              b. IF narrow range level in any narrow range level between 10%                  SG continues to increase in an and 50%                                          uncontrolled manner, THEN go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 22.        Check PAB Radiation - NORMAL:                    Evaluate cause of abnormal conditions:
o 98 ft. EL area monitor (R-5987) o Notify health physics and o Charging pump room area monitor                    chemistry.
(R-4)
IF the cause is a loss of RCS o Plant Vent monitors (R-43,              R-44)  inventory outside containment, THEN go to 2-ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
17 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA; IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[  2-E-O Number:
SE
 
==Title:==
ACINEPCE REACTOR TRIP OR SAFETY INJECTION REPNERESPONSE                  NOT OBTAINED REV. 0 Revision Number: 1
: 23. Check PRT Conditions - NORMAL:        Evaluate cause of abnormal conditions.
o Level o Pressure o Temperature
: 24. Reset Containment Isolation Phase A And Phase B:
: a. Place IVSW switches to OPEN on SN panel:
o  1410 o  1413 o  SOV-3518 o  SOV-3519
: b. Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: c. Verify personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: d. Place control switches for all remaining Phase A isolation valves to CLOSE on SN panel
: e. One at a time,  depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B This Step continued on the next page.
18 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions. listed below occur,  trip all RCPs:
: a. SI pumps    AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
mber:
2-E-O
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION Revision Number REV.
STE        ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDl
: f. Verify Train A AND B  - RESET      f. IF signal does NOT reset, THEN:
: 1) Place key switches to BYPASS.
: 2) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset.
THEN reset relays CAI AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
: g. Check Phase B  -  ACTUATED          g. Go To Step 25.
: h. Containment pressure - LESS        h. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig, THEN perform steps 24i, 24j and 24k.
: 2) Continue with Step 25.
: i. One at a time, depress Containment Spray Reset pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: j. One at a time,  depress Phase B reset buttons o CI Phase B Train A o CI Phase B Train B
: k. Verify Train A AND B - RESET        k. Verify relays reset (top of Safeguards Initiation Racks 1-2 AND 2-2):
o S1 o S2 o CB1 o CB2 19 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    LESS THAN 230F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 25. Establish Instrument Air To Containment:
: a. Open PCV-1228                  a. Verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAI o CA2
: 26. Check Secondary Radiation -        Go to 2-E-3, STEAM GENERATOR TUBE NORMAL:                            RUPTURE, Step 1.
o Request periodic activity samples of all SGs
: 27. Check Power Supply To Charging      Verify adequate diesel capacity Pumps - OFFSITE POWER AVAILABLE    to run charging pumps. IF necessary, shed sufficient non-essential loads.
20 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps    AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:    ITitle:                                                          Revision Number:
2-E-O                  REACTOR TRIP OR SAFETY INJECTION                      REV. 0
: 28. Check If Charging Flow Has Been Established:
: a. Charging pumps - AT LEAST ONE      a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected. RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
0  MOV-250A. MCC 26AA,    A2 0  MOV-250C,  MCC 26AA,    B2 0  MOV-250B. MCC 26BB,    L3 0  MOV-250D,  MCC 26BB,    M3
                                                                - OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
0  241A 0  241 B 0  241C 0  241D
: 2)  Startcharging pump(s)      as necessary.
: b. Establish charging flow as necessary:
: 1) Verify speed controller in MANUAL
: 2) Adjust charging pump speed 21 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
2-E-O        J.REACTOR TOitle:
TRIP OR SAFETY INJECTION Revision Number:
REV. 0 STP      ACTION/EXPECTED RESPONSE            ]IRESPONSE NOT OBTAINED
: 29. Check If Diesel Generators Should Be Stopped:
: a. Verify 480V busses - ENERGIZED    a. Try to restore  offsite power BY OFFSITE POWER                      to 480V busses  per 2-AOP-138KV-1,  LOSS OF POWER TO 6.9KV BUS 5  AND/OR 6.
IF offsite power can NOT be restored, THEN load the following equipment on 480V busses:
o MCCs:
o MCC 24A o MCC 27A o MCC 29A o Direct Support Facilities personnel to align lighting to TSC bus per 2-SOP-27.1.5, 480 VOLT SYSTEM via PAB Lighting Transformer 23 Alternate Power Supply as necessary.
o Start one cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW.
THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
This Step continued on the next page.
22 of 35
 
FOLDOUT PAGE FOR 2-E-0
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 23*F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
2-E-O                    REACTOR TRIP OR SAFETY INJECTION                  REV. 0 Number:
 
==Title:==
Revision Number: 1 o Locally start one 480V switchgear room exhaust fan.
o IF necessary, defeat fan interlock using bypass key.
Go to Step 29c.
: b. Manually load the following equipment on the 480V busses:
o All MCCs as necessary except MCC 28 and MCC 28A o All lighting as necessary o One cable tunnel exhaust fan o Verify radiation monitors R-43/R-44 in service and start PAB ventilation fans o Locally start one 480V switchgear room exhaust fan o IF necessary, defeat fan interlock using bypass key
: c. Locally stop any unloaded diesel generator(s) and place in standby
: 30. Return To Step 10'
                                          -END-23 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
I  2-E-O Number:
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION                          REV. 0 Revision Number:
STP          ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED-ATTACHMENT 1                  (Attachment page 1 of 10)
AUTOMATIC ACTION VERIFICATION NOTE This attachment should be terminated upon CRS transition to 2-ECA-O.O, LOSS OF ALL AC POWER
: 1. Verify Proper Charqinq System Operation:
a) CHECK Containment Condition    -      a)  Perform the following:
ADVERSE
: 1) IF CCW available, THEN start one charging pump to maintain RCP seal injection and PRZR inventory.
: 2) IF CCW NOT available, THEN start one changing pump in MANUAL at maximum speed for pump cooling.
: 3)  Continue with Step 2. WHEN Containment Condition is ADVERSE, THEN perform Steps 1.b) & 1.c).
b) Start At Least One Charging            b)  Go to Attachment 1 Step 2.
Pump In MANUAL At Maximum Speed c)  Align charging pump suction to        c)  Perform the following:
the RWST o Open emergency boration
: 1) Open charging pump suction                valve:
valve from RWST:
o MOV-333 o LCV-112B o Place both boric acid pumps
: 2) Close charging pump suction                in high speed mode valve from VCT:
o LCV-112C
: 3) Place RCS makeup control switch to STOP 24 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIAz IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 230 F (30OF FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
F  2-E-O Number:
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION                      REV. 0 Revision Number: 1 ATTACHMENT 1            (Attachment page 2 of 10)
AUTOMATIC ACTION VERIFICATION NOTE o Notify CRS of any automatic actions that failed to occur during performance of this Attachment.
o Equipment found misaligned due to operator action should NOT be repositioned.
: 2. Check 345 KV MO Disc Switch F7-9          IF Generator Output Breakers do
            -  OPEN                                  NOT open 30 seconds after Turbine trip, THEN manually open:
o BKR7 o BKR9
: 3. Check Status Of 480V Busses:
a)  All 480V busses      ENERGIZED BY    a) Direct Support Facilities OFFSITE POWER                            personnel to align lighting to TSC bus per 2-SOP-27.1.5. 480 VOLT SYSTEM via PAB Lighting Transformer 23 Alternate Power Supply.
Go to Step 3c.
b) Dispatch NPO to reset:
o  All  lighting o  MCC  24A o  MCC  27A o  MCC  29A c) Stop all condensate pumps 25 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 1            (Attachment page 3 of 10)
AUTOMATIC ACTION VFRTFICATTON
: 4. Verify FW Isolation:                      Manually trip pumps and close valves as necessary.
o Main boiler feed pumps    -  TRIPPED o Main boiler feed pump discharge valves - CLOSED o FW regulating valves - CLOSED o FW stop valves - CLOSED o SG blowdown isolation valves CLOSED
: 5. Check If Main Steamlines Should Be Isolated:
a)  Check for either:                    a) Go to Step 6.
o High steamline flow with either TAVE less than 542 0 F OR steamline pressure less than 570 psig OR  -
o Containment pressure    -  EVER GREATER THAN 24 PSIG b) VerifyMSIVs,-    CLOSED              b) Manually close valves.
: 6. Verify Proper Service Water System Operation:
a)  Three service water pumps -          a) Manually start pumps.
RUNNING ON ESSENTIAL HEADER b) Service water valves from              b) Locally open valves.
diesel generator - OPEN 26 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
1 2-E-0 REACTOR Number:
 
==Title:==
TRI  OR SAFETY  INJECTION Revision REV.O ATTACHMENT 1              (Attachment page 4 of 10)
AUTOMATIC ACTION VERIFICATION
        .7. Verify SI System Pumps Running:
a) Three SI pumps - RUNNING          a)  Perform the following:
: 1) Manually start pumps.
: 2) IF three SI pumps running, THEN:
a)  Verify MOV-851A AND)
MOV-851B are open.
b) Go to Step 7c.
: 3) IF 21 AND 22 SI pumps running, THEN:
a)  Verify MOV-851B opelne.
b) Verify MOV-851A clo*sed.
c)  Go to Step 7c.
: 4) IF 22 AND 23 SI pumps running, THEN:
a)  Verify MOV-851A opern.
b)  Verify MOV-851B clo*sed.
c)  Go to Step 7c.
This Step continued on the next page.
27 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    LESS THAN 230 F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
INumber; II 2-E-O
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION                Revision REV. Number:
0 STEP  ACTION/EXPECTED RESPONSE              REPNENTOTIE ATTACHMENT 1            (Attachment page 5 of 10)
AUTOMATIC ACTION VERIFICATION
: 5) IF only 22 SI pump running, THEN:
a) Open AND de-energize either MOV-851A OR MOV-851B as follows:
o Hold control switch in the open position to cycle valve open o De-energize power feed when valve is in OPEN position:
o MOV-851A - MCC-26A, Compt. 4DR
                                                                        - OR -
o MOV-851B - MCC-26B, Compt. 4DR b) Go to Step 7c.
b) 22 SI pump discharge isolation      b) Manually open valves.
MOV-851A AND MOV-851B - OPEN c) Two RHR pumps  -  RUNNING          c) Manually start pump(s) unless previously placed in PULLOUT.
: 8. Verify Proper Emergency SI System      Manually align valves as Valve Alignment:                      necessary.
o RHR Hx CCW outlet valves    - OPEN o 822A o 822B o RHR Hx MOVs - OPEN o 746 o 747 28 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
S 2-E-O                    REACTOR TRIP OR SAFETY INJECTION                          REV. 0 Number:                    RTitle:                                              Revision Number:
STEP      ACTION/EXPECTED RESPONSE                  R ATTACHMENT 1              (Attachment page 6 of 10)
AUTOMATIC ACTION VERIFICATION
: 9. Verify Containment Fan Coolers -
IN SERVICE:
a) Five fan coolers      RUNNING        a)  Manually start fan cooler(s).
b)' NORM OUT valves      OPEN            b) Manually open valve(s).
IF any normal outlet valve on any fan cooler can NOT be opened, THEN perform the following:
: 1) Notify TSC which containment fan cooler(s) are NOT available.
: 2) Go to Step 9c.
c) TCV-1104 and TCV-1105      - BOTH    c) Manually open valve(s).
OPEN 29 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
r  2-E-O Number:
 
==Title:==
REACTOR TRIP OR SAFETY INJECTION                        REV. 0 Revision Number:
STP      ACTION/EXPECTED RESPONSE IIRESPONSE              NOT OBTAINED ATTACHMENT 1                (Attachment page 7 of 10)
AUTOMATIC ACTION VERIFICATION
: 10. Verify AFW Flow To All SGs              Manually align valves as necessary.
: 11. Verify Containment Ventilation Isolation:
a)  Containment purge valves  -        a)  Manually close valves.
CLOSED:
                                                    .IF valves can NOT be closed, 0 FCV-1170                              THEN close valves from fan 0 FCV-1171                              room.
0 FCV-1172 0  FCV-1173                            IF valves can NOT be closed, THEN dispatch operator and HP personnel to close outside valves by isolating instrument air:
o FCV-1171,  IA-780 o FCV-1173,  IA-779 b)  Containment pressure relief        b)  Manually close valves.
valves - CLOSED:
IF valves can NOT be closed, o PCV-1190                              THEN close valves from fan o PCV-1191                              room.
o PCV-1192 IF valves can NOT be closed, THEN dispatch operator AND HP personnel to close outside valves by isolating instrument air:
o PCV-1191,  IA-777 o PCV-1192,  IA-778 IF containment pressure relief can NOT be isolated, THEN locally close the following valves (Fan House 88 ft. el):
o UH-1013, Pressure Relief Fan Inlet Stop o UH-1014, Pressure Relief Fan Outlet stop 30 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (309F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
ATTACHMENT 1            (Attachment page 8 of 10)
AUTOMATIC ACTION VERIFICATION
: 12. Verify Containment Isolation Phase A:
a) Phase A  -  ACTUATED                  a)  Manually actuate phase A.
o Train A master relay CAI (above rack E) o Train B master relay CA2 (above rack F) b) Phase A valves - CLOSED                b) Manually close valves.
c) IVSW valves    -  OPEN:              c)  Manually open valves.
o  1410 o  1413 o  SOV-3518 o  SOV-3519 d) WCP valves    -  OPEN:                d)  Manually open valves.
o  PCV  1238 o  PCV  1239 o  PCV  1240 o  PCV  1241 e) Place personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel f) Dispatch NPO to periodically check:
: 1) IVSW tank:                              1) Direct NPO to fill or pressurize tank as o Level  -  GREATER THAN 92%            necessary.
o Pressure    -  GREATER THAN 57 PSIG
: 2)  WCP header pressures -                2) Direct NPO to verify GREATER THAN 52 PSIG                      station air backup OR N2 backup are aligned as necessary.
31 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    - LESS THAN 230F (30°F FOR ADVERSE CONTAINMENT)
: 2. AF-W SUPPLY SWITCHOVER CRITERION:
IF CST level  decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 1            (Attachment page 9 of 10)
AUTOMATIC ACTION VERIFICATION
*13. Check If Containment Spray Should Be Actuated:                                                                  I a) Containment pressure  - EVER      a) Go to Step 14.
GREATER THAN 24 PSIG b) Verify spray pumps  - RUNNING      b) Manually initiate spray AND verify both spray pumps running. IF NOT, THEN manually start pumps.
c) Verify spray pump discharge        c) Manually open valves.
valves - OPEN:
o MOV-866A o MOV-866B o MOV-866C o MOV-866D d) Verify containment isolation      d) Manually close valves.
Phase B valves - CLOSED e) Stop all RCPs f) Verify IVSW isolation valves  -  f) Manually open valves.
OPEN:
0 7864 0 7865 0 7866 0 7867 32 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 239F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STEP    ACTION/EXPECTED RESPONSEI                RESPONSE NOT OBTAINEDI ATTACHMENT 1                (Attachment page 10 of 10)
AUTOMATIC ACTION VERIFICATION
: 14. Verify CCR Air Conditioner              At CCR Panel PY2,    perform the Train A And Train B - RUNNING IN        following:
INCIDENT MODE 2 a)  Place mode selector switch to 2 b)  Place the following switches to CUTOUT:
o Unit-i K-8 fan switch (0T2-3) o 0T2-1 o 0T2-2 c)  Check system aligned for INCIDENT - OUTSIDE AIR FILTERED FOR SI/HI RAD
: 15. Notify CRS That ATTACHMENT 1 Is Complete
                                      - END -
33 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 230 F (300F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number: 1 2-E-O                    REACTOR TRIP OR SAFETY INJECTION                    REV. 0 ATTACHMENT 2            (Attachment page 1 of 1)
CONTAINMENT ISOLATION VALVES
: 1. The following valves will close on Phase A isolation:
VALVE NAME                                        VALVE NUMBER(s)
CCW from excess letdown Hx                        796, 793 CCW to excess letdown Hx                          798. 791 Vent header from RCDT                              1786, 1787 Gas analyzer PRT                                  548, 549 Gas analyzer RCDT                                  1788, 1789 Letdown from regenerative HX                      201. 202 Letdown oriface control stop valves                200A, 200B, 200C Make-up to PRT                                    519, 552 Containment sump pumps to WDS - hold-up tank      1723, 1728 Instrument air to containment                      PCV-1228 RCDT to WDS - hold-up tank                        1702, 1705 SG blowdown and sampling system                    PCV-1214, 1214A PCV-1215, 1215A PCV-1.216, 1216A PCV-1217, 1217A Radiation monitor return to containment            PCV-1234, 1235 PCV-1236, 1237 Accumulator samples                                956G, 956H Sample - pressurizer steam                        956A, 956B Sample - pressurizer liquid                        956C, 956D Sample - RCS loops                                21, 22, 23 MOV-956E, 956F SJAE to containment                                1229, 1230 Hi-Rad sample system return to containment sump    MOV-4399, 5132 Recirculation pump discharge sample line          MOV-990A, 990B Accumulator N2 Supply Line Stop                    863
: 2. The followinq valves will close on Phase B isolation:
VALVE NAME                                            VALVE NUMBER(s)
Component cooling  to RCS pumps                      MOV-769, 797 Component cooling  from RCS thermal barrier return  MOV-789. FCV-625 Component cooling  from RCS.motor bearing return    MOV-786, 784 Seal water return  containment isolation valve      MOV-222
                                              -END-34 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 3                  (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the following table to determine 480V equipment load ratings:
211DG            22 DG            23 DG EQUIPMENT          BUS 5A        BUS 2A    BUS 3A    BUS 6A 21 SERVICE WATER PUMP    282 KW 22 SERVICE WATER PUMP                  282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP    282 KW 25 SERVICE WATER PUMP                  282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                      485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                        384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT        250 KW 22 FAN COOLER UNIT        250 KW 23 FAN COOLER UNIT                      250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                          250 KW 21 SI PUMP                316 KW 22 si PUMP                              316 KW    316 KW 23 SI PUMP                                                  345 KW 21 SPRAY PUMP            350 KW 22 SPRAY PUMP                                                350 KW 21 RHR PUMP                                        303 KW 22 RHR PUMP                                                  303 KW 21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                              150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                                299 KW 21 CCW PUMP              228 KW 22 CCW PUMP                            228 KW 23 CCW PUMP                                                  228 KW 21 LIGHTING TRAN:SFORMER                150 KW (N)            150 KW (E) 22 LIGHTING TRAN:SFORMER                          225 KW 23 LIGHTING TRAN SFORMER  225 KW TURBINE AUX OIL PUMP                                          112 KW STATION AIR COMPIRESSOR    93 KW
                                    .ENDI-35 of 35
 
FOLDOUT PAGE FOR 2-E-O
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur; trip all RCPs:
: a. SI pumps  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs  - LESS THAN 230 F (30°F FOR ADVERSE CONTAINMENT)
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Procedure Use Is: Control Copy:
  'En tery                  0 Continuous Nucleax Northeast      0 Reference      Effective Date: ("/9/*1 T,.-
V O Information i
2-ES-0.0, Revision: 0 Approved By:
Proceduh&'Sponsor, RPO/
Team P Procedure Owner EDITORIAL REVISION
 
A. PURPOSE This procedure provides a mechanism to allow the operator to determine or confirm the most appropriate post accident recovery procedure.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered based on operator judgement.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                        - OR -
o Containment pressure greater than 4 psig.
1 of 3
 
STP    ACTION/EXPECTED RESPONSEl              RESPONSE NOT OBTAINEOD
: 1. Check If Any SG Secondary Pressure Boundary Is Intact:
: a. Check pressures in all SGs  -    a. IF a controlled cooldown is in ANY STABLE OR INCREASING progress, THEN go to Step 2.
IF NOT, THEN the following applies:
o IF main steamlines NOT isolated. THEN you should be in 2-E-2. FAULTED STEAM GENERATOR ISOLATION.
OR o IF main steamlines isolated, THEN you should be in 2-ECA-2.1. UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.
: 2. Check If Any SG Is Faulted:
: a. Check pressures in all SGs -      a. Go to Step 3.
o ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER OR -
o ANY SG COMPLETELY DEPRESSURIZED
: b. Verify all faulted SG(s)          b. You should be in 2-E-2, isolated:                              FAULTED STEAM GENERATOR ISOLATION.
o Steamlines o Feedlines 2 of 3
: 3. Check If SG Tubes Are Intact:        You should be in an E-3 or ECA-3 series procedure.
o Main steamline radiation recorder (R-28, R-29, R-30, and R-31)  - NORMAL o Condenser air ejector radiation recorder (R-45)  - NORMAL o SG blowdown radiation recorder (R-49)  - NORMAL o NO SG LEVEL INCREASING IN AN UNCONTROLLED MANNER
: 4. You Should Be In An E-1 Or ECA-1 Series Procedure
                                  -END-3 of 3 3of3
 
Procedure Use Is: Control Copy:
Entegy                    0 Continuous Nuclear Northeast        O Reference      Effective Date:
o Information 2-ES-0.1, Revision: 1 REACTOR TRIP RESPONSE I
Approved By:
Proced'ure 4ponsor, RPO/ D TeamPP Procedure Owner EDITORIAL REVISION
 
A. PURPOSE This procedure provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 4, when SI is neither actuated nor required.
1 of 16
 
FOLDOUT PAGE FOR 2-ES-:0.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs        LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)                F 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
*  *  *    * *  * * * * * *
* a *
* a  *  *  *
* a  a *  * *
* a
* a  * * * *
* a  * *
* a
* CAUTION t
* o If SI actuation occurs during this procedure,                transition to 2-E-O,
* REACTOR TRIP OR SAFETY INJECTION, step 1.
* o Radiation levels and harsh environment conditions should be evaluated
* prior to performing local        actions.
0 .Check SG-Levels:
: a. Narrow range level  -  GREATER        a. Maintain total feed flow THAN 10%                                    greater than 400 gpm until narrow range level greater than 10% in at least one SG.
: b. Control feed flow to maintain            b. IF narrow range level in any narrow range level between 10%              SG continues to increase. THEN and 50%                                      stop feed to that SG.
2 of 16
 
FOLDOUT PAGE FOR 2-ES-O.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9Z o RCS subcooling based on core exit TCs      - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSEI            RESPONSE NOT OBTAINED
* 2. Check RCS Temperatures  -            IF_temperature less than 547°F and decreasing, THEN:
o RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 5470F IF ANY    a. Stop dumping steam.
RCP RUNNING
: b. Verify SG blowdown isolation
                - OR -                        valves closed.
o RCS COLD LEG TEMPERATURES          c. IF cooldown continues, THEN STABLE AT OR TRENDING TO 5470F          control TOTAL feed flow.
IF NO RCP RUNNING                      Maintain TOTAL feed flow greater than 400 gpm until narrow range level greater than 10% in at least one SG.
: d. IF cooldown continues, THEN close MSIVs. IF valves can NOT be closed, THEN locally close MSIVs per 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS.
IF temperature greater than 5470F and increasing,      THEN:
o Dump steam to condenser.
                                                        - OR -
o Dump steam using SG atmospheric steam dumps.
: 3. Check 345 KV MO Disc Switch F7-9    IF Generator Output Breakers do
      - OPEN                              NOT open 30 seconds after Turbine trip, THEN manually open:
o BKR7 o BKR9 3 of 16
 
FOLDOUT PAGE FOR 2-ES-0.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED (D 4. Verify All 480V Busses -            Perform the following:
ENERGIZED BY OFFSITE POWER
: a. IF necessary, THEN verify diesel generators have assumed the following loads:
o CCW pumps.
o Essential Service water pumps.
o Motor-driven AFW pumps as necessary.
: b. Try to restore offsite power per:
o 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR BUS 6.
o 2-SOP-27.1.3, OPERATION OF 13.8KV SYSTEM.
This Step continued on the next page.
4 of 16
 
FOLDOUT PAGE FOR 2-ES-:0.1
: 1. ~SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP ACTION/EXPECTED RESPONSEi            RESPONSE NOT OBTAINEDI
: c. IF necessary, THEN manually load the following equipment on the 480V busses:
o One charging pump.
o FCUs.
o All MCCs.
o One Non Essential Service Water Pump o All lighting.
o One cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW, THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
o Locally start one 480V switchgear room exhaust fan.
o IF necessary, defeat fan interlock using bypass key.
: d. OPEN the ABFP room roll-up door until room ventilation is restored.
5 of 16
 
FOLDOUT PAGE FOR 2-ES-O01
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AF'I SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP        ACTION/EXPECTeD RESPONSEI            RESPONSE NOT OBTAINEDI
: 5. Check PRZR Level Control:
: a. Level - GREATER THAN 18%        a. Perform the following:
: 1) Verify letdown isolation.
IF NOT, THEN manually isolate:
o  LCV-459 o  200A o  2008 o  200C
: 2) Verify PRZR heaters off. IF NOT, THEN manually turn off.
: 3) Control charging to restore PRZR level greater than 18%.
: 4) WHEN PRZR level greater than 18%, THE__N place letdown in service per 2-SOP-3.1. CHARGING, SEAL WATER AND LETDOWN CONTROL AND reenergize PRZR heaters as necessary.
: 5) Go to Step 5c.
: b. Verify charging and letdown -    b. Manually place in service:
IN SERVICE
: 1) Start charging pumps as necessary.
: 2) Establish charging flow as necessary.
: 3) Establish letdown as necessary per 2-SOP-3.1, CHARGING, SEAL WATER AND LETDOWN CONTROL.
This Step continued on the next page.
6 of 16
 
FOLDOUT PAGE FOR 2-ES-0,j
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              -F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: c. Any CCW pump - RUNNING          c. Perform the following:
: 1) Align charging pump in MANUAL at maximum speed for pump cooling.
: 2) Manually start CCW pumps.
IF NO CCW pumps can be started, THEN refer to 2-SOP-4.1.2 COMPONENT COOLING SYSTEM OPERATION to establish backup cooling to charging pumps.
: d. Level  TRENDING TO 37%        d. Perform the following:
: 1) IF Reactor Trip was UNPLANNED, THEN control charging and letdown to maintain pressurizer level at 37%.
: 2) IF Reactor Trip was PLANNED, THEN maintain pressurizer level as directed by CRS.
7 of 16
 
FOLDOUT PAGE FOR 2-ES-O.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              'F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
--*      ACTION/EXPECTED RES''SE              RESPONSE NOT OBTAINED]
: 6. Check PRZR Pressure Control:
: a. Pressure - GREATER THAN          a. Verify SI actuation. IF NOT, 1840 PSIG                            THEN manually actuate TI. Go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1.
: b. Pressure - STABLE AT OR          b. IF pressure less than TRENDING TO 2235 PSIG                2235 psig and decreasing,    THEN:
: 1) Verify PRZR PORVs closed.
IF NOT, THEN manually close.
IF any valve can NOT be closed, THEN manually close its block valve.
: 2) Verify PRZR spray valves closed. IF NOT, THEN place controller in manual and close valves.
IF valves can NOT be closed, THEN stop ANY RCP(s) required to stop spray flow.
: 3) Verify PRZR heaters on.      IF NOT, THEN manually turn on.
Refer to ATTACHMENT 1.
IF pressure greater than 2235 psig and increasing,    THEN:
: 1) Verify PRZR heaters off. IF NOT, THEN manually turn off.
: 2) Control pressure using normal PRZR spray.
IF NOT available and letdown is in service, THEN use auxiliary spray if differential temperature between PRZR and aux spray (TI-126) is less than 3200F:
o Refer to 2-SOP-1.4.
PRESSURIZER PRESSURE CONTROL.
IF auxiliary spray can NOT be used, THEN use PRZR PORV(s) in automatic or manual.
8 of 16
 
FOLDOUT PAGE FOR 2-ES-:01
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFM SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 7. Verify All Control Rods Fully Inserted:
: a. Check IRPI Indicators -          a. Implement 2-SOP-3.2, REACTOR ENERGIZED                            COOLANT SYSTEM BORON CONCENTRATION CONTROL.
: b. Check IRPI Indicators - ALL      b. Check all rod positions LESS RODS LESS THAN 7.5 INCHES            THAN 12 STEPS using PICS.
Refer to ATTACHMENT 2.
: 1) IF 2 OR more rod positions are greater than 12 steps withdrawn OR can NOT be I
determined, THEN emergency borate 255 PPM/Rod not fully inserted:
a)  Open emergency boration valve:
o MOV-333 b)  Place both boric acid pumps in high speed mode.
c) Place charging pump control(s) in MAN.
d)  Establish a minimum charging flow of 75 gpm.
e) WHEN emergency boration is complete, THEN secure per 2-SOP-3.2, REACTOR COOLANT SYSTEM BORON CONCENTRATION CONTROL.
9 of 16
 
FOLDOUT PAGE FOR 2-ES-:0.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              'F 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 8. Check FW Status:
: a. Check RCS average temperatures    a. Continue with Step 9. WHEN
        - LESS THAN 554 0 F                  temperature less than 554 0 F, THEN do Steps 8b, 8c and 8d.
: b. Verify main FW regulating        b. Manually close valves.
valves - CLOSED
: c. Verify bypass FW regulating      c. Manually close valves.
valves - CLOSED
: d. Verify total feed flow to SGs    d. Establish AFW flow to the SGs
        - GREATER THAN 400 GPM              as necessary.
: 9. Transfer Condenser Steam Dump To Pressure Control Mode:
: a. Check condenser - AVAILABLE        a. IF condenser NOT available, THEN use SG atmospheric steam dumps:
o Control pressure as directed by CRS
: b. Place steam dump controller switch to manual and adjust for zero output.
: c. Transfer condenser steam dump to pressure control mode and adjust manual switch as necessary
: d. Place controller in AUTO and CONTROL pressure as directed by CRS 10 of 16
 
FOLDOUT PAGE FOR 2-ES:O.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 -400              52 401-    800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
: 10. Check RCP Status    24 RCP RUNNING      Perform the following to provide 24 RCP RUNNING      normal PRZR spray:
: a. Establish conditions for starting RCP(s) per 2-SOP-1.3.
REACTOR COOLANT PUMP OPERATION.
: b. Start 24 RCP.
IF an 24 RCP can NOT be started, THEN start RCP(s) as requi red to provide PRZR spray flow.
IF no RCP can be started, THEN refer to ATTACHMENT 3 to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam.
: 11. Check If Source Ranqe Detectors Should Be Energized:
: a. Check intermediate range flux      a. Continue with Step 12. WHEN
          - LESS THAN 1E-10 AMPS                  flux less than 1E-10 amps.
THEN do Steps lib and 11c.
: b. Verify source range detectors      b. Manually energize source range
          - ENERGIZED                              detectors.
: c. Transfer nuclear recorders to source range scale 11 of 16 I
 
FOLDOUT PAGE FOR 2-ES-:0.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFM SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft.'switch to city water supply.
: 12. Shut Down Unnecessary Plant Eauipoment; o Verify secondary plant automatic actions:
o Heater drain pumps    TRIPPED o 22 condensate pump    TRIPPED o Main and UAT transformer cooling equipment - SHUTDOWN o Reheater steam supply valves
        - CLOSED o Extraction steam valves  -
CLOSED o MBFP turbine reheat steam supply non-return valve "A" valves - CLOSED o Circulating water pumps not required o Condensate pumps not required o Service water pumps not required o Evaluate secondary plant status and shut down equipment as required 12 of 16
 
FOLDOUT PAGE FOR 2-ES-O01
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-0, REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs        LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE. RCS SUBCOOLING (PSIG)              OF 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AF1 SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 13. Maintain Stable Plant Conditions:
o PRZR pressure - AT 2235 PSIG o PRZR level    -
o IF Reactor Trip was UNPLANNED, THEN control charging and letdown to maintain PRZR level at 37%
OR -
o IF Reactor Trip was PLANNED, THEN maintain PRZR level as directed by CRS o SG narrow range levels      -
BETWEEN 10% AND 50%
o RCS temperature    -
o AVERAGE TEMPERATURE AT 5470F IF ANY RCP RUNNING
                  - OR -
o COLD LEG TEMPERATURES AT 5470F IF NO RCP RUNNING
: 14. Determine If Natural Circulation Cooldown Is Reouired:
: a. Consult operations manager
: b. Natural circulation cooldown    -  b. Go to 2-POP-3.2, PLANT REOUIRED                                RECOVERY FROM TRIP, HOT STANDBY.
: c. Go to 2-ES-O.2,    NATURAL CIRCULATION COOLDOWN,    Step i
                                      - END-13 of 16
 
FOLDOUT PAGE FOR 2-ES-O.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 1                (Attachment page 1 of 1) 480V EOUIPMENT LOAD RATINGS
: 1. Use the following table to determine 480V equipment load ratings:
21 DG          22 DG              23 DG EQUIPMENT            BUS 5A    BUS 2A      BUS 3A    BUS 6A 21 SERVICE WATER PUMP    282 KW 22 SERVICE WATER PUMP                282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP    282 KW 25 SERVICE WATER PUMP                282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS.                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                    485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                        384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT        250 KW 22 FAN COOLER UNIT        250 KW 23 FAN COOLER UNIT                    250 KW  -'.
24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                            250 KW 21 SI PUMP                316 KW 22 SI PUMP                            316 KW      316 KW 23 SI PUMP                                                    345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP                                                350 KW 21 RHR PUMP                                        303 KW 22 RHR PUMP                                                  303 KW 21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                            150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                              299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW                228 KW 23 CCW PUMP 21 LIGHTING TRANSFORMER                150 KW (N)            150 KW (E) 22 LIGHTING TRANSFORMER                            225 KW 23 LIGHTING TRANSFORMER    225 KW TURBINE AUX OIL PUMP                                        112 KW STATION AIR COMPRESSOR      93 KW
                                    -END-14 of 16
 
FOLDOUT PAGE FOR 2-ES-:0.1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400              52 401 - 800              36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
ATTACHMENT 2            (Attachment page I of 1)
OBTAINING PICS ROD POSITION INDICATION
: 1. Obtain PICS Rod Position Indication by the followinq method:
o Obtain PICS Rod Indication from any screen:
a)  Depress Cancel on screen using mouse or depress escape key on keyboard b) Depress NSSS and BOP on screen using mouse c).Depress ROD SUPERVISION on screen using mouse d) Depress ALL ROD view or INDIVIDUAL BANK on screen using mouse e) Check all rods less than 12 steps withdrawn
                                  -END-15 of 16 I
 
FOLDOUT PAGE FOR 2-ES-O. 1
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              -F 0 -400              52 401-    800            36 801    1200          23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
ATTACHMENT 3              (Attachment page I of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The following conditions support or indicate natural circulation flow:
o RCS subcooling based on core exit TCs      - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE      RCS SUBCOOLING (PSIG)              -F 0 - 400              52 401 - 800              36 801 - 1200              23 1200 - 2500              19 o SG pressures - STABLE OR DECREASING o RCS hot leg temperatures - STABLE OR DECREASING o Core exit TCs - STABLE OR DECREASING o RCS cold leg temperatures    - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                    -END-16 of 16
 
FOLDOUT PAGE FOR 2-ES-OQ.
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go. to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE      RCS SUBCOOLING (PSIG)              -F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  -  2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Procedure Use Is: Control Copy:
    'Entergy                0 Continuous Nuclear Northeast rwat Tea.
o Reference      Effective Date: W/4/11 7
[O Information in&ari Point 1-rxW (;evu-2-ES-0.2, Revision: 0 NATURAL CIRCLATION COOLDOWN Approved By:
Procedur  ponsor, RPO/ Dq Team P Procedure Owner PARTIAL REVISION
 
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 OR ENTRY CONDITIONS This procedure is entered from:
: 1) 2-ES-0.1, REACTOR TRIP RESPONSE, Step 14, when it has been determined that a natural circulation cooldown is required.
: 2) 2-ECA-O.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, Step 19, after the plant conditions have been stabilized following the restoration of 480V bus power.
1 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O,  REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
CAUTION o If SI actuation occurs during this procedure,    transition to 2-E-O,  *#
REACTOR TRIP OR SAFETY INJECTION, step 1.
* o If RCP seal cooling had previously been lost, the affected RCP should  *
* NOT be started prior to a status evaluation.
NOTE o RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to    I provide adequate spray flow.
o If conditions can be established for starting an RCP during this procedure, Step 1 should be repeated.
* 1. Try To Restart An RCP:
: a. Establish conditions for          a. Go to Step 2.
starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION
: b. Start one RCP                      b. Go to Step 2.
: c. Go to 2-POP-3.2, PLANT RECOVERY FROM TRIP, HOT STANDBY
: 2. Borate RCS To Cold Shutdown Boron Concentration
: 3. Verify Cold Shutdown RCS Boron Concentration By Sampling:
: a. Verify Boration Complete          a. Return to Step 2.
: b. Verify RCS Boron Concentration    b. Return to Step 2.
exceeds cold shutdown requirement by sampling prior to continuing with next step 2 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to
  .-2-E-O. REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            -F 0 -400              52 401    800          36 801    1200          23 1200 - 2500            19
: 2. AFI  SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. Check VCT Makeup Control System:        Adjust controls as necessary.
: a. Makeup set for cold shutdown boron concentration
: b. RCS makeup control switch placed to START 5.
6.
Verify All CRDM Fans - RUNNING Initiate RCS Cooldown To Cold Start all fans.
i Shutdown:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN 25 0 F/HR
: b. Dump steam to condenser:            b. Dump steam using SG atmospheric steam dumps.
: 1) Check condenser - AVAILABLE
: 2)  Place steam dump controller switch to manual and adjust for zero output.
: 3) Transfer condenser steam dump to pressure control mode and adjust manual setpoint as necessary.
: c. Maintain SG narrow range level      c. Control feed flow as necessary.
        - BETWEEN 46% AND 52%
: d. RCS temperature and pressure -
WITHIN LIMITS OF FIGURE ES02-1
: 7. Check RCS Hot Leg Temperatures    -    Return to Step 6.
LESS THAN 550°F 3 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 8.      Depressurize RCS To 1890 psig:
: a. Check letdown - IN SERVICE                a. Try to establish letdown per 2-SOP-3.1, CHARGING, SEAL WATER AND LETDOWN CONTROL.
IF letdown can NOT be established, THEN use one PRZR PORV. Go to Step 9. OBSERVE CAUTION PRIOR TO STEP 9.
: b. Check differential temperature                b. Use one PRZR PORV.        Go to between PRZR and auxiliary                      Step 9.      OBSERVE CAUTION PRIOR spray (TI-126)    -  LESS THAN                TO STEP 9.
320OF
: c. Use auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL Vl                                                                                                      II CAUTION                                                Vk t
* SI actuation circuits will automatically unblock if                      PRZR pressure
* increases to greater than 1940 psig.                                                                Vl dS                                                                                                      *
.  *  *    *  *  * * * *, * *r *  *  * * * *r *  *
* r  ,* *  *  *k *  *  *  * * * * * *r * * *r * * *
: 9.      Block Low PRZR Pressure SI
: 10.      Maintain Following RCS Conditions:
o RCS pressure - AT 1890 PSIG o PRZR level      - AT 37%
o Cooldown rate in RCS cold legs.
              - LESS THAN 250F/HR o RCS temperature and pressure -
WITHIN LIMITS OF FIGURE ES02-1 4 of 14
 
FOLDOUT PAGE FOR 2-ES-OZ
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              'F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
[ 2-ES-0.2 Number:
 
==Title:==
NATURAL CIRCULATION COOLDOWN      REV. 0 Revision Number:]
: 11. Monitor RCS Cooldown:
o Core exit TCs  - DECREASING o RCS hot leg temperatures DECREASING o RCS subcooling based on core exit.TCs - INCREASING 5 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
F 2-ES-0.2 Number:            itle:
NATURAL CIRCULATION COOLDOWN                      REV. 0 Revision Number:
j 1
NOTE 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, one of the following procedures should be used:
o    2-ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
                                        -OR-o    2-ES-0.4, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
: 12. Initiate RCS Depressurization:
: a. Check CRDM fans  -  ALL RUNNING      a. Maintain RCS temperature and pressure per ATTACHMENT I and FIGURE ES02-2. Go to Step 12c.
: b. Maintain RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              °F 0 - 400            102 401 - 800              86 801 - 1200            73 1201 - 2500            69
: c. Check letdown    IN SERVICE          c. Use one PRZR PORV. Go to Step 13. OBSERVE NOTE PRIOR TO STEP 13.
: d. Check differential temperature      d. Use one PRZR PORV. Go to between PRZR and auxiliary              Step 13. OBSERVE NOTE PRIOR spray (TI-126) - LESS THAN              TO STEP 13.
320°F
: e. Use auxiliary spray:
o Refer to 2-SOP-1.4.
PRESSURIZER PRESSURE CONTROL 6 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF O - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-ES-0.2                      NATURAL CIRCULATION COOLDOWN                          REV. 0 NOTE 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,        should be referred to for plant alignment during cooldown.
: 13. Continue RCS Cooldown And Depressurization:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN 25 0 F/HR
: b. Maintain subcooling                  b. Stop depressurization and requirements of Step 12                  re-establish subcooling.
: c. Maintain RCS temperature and pressure - WITHIN LIMITS OF FIGURE ES02-1
: 14. Verify Steam Void In Reactor.            Repressurize RCS within limits of Vessel Does Not Exist:                  FIGURE ES02-1 to collapse potential voids in system and o PRZR level - NO UNEXPECTED            continue cooldown. IF RCS LARGE VARIATIONS                      depressurization must continue, THEN go to one of the following:
o RVLIS natural circulation range indication - GREATER THAN 100%        o 2-ES-0.3, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
                                                              -  OR -
o 2-ES-0.4, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) 7 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            °F 0  -  400          52 401  -  800          36 801  -  1200          23 1200  -  2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
      * ~ ~ ~ ~ ~ ~~E *****ft*****  RE *                *****ft*****
* CAUTION                                *
* Radiation levels and harsh environment conditions should be evaluated        *
* prior to performing local actions.
: 15. Check If SI Accumulators Should Be Isolated:
: a. RCS pressure - LESS THAN              a. Continue with Step 16. WHEN 1000.PSIG                                RCS pressure less than 1000 psig, THEN do Steps 15b through 15d.
: b. Locally restore power to isolation valves:
0  894A (MCC          26A) 0  894C (MCC          26A)
: 0. 894B (MCC          26B) 0  894D (MCC          26B)
This Step continued on the next page.
8 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)              F 0 - 400            52 401 - 800            36 801 - 1200          23 1200 - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
Nm2-ES-0.2                      NATURAL CIRCULATION COOLDOWN                      REV. 0 STEP      ACTION/EXPECTED RESPONSE I            RESPONSE NOT OBTAINED
: c. Close all SI accumulator            c. Vent any unisolated isolation valves                      accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 8910 o HCV-943
: d. Open all SI accumulator isolation valve breakers 9 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 16. Check If SI Pumps Should Be Locked Out:
: a. RCS hot leg temperature - LESS    a. Continue with Step 17. WHEN THAN 350°F                          RCS hot leg temperature less than 350 0 F, THEN do Step 16b.
: b. Place SI pump control switches in PULLOUT
: 17. Maintain  Letdown Flow:
: a. Open letdown orifice isolation valves as necessary
: b. Adjust low pressure letdown control valve PCV-135 setpoint as necessary
: 18. Maintain Required RCP Seal Injection Flow:
o 6 gpm to 10 gpm per pump
: 19. Check If RHR System Can Be Placed In Service:
: a. RCS temperature - LESS THAN      a. Return to Step 13. OBSERVE 3500 F                              NOTE PRIOR TO STEP 13.
: b. RCS pressure - LESS THAN          b. Return to Step 13. OBSERVE 370 PSIG                            NOTE PRIOR TO STEP 13.
: c. Place RHR System in service per 2-SOP-4.2.1, RESIDUAL HEAT REMOVAL SYSTEM
: 20. Continue RCS Cooldown To Cold Shutdown 10 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            -F 0  -  400          52 401  -  800          36 801  -  1200          23 1200  -  2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP            ACTION/EXPECTED RESPONSEI                  RESPONSE NOT OBTAINEDI
  *  *  *  *  *  * * * * * * * * * *  * * *  *  * *  *              *  * * * *  * * * *  *
* t Q
CAUTION i
Depressurizing the RCS before the entire RCS is            less than 200OF may            Q result in void formation in the RCS. -
: 21.        Continue Cooldown Of Inactive Portion Of RCS:
o Cool upper head region using CRDM fans o Cool SG U-tubes by dumping steam from all SGs NOTE If CRDM fans are NOT running, a waiting period of 27 hours is              necessary to allow thehead to cool to less than 200 0 F.
: 22.      Determine If RCS Depressurization Is Permitted:
: a. Entire RCS - LESS THAN 200°F          a. Return to Step 20.
: b. Go to 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN
                                                -END-11 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION.      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:        IT itle:Revision                                                                              Number:
2-ES-0.2                                      NATURAL CIRCULATION COOLDOWN                          REV. 0 FIGURE ES02-1 RCS PRESSURE (PSIG) 2500 I
2000  -                                                                                I I
I I F I  I -T-1500    #--P---q                                                                          SU NACCEPTABLE                    I
                                                      , OPERATION I#
                -7 V
1000  -
Z =I 21=  =  I      I=
F MAXIMUI M1C00LDOW~
RATES: oF/HR
                  -t p-  -    9-  p-0 K
500                            20 40                                          ACCEPTABLE 60                                          OPERATION 100 F
0                        0 0                    50              100        150      200        250          300      350 RCS COLD LEG TEMPERATURE (oF)
FIGURE ES02-1,                REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
                                                                -END-12 of 14
 
FOLDOUT PAGE FOR 2-ES-O.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              'F 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[Number:
 
==Title:==
Revision Number:    1 2-ES-0.2                        NATURAL CIRCULATION COOLDOWN                          REV. 0 FIGURE ES02-2 RCS Pressure (PSIG) 2800 2600 UNACCEPTABLE 2400 -                                    OPERATION AFTER SI BLOCKED 2200 2000                                          1il940 PSIG 1800 -
                -I UNACCEPTABLE OPERATION EACCEPTABLE OPERATION 11840 PSIG 1600 -
1400 -
UNACCEPTABLE PRS                                OPERATION 1200 1000 800                                                              SATURAT    I CURVE  I 600 400 -
200 -
0            I    I        I                              I        I        I        I 200        250  300      350      400        450    500 550      600        650      700 RCS Cold Leg Temperature (oF)
FIGURE ES02-2,  NATURAL CIRCULATION COOLDOWN WITHOUT CRDM FANS
                                                  -END-13 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-0, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0    400          52 401    800          36 801    1200          23 1200    2500          19
: 2. AFI SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[  2-ES-0.2 Number:
 
==Title:==
NATURAL CIRCULATION COOLDOWN                      REV. 0 Revision Number:
ATTACHMENT 1            (Attachment page 1 of 1)
RCS SUBCOOLING WITHOUT CRDM FANS
: 1. Perform the following in conjunction with Procedure Steps.
a) Refer to FIGURE ES02-2 for the acceptable operating region.
b) Maintain RCS pressure approximately 1890 psig until RCS cold leg temperature is decreased to 400°F at a rate less than.
250F/hr.
c) Continue the cooldown at a rate less than 25 0 F/hr and initiate a depressurization of the RCS while maintaining a minimum of 150°F subcooling (or the Tech Spec limit) until RCS pressure is 1100 psig.
d) Maintain RCS pressure approximately 1100 psig until RCS cold leg temperature is decreased below320°F at a rate less than 250F/hr.
e) Wait 8 hours to allow the upper head to cool before continuing depressurization.
f) Continue the cooldown at a rate less than 25°F/hr and initiate a depressurization of the RCS while maintaining a minimum of 50°F subcooling (or the Tech Spec limit) until RCS pressure is between 350 psig and 370 psig..
g) With RHR in service for cooldown, maintain RCS pressure between 350 psig and 370 psig for 27 hours until the entire RCS is decreased below 200 0 F.
                                            -END-14 of 14
 
FOLDOUT PAGE FOR 2-ES-0.2
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION.      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE, OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0 -400              52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Procedure Use Is:  Control Copy:
SEnteWg                      0 Continuous Nuclear Northeast      O Reference        Effective Date: ,
o  Information 2-ES-0.3, Revision: 0 NATURAL CIR                    NCOOLDOWN WI T  HSirwSEL Approved By:
Procedure(Sponsor, RF Team P Procedure Owner PARTIAL REVISION
 
2-ES-0.3          NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN        R VESSEL (WITH RVLIS)                    REV. 0 A. PURPOSE This procedure provides actions to continue plant cooldown and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void in the upper head region with a vessel level system available to monitor void growth.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from 2-ES-0.2, NATURAL CIRCULATION COOLDOWN, after completing the first eleven steps.
1 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O,  REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0  -  400            52 401  -  800            36 801  -  1200          23 1200  -  2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
le:                                                        Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITH RVLIS)
I STP      ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINED t
CAUTION
* o If SI actuation occurs during this procedure,      transition to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,.step 1.
* o The first eleven steps of 2-ES-0.2, NATURAL CIRCULATION COOLDOWN, should be performed before continuing with this procedure.
* o If RCP seal cooling had previously been lost, the affected RCP should            *
* NOT be started prior to a status evaluation.
NOTE o RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
o If conditions can be established for starting an RCP during this procedure, Step 1 should be repeated.
* 1. Try To Restart An RCP:
: a. Establish conditions for            a. Go to Step 2. OBSERVE NOTE starting an RCP per 2-SOP-1.3,          PRIOR TO STEP 2.
REACTOR COOLANT PUMP OPERATION This Step continued on the next page.
2 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            °F 0 -400              52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
e :
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
: b. Check RVLIS natural                b. Perform the following:
circulation range indication    -
GREATER THAN 100%                      1) Increase PRZR level to 62%
using charging and letdown.
: 2) Establish subcooling based on core exit TCs greater than value obtained from table using steam dump:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0  -  400          74 401  -  800          58 801  -  1200          45 1200  -  2500          41
: 3)  Use PRZR heaters, as necessary to saturate the pressurizer water.
: c. Start one RCP                      c. Go to Step 2. OBSERVE NOTE PRIOR TO STEP 2.
: d. Go to 2-POP-3.2, PLANT RECOVERY FROM TRIP, HOT STANDBY 3 of 11
 
FOLDOUT PAGE FOR 2-ES-O.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
e.:                                                        Revision Number- ==n NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITH RVLIS)
I              JJ NOTE Saturated conditions in the PRZR should be established before trying to decrease PRZR level.
: 2. Establish PRZR Level To Accommodate Void Growth:
: a. Check PRZR level    - BETWEEN 28%    a. Control charging and letdown AND 38%                                as necessary.
: b. Place charging pump speed controls in manual 4 of 11
 
FOLDOUT PAGE FOR 2-ES-O.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            -F 0 -400              52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AF' SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
STP        ACTION/EXPECTED RESPONSEI                RESPONSE NOT OBTAINEDI NOTE 2iPOP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,          should be referred to for plant alignment during cooldown.
: 3. Continue RCS Cooldown And Initiate DeDressurization:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN IO0F/HR
: b. Maintain RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE      RCS SUBCOOLING (PSIG)              °F 0  - 400            72 401  - 800            56 801 -  1200          43 1201  - 2500          39
: c. Maintain temperature and pressure - WITHIN LIMITS OF FIGURE ES03-1
: d. Check letdown - IN SERVICE            d. Depressurize RCS using one PRZR PORV. Go to Step 4.
: e. Check differential temperature.      e. Depressurize RCS using one between PRZR and auxiliary                PRZR PORV. Go to Step 4.
spray (TI-126) - LESS THAN 3200 F
: f. Depressurize RCS using auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL 5 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)              -F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
I Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
REV. 0 I
: 4. Control PRZR Level:
: a. Level - GREATER THAN 28%          a. Control charging and letdown, I
as necessary, to increase PRZR level to greater than 28%.
: b. Level - LESS THAN 90%              b. Perform the following:
: 1) Turn on PRZR heaters to maintain PRZR pressure stable.
: 2) Decrease PRZR level to less than 90% by one of the following:
o Control charging and letdown as necessary.
                                                          - OR -
o Continue cooldown to shrink RCS inventory.
: 5. Check RVLIS Natural Circulation      Repressurize RCS to maintain Range Indication - GREATER THAN      RVLIS natural circulation range 76%                                  greater than 76%. Return to Step 3.
6 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
2-E S-0. 3                  NATURAL CIRCULATION  VESSEL COOLDOWN (WITH RVLIS)  WITH STEAM VOID IN
        .  .  .*  *..    .  . .*  .*  . .  .  . . .4 ..  .  .* *. *..  *  *  . *  *  . . . * . .4  . . * . .
CAUTION Q
Radiation levels and harsh environment conditions should be evaluated t
t prior to performing local actions.
: 6.      Check If SI Accumulators Should Be Isolated:
: a. RCS pressure            LESS THAN                a. Continue with Step 7. WHEN 1000 PSIG                                              RCS pressure less than 1000 psig, THEN do Steps 6b through 6d.
: b. Locally restore power to isolation valves:
0  894A    (MCC    26A) 0  894C    (MCC    26A) 0  894B    (MCC    26B) 0  894D    (MCC    26B)
This Step continued on the next page.
7 of 1I
 
FOLDOUT PAGE FOR 2-ES-O.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)              -F 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
2-ES-0.3 2-SO3      J      NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN NTRLVESSEL          (WITH RVLIS)
REV.I REV. 0
: c. Close all SI accumulator          c. Vent any unisolated isolation valves                    accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943
: d. Open all SI accumulator isolation valve breakers 8 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O,  REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
                                                                                        'U Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITH RVLIS)
                                                                                      -j
: 7. Check If  SI Pumps Should Be Locked Out:
: a. RCS hot leg temperature - LESS    a. Continue with Step 8. WHEN THAN 350°F                          RCS hot leg temperature less than 350 0 F, THEN do Step 7b.
: b. Place Si pump control switches in PULLOUT
: 8. Maintain Letdown Flow:
: a. Open letdown orifice isolation valves as necessary
: b. Adjust low pressure letdown control valve PCV-135 setpoint as necessary
: 9. Maintain Required RCP Seal Injection Flow:
o 6 gpm to 10 gpm per pump
: 10. Check If RHR System Can Be Placed In Service:
: a. RCS temperature - LESS THAN      a. Return to Step 3.
350°F
: b. RCS pressure - LESS THAN          b. Return to Step 3.
370 PSIG
: c. Place RHR System in service per 2-SOP-4.2.1, RESIDUAL HEAT REMOVAL SYSTEM
: 11. Continue RCS Cooldown To Cold Shutdown 9 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200          23 1200 - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
le:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITH RVLIS)
STEP            ACTION/EXPECTED RESPONSE                    RESPONSE NOT OBTAINED
* CAUTION
* Depressurizing the RCS before the entire .RCS is                less than 200°F may
  "    result in additional void formation in the RCS.
: 12.      Continue Cooldown Of Inactive Portion Of RCS:
: a. Cool upper head region using CRDM fans
: b. Cool SG U-tubes by dumping steam from all SGs
: c. RVLIS natural circulation              c. Return to Step 11.
range indication - GREATER THAN 100%
NOTE If CRDM fans are NOT running, a waiting period of 27 hours is                  necessary to allow the head to cool to less than 200 0 F.
: 13.      Determine If RCS Deoressurization Is Permitted:
: a. Entire RCS - LESS THAN 2000F            a. Return to Step 11.
: b. Go to 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN
                                                  -END-10 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0    400            52 401    800            36 801    1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:              Title-                                                          Revision Number:
2-ES-0.3*                NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN                REV. 0  1 t      -
FIGURE ES03-1 RCS PRESSURE (PSIG) 2500 200  -        I 1000 -
4                                -NAACCEPTABLE 60OPERARATIO 1000II                        1                    i100 0                    i 0            50      100        150      200        250    300            350 RCS COLD LEG TEMPERATURE ('F)
FIGURE ES03-1,    REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
                                                        -END-11 of 11
 
FOLDOUT PAGE FOR 2-ES-0.3
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            oF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Procedure Use Is:  Control Copy:
  '-Entergy                  0 Continuous Nuclear Northeast      [3 Reference        Effective Date:_ _/_//__
0 Information 2-ES-0.4, Revision: 0 NATURAL CIR            .      N COOLDOWNN WITHV    E                          L Approved By:
ProcedureSponsor, F Team P Procedure Owner PARTIAL REVISION
 
Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITHOUT RVLIS)
A. PURPOSE This procedure provides actions to continue plant cooldown and depressurization to cold shutdown, with no accident in progress, under conditions that allow for the potential formation of a void in the upper head region without a vessel level system available to monitor void growth.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from 2-ES-0.2. NATURAL CIRCULATION COOLDOWN. after completing the first eleven steps.
1 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
I Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)                                  REV. 0
                                                                                                              =IJ CAUTION
* o If SI actuation occurs during this procedure,                transition to 2-E-O.
* REACTOR TRIP OR SAFETY INJECTION, step 1.
o The first eleven steps of 2-ES-0.2, NATURAL CIRCULATION COOLDOWN, o
* should be performed before continuing with this procedure.
* o If    RCP seal cooling had previously been lost, the affected RCP should
* NOT be started prior to a status evaluation.
NOTE o RCPs should be run in the following order to provide normal PRZR spray:
RCP 24. RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.                                                                            i o If conditions can be established for starting an RCP during this procedure, Step 1 should be repeated.
* 1.      Try To Restart An RCP:
: a. Establish conditions for                  a. Go to Step 2.      OBSERVE NOTE starting an RCP per 2-SOP-1.3,                  PRIOR TO STEP 2.
REACTOR COOLANT PUMP OPERATION
: b. Check PRZR level    -  GREATER            b. Control charging and letdown THAN 62%                                        as necessary to increase level to greater than 62%.
This Step continued on the next page.
2 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            'F 0 -400              52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Ie:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS) c.. RCS subcooling based on core            c. Establish subcooling based on pxit TC_ - GRFATFR THAN VAILIF            cnre exit TCs oreater than OBTAINED FROM TABLE:                      value obtained from table using steam dump:
WR RCS PRESSURE        RCS SUBCOOLING (PSIG)              OF 0- 400                74 401 - 800              58 801 - 1200              45 1200 7 2500              41
: d. Use PRZR heaters, as necessary to saturate the pressurizer water
: e. Start one RCP                          e. Go to Step 2. OBSERVE NOTE PRIOR TO STEP 2.
: f. Go to 2-POP-3.2, PLANT RECOVERY FROM TRIP, HOT STANDBY NOTE Saturated conditions in the PRZR should be established before trying to decrease PRZR level.
: 2. Establish PRZR Level To Accommodate Void Growth:
: a. Check PRZR level    -  BETWEEN 28%      a. Control charging and letdown AND 38%                                    as necessary.
: b. Place charging pump speed controls in manual 3 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
le:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
RESPONSE NOT OBTAIE
: 3. Decrease RCS Hot Leg Temperatures To 500OF:
: a. Maintain cooldown rate in RCS cold legs      LESS THAN 50°F/HR
: b. Maintain RCS pressure - LESS THAN 1890 PSIG
: c. Maintain RCS temperature and pressure - WITHIN LIMITS OF.
FIGURE ES04-1
: d. Maintain stable PRZR level using charging
: e. Check RCS hot leg temperatures        e. Return to Step 3a.
      - LESS THAN 5000F
: f. Stop RCS cooldown
: 4. Depressurize RCS To 1600 psiq:
: a. Check letdown    - IN SERVICE        a. Use one PRZR PORV. Go to Step 4d.
: b. Check differential temperature        b. Use one PRZR PORV. Go to between PRZR and auxiliary                Step 4d.
spray (TI-126) - LESS THAN 320OF
: c. Use auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL
: d. Check RCS pressure - LESS THAN        d. Return to Step 4a.
1600 PSIG
: e. Stop RCS depressurization 4 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200          23 1200 - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[Number:
2-ES-0.4~
 
==Title:==
NATURAL CIRCULATION  COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
RV Number:
Revision STEP    ACTION/EXPECTED RESPONSE                REPNENTOTIE NOTE o 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,      should be referred to for plant alignment during cooldown.
o After cooldown is    stopped,  RCS hot leg temperatures will decrease due to decrease in heat transfer rate.
: 5. Decrease RCS Hot Leg Temperatures To 450°F:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN 1O0°F/HR
: b. Maintain RCS pressure - AT 1600 PSIG
: c. Maintain RCS temperature and pressure - WITHIN LIMITS OF FIGURE ES04-1
: d. Maintain stable PRZR level using charging
: e. Check RCS hot leg temperatures      e. Return to Step 5a.
              - LESS THAN 450°F
: f. Stop RCS cooldown
: 6. Equalize Charging And Letdown Flows:
: a. Place charging and letdown controls in manual
: b. Control charging and seal injection flows to equal letdown and seal return flows
: 7. Maintain Required RCP Seal InJection Flow:
o 6 gpm to 10 gpm per pump 5 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITHOUT RVLIS)
*  *  *    * *
* A *  *
* A *  *  *  *
* A-A    *  * *  *  * *  * * *
* A * *
* A *  *  *  * *  ~*
* CAUTION                                              *r Radiation levels and harsh environment conditions should be evaluated prior to performing local actions.
: 8.  *
* A *
* I * *
* Ac*
* u
* u  a* o*  *
* Sh o* u *  * * *  * * *  *        *  *                    *
: 8.        Check If SI Accumulators Should Be Isolated:
a..RCS pressure - LESS THAN                            a.. Continue with Step 9. OBSERVE 1000 PSIG NOTE PRIOR TO STEP 9. WHEN RCS pressure less than 1000 psig, THEN do Steps 8b through 8d.
: b. Locally restore power to isolation valves:
0 894A    (MCC    26A) 0 894C    (MCC    26A) 0 894B    (MCC    26B) 0 894D    (MCC    26B)
This Step continued on the next page.
6 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. ARW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITHOUT RVLIS)
STP    ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI
: c. Close all SI accumulator            c. Vent any unisolated isolation valves                        accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943
: d. Open all SI accumulator isolation valve breakers 7 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O,  REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
STP      ACTION/EXPECTED RESPONSEi                    RESPONSE NOT OBTAINED NOTE The upper head region may void during depressurization.            This will result in a rapidly increasing PRZR level.
: 9. DeDressurize RCS:
: a. Check letdown    -  IN SERVICE          a. Use one PRZR PORV. Go to Step 9d.
: b. Check differential temperature          b. Use one PRZR PORV. Go to between PRZR and auxiliary                    Step 9d.
spray (TI-126) - LESS THAN 320OF
: c. Use auxiliary spray:
o Refer to 2-SOP-1.4.
PRESSURIZER PRESSURE CONTROL
: d. Depressurize RCS until either of the following conditions satisfied:
o RCS pressure    -  LESS THAN 800 PSIG
                    - OR o PRZR level  -  GREATER THAN 90%
: e. Stop RCS depressurization 8 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O. REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)            OF 0 -  400          52 401 -  800          36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
NOTE In order to continue overall system depressurization, it may be necessary to cycle PRZR level (cycle pressure) to enhance upper head cooling.
: 10. Check PRZR Level - LESS THAN 90%        Increase RCS pressure by 100 psi using PRZR heaters. Return to Step 9. OBSERVE NOTE PRIOR TO STEP 9.
: 11. Decrease RCS Hot Leg Temperatures To 4000F:
: a. Maintain cooldown rate in RCS cold legs  - LESS THAN 1000 F/HR
: b. Maintain RCS pressure  - STABLE
: c. Maintain RCS temperature and pressure - WITHIN LIMITS OF FIGURE ES04-1
: d. Maintain stable PRZR level using charging
: e. Check RCS hot leg temperatures
: e. Return to Step 11a.
        - LESS THAN 4000F
: f. Stop RCS cooldown
: 12. Equalize Charging And Letdown Flows:
: a. Place charging and letdown controls in manual
: b. Control charging and seal injection flows to equal letdown and seal return flows 9 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              -F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)
: 13. Depressurize RCS:
: a. Check letdown  -  IN SERVICE        a. Use one PRZR PORV. Go to Step 13d.
: b. Check differential temperature        b. Use one PRZR PORV. Go to between PRZR and auxiliary                Step 13d.
spray (TI-126) - LESS THAN 320OF
: c. Use auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL
: d. Depressurize RCS until either of the following conditions satisfied:
o RCS pressure    -  LESS THAN 600 PSIG
_ OR -
o PRZR level      GREATER THAN 90%
: e. Stop RCS depressurization
: 14. Check PRZR Level  -  LESS THAN 90%      Increase RCS pressure by 100 psi using PRZR heaters. Return to Step 13.
10 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
I.F EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            'F 0  - 400          52 401 -  800          36 801 -  1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
2:                                                    Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL (WITHOUT RVLIS)                      REV. 0
                                                                                        =I SFTEP - ACTION/EXPECTED RESPONSE              i RESPONSE NOT.OBTAIE
: 15. Decrease RCS Hot Leg Temperatures To 350°F:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN IO0F/HR
: b. Maintain RCS pressure - STABLE
: c. Maintain RCS temperature and pressure - WITHIN LIMITS OF FIGURE ES04-1
: d. Maintain stable PRZR level using charging
: e. 'Check RCS hot leg temperatures      e. Return to Step 15a.
          - LESS THAN 350oF
: f. Stop RCS cooldown
: 16. Place SI Pump Control Switches In PULLOUT
: 17. Equalize Charging And Letdown Flows:
: a. Place charging and letdown controls in manual
: b. Control charging and seal injection flows to equal letdown and seal return flows 11 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
I.F EITHER condition listed below occurs, actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)              OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
[2-ES-0.4            NATURAL CIRCULATION VESSEL COOLDOWN    RVLIS)STEAM VOID IN (WITHOUT WITH                            REV. 0
: 18. Depressurize RCS:
: a. Check letdown      IN SERVICE          a. Use one PRZR PORV. Go to Step 18d.
: b. Check differential temperature          b. Use one PRZR PORV. Go to between PRZR and auxiliary                  Step 18d.
spray (TI-126)        LESS THAN 320OF
: c. Use auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL
: d. Depressurize RCS until either of the following conditions satisfied:
o RCS pressure    -  LESS THAN 370 PSIG OR o PRZR level    GREATER THAN 90%
: e. Stop RCS depressurization
: 19. Check PRZR Level      I FSS TI-AN qOI%    Increase RCS pressure by 100 psi LESS THAN 90%      using PRZR heaters. Return to Step 18.
: 20. Check If  RHR SYstem Can Be Placed In Service:
: a. RCS temperature    - LESS THAN        a. Return to Step 15.
350°F
: b. RCS pressure - LESS THAN                b. Return to Step 18.
370 PSIG
: c. Place RHR System in service per 2-SOP-4.2.1, RESIDUAL HEAT REMOVAL SYSTEM
: 21. Continue RCS Cooldown To Cold Shutdown 12 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING (PSIG)            OF 0 - 400            52 401 - 800            36 801 - 1200            23 1200 - 2500            19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Revision Number:
NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN REV. 0 VESSEL (WITHOUT RVLIS)
*~*  *  *  *  * * *  * *  *  * * *  * * * *  *  * *  *
* ft * *  * * * * * * *  *  * *
* ft  *
* CAUTION                                                  r
  ¢r Depressurizing the RCS before the entire RCS is              less than 200OF may result in additional void formation in the RCS.
: 22. Continue Cooldown Of Inactive Portion Of RCS:
o Cool upper head region using CRDM fans o Cool SG U-tubes by dumping steam from all SGs NOTE If CRDM fans are NOT running, a waiting period of 27 hours is                necessary to allow the head to cool to less than 200 0 F.
: 23. Determine If RCS Depressurization Is Permitted:
: a. Entire RCS  -  LESS THAN 200OF        a. Return to Step 21.
: b. Go to 2-POP-3.3, PLANT COOLDOWN, HOT TO COLD SHUTDOWN
                                              -END-13 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,    actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,    Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9%
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE  RCS SUBCOOLING (PSIG)            OF 0  - 400            52 401  - 800          36 801 -  1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number-2-ES-0.4              NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN                REV. 0 FIGURE ES04-1 RCS PRESSURE (PSIG) 2500  -
2000  -
E A
i 1500  -                                                        A UNACCEPTABLE                    I OPERATION I
A 1000 MAXIMUM COOLDOWN RATES: OF/HR                            r 500  -
20 40 0
ACCEPTABLE
                                                                                    . i  I 60                                    OPERATION 100 I-J I I                                        -- J    I I I 0 I "T- pli                                              2 0          50      100        150      200        250      300          350 RCS COLD LEG TEMPERATURE (oF)
FIGURE ES04-1,  REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
                                                  -END-14 of 14
 
FOLDOUT PAGE FOR 2-ES-0.4
: 1. SI ACTUATION CRITERIA:
IF EITHER condition listed below occurs,      actuate SI AND go to 2-E-O, REACTOR TRIP OR SAFETY INJECTION,      Step 1:
o PRZR level  - CANNOT BE MAINTAINED GREATER THAN 9Z o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING 0
(PSIG)                F 0  - 400            52 401  - 800            36 801  - 1200          23 1200  - 2500          19
: 2. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
a Entery                      Procedure Use Is:
0 Continuous Control Copy:
Nuclear Northeast evat Tfat.
o  Reference      Effective Date: ýA/Lo*
O Information A- J:,  It 2-E-1, Revision: 0 LOSS OF REACTOR/OR.SECONDARY                    COOLANT Approved By:
Proced e Sponsor, RPO/ De Team P Procedure Owner PARTIAL REVISION
 
2-E-1                  LOSS OF REACTOR OR SECONDARY COOLANT                  REV. 0 Number:
 
==Title:==
Revision Number:
A. PURPOSE This procedure provides actions to recover from a loss of reactor or secondary coolant.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:
: 1) 2-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 11, and 2-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 26, when a PRZR PORV is stuck open and its block valve can not be closed.
: 2) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 15, with any of the following symptoms:    high containment radiation, high containment pressure, or high containment recirculation sump levels.
: 3) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 20, and 2-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 6. 2-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. Step 28, when RCS pressure is less than the shutoff head pressure of the RHR pumps.
: 4) 2-ES-1.1, SI TERMINATION, Step 6 and 24, and 2-FR-I.2. RESPONSE TO LOW PRESSURIZER LEVEL, Step 5,  if  SI has to be reinitiated.
: 5) 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 7. after identification and isolation of a faulted SG.
: 6) 2-ECA-O.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 12, after normal injection mode conditions are established.
: 7) 2-.ECA-1.2. LOCA OUTSIDE CONTAINMENT,  Step 6, when a LOCA outside containment is isolated.
: 8) 2-FR-C.I. RESPONSE TO INADEQUATE CORE COOLING, Step 17 and 26, and 2-FR-C.2, RESPONSE TO DEGRADED CORE COOLING, Step 17, after core cooling has been reestablished.
: 9) 2-FR-H.I. RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 26, after heat sink has been reestablished and all PRZR PORVs are closed.
1 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING 0
: b. RCS subcooling based on core exit TCs - LESS THAN 23        F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1,      SI TERMINATION:
0
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26        F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:.
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level    GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
      "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
      "  RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200      1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to'less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
[
Number:
 
==Title:==
Revision Number:
2-E-1                  LOSS OF REACTOR OR SECONDARY COOLANT              REV. 0 C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr..
OR -
o Containment pressure greater than 4 psig.
2 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30    0 F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
    "  RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE    PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.        TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
* CAUTION
* t*
* FRPs should NOT be implemented.prior to completion of 2-E-O, REACTOR TRIP
* OR SAFETY INJECTION,  ATTACHMENT 1, AUTOMATIC ACTION VERIFICATION.
S  *                                            * * * * * * *  * *
* S S S *
: 1. Check If  RCPs Should Be Stopped:
: a. SI pumps - AT LEAST ONE RUNNING    a. Go to Step 2.
: b. RCS subcooling based on core        b. Go to Step 2.
exit TCs - LESS THAN 230 F (30OF FOR ADVERSE CONTAINMENT)
: c. Stop all RCPs
: 2. Check If  Any SG Is Faulted:
: a. Check pressures in all SGs    -    a. Go to Step 3.
o ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
                    - OR -
o ANY SG COMPLETELY DEPRESSURIZED
: b. Verify all. faulted SG(s)          b. Go to 2-E-2. FAULTED STEAM isolated:                                GENERATOR ISOLATION, Step 1.
o Steamlines o Feedlines 3 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs        LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1,        SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
    "  RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500  )
RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-1                          LOSS OF REACTOR OR SECONDARY COOLANT                        REV. 0
: 3.        Check Intact SG Levels:
: a. Narrow range level - GREATER          a. Maintain total feed flow THAN 10% (27% FOR ADVERSE                  greater than 400 gpm until CONTAINMENT)                              narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain        b. IF narrow range level in any narrow range level between 10%            SG continues to increase in an (27% FOR ADVERSE CONTAINMENT)            uncontrolled manner, THEN go and 50%                                    to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
CAUTION o IF any PRZR PORV opens because of high PRZR pressure, Step 4b should be repeated after pressure decreases to less than the PORV setpoint.
* o Radiation levels and harsh environment          conditions should be evaluated
* prior to performing local actions.
* d*
: 4.        Check PRZR PORVs And Block Valves:
: a. Power to block valves                a. Restore power to block valves AVAILABLE                                  by closing the following breakers as necessary:
o MCC 26B/lH (MOV-535) o MCC 26A/IH (MOV-536)
: b. PORVs - CLOSED                        b. IF PRZR pressure less than 2335 psig, THEN manually close PORVs. IF any valve can NOT be closed. THEN manually close its block valve.
: c. Block valves - AT LEAST ONE          c. Open one block valve unless it OPEN                                      was closed to isolate an open PORV.
4 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps  - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    -  LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1,        SI TERMINATION:
: a. RCS subcooling based on core exit TCs      GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
        "  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800      801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft.      switch to city water supply.
 
* *  *  * *  * *  * * * * *
* a * * * *  * * *
* a *  *  * * * * * * * * * * * * * *
* Q CAUTION o If offsite power is lost after SI reset, manual action may be required
* to restart safeguards equipment.
o Overriding breaker anti-pump/lockout may require placing control switches to TRIP or may require Containment Spray Reset
* o Placing key switches to DEFEAT will prevent auto SI actuation.
: 5. Reset SI:
: a. Check all CCW pumps - RUNNING        a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1 o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2) o Train A o Train B
: e. Verify Train A AND B - RESET        e. Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o  SIA-1 o  SIM-1 o  SIA-2 o  SIM-2 5 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps    AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on.core exit TCs - GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                          -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
a  STABLE OR INCREASING 0  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
  "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14%.(33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,      TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
SNumber:          Title-                                                      Revision Number:
S 2-E-1                      LOSS OF REACTOR OR SECONDARY COOLANT                  REV. 0
: 6. Reset Containment Isolation Phase A And Phase B:
: a. Place IVSW switches to OPEN on SN panel:
o  1410 o  1413 o  SOV-3518 o  SOV-3519
: b. Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: c. Verify personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: d. Place control switches for all remaining Phase A isolation valves to CLOSE on SN panel
: e. One at a time, depress Phase A reset buttons o CI Phase A Train A o CI Phase A Train B
: f. Verify Train A AND B  - RESET      f. IF signal does NOT reset,    THEN:
: 1) Place key switches to BYPASS.
: 2) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset, THEN reset relays CAl AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
This Step continued on the next page.
6 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30    0 F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
LF ALL conditions listed below occur,    go to 2-ES-1.1., SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs    GREATER THAN 400 gpm
                          -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
        "  STABLE OR INCREASING
        "  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2,.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:        fTitle:                                                          Revision Number:
2-E-1                    LOSS OF REACTOR OR SECONDARY COOLANT                    REV. 0 STEP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED
: g. Check Phase B    -  ACTUATED          g. Go To Step 7.
: h. Containment pressure - LESS        h. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig, THEN do Steps 6i, 6j and 6k.
: 2) Continue with Step 7.
: i. One At A Time, Depress Containment Spray Reset Pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: j. One at a time,  depress Phase B reset buttons o CI Phase B Train A o CI Phase B Train B
: k. Verify Train A AND B - RESET        k. Verify Relays reset (Top of Safeguards Initiation Racks 1-2 AND 2-2):
o S1 o S2 o CB1 o CB2
: 7. Establish Instrument Air To Containment:
: a. Open PCV-1228                      a. Verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAI o CA2 7 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs                    0
                                                  -  LESS THAN 23  F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manual-ly start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSEI            RESPONSE NOT OBTAINEDI
: 8. Check Secondary Radiation  -          Go to 2-E-3, STEAM GENERATOR TUBE NORMAL:                              RUPTURE, Step 1.
o Main steamline radiation recorder (R-28, R-29, R-30,  and R-31) o Condenser air ejector radiation recorder (R-45) o SG blowdown radiation recorder (R-49) o Request periodic activity samples of all SGs
: 9. Check Power SuDplY To CharQing        Verify adequate diesel capacity Pumps - OFFSITE POWER AVAILABLE      to run charging pumps. IF necessary, shed sufficient non-essential loads.
8 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-i.1,      SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690    PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)    23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
CAUTION
* If RWST level decreases to less than 15 ft. charging pumps that are            *
* started or running should be monitored for loss of suction which may
* result in pump damage.
: 10. Check If Charging Flow Has Been Established:
: a. Charging pumps    AT LEAST ONE    a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
o  MOV-250A. MCC 26AA,  A2 o  MOV-250C,  MCC 26AA,  B2 o  MOV-250B,  MCC 26BB,  L3 o  MOV-250D,  MCC 26BB,  M3
                                                              - OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
o  241A o  241B o  241C o  241D
: 2) Start charging pump(s)      as necessary.
: b. Establish charging flow as necessary:
: 1) Verify speed controller in MANUAL
: 2) Adjust charging pump speed 9 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,      trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (3 0 °F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,      go to 2-ES-1.1,  SI TERMINATION:
0
: a. RCS subcooling based on core exit TCs      - GREATER THAN 19°F (26    F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level    - GREATER THAN 14% (33Z FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  -  PSIG          0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING °F (ADVERSE)      52 (83)    36 (49)    23 (30)    19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step I.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
2-E-1                  LOSS OF REACTOR OR SECONDARY COOLANT              REV. 0
*11. Check If SI Flow Should Be Terminated:
: a. RCS subcooling based on core        a. Go to Step 12.
exit TCs - GREATER THAN 190 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Secondary heat sink:                b. IF neither condition satisfied, THEN go to Step 12.
o Total feed flow to intact SGs - GREATER THAN 400 GPM
                    - OR -
o Narrow range level in at least one intact SG -
GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:                      c. Go to Step 12.
o Pressure - GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT) o Pressure - STABLE OR INCREASING
: d. PRZR level - GREATER THAN 14%      d. Try to stabilize RCS pressure (33% FOR ADVERSE CONTAINMENT)          with normal PRZR spray. Go to Step 12.
: e. Go to 2-ES-1.1, SI TERMINATION, Step 1 10 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1., SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                          -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3,    TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 12. Check If Containment Spray Should Be Stopped:
: a. Spray pumps    RUNNING              a. Go to Step 13. OBSERVE CAUTION PRIOR TO STEP 13.
: b. Containment pressure  - LESS      b. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig. THEN do Steps 12c through 12f.
: 2)  Continue with Step 13.
OBSERVE CAUTION PRIOR TO STEP 13.
: c. One at a time, depress containment spray reset pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: d. Containment area radiation          d. Perform the following:
NORMAL
: 1) WHEN containment spray has o R-25. R-26                            been in service for 3.5 hours, THEN do Steps o R-41. R-42                            12e and 12f.
o R-2,  R-7                          2) Go to Step 13. OBSERVE CAUTION PRIOR TO STEP 13.
: e. Stop containment spray pumps and place in AUTO
: f. Close containment spray pump discharge valves:
o MOV-866A o MOV-866B o MOV-866C o MOV-866D 11 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    -  LESS THAN 23 0 F (30 0 F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
0  STABLE OR INCREASING
        &  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
0  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  -  PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3,          TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
INumber:
2-E-1
 
==Title:==
LOSS OF REACTOR OR SECONDARY COOLANT Revision Number:
REV. 0
  *  *  *  *
* a  * * * * * *  * * *  * *  *  * *  *  * *  * * * * * *  * * * *
* a  *  *  *  *
* CAUTION RCS pressure should be monitored.              If RCS pressure decreases in an
* t t
uncontrolled manner to less than 320 psig (340 psig FOR ADVERSE CONTAINMENT), the RHR pumps must be manually restarted to supply water to the RCS.
t
: 13.      Check If      RHR Pumps Should Be Stopped:
: a. Check RCS pressure:
: 1) Pressure - GREATER THAN                    1) Go to Step 15.
320 PSIG (340 PSIG FOR ADVERSE CONTAINMENT)
: 2) Pressure - STABLE OR                        2) Go to Step 14.
INCREASING
: b. RHR pumps - ANY RUNNING WITH              b. Go to Step 14.
SUCTION ALIGNED TO RWST
: c. Stop RHR pumps and place in AUTO
: 14.      Check RCS And SG Pressures:                    Return to Step I.
o Check pressure in all SGs        -
STABLE OR INCREASING o Check RCS pressure - STABLE OR DECREASING 12 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    -  LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit.TCs    -  GREATER THAN 19 0 F (26°F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
        "  STABLE OR INCREASING
        "  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500  )
RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step I.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
E Number:
2-E-1
 
==Title:==
LOSS OF REACTOR OR SECONDARY COOLANT              Revision REV.Number:
0    ]
STP        ACTION/EXPECTED RESPONSE'              RESPONSE NOT OBTAINED
: 15. Check If Diesel Generators Should Be Stopped:
: a. Verify 480V busses - ENERGIZED    a. Try to restore offsite power BY OFFSITE POWER                      to 480V busses per 2-AOP-138KV, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
IF offsite power can NOT be restored, THEN load the following equipment on 480V busses:
o MCCs:
o MCC 24A o MCC 27A o MCC 29A o Direct Support Facilities personnel to align PAB LIGHTING TRANSFORMER 23 ALTERNATE POWER SUPPLY to TSC bus per 2-SOP-27.1.5, 480 VOLT SYSTEM, as necessary.
o Start one cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW, THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
This Step continued on the next page.
13 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,  trip all RCPs:
: a. SI pumps    - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                          -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
0  STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3,      TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
1Number:
 
==Title:==
Revision Number:
2-E-1                  LOSS OF REACTOR OR SECONDARY COOLANT                REV. 0 o Locally start one 480V switchgear room exhaust fan.
o IF necessary, defeat fan interlock using bypass key.
Go to Step 15c.
: b. Manually load the following equipment on the 480V busses:
o All MCCs as necessary except MCC 28 and MCC 28A o All lighting as necessary o One cable tunnel exhaust fan o Verify radiation monitors R-43/R-44 in service and start PAB ventilation fans o Locally start one 480V switchgear room exhaust fan o IF necessary, defeat fan interlock using bypass key
: c. Locally stop any unloaded diesel generator(s) and place in standby 14 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19°F (26°F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
    "  RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)    23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-1                  LOSS OF REACTOR OR. SECONDARY COOLANT                REV. 0
: 16. Initiate Evaluation Of Plant Status:
: a. Verify cold leg recirculation        a. IF at least one train of cold capability:                              leg recirculation capability can NOT be verified, THEN go o Power to recirculation                to 2-ECA-1.1, LOSS OF pump(s) and discharge header          EMERGENCY COOLANT valve(s) - AVAILABLE                  RECIRCULATION. Step 1.
                        - OR -
o Power to RHR pump(s) and associated valve(s) -
AVAILABLE
: b. Check PAB radiation - NORMAL:        b. Try to identify and isolate leakage:
o 98 ft. EL area monitor (R-5987)                              o Notify health physics and chemistry.
o Charging pump room area monitor (R-4)                        IF the cause is a loss of RCS inventory outside containment, o Plant vent monitors (R-43,            THEN go to 2-ECA-1.2, LOCA R-44)                                OUTSIDE CONTAINMENT, Step 1.
: c. Obtain samples:
o RCS boron concentration o RCS activity o Containment atmosphere o Containment sump boron concentration
: d. Evaluate plant equipment:
o Routinely check operating safeguards equipment for proper operation as necessary
: e. Start additional plant equipment to assist in recovery as necessary:
o House service boilers o Ventilation systems o Circulating water pumps o Instrument air closed cooling system 15 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps    AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1, SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                        -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
0  STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,    TRANSFER TO COLD LEG RECIRCULAT]ON, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-E-1                      LOSS OF REACTOR OR SECONDARY COOLANT                REV. 0
: 17. Check If RCS Cooldown And flnrPssuri7at-inn Tq Rpniiirpd-
: a. RCS pressure - GREATER THAN          a. IF RHR pump flow greater than 320 PSIG (340 PSIG FOR ADVERSE          240 gpm (400 gpm FOR ADVERSE CONTAINMENT)                            CONTAINMENT), THEN go to Step 18.
: b. Go to 2-ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1
: 18. Check If Transfer To Cold Leg Recirculation Is Required:
: a. RWST level  -  LESS THAN 9.24 FT    a. Return to Step 16.
: b. Go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1 unless previously performed
: 19. Check If SI Accumulators Should Be Isolated:
: a. At least two RCS hot leg            a. Continue with Step 20. WHEN temperatures - LESS THAN 350°F          at least two RCS hot leg temperatures less than 350°F THEN do steps 19b through 19d.
: b. Locally restore power to isolation valves:
o  894A (MCC  26A) o  894C (MCC  26A) o  894B (MCC  26B) o  894D (MCC  26B)
This Step continued on the next page.
16 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs        LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs      GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  -  PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
(    2-E-1 Number:
 
==Title:==
LOSS OF REACTOR OR SECONDARY COOLANT                  REV. 0 Revision Number:
STE      ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI
: c. Close all SI accumulator            c. Vent any unisolated isolation valves                        accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943
: d. Open all SI accumulator isolation valve breakers 17 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit T.Cs  - LESS THAN 23 0 F (3 0 °F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1. SI TERMINATION:
0
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26      F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs    GREATER THAN 400 gpm
                        -OR-Narrow range level in at least one intact SG.- GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
  "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any 56 has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-I.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
(  2-E-2 Number:
 
==Title:==
LOSS OF REACTOR OR SECONDARY COOLANT                REV. 0 Revision Number:
STP      ACTION/EXPECTED RESPONSE I!RESPONSE              NOT OBTAINED
* CAUTION To prevent main steamline isolation,      steam dump to condenser should NOT t
exceed 0.5 E6 lbs/hr per SG.
: 20. Check If Intact SGs Should Be Denressurized To RCS Pressure:
: a. RCS pressure - LESS THAN            a. Go*to Step 21.
INTACT SG PRESSURES
: b. Sample all SGs for radioactivity levels
: c. Request a dose projection on steaming SGs from the TSC
: d. Dose projection for each SG    -    d. Do NOT dump steam from a SG ACCEPTABLE                              with an unacceptable dose projection.
: e. Dump steam to condenser from        e. Dump steam using intact SG intact SGs, NOT to exceed              atmospheric steam dumps until 0.5 E6 lbs/hr per intact SG,            SG pressure less than RCS until SG pressure less than            pressure.
RCS pressure:
: 1) Check condenser - AVAILABLE
: 2)  Place steam dump controller switch to manual and adjust for zero output.
: 3) Transfer condenser steam dump to pressure control mode and adjust manual setpoint as necessary.
18 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all  RCPs:
: a. SI pumps - AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs    -  LESS THAN 23 0 F (30 0 F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
        "  STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 21. Determine If Reactor Vessel Head Should Be Vented:
: a. Consult TSC
: 22. Check Containment Hydrogen Concentration:
: a. Obtain a hydrogen concentration measurement:
o Dispatch chemistry personnel to obtain sample
                - OR -
o Use H2-02 analyzer on Accident Assessment Panel
: b. Hydrogen concentration  -  LESS    b. Consult TSC for additional THAN 3.0% IN DRY AIR                  recovery actions.
19 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur, trip all RCPs:
: a. SI pumps - AT LEAST ONE RUNNING 0
: b. RCS subcooling based on core exit TCs  - LESS THAN 23  F (3 0 °F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1, SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26  0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                          -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level    GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
    "    RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3,      TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
INumber:
2-E-1
 
==Title:==
LOSS OF REACTOR OR SECONDARY COOLANT                  REV.
Revision 0
Number:
: 23. At 3.5 Hours After Event Tnitiatinn      Prpnare  Fnr Hnt Ipa Recirculation
: a. Check hot leg injection valves        a. Place valve switches in  proper in the following position:              position.
o MOV-856B      CLOSED o MOV-856F    -  CLOSED
: b. Dispatch NPO to energize cold        b. Close circuit breakers as leg and hot leg injection                necessary.
valves:
0  MOV-856A  (MCC  26A) 0  MOV-856C  (MCC  26A) 0  MOV-856F  (MCC  26A) 0  MOV-856D  (MCC  26B) 0  MOV-856E  (MCC  26B) 0  MOV-856B  (MCC  26B)
: c. Check RHR spray header                c. Manually close valves.
isolation valves - CLOSED:
o MOV-889A o MOV-889B
: 24. At 6.5 Hours After Event Tnitiatinn      Gn Tn 2-FS-1_4 TRANSFER TO HOT LEG RECIRCULATION, Step 1
: 25. Evaluate Long Term Plant Status
: a. Consult TSC
                                            -END-20 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,    trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs - LESS THAN 23 0 F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26      0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
        "  STABLE OR INCREASING
* GREATER THAN 1660 PSIG (1690    PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT).
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
* PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)      19 (26)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE., Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,        TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number: 1 2-E-1                  LOSS OF REACTOR OR SECONDARY COOLANT                    REV. 0 ATTACHMENT 1                (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the following table to determine 480V eauipment load ratinqs:
21 DG          22 DG            23 DG EQUIPMENT          BUS 5A      BUS 2A    BUS 3A I  BUS 6A 21 SERVICE WATER PUMP      282 KW 22 SERVICE WATER PUMP                  282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP      282 KW 25 SERVICE WATER PUMP                  282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                      485 KW 23 PRZR BU HEATERS          485 KW 21 AFW PUMP                                        384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT          250 KW 22 FAN COOLER UNIT          250 KW 23 FAN COOLER UNIT                      250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                          250 KW 21 SI PUMP                  316 KW 22 SI PUMP                              316 KW    316 KW 23 SI PUMP                                                  345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP
          .21 RHR PUMP 22 RHR PUMP 21 CHARGING PUMP            150 KW 303 KW 350 KW 303 KW I
22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                            150 KW 21 RECIRC PUMP              299 KW 22 RECIRC PUMP                                              299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW 23 CCW PUMP                                                  228 KW 21 LIGHTING TRANSFORMER                150 KW (N)          150 KW (E) 22 LIGHTING TRANSFORMER                            225 KW 23 LIGHTING TRANSFORMER    225 KW TURBINE AUX OIL PUMP                                        112 KW STATION AIR COMPRESSOR      93 KW
                                            - END -
21 of 21
 
FOLDOUT PAGE FOR 2-E-1
: 1. RCP TRIP CRITERIA:
IF BOTH conditions listed below occur,      trip all RCPs:
: a. SI pumps  -  AT LEAST ONE RUNNING
: b. RCS subcooling based on core exit TCs                      0 LESS THAN 23  F (30°F FOR ADVERSE CONTAINMENT)
: 2. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,      go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs      - GREATER THAN 19 0 F (26 0 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
* STABLE OR INCREASING 0  GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level    -  GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 3. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
    "  PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
* RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  -  PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)      52 (83)
: 4. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 5. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 6. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3,          TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 7. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Procedure Use Is: Control Copy:
  'Entergy                    12 Continuous Nuclear Northeast        0 Reference      Effective Date:
0 Information 2-ES-1.1, Revision: 1 SI TERMI!NATION Approved By:
Procedure Sponsor, RPO/ C Team P Procedure Owner EDITORIAL REVISION
 
A. PURPOSE This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditions.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:    ,
: 1) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 16, and 2-E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 11, when specified termination criteria are satisfied.
: 2)  2-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 30, after heat sink has been reestablished and SI has been terminated.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions .exist:
o Containment radiation levels greater than IE5 R/hr.
                          - OR -
o Containment pressure greater than 4 psig.
1 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA: '
IF EITHER condition listed below occurs following SI termination.
manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
CAUTION o If offsite power is lost after SI reset, o                                                manual action may be required *
* to restart safeguards equipment.
* o Overriding breaker anti-pump/lockout may require placing control
* switches to TRIP or may require Containment Spray Reset
* o FRPs should NOT be implemented prior to completion of 2-E-O, REACTOR
* TRIP OR SAFETY INJECTION, ATTACHMENT 1, AUTOMATIC ACTION VERIFICATION.
o Placing key switches to DEFEAT will prevent auto SI actuation.
: 1. Reset SI:
: a. Check all CCW pumps  -  RUNNING    a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1 o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2) o Train A o Train B
: e. Verify Train A AND B  -  RESET      e. Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o SIA-I o SIM-1 o SIA-2 o SIM-2 2 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 2. Reset Containment Isolation Phase A And Phase B:
: a. Place IVSW switches to OPEN on SN panel:
o 1410 o 1413 o SOV-3518 o SOV-3519
: b. Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: c. Verify personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: d. Place control switches for all remaining Phase A isolation valves to CLOSE on SN panel
: e. One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B
: f. Verify Train A AND B  RESET      f. IF signal does NOT reset, THEN:
: 1) Place key switches to BYPASS.
: 2) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset, THEN reset relays CA1 AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
This Step continued on the next page.
3 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSE          IRESPONSE NOT OBTAINED...
: g. Check Phase B - ACTUATED          g. Go To Step 3.
: h. Containment pressure - LESS        h. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig. THEN do Steps 2i. 2j and 2k.
: 2)  Continue with Step 3.
: i. One At A Time, Depress Containment Spray Reset Pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: j. One at a time, depress Phase B reset buttons:
o CI Phase B Train A o CI Phase B Train B
: k. Verify Train A AND B - RESET      k. Verify Relays reset (Top of Safeguards Initiation Racks 1-2 AND 2-2):
o  S1 o  S2 o  CB1 o  CB2
: 3. Establish Instrument Air To Containment:
: a. Open PCV-1228                    a. Verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAI o CA2 4 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY  INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. STOP SI PumDs AND PLACE In AUTO:
: a. STOP SI pumps AND PLACE in AUTO
: b. RHR pumps - ANY RUNNING WITH      b. GO To Step 5.
SUCTION ALIGNED TO RWST
: c. STOP RHR pumps AND PLACE in AUTO 5 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
  ..*.** N....X.*..*....
                .....                CAUTION PONO.  **OfO.T. ... .
* Radiation levels and harsh environment conditions should be evaluated          *
* prior to performing local actions.
* ft NOTE ATTACHMENT 1 provides a list  of 480V equipment load ratings.
: 5. Check If Charging Flow Has Been Established:
: a. Charging pumps  - AT LEAST ONE      a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
o  MOV-250A,  MCC 26AA. A2 o  MOV-250C. MCC 26AA,  B2 o  MOV-250B,  MCC 26BB,  13 o  MOV-250D,  MCC 26BB,  M3 OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
o  241A o  241B o  241C o  241D
: 2) Start charging pump(s)      as necessary.
: b. Establish charging flow as necessary:
: 1) Verify speed controller in MANUAL
: 2)  Adjust charging pump speed 6 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP      ACTION/EXPECTED RESPONSEl                RESPONSE NOT OBTAINEDl
: 6. Verify SI System Flow Not Required:
: a. RCS subcooling based on core        a. Manually start SI system pumps exit TCs - GREATER THAN VALUE            as necessary. Go to 2-E-1, OBTAINED FROM TABLE:                      LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0  -  400          52 (83) 401  -  800          36 (49) 801  -  1200          23 (30) 1201  -  2500          19 (26)
: b. PRZR level - GREATER THAN 14%        b. Control charging flow to (33% FOR ADVERSE CONTAINMENT)            maintain PRZR level. IF PRZR level can NOT be maintained, THEN manually start SI system pumps as necessary. Go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
7 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
( 7. Check If Containment Spray Should Be Stopped:
: a. Spray pumps - RUNNING            a. Go to Step 8.
: b. Containment pressure - LESS      b. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig. THEN do Steps 7c through 7f.
: 2) Continue with Step 8.
: c. One at a time, depress containment spray reset pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: d. Containment area radiation  -    d. Perform the following:
NORMAL
: 1) WHEN containment spray has o R-25. R-26                            been in service for 3.5 hours, THEN do Steps 7e o R-41. R-42                            and 7f.
o R-2,  R-7                          2) Go to Step 8.
: e. Stop containment spray pumps and place in AUTO
: f. Close containment spray pump discharge valves:
o  MOV-866A o  MOV-866B o  MOV-866C o  MOV-866D 8 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 8. Verify All Control Rods Fully Inserted:
: a. Check IRPI Indicators -          a. Implement 2-SOP-3.2. REACTOR ENERGIZED                            COOLANT SYSTEM BORON CONCENTRATION CONTROL.
: b. Check IRPI Indicators - ALL      b. Check all rod positions LESS RODS LESS THAN 7.5 INCHES            THAN 12 STEPS using PICS.
Refer to ATTACHMENT 2.
: 1) IF 2 OR more rod positions are greater than 12 steps withdrawn OR can, NOT be determined. THEN emergency borate 255 PPM/Rod not fully inserted:
a)  Open emergency boration I
valve:
o MOV-333 b) Place both boric acid pumps in high speed mode.
c)  Place charging pump control(s) in MAN.
d)  Establish a minimum charging flow of 75 GPM.
9 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA: ,
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
a.CPRRIfee Le    GREATwERe THAN8
: 9. Check If Letdown CanBe Established:
: a. PRZR level -GREATER THAN 28%        a. Continue with Step 10. WHEN (47% FOR ADVERSE CONTAINMENT)          level increases to greater than 28% (47% for ADVERSE CONTAINMENT), THEN do Steps 9b through 9d.
: b. CCW pumps  - ANY RUNNING            b. Perform the following:
: 1) Check for adequate power to run one CCW pump:
o Any 480V bus supplying CCW pump energized from offsite power.
OR -
o Load on any running diesel generator less than 1775 KW.
IF NOT,  THEN go to Step 10.
: 2)  Start one CCW pump.
IF no CCW pump can be started, THEN go to Step 10.
This Step continued on the next page.
10 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY  INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STP    ACTION/EXPECTED RESPONSE              IRESPONSE NOT OBTAINED
: c. Service water pumps - ANY          c. Perform the following:
RUNNING ON NON-ESSENTIAL HEADER
: 1) Check for adequate power to run one service water pump on non-essential header:
o Any 480V bus energized from offsite power.
                                                              - OR -
o Load on any running diesel generator less than 1725 KW.
IF NOT,  THE___NN go to Step 9d.
: 2)  Start one service water pump on non-essential header.
: d. Establish letdown:                d. Establish excess letdown:
: 1) Close letdown orifice stops:        1) Establish CCW flow through excess letdown heat o 200A                                  exchanger by opening CCW o 200B                                  valves:
o 200C o Inlet valves 791,798
: 2) Open letdown line isolation              o Outlet valves 793,796 valves 201 and 202
: 2) Position excess letdown
: 3)  Place letdown flow control              diversion valve 215 to valves 200 A B C switch to              NORMAL to direct flow to REMOTE                                  the VCT.
: 4) Open letdown stop valve              3) Verify seal water return LCV 459 and return to AUTO              containment isolation valve 222 open.
: 5)  Place low pressure letdown backpressure controller            4)  Verify excess letdown flow PCV-135 in MANUAL and                  control valve HCV-123 adjust to 75 percent open              closed.
: 6) Open letdown orifice stops          5) Open excess letdown to establish desired flow:              isolation stop valve 213.
o 200A,  75 gpm                    6) Slowly open HCV-123 to o 200B,  45 gpm                        warmup the excess letdown o 200C. 75 gpm                        heat exchanger.
: 7) Set PCV-135 to maintain              7)  Establish desired excess pressure between 225 psig              letdown flow using HCV-123.
and 275 psig
: 8) Maintain excess letdown
: 8) Place PCV-135 in AUTO                    heat exchanger outlet temperature less than 195 0 F.
11 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
[ 2-ES-1.1 Number:
STEP
 
==Title:==
ACTION/EXPECTED RESPONSE SI TERMINATION RESPONSE NOT REV.
Revision 1
Number: 1
: 10. Check VCT Makeup Control System:        Adjust controls as necessary.
: a. Makeup set for greater than RCS boron concentration
: b. Place RCS makeup control switch to START
: 11. Check Charging Pump Suction.-            Align suction to VCT:
ALIGNED TO VCT
: a. Open charging pump suction valve from VCT and return to AUTO:
o LCV-112C
: b. Close charging pump suction valve from RWST and return to AUTO:
o LCV-112B
: 12. Transfer Condenser Steam Dump To        IF condenser NOT available, THEN Pressure Control Mode:                  use SG atmospheric steam dumps.
: a. Check condenser - AVAILABLE
: b. Place steam dump controller switch to manual and adjust for zero output.
: c. Transfer condenser steam dump to pressure control mode and adjust manual setpoint as necessary.
: 13. Check RCS Hot Lea TemDeratures -        Control steam dump and total'feed STABLE                                  flow as necessary to stabilize RCS temperature.
12 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
STE      ACTION/EXPECTED RESPONSEIRSOS                      NO!OT    INE
: 14. Check RCP Cooling - NORMAL:              IF all seal cooling has NOT been lost. THEN establish normal
: a. RCP CCW system alarms  -  CLEARED  cooling to RCPs. Refer to the following as necessary:
: b. RCP seal injection flow -
BETWEEN 6 GPM AND 10 GPM PER          o 2-SOP-1.3, REACTOR COOLANT PUMP RCP                                      STARTUP AND SHUTDOWN.
o 2-SOP-3.1, CHARGING, SEAL WATER. AND LETDOWN CONTROL.
: 15. Check If RCP Seal Return Flow Should Be Established:
: a. RCP thermal barrier AP    -          a. Go to Step 16.
POSITIVE
: b. CCW pump - AT LEAST ONE RUNNING      b. Go to Step 16.
: c. Establish seal return flow:
: 1) Check No. 1 seal return                1) Manually open valves.
valves - OPEN:
o 261A o 261B o 261C o 261D
: 2) Open seal return containment isolation valve:
o MOV-222 13 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION; IF CST level decreases to less than 2 ft. switch to city water supply.
: 16. Control PRZR Pressure:
: a. Maintain pressure stable using    a. IF normal spray NOT available PRZR heaters and normal PRZR          and letdown is in service, spray as necessary                    THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
14 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 17. Check Intact SG Levels:
: a. Narrow range level - GREATER      a. Maintain total feed flow THAN 10% (27% FOR ADVERSE            greater than 400 gpm until CONTAINMENT)                          narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain      b. IF narrow range level in any narrow range level between 10%        SG continues to increase, THEN (27% FOR ADVERSE CONTAINMENT)        stop feed flow to that SG.
and 50%
15 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
NOTE ATTACHMENT 1 provides a list  of 480V equipment load ratings.
: 18. Check Status Of 480V Busses:
: a. All 480V busses  - ENERGIZED BY    a. Try to restore  offsite power OFFSITE POWER                          to 480V busses  per 2-AOP-138KV-1,  LOSS OF POWER TO 6.9KV BUS 5  AND/OR 6.
IF necessary, THEN manually load the following equipment on the 480V busses:
o MCCs:
o MCC 24A o MCC 27A o MCC 29A o Direct Support Facilities personnel to align PAB LIGHTING TRANSFORMER 23, ALTERNATE POWER SUPPLY to TSC per 2-SOP-27.1.5, 480 VOLT SYSTEM, as necessary.
o Start one cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW, THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
o Locally start one 480V switchgear room exhaust fan.
o IF necessary,  defeat fan interlock using bypass key.
This Step continued on the next page.
16 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ACTION/EXPECTED RESPONSE            R
 
===RESPONSE===
ED NOT OBTAINED I        P Go to Step 19. OBSERVE CAUTION AND NOTE PRIOR TO STEP 19.
: b. Manually load the following equipment on the 480V busses:.
o All MCCs as necessary except MCC 28 and MCC 28A o All lighting as necessary o One cable tunnel exhaust fan o Verify radiation monitors R-43/R-44 in service and start PAB ventilation fans o Locally start one 480V switchgear room exhaust fan o IF necessary, defeat fan interlock using bypass key 17 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
CAUTION
* Q If RCP seal cooling had previously been lost, the affected RCP(s)                        should
* NOT be started prior to a status evaluation.
  *  *  *  * *  *  * * *
* ft * * * * * *  *  *  * *    *    * *  *  *
* a * *  * *
* a
* a a  * *
* NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
019.      Check RCP Status - 24 RCP RUNNING          Perform the following to provide normal PRZR spray:
: a.      IF RVLIS natural circulation range indication less than 100%. THEN perform the following:
o Increase PRZR level greater than 62% (81% FOR ADVERSE CONTAINMENT) o Increase RCS subcooling based on core exit TCs greater than value obtained from table:
WR RCS PRESSURE            RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400              74  (105) 401 - 800                58  (71) 801 - 1200              45  (52) 1201 - 2500              41  (48) o Use PRZR heaters, as necessary to saturate the pressurizer water.
This Step continued on the next page.
18 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: b. IF containment sump level less than 42'10 1/2" AND containment conditions NOT adverse, THEN:
: 1) Reset MCC 28 and MCC 28A.
: 2) Establish conditions for starting RCP(s) per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
: 3)  Start 24 RCP.
: 4) IF 24 RCP can NOT be started, THEN start RCP(s) as required to provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer to ATTACHMENT 3 to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam from intact SGs.
: 20. Check If Source Range Detectors Should Be Energized:
: a. Check intermediate range flux    a. Continue with Step 21. WHEN
      - LESS THAN 1E-10 AMPS                flux less than 1E-1O amps, THEN do Steps 20b and 20c.
: b. Verify source range detectors    b. Manually energize source range
      - ENERGIZED                          detectors.
: c. Transfer nuclear recorders to source range scale 19 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 21. Check If Diesel Generators Should Be Stopped:
: a. Verify 480V busses - ENERGIZED      a. Try to restore offsite power BY OFFSITE POWER                        to 480V busses per 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
: b. Locally stop any unloaded diesel generator(s) and place in standby
: 22. Shut Down Unnecessary Plant Equipment And Reset Ventilation:
o Verify secondary plant automatic actions:
o Heater drain pumps - TRIPPED o 22 condensate pump - TRIPPED o Main and UAT transformer cooling equipment - SHUTDOWN o Reheater steam supply valves
            - CLOSED o Extraction steam valves  -
CLOSED o MBFP turbine reheat steam supply non-return valve "A" valves  - CLOSED o Circulating water pumps not required o Service water pumps not required oEvaluate secondary plant status and shut down equipment as required o Place main turbine and MBFP turbines on turning gear after shafts stop This Step continued on the next page.
20 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
o Reset FCU services and CCR ventilation as necessary:
: a. Place the following control switches in the position indicated:
o FCU service water valve TCV-1104 - OPEN o FCU service water valve TCV-1105 - OPEN o FCU NORM OUT valves  -  OPEN o At CCR Panel PY2:
: 1) Place mode selector switch to 2
: 2)  Place the follow switches to CUTOUT:
o Unit-1 K-8 fan switch (0T2-3) o 0T2-1 o OT2-2
: b. Depress both reset buttons in racks E-7 and F-8 for each of the following:
o FCU service water o FCU ventilation o CCR ventilation
: 23. Maintain Plant Conditions  -
STABLE:
o PRZR pressure
* o PRZR level o RCS temperatures o Intact SG levels 21 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination.
manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 24. Verify SI System Flow NOT Required:
: a. RCS subcooling based on core        a. Manually start SI system pumps exit TCs - GREATER THAN VALUE          as necessary. Go to 2-E-1, OBTAINED FROM TABLE:                    LOSS OF REACTOR OR SECONDARY COOLANT. Step 1.
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0  -  400          52 (83) 401  -  800          36 (49) 801  -  1200        23 (30) 1201  -  2500        19 (26)
: b. PRZR level - GREATER THAN 14%        b. Control charging flow to (33% FOR ADVERSE CONTAINMENT)          maintain PRZR level. IF PRZR level can NOT be maintained, THEN manually start SI system pumps as necessary. Go to 2-E-1. LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
: 25. Go To 2-POP-3.2 PLANT RECOVERY FROM TRIP. HOT STANDBY
                                      - END-22 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination.
manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
ATTACHMENT 1                (Attachment page 1 of 1) 480V FOIJiPMENT LOAD RATINGS
: 1. Use the following table to determi ne 480V eauinment load ratinas:
U G1 21              22 DG            23 DG EQUIPMENT          BUS 5A      BUS 2A    BUS 3A    BUS 6A 21 SERVICE WATER PUMP      282 KW 22 SERVICE WATER PUMP                  282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP      282 KW 25 SERVICE WATER PUMP                  282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                      485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                        384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT          250 KW 22 FAN COOLER UNIT          250 KW 23 FAN COOLER UNIT                      250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                            250 KW 21 SI PUMP                  316 KW 22 SI PUMP                              316 KW    316 KW 23 SI PUMP                                                    345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP                                                350 KW 21 RHR PUMP                                        303 KW 22 RHR PUMP                                                  303 KW 21 CHARGING PUMP            150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                            150 KW 21 RECIRC PUMP              299 KW 22 RECIRC PUMP                                              299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW 23 CCW PUMP                                                  228 KW 21 LIGHTING TRANS FORMER                150 KW (N)          150 KW (E) 22 LIGHTING TRANS FORMER                          225 KW 23 LIGHTING TRANS 5FORMER  225 KW TURBINE AUX OIL F'UMP                                        112 KW STATION AIR COMPR RESSOR    93 KW
                                    -END-23 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATAHET                    Atchetpge1o.1 ATTACHMENT 2            (Attachment page 1 of.l)
OBTAINING PICS ROD POSITION INDICATION
: 1. Obtain PICS Rod Position Indication by the following method:
o Obtain PICS Rod Indication from any screen:
a)  Depress CANC on screen using mouse or depress Esc key on keyboard b)  Depress NSSS and BOP on screen using mouse c)  Depress ROD SUPERVISION on screen using mouse d)  Depress ALL ROD view or INDIVIDUAL BANK on screen using mouse e)  Check all rods less than 12 steps withdrawn
                                    -END-24 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 3              (Attachment page 1 of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The following conditions support or indicate natural circulation flow:
o RCS subcooling based on core exit TCs - GREATER THAN VALUE
    . OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400              52 (83) 401  -  800,            36 (49) 801  - 1200            23 (30) 1201  -  2500            19 (26) o SG pressures - STABLE or DECREASING o RCS hot leg temperatures - STABLE OR DECREASING o Core exit TCs - STABLE OR DECREASING o RCS cold leg temperatures    -  AT SATURATION TEMPERATURE FOR SG PRESSURE
                                      -END-25 of 25
 
FOLDOUT PAGE FOR 2-ES-1.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs following SI termination, manually start SI system pumps as necessary AND go to 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Procedure Use Is: Control Copy:
Entergy                  0 Continuous Nuclear Northeast        O3 Reference      Effective Date: 6 1(161 o3 Information 2-ES-1.2, Revision: 0 POST LOCA COOLDOQYJŽALD DEPRESSURIZATION Approved By:
Procedure'ponsor, RPO/ I Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number:
2-ES-1.2              POST LOCA COOLDOWN AND DEPRESSURIZATION                REV. 0 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. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 17, when RCS pressure is greater than the shutoff head pressure of the RHR pumps.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
OR  -
o Containment pressure greater than 4 psig.
1 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS, pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
[Number:
2 -ES-1.2
 
==Title:==
Revision Number:
POST LOCA COOLDOWN AND DEPRESSURIZATION                    REV. 0
: 1.      Check Status Of 480V Busses:
: a. All 480V busses  - ENERGIZED BY    a. Try to restore  offsite power OFFSITE POWER                          to 480V busses  per 2-AOP-138KV-1,  LOSS OF POWER TO 6.9KV BUS 5  AND/OR 6.
IF necessary,  THEN perform the following:
: 1) Manually load the following equipment on the 480V busses:
o MCCs:
o MCC 24A o MCC 27A o MCC 29A o Direct Support Facilities personnel to align lighting to PAB LIGHTING TRANSFORMER 23 ALTERNATE POWER SUPPLY to TSC bus per 2-SOP-27.1.5, 480 VOLT SYSTEM, as necessary.
o Start one cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW, THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
    .This Step continued on the next page.
2 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
o PRZR level - CANNOT BE-MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800  ) 801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30). 19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-l.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number: I 2-ES-r.2                POST LOCA COOLDOWN AND DEPRESSURIZATION                  REV. 0 fACTION/EXPECTED RESPONSE1"              FIRESPONSE NOT OBTAINE o Locally start one 480V switchgear room exhaust fan.
o IF necessary, defeat fan interlock using bypass key.
: 2) Verify adequate diesel capacity to run charging pumps. Il necessary, shed sufficient non-essential loads.
Go to Step 2.
: b. Manually load the following equipment on the 480V busses:
o All MCCs as necessary except MCC 28 and MCC 28A o All lighting as necessary o One cable tunnel exhaust fan o Verify radiation monitors R-43/R-44 in service and start PAB ventilation fans o Locally start one 480V switchgear room exhaust fan o IF necessary, defeat fan interlock using bypass key
: 2. Deenergize PRZR Heaters:
: a. Place all PRZR heater switches in OFF position 3 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1.      S1 TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs  -  GREATER THAN 190 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)      52 (83)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go'to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ACTION/EXPECTED RESPOS                RES.PONSE NOT OBTAINED
            *                          ~CAUTION*
RCS pressure should be monitored. If RCS pressure decreases in an    *
* uncontrolled manner to less than 320 psig (340 psig FOR ADVERSE          *
* CONTAINMENT), the RHR pumps must be manually restarted to supply water to *
* the RCS.                                                                  *
: 3. Check If RHR Pumns Should Be Stopped:
: a. RHR pumps    ANY RUNNING WITH      a. Go to Step 4.
SUCTION ALIGNED TO RWST
: b. Check RCS pressure:                b. Go to Step 4.
: 1) Pressure - GREATER THAN 320 PSIG (340 PSIG FOR ADVERSE CONTAINMENT)
: 2)  Pressure - STABLE OR INCREASING
: c. Stop RHR pumps and place in AUTO 4 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (26°F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
2-ES-1.2                        POST LOCA COOLDOWN AND DEPRESSURIZATION                          REV. 0 Number:
 
==Title:==
Revision Number:
CAUTION
* o If RWST level decreases to less than 15 ft, charging pumps that are
* started or running should be monitored for loss of suction which may
* result in pump damage.
* o Radiation levels and harsh environment conditions should be evaluated
* prior to performing local actions.                                                                *r t
        *  .  *    . *
* i * * * * * * *  * * * * *  * * *  * *  *  *  *  * 'k  * *  *  *  *  *  *  * *  * *
: 4.      Establish Chargiing Flow:
: a. Charging pumps        AT LEAST ONE      a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
o  MOV-250A,  MCC  26AA,    A2 o  MOV-250C,  MCC  26AA,    B2 o  MOV-250B. MCC  26BB,    L3 o  MOV-250D,  MCC  26BB,    M3
                                                                                - OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
o  241A o  241B o  241C o  241D
: 2)  Start charging pump(s)          as necessary.
This Step continued on the next page.
5 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level -  GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)      52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-I.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft,      switch to city water supply.
 
2-ES-1.2                POST LOCA COOLDOWN AND DEPRESSURIZATION                REV. 0 Number:          Title-                                                      Revision Number: 1
: b. Align charging pump suction to RWST:
: 1) Open charging pump suction valve from RWST:
o LCV-112B
: 2)  Close charging pump suction valve from VCT:
o LCV-112C
: 3) Place RCS Makeup Control switch to STOP
: c. Establish maximum flow:
: 1) Start additional charging pump(s)
: 2) Verify speed controllers in MANUAL
: 3) Open HCV-142 as necessary and adjust charging pump speed controllers for maximum flow
: 5. Check Intact SG Levels:
: a. Narrow range level - GREATER        a. Maintain total feed flow THAN 10% (27% FOR ADVERSE              greater than 400 gpm until CONTAINMENT)                            narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain        b. IF narrow range level in any narrow range level between 10%          SG continues to increase in an (27% FOR ADVERSE CONTAINMENT) and 50%
uncontrolled manner, THE._N stop RCS cooldown AND go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
I 6 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE    - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING    OF  (ADVERSE)  52 (83)  36 (49)      23 (30). 19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
STP        ACTION/EXPECTED RESPONSEi                  RESPONSE NOT OBTAINEDI
: 6. Initiate RCS Cooldown To Cold Shutdown:
: a. 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. Dump steam using intact SG(s) intact SG(s):                            atmospheric steam dumps.
: 1) Check condenser - AVAILABLE
: 2)  Place steam dump controller switch to manual and adjust for zero output.
: 3) Transfer condenser steam dump to pressure control mode and adjust manual setpoint as necessary.
: 7. Check RCS Subcoolinq Based On              Go to Step 16.
Core Exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400            52  (83) 401    - 800            36  (49) 801    - 1200            23  (30) 1201    - 2500            19  (26) 7 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1,      SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2.      SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400  401-800      801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step I.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
[
Number:
2-ES-1.2        jPOST.LOCA    PTitle:  COOLDOWN AND DEPRESSURIZATION                Revision REV.Number:
0 STP            ACTION/EXPECTED RESPONSEI                  RESPONSE NOT OBTAINED]
: 8.      Check SI System Pump Status:                Go to Step 12.
o SI pumps    -  ANY RUNNING
                          -  OR -
o RHR pumps    -  ANY RUNNING IN SI MODE NOTE The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.
: 9. Depressurize RCS To Refill      PRZR:
: a. Use normal PRZR spray                  a. Use one PRZR PORV. IF no PORV available, THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control  valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A  -  Loop 22 o 204B  -  Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B This Step continued on the next page.
8 of 24 page.
on the next This Step continued
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2.      SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    -    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE    - PSIG            0-400    401-800      801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)      52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
: b. PRZR level - GREATER THAN 28%      b. Continue with Step 10.
(47% FOR ADVERSE CONTAINMENT)        OBSERVE CAUTION AND NOTE PRIOR TO STEP 10. WHEN level greater than 28% (47% FOR ADVERSE CONTAINMENT), THEN do Step 9c.
: c. Stop RCS depressurization CAUTION
"    If RCP seal cooling had previously been lost, the affected RCP(s)    should
"    NOT be started prior to a status evaluation.
NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
: 10. Check If An RCP Should Be Started:
This Step continued on the next page.
9 of 24
 
FOLDOUT PAGE FOR 2-ES-I.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-l.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS, pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  -  GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)      52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
SNumber:
 
==Title:==
Revision Number:
S2-ES-I.2                      POST LOCA COOLDOWN AND DEPRESSURIZATION                    REV. 0 STP        ACTION/EXPECTED RESPONSEI                  RESPONSE NOT OBTAINEDI
: a. All RCPs    -  STOPPED                a. Perform the following:
: 1) Stop all but 24 RCP.
: 2)  IF 24 RCP already stopped, THEN ONLY stop RCP(s) NOT required to provide PRZR spray.
: 3) Go to Step 11. OBSERVE NOTE PRIOR TO Step 11.
: b. RCS subcooling based on core            b. Go to Step 16.
exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE          RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  -  400              52 (83) 401  -  800              36 (49) 801  -  1200            23 (30) 1201  -  2500            19 (26)
: c. PRZR level -GREATER THAN 28%            c. Return to Step 9. OBSERVE (47% FOR ADVERSE CONTAINMENT)                NOTE PRIOR TO STEP 9.
: d. Try to start 24 RCP:                    d. IF 24 RCP can NOT be started, THEN start RCP(s) as required
: 1) Check containment                        to provide PRZR spray flow AND conditions - NOT ADVERSE                go6 to Step 11. OBSERVE NOTE
: 2)  Check containment sump                  PRIOR TO STEP 11.
level  -  LESS THAN 42'10 1/2"
: 3)  Reset MCC 28 and MCC 28A
: 4)  Establish conditions for starting RCP(s) per 2-SOP-1.3, REACTOR COOLANT 5)
PUMP OPERATION Start 24 RCP IJ 10 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs      -  GREATER THAN 190 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400    401-800      801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)    I
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
F 2-ES-1.2 Number STP
 
==Title:==
POST LOCA COOLDOWN AND DEPRESSURIZATION ACTION/EXPECTED RESPONSE                  RESPONSE NOT OTIE REV. 0 Revision Number: 1 NOTE After stopping any SI pump, RCS pressure should be allowed to stabilize or increase before stopping another SI pump.
: 11. Check If One SI PumD Should Be Stopped:
: a. Any SI pump - RUNNING                  a. IF RHR pump running in SI mode, THEN go to Step 16,      IF NOT, THENN go to Step 12.
: b. Determine required RCS subcooling from table:
RCS SUBCOOLING OF (ADVERSE CONTAINMENT°F)
ANY RCP RUNNING                    NO RCP RUNNING CHARGING      ONE SI      TWO SI    THREE SI      ONE SI      TWO SI    THREE SI PUMP          PUMP        PUMPS      PUMPS        PUMP        PUMPS      PUMPS STATUS        RUNNING    RUNNING    RUNNING      RUNNING    RUNNING    RUNNING NONE          DO NOT        127        61        DO NOT        138        69 RUNNING      STOP SI      (146)      (81)        STOP SI      (154)      (85)
PUMP                                PUMP ONE              274        119        59            274        130        68 RUNNING        (286)        (137)      (76)          (286)      (146)      (83)
TWO              247        111        58          250        122        66 RUNNING        (261)      (129)      (74)          (264)      (137)      (82)
THREE            209        105        57          219        115        64 RUNNING        (228)      (123)      (73)          (235)      (131)      (80)
This Step continued on the next page.
11 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs      - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS, pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  -  GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 52 (83)    36 (49)      23 (30)    19 (26)
RCS SUBCOOLING OF (ADVERSE)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-I.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number: 1 2-ES-1.2                POST LOCA COOLDOWN AND DEPRESSURIZATION                    REV. 0 STP    ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
: c. RCS subcooling based on core      c. IF RCS hot leg temperatures exit TCs - GREATER THAN                greater than 345 0 F (335 0 F FOR REQUIRED SUBCOOLING                    ADVERSE CONTAINMENT), THEN go to Step 16.
IF RCS hot leg temperatures less than 345 0 F (335 0 F FOR ADVERSE CONTAINMENT). THEN start one RHR pump if none running. IF_at least one RHR pump can NOT be started, THEN go to Step 16.
: d. PRZR level - GREATER THAN 28%      d. Return to Step 9. OBSERVE (47% FOR ADVERSE CONTAINMENT)          NOTE PRIOR TO STEP 9.
: e. Stop one additional SI pump
: f. Return to Step 11a
: 12. Check If Charging Flow Should Be Controlled To Maintain PRZR Level :
: a. Check RHR pumps  - NONE RUNNING    a. Go to Step 16.
IN SI MODE
: b. Control charging flow to maintain PRZR level 12 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA; IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 190 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3'TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:                  Title.                                                                                                            Revision Number:
2-ES-1.2                                POST LOCA COOLDOWN AND DEPRESSURIZATION                                                                REV.      0
        .  .    .  .  .  .  . .    .  . .    *.  *.    *. *.  *..  *  *  *
* 4 CAUTION t
        *r If RCP seal cooling had previously been lost, the affected RCP(s)                                                                should              dr
        *r NOT be started prior to a status evaluation.
        *r r  *r  r    * *,    * *  *r  r *  *r    r    *r  r    *  *r *1  *  *r  *  *  *    *,  *    *    *  *r  * *  *r  *  * *r  *  *  *r *      *  *t
* NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
: 13.            Check RCP Status:
: a. 24 RCP - RUNNING                                                  a. Start RCP(s) to provide normal PRZR spray as follows:
: 1) IF RVLIS natural circulation range indication less than 100%.
THEN perform the following:
o Increase PRZR level to greater than 62% (81% FOR ADVERSE CONTAINMENT).
o Increase RCS subcooling based on core exit TCs to greater than value obtained from table:
WR RCS PRESSURE                      RCS SUBCOOLING OF (PSIG)                (ADVERSE CONTAINMENT) 0    -    400                    74    (105) 401    -    800                    58    (71) 801    -    1200                  45    (52) 1201      -    2500                  41    (48)
This Step continued on the next page.
13 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. Si TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS, pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start S] system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
NumberP                        CTtle:                                      Revision Number:
2-ES-I.2              POST LOCA COOLDOWN AND DEPRESSURIZATION                REV. 0 o Use PRZR heaters, as necessary to saturate the pressurizer water.
: 2) IF containment sump level less than 42'10 1/2" AND containment conditions NOT adverse, THEN:
a)  Reset MCC 28 and MCC 28A.
b)  Establish conditions for starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
c)  Start 24 RCP.
d)  IF 24 RCP can NOT be started, THEN start RCP(s) as required to provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer to ATTACHMENT 2 to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam.
: b. Stop all RCP(s) NOT required to supply ONE PRZR spray path 14 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur, go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs  -  GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start ST system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)      52 (83)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
CAUTION                                              tl Ill
* If SI has been terminated, the SI accumulators should be isolated prior
* to depressurizing the RCS to less than 700 psig.                                          It lit NOTE The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.
: 14.        DeDressurize RCS To Minimize RCS Subcooling:
: a. Use normal PRZR spray              a. Use one PRZR PORV.      IF no PORV available, THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2)  Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4)  Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5)  Close the pressurizer spray valves:
o PCV-455A o PCV-455B This Step continued on the next page.
15 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA; IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-ES-1.2                  POST LOCA COOLDOWN AND DEPRESSURIZATION                    REV. 0 STP        ACTION/EXPECTED RESPONSE                    RESPONSE NOT OBTAIE
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
: b. Turn on PRZR heaters as necessary
: c. Depressurize RCS until either of the following conditions satisfied:
o PRZR level - GREATER THAN 71% (65% FOR ADVERSE CONTAINMENT)
                            -  OR -
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400            62 (93) 401  - 800            46 (59) 801  - 1200            33 (40) 1201  - 2500            29 (36)
: 15. Verify Adequate Shutdown Margin:
: a. Sample RCS
: b. Shutdown margin from graphs            b. Borate as necessary.
book - ADEQUATE 16 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-l.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. S1 REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE., Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:          ITitle:                                                          Revision Number:
2-ES-1.2                    POST LOCA COOLDOWN AND DEPRESSURIZATION                  REV. 0
: 16. Verify SI System Flow Not Required:
: a. RCS subcooling based on core          a. Manually start SI system pumps exit TCs - GREATER THAN VALUE            as necessary. Go to Step 17.
OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENI 0  -  400            52 (83) 401  -  800          36  (49) 801  -  1200          23  (30) 1201  -  2500          19 (26)
: b. PRZR level    GREATER THAN 14%      b. Manually start SI system pumps (33% FOR ADVERSE CONTAINMENT)          as necessary. Return to Step 9. OBSERVE NOTE PRIOR TO STEP 9.
: 17. Check If SI Accumulators Should Be Isolated:
: a. RCS subcooling based on core        a. IF at least two RCS hot leg exit TCs - GREATER THAN VALUE          temperatures less than 350 0 F.
OBTAINED FROM TABLE:                    THEN go to Step 17c. IF NOT, THEN go to Step 18.
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENI 0 - 400              52 (83) 401 - 800              36 (49) 801 - 1200              23 (30) 1201 - 2500              19 (26)
: b. PRZR level - GREATER THAN 14%        b. Return to Step 9. OBSERVE (33% FOR ADVERSE CONTAINMENT)          NOTE PRIOR TO STEP 9.
This Step continued on the next page.
17 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED-GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2.
FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
HT IH.ACTIoNEXPECTE0 REPOSI                  RSPO NSE  NOT  OBTAINEDI
: c. Locally restore power to isolation valves:
o 894A  (MCC 26A) o 894C  (MCC 26A) o 894B  (MCC 26B) o 894D  (MCC 26B)
: d. Close all SI accumulator        d. Vent any unisolated isolation valves                    accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN' consult the TSC to determine contingency actions.
: e. Open all SI accumulator isolation valve breakers 18 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs    GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 18. Check If Diesel Generators Should Be Stopped:
: a. Verify 480V busses - ENERGIZED      a. Try to restore offsite power BY OFFSITE POWER                        to 480V busses per 2-AOP-138KV-1,  LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
: b. Locally stop any unloaded diesel generator(s) and place in standby
: 19. Check RCP Cooling  - NORMAL:          _IFall seal cooling has NOT been lost, THEN establish normal
: a. RCP CCW system alarms - CLEARED    cooling to RCPs. Refer to the following as necessary:
: b. RCP seal injection flow -
BETWEEN 6 GPM AND 10 GPM PER        o 2-SOP-1.3, REACTOR COOLANT PUMP RCP                                    STARTUP AND SHUTDOWN.
o 2-SOP-3.1, CHARGING, SEAL WATER, AND LETDOWN CONTROL.
: 20. Check If RCP Seal Return Flow Should Be Established:
: a. RCP thermal barrier AP -            a. Go to Step 21.
POSITIVE
: b. CCW pumps  - AT LEAST ONE
: b. Go to Step 21.
RUNNING
: c. Establish seal return flow:
: 1) Check No. 1 seal  return            1) Manually open valves.
valves - OPEN:
o 261A o 261B o 261C o 261D
: 2)  Open seal return containment isolation valve:
o MOV-222 19 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (269F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs    GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, T.RANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 21. Check If  RCPs Must Be Stopped:
: a. Check the following:              a. IF neither condition satisfied, THEN go to Step 22.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                  - OR -
o Number 1 seal return flow -
LESS THAN 0.2 GPM
: b. Stop affected RCP(s)
: 22. Check If Source Range Detectors Should Be Energized:
: a. Check intermediate range flux      a. Continue with Step 23. WHEN
        - LESS THAN 1E-10 AMPS                flux less than IE-10 amps, THEN do Steps 22b and 22c.
: b. Verify source range detectors      b. Manually energize source range
        - ENERGIZED detectors.
: c. Transfer nuclear recorders to source range scale 23, Shut Down Unnecessary Plant Equipment:
o Circulating water pumps not required o Service water pumps not required o Evaluate secondary plant status and shut down equipment as required 20 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19 0 F (26°F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)    23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step I.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
 
Number:
 
==Title:==
Revision Number:
2-ES-1.2                POST LOCA COOLDOWN AND DEPRESSURIZATION                    REV. 0 NOTE 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,        should be referred to for plant alignment during cooldown.
: 24. Check If RHR System Can Be Placed In Service:
: a. Check both the following:              a. Go to Step 25.
o RCS temperatures    -  LESS THAN 3500 F o RCS pressure - LESS THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Consult TSC to determine if RHR System should be placed in service
: 25. Check Containment Hydrogen Concentration:
: a. Obtain a hydrogen concentration measurement:
o Dispatch chemistry personnel to obtain sample
                        -  OR -
o Use H2-02 analyzer on Accident Assessment Panel
: b. Hydrogen concentration      - LESS      b. Consult TSC for additional THAN 3.0% IN DRY AIR                      recovery actions.
: 26. Check RCS Temperatures    -  LESS        Return to Step 3. OBSERVE THAN 2000F                                CAUTION PRIOR TO STEP 3.
21 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,    SI TERMINATION:
: a. RCS subcooling based on core exit TCs    -  GREATER THAN 19°F (26°F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs    GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    -    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800      801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION. Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 27. Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions per 2-POP-3.3, PLANT COOLDOWN    HOT TO COLD SHUTDOWN
: b. Consult TSC
                                  -END-22 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1. SI TERMINATION:
: a. RCS subcooling based on core exit TCs    - GREATER THAN 19 0 F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                            -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,    manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 1                (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the followinq table to determine 480V eauiDment load ratinas:
21 DG          22 DG            23 DG EQUIPMENT          BUS 5A      BUS 2A      BUS 3A    BUS 6A 21 SERVICE WATER PUMP    282 KW.
22 SERVICE WATER PUMP                282 KW OR 282 KW 23 SERVICE WATER PUMP                                      282 KW 24 SERVICE WATER PUMP    282 KW 25 SERVICE WATER PUMP                282 KW OR 282 KW 26 SERVICE WATER PUMP                                      282 KW PRZR CONTROL HEATERS                                      277 KW 21 PRZR BU HEATERS                              554 KW 22 PRZR BU HEATERS                  485 KW 23 PRZR BU HEATERS      485 KW 21 AFW PUMP                                      384 KW 23 AFW PUMP                                                384 KW 21 FAN COOLER UNIT      250 KW 22 FAN COOLER UNIT      250 KW 23 FAN COOLER UNIT                    250 KW 24 FAN COOLER UNIT                              250 KW 25 FAN COOLER UNIT                                        250 KW 21 SI PUMP              316 KW 22 SI PUMP                            316 KW    316 KW 23 SI PUMP                                                345 KW 21 SPRAY PUMP            350 KW 22 SPRAY PUMP                                              350 KW 21 RHR PUMP                                      303 KW 22 RHR PUMP                                                303 KW 21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                150 KW 23 CHARGING PUMP                                          150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                            299 KW 21 CCW PUMP              228 KW 22 CCW PUMP                          228 KW 23 CCW PUMP                                                228 KW 21 LIGHTING TRANSFORMER              150 KW (N)          150 KW (E) 22 LIGHTING TRANSFORMER                          225 KW 23 LIGHTING TRANSFORMER  225 KW TURBINE AUX OIL PUMP                                      112 KW STATION AIR COMPRESSOR    93 KW
                                  -END-23 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1. SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,    go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs - GREATER THAN 19°F (260 F FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs -.,GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,      manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)      52 (83)  36 (49)      23 (30)    19 (26)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
ATTACHMENT 2                  (Attachment page 1 of 1)
NATURAL CIRCULATION VERIFICATION 1.. The following conditions support or indicate natural circulation flow:
o RCS subcooling based on core exit TCs          - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 -  400              52 (83) 401 -    800              36 (49) 801 -    1200              23 (30) 1201 -. 2500              19 (26) o SG pressures  -  STABLE OR DECREASING o RCS hot leg temperatures - STABLE OR DECREASING o Core exit TCs  -  STABLE OR DECREASING o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                      - END -
24 of 24
 
FOLDOUT PAGE FOR 2-ES-1.2
: 1.      SI TERMINATION CRITERIA:
IF ALL conditions listed below occur,  go to 2-ES-1.1,  SI TERMINATION:
: a. RCS subcooling based on core exit TCs  -  GREATER THAN 19 0 F (260 F.
FOR ADVERSE CONTAINMENT)
: b. Total feed flow to intact SGs - GREATER THAN 400 gpm
                              -OR-Narrow range level in at least one intact SG - GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure:
o STABLE OR INCREASING o GREATER THAN 1660 PSIG (1690 PSIG FOR ADVERSE CONTAINMENT)
: d. PRZR level  - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: 2. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs,  manually start SI system pumps as necessary:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 3. SECONDARY INTEGRITY CRITERIA:
IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step I.
: 4. E-3 TRANSITION CRITERIA:
IF any SG level increases in an uncontrolled manner or any SG has abnormal radiation, manually start SI system pumps as necessary and go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 5. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-I.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 6. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
 
Procedure Use Is: Control Copy:
NcEntergy                El Continuous Nuclear Northeast 0 Reference      Effective Date: i]--- o',
O3 Information 2-ES-1.3, Revision: 1 TRANSFER TO COJL-LEG RECIRCULATION Approved By:
Procedure Sponsor, RPO/ D Team P Procedure Owner PARTIAL REVISION
 
A. PURPOSE This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:
: 1) 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT,  Step 18, on low RWST level.
: 2)  2-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 8. on low RWST level.
: 3) Other procedures,  whenever RWST level  reaches the switchover setpoint.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                        -  OR -
o Containment pressure greater than 4 psig.
I of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. iF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-l.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE. Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
 
STP      ACTION/EXPECTED RESPONSE IIRESPONSE            NOT OBTAINED
* CAUTION o SI system recirculation flow to RCS must be maintained at all times.
* o If offsite power is lost after SI reset, manual    action may be required
* to restart safeguards equipment.
It o Overriding breaker anti-pump/lockout may require placing control switches to TRIP or may require Containment Spray Reset
* o Switchover to recirculation may cause high radiation in the PAB.
* o Placing key switches to DEFEAT will prevent auto SI actuation.
o Foldout page contains criteria for transition to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1 whenever ALL trains of recirculation are affected by sump blockage.
NOTE Steps 1 through 40 should be performed without delay.      FRPs should NOT be implemented prior to completion of these steps.
: 1. Determine If Transfer To Cold Leg      Perform the following:
Recirculation Is Required:
: a. IF VC level is GREATER THAN o Check BOTH RWST Low Low Level          46' 8 1/2" on LI-941, THEN GO alarms - LIT                          To Step 2.
o Containment Level - TRENDING        b. Go to 2-ECA-1.1, LOSS OF UPWARDS (LR-3300/LR-3301)              EMERGENCY COOLANT RECIRCULATION.
2 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due'to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
: 2. Reset SI if necessary:
: a. Check all CCW pumps  - RUNNING    a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-I o Train. B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2) o Train A o Train B
: e. Verify Train A AND B - RESET      e. Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o SIA-1 o SIM-1 o SIA-2 o SIM-2
: 3. Establish Service Water Flow To CCW Heat Exchanaers:
: a. Dispatch NPO to fully open CCW heat exchanger SW outlet valves:
o SWN-35 o SWN-35-1 3 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE. Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
STEPACTION/EXPECTED RESPONSE                  EPNS O OTIE
* CAUTION
* Any pumps taking suction from RWST should be stopped if      RWST level
* decreases to:
o 3.0 ft for SI,  RHR and charging pumps.
* o 2.0 ft for containment spray pumps.
: 4. Reduce 480V Bus Loads;
: a. Stop all charging pumps
: b. Turn off all  PRZR heaters
: 5. One At A Time, Depress Cnnt~inm~nt Snrav Rp~pt Pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: 6. Place Safety Injection Recirc Switches 1 AND 3 To ON:
: a. Check 22 SI pump - STOPPED          a. IF three SI pumps running, THEN stop 22 SI pump.
: b. Check 21 containment spray
: b. IF both pumps running, THEN pump - STOPPED                          place 21 containment spray pump in PULLOUT.
: c. Check RHR pumps  - BOTH STOPPED    c. Manually trip BOTH RHR pumps.
4 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3 LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
: 7. Align Service Water System As Follows:
: a. Check service water system -      a. Verify the following valves ALIGNED FOR THREE HEADER            are closed:
OPERATION o Service water valve pit:
o FCV-1111 o FCV-1112 o SWN-6 o SWN-7 o Zurn strainer pit:
o SWN-4 o SWN-5 Go to Step 8. OBSERVE NOTE PRIOR TP STEP 8.
: b. Verify following valves -
CLOSED:
o SWN-4 o SWN-5 5 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication 4
 
STP    ACTION/EXPECTED RESPONSEl            RESPONSE NOT OBTAINEDt
: 8. Place Safety Injection Recirc Switch 2 To ON:
: a. Check one service water pump -    a. Manually start one service SUPPLYING NON-ESSENTIAL HEADER        water pump on NON-essential header in preferred order:
o 22, 23, 21 if  1-2-3 header NON-essential
                                                          - OR -
o 25, 26, 24 if 4-5-6 header NON-essential
: b. Check CCW Pumps - THREE RUNNING  b. Verify at least one CCW pump running (preferred order 22, 21, 23)
Go to Step 8d.
: c. Stop 23 CCW pump
: d. Function complete light - LIT    d. Recheck required actions and manually initiate as necessary.
IF no CCW pumps can be started THEN, verify ACC pumps are running.
6 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-l.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
: 9. Place Safety Injection Recirc Switch 4 To ON
: a. Verify 21 recirculation pump      a. IF 21 pump can NOT be started, RUNNING                              THEN manually start 22 recirculation pump.
IF neither recirculation pump can be started, THEN:
: 1) Perform ATTACHMENT 2.
: 2) WHEN ATTACHMENT 2 is complete, THEN go to Step 11.
: b. Recirculation pump header          b. Verify at least one valve is discharge valves - OPEN              STROKING open.
o MOV-1802A                          IF valve is stroking open, o MOV-1802B                          THEN go to Step 11.
IF NOT,  THEN:
: 1) Perform ATTACHMENT 2.
: 2) WHEN ATTACHMENT 2 is complete, THEN go to Step 11.
: c. Function complete light - LIT    c. Recheck required actions and manually initiate as necessary.
7 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS .OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
STP    ACTION/EXPECTED RESPONSE !IiRESPONSE            NOT OBTAINEDI
: 01. Verify Recirculation Trains NOT        IF both trains are affected such Affected By Sump Blockage:              that at least one train of recirculation flow can not be
: a. Indications of sump blockage        established or maintained, THEN may include:                        go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION
: 1) LOW HEAD INJECTION LINE LOW      CAUSED BY SUMP BLOCKAGE, Step 1.
FLOW alarm on panel SBF-1
: 2) SI PUMP SUCTION LOW PRESSURE alarm on panel SBF-i
: 3)  Indication of erratic or reduced flow
: 4) Abnormal sump level indication 8 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY. COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d)  Abnormal sump level indication
: 11.      Determine If Adeauate Low Head Recircula ion Flow.Has Been Established:
: a. Determine required core cooling from table:
No. of 946A-D          Core flow rate                  Core flow rate flow meters                with                            with INDICATING  -    I Pump AND 1 RHR HX            2 Pumps AND/OR 2 RHR HXs 2nd Highest indicator -        2nd Highest indicator -
GREATER THAN 470 gpm          GREATER THAN 620 gpm OR                              OR 4          2 Middle indicators -          2 Middle indicators -
SUM GREATER THAN 780 gpm      SUM GREATER THAN 910 gpm OR                              OR 3 Lowest indicators -          3 Lowest indicators -
SUM GREATER THAN 1020 gpm      SUM GREATER THAN 1110 gpm 2nd Highest indicator -        2nd Highest indicator -
GREATER THAN 470 gpm          GREATER THAN 620 gpm 3                    OR                              OR 2 Lowest indicators -          2 Lowest indicators -
SUM GREATER THAN 780 gpm      SUM GREATER THAN 910 gpm 2          EACH GREATER THAN 470 gpm      EACH GREATER THAN 620 gpm I or None              Required core cooling - NOT MET
: b. Core cooling flow required by      b. IF valves 746 AND 747 BOTH table - ESTABLISHED                    CLOSED, THEN go to Step 25.
IF NOT,  THEN perform the following:
: 1) Start 22 recirc pump.
: 2)  IF core flow rate required by table can NOT be established, THEN:
a)  IF BOTH recirc pumps running, THEN stop 22 recirc pump.
b)  Go to Step 25.
9 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d)  Abnormal  sump level indication
 
[
Number:      ITitle:                                                      Revision Number:
2-ES-1.3                  TRANSFER TO COLD LEG RECIRCULATION                REV. I
: 12. Place Safety Injection Recirc Switch 7 To ON:
: a. Check SI pumps - ALL STOPPED      a. Manually stop pumps.
: b. Function complete light - LIT    b. Recheck required actions and manually initiate as necessary.
: 13. Place Safety InJection Recirc Switch 8 To ON:
: a. Check containment spray pump      a. Manually close valve.
test line valve - CLOSED:
o 1813
: 14. Close SI Test Line Valves To RWST:
: a. Place interlock switches for SI valves to OFF:
o MOV-842 o MOV-843
: b. Close valves:
o MOV-842 o MOV-843
: 15. Check Recirculation Pumps    AT      IF RHR pump is running for core LEAST ONE RUNNING                    recirculation, THEN:
: a. Dispatch NPO to energize the following MOVs:
o MOV-882 on MCC 26B o MOV-1810 on MCC 26A
: b. Go to Step 19.
: 16. Check All 480V Busses - ENERGIZED    Go to Step 18.
10 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can. NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON  LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication.of errratic or reduced flow d) Abnormal  sump level indication 4
 
[  2-ES-1.3 Number:
 
==Title:==
TRANSFER TO COLD LEG RECIRCULATION                        REV. 1 Revision Number:
STEP..... ACTION/EXPECTED RESPON''1S'E'              RSPONSE NOT OBTAINED1 CAUTION A second train of recirculation should NOT be started if          pump cavitation
* due to Sump Blockage is expected.
: 17. Place Safety InJection Recirc Switch 5 To ON:
: a. Check at least two service          a. Manually start one service water pumps - SUPPLYING                  water pump on NON-essential NON-ESSENTIAL HEADER                      header in preferred order:
o 22. 23, 21 if 1-2-3 header non-essential
                                                                      - OR  -
o 25, 26. 24 if 4-5-6 header non-essential IF second service water pump will NOT start, THEN perform the following:
: 1) IF both recirculation pumps running. THEN stop ONE recirculation pump.
: 2)  Close valve 804 to isolate spent fuel pit heat exchanger.
: b. Check CCW pumps - AT LEAST TWO      b. Manually start CCW pump as RUNNING                                  necessary (preferred order 22, 21, 23).
IF second CCW pump will NOT start AND BOTH recirc pumps are running, THEN stop ONE recirculation pump.
: c. Check recirculation pump -          c. IF at least 2 CCW pumps AND BOTH RUNNING                              at least 2 non-essential SW pumps are running, THEN start a second recirculation pump.
: d. Function complete light    - LIT    d. Recheck required actions and manually initiate as necessary.
11 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THENN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
: 18. Dispatch NPO To Perform The Following (on 98 ft. EL PAB):
: a. Energize AND close RHR miniflow test line valves:
o MOV-743 on MCC 26BB o MOV-1870 on MCC 26AA
: b. Energize the following MOVs:
o MOV-882 on MCC 26B o MOV-744 on MCC 26A o MOV-1810 on MCC 26A 019. Check CCW Pump Status:
: a. Three CCW pumps - RUNNING          a. Perform the following:
: 1) Verify at least two CCW pumps running.
: 2) Go to Step 20.
: b. Stop 23 CCW pump 12 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
jlNumber:
2-ES-1.3
 
==Title:==
TRANSFER TO COLD LEG RECIRCULATION                    REV. Number:
Revision  N STEP        ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED1 CAUTION
* IF Sump Blockage is a concern, THEN refilling the RWST should be
          " considered after ALL injection from RWST has stopped. TSC should be
          " consulted.
: 20. Check If Recirc Spray Is Reaui red:
: a. Containment spray pumps - ANY      a. Perform the following:
RUNNING
: 1) IF containment pressure EVER greater than 24 psig, THEN go to Step 21.
: 2) IF NOT,  THEN go to Step 23.
: b. Check RWST level    LESS THAN    b. Return to Step 20a.
2.0 FT
: c. Stop containment spray pumps
: d. Close containment  spray pump discharge valves:
o 21 spray pump:
o MOV-866A o MOV-866B o 22 spray pump:
o MOV-866C o MOV-866D 13 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2;ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. If at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
 
2-ES-1.3                  TRANSFER TO COLD LEG RECIRCULATION                REV. 1 Number:      jTitle:                                                    Revision Number: 1
: 21. Verify One RHR Heat Exchanqer Isolated As Follows:
: a. Check 822A AND 822B - OPEN        a. IF only 822B is open, THEN close 746. Go to Step 22.
IF only 822A is open, THEN close 747. Go to Step 22.
: b. Close either 746 OR 747
: 22. Open Sprav Header Valve For In Service RHR Heat Exchanaer:
o MOV-889B (21 Hx with 747 open)
                      - OR -
o MOV-889A (22 Hx with 746 open) 14 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION. Step 1.
: b. IF at any time recirculation flow from Containment to RCS.can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE. Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d)  Abnormal sump level indication 4
: 23. Check Minimum AcceDtable Flow To Core And Containment SDrav:
: a. Determine required core cooling flow from table:
No. of 946A-D          Core flow rate                Core flow rate flow meters                with                          with INDICATING -      1 Pump AND I RHR HX          2 Pumps AND/OR 2 RHR HXs 2nd Highest indicator -      2nd Highest indicator -
GREATER THAN 410 gpm          GREATER THAN 580 gpm OR                            OR 4            2 Middle indicators -        2 Middle indicators -
SUM GREATER THAN 710 gpm      SUM GREATER THAN 860 gpm OR                            OR 3 Lowest indicators -        3 Lowest indicators -
SUM GREATER THAN 970 gpm      SUM GREATER THAN 1080 gpm 2nd Highest indicator -      2nd Highest indicator -
GREATER THAN 410 gpm          GREATER THAN 580 gpm 3                    OR                            OR 2 Lowest indicators -        2 Lowest indicators -
SUM GREATER THAN 710 gpm      SUM GREATER THAN 860 gpm 2            EACH GREATER THAN 410 gpm    EACH GREATER THAN 580 gpm 1 or None            Required core cooling - NOT MET
: b. Core cooling flow required by      b. Align system for high head table - ESTABLISHED                  recirculation as follows:
: 1) Close RHR spray header isolation valves:
o MOV-889A o MOV-889B
: 2) Go to Step 25.
: c. Recirculation spray flow          c. IF spray flow was previously GREATER THAN 960 GPM                  established or required, THEN consult TSC.
15 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication 4
: 24. Go To Step 38
: 25. Dispatch NPO To Shut Down FSB        IF FSB ventilation can NOT be Ventilation                          shut down, THEN notify TSC that FSB ventilation exhaust should be monitored for radioactive contamination.
: 26. Place Interlock Switches For SI Valves To OFF:
o MOV-842 o MOV-843 16 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-..1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal sump level indication
 
        . .t*. ..                    .*R Ot*. . ..fSO            .. ftS.f.t.O*        Oftft, .t t i
CAUTION SI pumps should be stopped if RCS pressure is                          greater than their shutoff            t head pressure.
ft ft  ft    ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft  ft ft    ft ft ft  ft ft ft ft ft  ft ft ft ft ft ft t ft
: 27.        Place Safety Injection Recirc Switch 6 To ON:
: a. Check RHR heat exchanger                        a. Manually close valves.
discharge valves - CLOSED:
o MOV-746 o MOV-747
: b. Check RHR heat exchanger                        b. Manually open valves.
No. 21 to SI pump suction header valves - OPEN:
o MOV-888A o MOV-888B
: c. Check SI test line valves              -        c. Manually close valves.
CLOSED:
o MOV-842 o MOV-843
: d. Arm SI pump suction low pressure alarm by placing toggle switch to ON:
o PT-947
: e. Function complete light            -  LIT      e. Recheck required actions and manually initiate as necessary.
17 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
STEP    ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED
: 28. Check SI Suction Pressure  -        IF suction pressure is less than GREATER THAN 75 PSIG                75 psig, THEN perform the following:
: a. IF RHR pump running,  THEN:
: 1) Recheck RHR alignment per ATTACHMENT 2.
WHEN ATTACHMENT 2 is complete, THEN go to Step 29.
: b. IF 22 Recirculation pump running, THEN:
: 1) Stop 22 Recirculation pump.
: 2) Perform ATTACHMENT 2.
WHEN ATTACHMENT 2 is complete, THEN go to Step 29.
: c. IF 21 Recirculation pump running, THEN:
: 1) Stop 21 Recirculation pump.
: 2) Start 22 Recirculation pump.
: 3) IF 22 Recirc pump can NOT be started, THEN:
a)  Perform ATTACHMENT 2.
WHEN ATTACHMENT 2 is complete, THEN go to Step 29.
: d. IF SI pump suction pressure can NOT be established, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step I 18 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF-EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal sump level indication
: 29. Check SI Pumps AT LEAST 2        Perform the following:
RUNNING
: a. Verify Safety Injection recirc switch 7 is OFF
: b. Start two SI pumps:
o 21 o 23 IF 21 OR 23 SI pump can NOT be started, THEN perform the following:
: 1) Place 21 containment spray pump control switch in PULLOUT.
: 2)  Place 22 SI pump control switch in PULLOUT.
: 3) Place recirculation switch No. I to OFF.
: 4) Manually OR locally open 22 SI pump suction valves:
o MOV-887A o MOV-887B
: 5)  Start 22 SI pump.
: 6)  IF 21 AND 22 SI pumps running, THEN:
a)  Verify MOV-851B open.
b)  Verify MOV-851A closed.
: 7) IF 22 AND 23 SI pumps running, THEN:
a)  Verify MOV-851A open.
b)  Verify MOV-851B closed.
19 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION. Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication 4
: 30. Place Safety Injection Recirc Switch 8 To ON:
: a. Check containment spray pump      a. Manually close valve.
test line valve - CLOSED:
o 1813
: 31. Check Recirculation Pumps - AT        Perform the following:
LEAST ONE RUNNING
: a. Dispatch NPO to energize the following MOVs:
o MOV-882 on MCC 26B o MOV-1810 on MCC 26A
: b. Go to Step 35.
: 32. Check All 480V Busses  - ENERGIZED  Go to Step 34.
* CAUTION
* Starting a second recirculation pump is NOT allowed due to potential pump *r
* damage from strong pump/weak pump interaction or from sump blockage
* cavitation.
: 33. Align Safety Injection Recirc Switch 5 As Follows:
: a. Place non-running recirculation pump in trip pullout
: b. Place Safety Injection Recirc Switch 5 to ON This Step continued on the next page.
20 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. Il at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1,  LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. Il at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication ii
 
STEP    ACTION/EXPECTED RESPONSEi            RESPONSE NOT OBTAINEDI
: c. Check at least two service        c. Manually start one service water pumps - SUPPLYING                water pump on NON-essential NON-ESSENTIAL HEADER                  header in preferred order:
o 22, 23. 21 if  1-2-3 header non-essential
                                                          - OR -
o 25, 26, 24 if  4-5-6 header non-essential IF second service water pump will NOT start, THEN perform the following:
: 1) IF both recirculation pumps running, THEN stop ONE recirculation pump.
: 2) Close valve 804 to isolate spent fuel pit heat exchanger.
: d. Check CCW pumps  - AT LEAST TWO  d. Manually start CCW pump as RUNNING                              necessary (preferred order 22, 21, 23).
IF second CCW pump will NOT Start AND BOTH recirc pumps are running. THEN stop ONE recirculation pump.
: e. Check recirculation pumps -      e. Ensure ONLY ONE recirculation ONLY ONE RUNNING                      pump is running.
21 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION. Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
[Nuber
 
==Title:==
Revision Number:
2-ES-I.3                  TRANSFER TO COLD LEG RECIRCULATION                  REV. 1 STP        ACTION/EXPECTED RESPONSE          Fs REPONSE NOT OBTAINED1
: 34. Dispatch NPO To Perform The Following (on 98 ft. EL PAB):
: a. Energize AND close RHR miniflow test line valves:
o MOV-743 on MCC 26BB o MOV-1870 on MCC 26AA
: b. Energize the following MOVs:
o MOV-882 on MCC 26B o MOV-744 on MCC 26A o MOV-1810 on MCC 26A
    @35. Check CCW Pump Status:
: a. Three CCW pumps - RUNNING        a. Perform the following:
: 1) Verify at least two CCW pumps running.
: 2) Go to Step 36.
: b. Stop 23 CCW pump 22 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1,  LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
 
TO *................a...
X*...N              CAUTION
                                                        *OTOTA*a*..
* IF Sump Blockage is a concern, THEN refilling the RWST should be
* considered after ALL injection from RWST has stopped. TSC should be
* consulted.                                                                *
: 36. Check If Recirc Spray Is Required:
: a. Containment spray pumps - ANY      a. Perform the following:
RUNNING
: 1) IF containment pressure EVER greater than 24 psig, THEN go to Step 37.
: 2)  IF NOT. THEN go to Step 38.
: b. Check RWST level  - LESS THAN      b. Return to Step 36a.
2.0 FT
: c. Stop containment spray pumps
: d. Close containment spray pump discharge valves:
o 21 spray pump:
o MOV-866A o MOV-866B o 22 spray pump:
o MOV-866C o MOV-866D
: 37. Open One SDray Header Valve:
o MOV-889B
                - OR -
o MOV-889A 23 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IFF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE. Step 1.
i) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel  SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
: 38. Check Recirculation Switch Sequence Status:
: a. Switch 1 function complete        a. Perform the following:
light - LIT
: 1) IF 22 SI pump is stopped, THEN verify suction valves closed:
o MOV-887A o MOV-887B
: 2) Verify discharge valves for STOPPED containment spray pump closed:
o 21 spray pump:
o MOV-866A o MOV-866B o 22 spray pump:
o MOV-866C o MOV-866D
: b. Check RHR pumps - ALL STOPPED    b. Go to Step 38d.
This Step continued on the next page.
24 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.I. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication 4
 
STE    ACIONEXECTD RSPOSERESPONSE            NOT OBTAINED
: c. Switch 3 function complete        c. Check RHR pump suction and light - LIT                          discharge valves - CLOSED:
o MOV-882 o MOV-744 IF NOT. THEN perform the following:
: 1) Verify valve motor controls re-energized:
o MOV-882 on MCC 26B o MOV-744 on MCC 26A
: 2)  Manually close valves.
I.F valves can NOT be closed, THEN locally close valves.
: d. Switch 8 function complete        d. Check SI pump suction valve light - LIT                          from RWST - CLOSED:
o MOV-1810 IF NOT, THEN perform the following:
: 1) Verify valve motor control re-energized:
o MOV-1810 on MCC 26A
: 2)  Manually close valve.
LF valve can NOT be closed, THEN locally close valve.
25 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. 1E at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1,  LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal sump level indication 4
 
039. Check CCW System TemDerature        Perform the following:
LESS THAN 130°F
: a. Verify CCW heat exchanger SW outlet valves FULLY open:
o SWN-35 o SWN-35-1
: b. Refer to 2-SOP-4.1.2 COMPONENT COOLING SYSTEM OPERATION to establish backup cooling to the following:
o RHR pumps o SI pumps
: c. IF CCW system temperature increases greater than 145 0 F AND recirc flow has been established through both RHR heat exchangers, THEN shut one RHR heat exchanger discharge valve:
o MOV-747
                                                      - OR -
o MOV-746 26 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT
      .be established OR maintained, THEN go to 2-ECA-I.I. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal sump level indication ii
: 40. Verify Adequate Recirculation Flow:
: a. Core exit TCs - STABLE OR        a. Verify CCW heat exchanger SW DECREASING                          outlet valves FULLY open:
o SWN-35 o SWN-35-1 IF core exit TCs temperatures can NOT be stabilized, THEN align system for high head recirculation as follows:
: 1) Close RHR spray header isolation valves:
o MOV-889A o MOV-889B
: 2)  Return to Step 25.
27 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal sump level indication
 
STP    ACTION/EXPECTED RESPONSE;              RESPONSE NOT OBTAINEDI
: 41. Check If Containment Spray Should Be Terminated:
: a. 889A OR 889B - OPEN                a. Go to Step 42.
: b. Containment spray - IN SERVICE      b. WHEN condition is satisfied, GREATER THAN 3.5 HOURS                  THEN close 889A AND 889B.
Go to Step 42.
: c. Close 889A AND 889B
: 42. Determine If Transfer To Hot Leg Recirculation Will Be Reouired:
: a. Check if entry for this            a. Perform the following:
procedure - FROM 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT          1) Consult TSC to determine IF AND WHEN transfer to hot leg recirculation will be subsequently required.
: 2) Return to procedure and step in effect.
: 43. Return To Procedure And Step In Effect
                                    - END -
28 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 27ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal sump level indication
 
ATTACHMENT 1                (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATING
: 1. Use the following table to determine 480V equipment load ratings:
21 DG          22 DG            23 DG EOUIPMENT            BUS 5AI BUS 2A        BUS 3A    BUS 6A 21 SERVICE WATER PUMP      282 KW 22 SERVICE WATER PUMP                282 KW OR 282 KW 23 SERVICE WATER PUMP                                      282 KW 24 SERVICE WATER PUMP      282 KW 25 SERVICE WATER PUMP                282 KW OR 282 KW 26 SERVICE WATER PUMP                                      282 KW PRZR CONTROL HEATERS                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                    485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                      384 KW 23 AFW PUMP                                                384 KW 21 FAN COOLER UNIT        250 KW 22 FAN COOLER UNIT        250 KW 23 FAN COOLER UNIT                    250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                          250 KW 21 SI PUMP                316 KW 22 SI PUMP                            316 KW      316 KW 23 SI PUMP                                                  345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP                                              350 KW 21 RHR PUMP                                      303 KW 22 RHR PUMP                                                303 KW 21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                            150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                              299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW              228 KW 23 CCW PUMP 21 LIGHTING TRAN: SFORMER              150 KW (N)          150 KW (E) 22 LIGHTING TRAN: SFORMER                        225 KW 23 LIGHTING TRAN: SFORMER  225 KW TURBINE AUX OIL PUMP                                        112 KW STATION AIR COMPi RESSOR    93 KW
                                    -END-29 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
i) Indications of sump blockage may include:
a)  LOW HEADINJECTON LINE LOW FLOW alarm on panel SBF-I b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication
 
Number:        Ti t1e                                                          Revision Number: ]
2-ES-1.3                  TRANSFER TO COLD LEG RECIRCULATION                    REV.    ]
A-F7  O-7EXPECTED RES'O"EI'''T''''PONSE NOT ATTACHMENT 2 0BTAINED (Attachment page 1 of 4)
COLD LEG RECIRCULATION USING RHR PUMPS
: 1. Check If FSB Ventilation    -            Dispatch NPO to shut down FSB PREVIOUSLY SHUTDOWN                      ventilation.
IF FSB ventilation can NOT be shut down, THEN notify TSC that FSB ventilation exhaust should be monitored for radioactive contamination.
30 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication ii
 
STEP        ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI ATTACHMENT 2                (Attachment page 2 of 4)
COLD LEG RECIRCULATION USING RHR PUMPS Q
Q CAUTION o IF either 885A OR 885B is de-energized, do NOT open the energized valve UNTIL de-energized valve has been fully opened locally. Opening the energized valve first may significantly increase local dose levels.
o Extremely high radiation fields may exist in the area of 885A AND 885B.
      *o Starting an RHR pump, will cause a significant increase in local dose levels. Valving piping and pump areas should be evacuated prior to pump start.
NOTE Position of de-energized MOVs may be verified by Two is True indication OR position prior to loss of power.
: 2. Establish Cold Leg Recirculation Usinq RHR Pumps:
a)  Check 885A AND 885B - BOTH        a)  Dispatch NPO to locally open ENERGIZED                              the de-energized valve.
WHEN the de-energized valve is open. THEN you should return to this step.
Go to 2-ECA-1.I, LOSS OF EMERGENCY COOLANT RECIRCULATION.
b) Dispatch NPO to energize the following MOV:
o MOV-882 at MCC 26B This Step continued on the next page.
31 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY, COOLANT RECIRCULATION, Step 1.
: b. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c) Indication of errratic or reduced flow d) Abnormal  sump level indication
 
ATTACHMENT 2            (Attachment page 3 of 4)
COLD LEG RECIRCULATION USING RHR PUMPS c) Verify the following Safety Injection Recirc Switches are OFF:
o Recirc Switch 3 o Recirc Switch 4 o Recirc Switch 5 d) Verify RHR Pumps - BOTH STOPPED:
o 21 RHR Pump o 22 RHR Pump e) Stop BOTH Recirculation Pumps:
o 21 Recirculation Pump o 22 Recirculation Pump f) Close 1802A AND 1802B g) Close RHR pump suction valve from RWST:
o MOV-882 This Step continued on the next page.
32 of 33
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1, LOSS OF EMERGENCY COOLANT RECIRCULATION. Step 1.
: b. IF at any time recirculation flow from. Containment to RCS can NOT be established OR maintained due to Sump Blockage.-THEN go to 2-ECA-1.3. LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE. Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication 4
 
I RESPONSE NOT OBTAINED
--j    ACTION/ EXRECTED RESPE4",11 I
CALD IACLATI1N" R  I US NGrH-COLD LEG RECIRCULATION USING RHR PUMPS UM    LLachmenu page 4 ol 4) h) Establish recirculation flow              h)  IF a recirculation flow path path for RHR pumps:                        can NOT be established, THEN go to 2-ECA-1.1. LOSS OF
: 1) Verify RHR pump discharge                EMERGENCY COOLANT valve is open:.                          RECIRCULATION. Step 1.
o MOV-744 (normally de-energized open)
: 2) Verify RHR pump suction valves from containment sump are open:
o 1805 (normally open) o MOV-885A o MOV-885B i) Start 22 RHR pump                        i)  IF 22 RHR pump can NOT be started, THEN start 21 RHR pump.
IF,21 RHR pump can be NOT be started, THEN Go To 2-ECA-1.1.
LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
j)  Return to Step in effect
                                        - END -
33 of 33 j
 
FOLDOUT PAGE FOR 2-ES-1.3
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained, THEN go to 2-ECA-1.1. LOSS OF EMERGENCY COOLANT RECIRCULATION, Step 1.
: b. _F at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to Sump Blockage, THEN go to 2-ECA-1.3, LOSS OF EMERGENCY COOLANT RECIRCULATION CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTON LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP LOW PRESSURE alarm on panel SBF-1 c)  Indication of errratic or reduced flow d) Abnormal  sump level indication j
 
Procedure Use Is:    Control Copy:
--ýEntergy                      Ed Continuous Nuclear Northeast        IJ Reference        Effective Date: i1-- 1
            -n Tan..
(I 0 Information
_V;  4" a ian Point
                -Uruer 2-ES-1.4, Revision: 1 TRANSFER TO H*OTLEG RECIRCULATION Approved By:
Procedure Sponsor, RPO/tDO Team P Procedure Owner PARTIAL REVI ,      IN
 
Number:.      JTitle:                                                      Revision Number:
2-ES-1.4                  TRANSFER TO HOT LEG RECIRCULATION                  REV. 1 A. PURPOSE This procedure provides the necessary instructions for transferring the safety injection system to hot leg recirculation.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered:
: 1) From 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT,    Step 24, when the specified time interval has elased, or
: 2) When a decision is made, based upon the recommendation of the TSC, that transfer to hot leg recirculation is required.
Transfer to hot leg recirculation might be required eventually, after transferring to cold leg recircultion during the implementation of:
o 2-ES-1.2,  POST LOCA COOLDOWN AND DEPRESSURIZATION; o 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED; o 2-ECA-3.2. SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if    either of the following conditions exist:
o Containment radiation levels greater than IE5 R/hr.
                                  - OR -
o Containment pressure greater than 4 psig.
1 of 16
 
Number:
 
==Title:==
Revision Number:
2-ES-1.4                  TRANSFER TO HOT LEG RECIRCULATION                    REV. 1 STEP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
: 1. Check Low-Head Recirculation FLOW INDICATED
                                          -      IF any HHSI Pump is go to step 15.
running,  THEN I
: 2. Check If FSB Ventilation  -          Dispatch NPO to shut down FSB PREVIOUSLY SHUTDOWN                    ventilation.
IF FSB ventilation can NOT be shut down, THEN notify TSC that FSB ventilation exhaust should be monitored for radioactive contamination.
: 3. Close Cold Leg Injection Valve:
o MOV-856A
                      - OR -
o MOV-856E
: 4. Open Hot Leq InJection Valve To Loop 23:
o MOV-856B
: 5. Close Cold Leq.Injection Valve:
o MOV-856C OR -
o MOV-856D
: 6. Open Hot Leg Injection Valve To Loop 21:
o MOV-856F 2 of 16
 
[ Number:
2-ES-1.4
 
==Title:==
TRANSFER TO HOT LEG RECIRCULATION Revision Number:
REV. I
: 7. Check Recirculation System Alignment:
: a. MOV-746 OR MOV-747  - CLOSED        a. Verify 746 OR 747 closed.
IF neither valve can be closed, THEN close HCV-638 OR 640.
: b. Safety injection recirc              b. Place safety injection recirc switch 6 - OFF                        switch 6 to OFF.
I r
: 8. Check System Alignment For Starting SI Pumps:                                                                  I
: a. Check recirculation pumps            a. Place ONE recirculation pump ONLY ONE running                        in trip pullout.
: b. SI pump miniflow valves    -        b. Manually close valves.
PREVIOUSLY CLOSED o MOV-842 o MOV-843,
: c. SI pump suction Valves from          c. Manually open valve(s).
RHR Hx - OPEN:
o MOV-888A o MOV-888B
:d. Arm SI pump suction low pressure alarm by placing toggle switch to ON:
o PT-947
: e. Check recirculation switch          e. Place switch in off.
                .No. 7 - OFF
: 9. Check SI Suction Pressure    -          Check SI-valve alignment.
GREATER THAN 75 PSIG IF adequate suction pressure can NOT be established, THEN consult TSC prior to continuing.
3 of 16
 
[ Number:
2-ES-1.4
 
==Title:==
TRANSFER TO HOT LEG RECIRCULATION Revision Number:
REV. 1
* CAUTION                                        *
* EDG load should be maintained less than 1650 KW. but may be increased to
* 2000 KW for a maximum of 2 hrs in any 24 hr period.
1  S
: 10. Start 23 SI Pump As Follows:
: a. Verify adequate power:            a. IF adequate power can NOT be established, THEN consult TSC o Bus 6A - ENERGIZED BY              prior to continuing.
OFFSITE POWER
                          - OR -
o Load on 23 diesel generator
                    - LESS THAN 1300 KW
: b. Start 23 SI pump                  b. Perform the following:
: 1) Place 21 containment spray pump in PULLOUT.
: 2) Place 22 SI pump in  PULLOUT.
: 3) Place Safety Injection Recirc Switch 1 to OFF.
: 4) Open 22 SI pump suction valves:
o MOV-887A o MOV-887B
: 5) Verify:
o MOV-851B open
                                                                  - AND -
o MOV-851A closed
: 6) Start 22 SI pump.
4 of 16
 
ACTION/EXPECTED RESPONSE RRESPONSE                NOT OBTAINED
: 11. Verify 746 AND 747 -  CLOSED        IF either valve can NOT be closed, THEN close HCV-638 AND 640.
IF either HCV-638 OR 640 can NOT be closed, THE__N go to step 21.
: 12. Check SI Suction Pressure -          Check SI valve alignment.
GREATER THAN 75 PSIG IF adequate suction pressure can NOT be established, THEN consult TSC prior to continuing.
5 of 16
 
SE            ACTION/ EXPECTED RESPONSE                  RESPONSE NOT OBTAINED1
* CAUT ION*
t t
EDG load should be maintained less than 1650 KW, but may be increased to 2000 KW for a maximum of 2 hrs in any 24 hr period.
  * *  *  *  *  * * * *  * * * * * * * * *  * *  *  *  *
* A * *  *  *  *  *  * * * * * * * * *
: 13.      Start 21 SI Pump As Follows:
: a. Verify adequate power:                a. IF adequate power can NOT be established, THEN consult TSC o Bus 5A - ENERGIZED BY                    prior to continuing.
OFFSITE POWER
                          - OR -
o Load on 21 diesel generator
                  - LESS THAN 1300 KW
: b. Start 21 SI pump                        b. Perform the following:
: 1) Place 21 containment spray pump in PULLOUT.
: 2) Place 22 SI pump in PULLOUT.
: 3)  Place Safety Injection Recirc Switch 1 to OFF.
: 4) Open 22 SI pump suction valves:
o MOV-887A o MOV-887B
: 5)  Verify:
o MOV-851A open
                                                                          -  AND  -
o MOV-851B closed
: 6)  Start 22 SI pump.
: 14.      Go To Step 20 6 of 16
 
2-ES-1.4                  TRANSFER TO HOT LEG RECIRCULATION      REV. 1 Number        jTitle:                                          Revision Number:
: 15. Close Cold Leg Injection Valve:
o MOV-856A
                      - OR -
o MOV-856E
: 16. Open Hot Leg Injection Valve To Loop 23:
o MOV-856B
: 17. Close Cold Leg Injection Valve:
o MOV-856C
                      - OR -
o MOV-8560
: 18. Open Hot Leg Injection Valve To Loop 21:
o MOV-856F 7 of 16
: 19. Check High-Head Recirculation Status:
: a. Check SI pumps - ANY RUNNING      a. IF SI pumps 21 and 23 were shutdown, THEN CONSULT with TSC.
: b. Check SI pumps - 21 AND 23        b. IF 21 OR 23 SI pump can NOT be RUNNING                              started, THEN perform the following:
: 1) Place 21 containment spray pump control switch in PULLOUT.
: 2) Place 22 SI pump control switch in PULLOUT.
: 3) Place recirculation switch No. 1 to OFF.
: 4) Manually open 22 SI pump suction valves:
o MOV-887A o MOV-887B
: 5)  Start 22 SI pump.
: 6) IF 21 AND 22 SI pumps running, THEN:
a) Verify MOV-851B open.
b) Verify MOV-851A closed.
: 7) IF 22 AND 23 SI pumps running, THEN:
a) Verify MOV-851A open.
b) Verify MOV-851B closed.
8 of 16
: 20. Verify Adequate Recircualtion Flow:
: a. Core exit TCs - STABLE OR          a. Return to Step 1.
DECREASING
: 21. Align Seal Gas System:
: a. Verify following valves are closed:
o PCV-1090 outlet stop 1443 o PCV-1090 bypass stop 1444
: b. Verify nitrogen supply is available - PI-1075 GREATER THAN 250 PSIG
: c. Slowly open PCV-1090 outlet stop valve 1443
: d. Verify PCV-1090 set to maintain 250 psig on PI-1089
: 22. Close Containment Manual Isolation Valves:
: a. Consult SM to determine the necessary valves on ATTACHMENT 1 to be isolated
: b. Dispatch NPO to isolate the necessary valves with Health Physics assistance
: 23. Return To Procedure And Step In Effect
                                  -END-9 of 16
 
ATTACHMENT 1                (Attachment page 1 of 7)
Permission*                                                                Valving*
* Granted                Valve Operation              Location            Completed A                    Isolate Charging Line a) Close MOV-205                      4 b) Close MOV-226                      4 c)  Close MOV-227                    4 d) Open SOV 3501 (IVSW)              2 B                    Isolate RCP 21 Seal Injection a) Close MOV-4925                    4 b)  Close MOV-250A                  4 c)  Open SOV 3514 (IVSW)            2 C                    Isolate RCP 22 Seal Injection a)  Close MOV-4926                  4 b)  Close MOV-250B                  4 c)  Open SOV 3515 (IVSW)            2 D                    Isolate RCP 23 Seal Injection a) Close MOV-4927                    4 b) Close MOV-250C                    4 c) Open SOV 3516 (IVSW)              2 Location:              1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft. El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft.      El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft.      El.
  " The SM should initial those lines which it    is permissible to isolate.
**  The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs. If he does so, he should initial the appropriate right hand column entry.
10 of 16
 
ATTACHMENT 1              (Attachment page 2 of 7)
(Continued)
Permission*                                                            Valving**
Granted                Valve Operation                Location      Completed E                  Isolate RCP 24 Seal Injection a) Close MOV-4928                      4 b) Close MOV-250D                      4 c)  Open SOV 3517 (IVSW)              2 F                  Isolate RCP Seal Return a)  Close MOV-222                    CCR G                  Isolate RCP Component Cool. Wtr.
a) Close MOV-769 (Supply)              CCR b) Close MOV-797 (Supply)              CCR c)  Close MOV-786 (Mtr Brg  Return)  CCR d)  Close MOV-784 (Mtr Brg  Return)  CCR e)  Close MOV-789 (Thermal  Barrier) CCR f)  Close FCV-625 (Thermal  Barrier) CCR H                  Isolate Containment Spray Headers a)  Close MOV-869A                    4 b) Close MOV-869B                      4 c)  Open SOV 3504 (IVSW-869B)          2 d) Open SOV 3511 (IVSW-869A)            2 e)  Close 878A (Test Line Stop)        6 Isolate Recirculation Sample Line a) Close MOV-990A                      4 b)  Close MOV-990B                    4 c)  Open (N2 Gas) SOV 3505            2 Location:              1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft. El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft. El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft. El.
* The SM should initial those lines which it    is  permissible to isolate.
The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs. If he does so.
he should initial the appropriate right hand column entry.
11 of 16
 
(Attachment  page 3 of 7)
ATTACHMENT 1 ATTACHMENT  I                (Attachment page 3 of 7)
(Continued)
Permission*                                                                  Valving*
* Granted                  Valve Operation                  Location          Completed J                    Isolate RHR System a) Close MOV-882                        CCR b)  Close MOV-744                      CCR c)  Close MOV-743                        4 d)  Close MOV-1870                        4 e)  Close MOV-958 (Sample Line)          4 f)  Close MOV-959 (Sample Line)          4 g)  Close 990D      (Sample Line)        3 h)  Open SOV 3500 (N2Gas 732)            2 i)  Open SOV 3506 (N2Gas MOV-744)        2 j)  Open SOV 3509 (N2Gas Sample Lin e)2 k)  Open SOV 3510 (N2Gas -
Between Mov-743/1870)              2
: 1) Close 732 (RHR Suction)                1 m) Close 859A (SIS Test Line Stop)        1 n)  Close 859C (SIS Test Line Stop) 1 o)  Close MOV-885A (VC Sump To RHR) CCR p)  Close MOV-885B (VC Sump To RHR) CCR K                    Isolate N2 to PRT/RCDT/SIS ACCUM/PORV a)  Close SOV 3418 and 3419 (PRT)          2 b)  Close SOV 3416 and 3417 (RCDT)        2 c)  Close PCV-863 (VC N2 Supply)        C(CR d)  Close 5459 (RCDT N2 Supply)            1 e)  Close 4136 (PRT N 2 Supply)            1 Location:                1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft.      El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft.        El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft.        El.
* The SM should initial those lines which it    is permissible to isolate.
**  The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs.      If he does so, he should initial the appropriate right hand column entry.
12 of 16
 
F  2-ES-1.4 Number:
 
==Title:==
TRANSFER TO HOT LEG RECIRCULATION ATTACHMENT I REV. 1 eviso Number:
(Attachment page 4 of 7)
(Continued)
Permission*                                                            Valving*"
Granted                Valve Operation              Location        Completed L                    Isolate Containment Pressure Instrumentation a)    Close 1814A                      1 b)    Close 1814B                      1 c)    Close 1814C                      1 M                    Isolate PRZR Level Instrumentation DW Tester a) Close 580A                          1 b)    Close 580B                        1 N                    Isolate CCW To Recirc Pump Motors a)    Close 753G (Return)              1 b)    Close 753H (Supply)              1 0                    Isolate Weld Channel to Racks in VC a)    Close PCV-1111-1 Rack 16 & 17    1 b)    Close PCV-1111-2 Rack 14 & 18    1 P                    Isolate Station Air To VC a)    Close SA-24                      1 b)    Close SA-24-1                    1 Q                    Isolate Service Water to FCU's a)    Close SWN-41-1A (21 Inlet Iso)    4 b)    Close SWN-41-1B (21 Block)        4 c)    Close SWN-41-2A (22 Inlet Iso)    4 d) Close SWN-41-2B (22 Block)          4 Location:              1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft. El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft. El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft. El.
* The SM should initial those lines which it    is permissible to isolate.
The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs.      If he does so.
he should initial the appropriate right hand column entry.
13 of 16
 
Number:
2-ES-1.4    1
 
==Title:==
TRANSFER TO HOT LEG RECIRCULATION Revis REV.
Num ATTACHMENT 1                (Attachment page 5 of 7)
(Continued)
Permission*                                                                Valving**
Granted                Valve Operation                Location        Completed Q                    Isolate Service Water to FCU's (continued) e)    Close SWN-41-3A (23 Inlet Iso)      4 f)    Close SWN-41-3B (23 Block)          4 g) Close SWN-41-4A (24 Inlet Iso)          4 h) Close SWN-41-4B (24 Block)              4 i) Close SWN-41-5A (25 Inlet Iso) 4 j) Close SWN-41-5B (25 Block)              4 k) Close SWN-43 -1    (21 Hdr Drain)
: 1) Close SWN-43-2      (22 Hdr Drain) m) Close SWN-43-3      (23 Hdr Drain) 1 n) Close SWN 4    (24 Hdr Drain)      1 Close SWN-43-5                      1 o)                    (25 Hdr Drain) 1 1
p)    Close SWN-44-1A (21 Out Isol        4 q)    Close SWN 1B (21 Block)          4 r)    Close SWN-44-2A (22 Out Isol ) 4 s) Close SWN-44-2B (22 Block)              4 t)    Close SWN-44-3A (23 Out Isol ) 4 u)    Close SWN-44-3B (23 Block)          4 v) Close SWN-44-4A (24 Out Isol ) 4 w) Close SWN-44-4B (24 Block)              4 x)    Close SWN-44-5A (25 Out Isol ) 4 y)    Close SWN-44-5B (25 Block)          4
                                                                .4 z)    Close SWN-51-1A (21 but Sample) 4 aa) Close SWN-51-2A (22 Out Sample) 4 ab) Close SWN-51-3A (23 Out Sample) 4 ac)    Close SWN-51-4A (24 Out Sample) 4 ad) Close SWN-51-SA (25 Out Sample)
Location:                1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft. El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels  - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft. El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft. El.
* The SM should initial those lines which it    is  permissible to isolate.
**    The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs.        If he does so, he should initial the appropriate right hand column entry.
14 of 16
 
ATTACHMENT 1                (Attachment page 6 of 7)
(Continued)
Permission*                                                              Valving**
Granted                  Valve Operation                  Location      Completed Q                    Isolate Service Water to FCU's (continued) ae)    Close SWN-71-1A (21 Mtr Isol)      4 af) Close SWN-71-1B (21 Mtr Block)        4 ag)    Close SWN-71-2A (22 Mtr Isol)      4 ah)    Close SWN-71-2B (22 Mtr Block)      4 ai) Close SWN-71-3A (23 Mtr Isol)          4 aj)    Close SWN-71-3B (23 Mtr Block)      4 ak) Close SWN-71-4A (24 Mtr Isol)          4 al) Close SWN-71-4B (24 Mtr Block)        4 am)    Close SWN-71-5A (25 Mtr Isol)      4 an) Close SWN-71-5B (25 Mtr Block)        4 R                    Isolate Auxiliary Steam to VC a)    Close UH-43 (Steam Supply)          1 b)    Close UH-44 (Condensate Return)      1 S                    Isolate Alternate    Safe Shutdown Instrumentation a)    Close IIP-504  (Przr LI-3101-1)      1 b) Close IIP-505    (Przr LI-3101-1)      1 c)    Close IIP-506  (Przr PI-3105-I)      1 d)    Close IIP-507  (Przr PI-3105-1)      1 e)    Close IIP-500  (22 SG LI-5002-1)    1 f)    Close IIP-501  (22 SG LI-5002-1)    1 g)    Close IIP-502  (21 SG LI-5001-1)    1 h) Close IIP-503    (21 SG LI-5001-1)    1 Location:              1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft. El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft. El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft. El.
* The SM should initial those lines which it      is  permissible to isolate.
**  The NPO should initial each valve as he properly positions it. The CRS can previously position some MOVs.      If he does so, he should initial the appropriate right hand column entry.
15 of 16
 
ATTACHMENT 1                (Attachment page 7 of 7)
(Continued)
Permission*                                                                  Valving**
Granted                  Valve Operation                Location          Completed T                      Isolate Post    Accident Air Sampling a)    Move SOV  5018 (VC Samp Ch 1)      5.
b) Move SOV    5019 (VC Samp Ch 1)      5 c)    Move SOV  5020 (VC Samp Ch 2)      5 d)    Move SOV  5021 (VC Samp Ch 2)      5 e)    Move SOV  5022 (VC Return Ch 1)    5 f)    Move SOV  5023 (VC Return Ch 1)    5 g)    Move SOV  5024 (VC Return Ch 2)    5 h) Move SOV    5025 (VC Return Ch 2)    5 U                      Isolate City Water, To VC a) Close MW-17.                          1 b) Close MW-17-1                          1 V                      Isolate Post A.ccident Venting (Ventilation) a)    Close E-1 (VC IA Supply Stop)      5.
b) Close E-2 (VC Isolation Stop)          5 c)    Close E-3 (Vent Exhaust Isol)      5 d) Close E-5 (Vent Exhaust Isol)          5 W                      IF Personnel And Equipment Hatch Air Lock Doors NOT Operating, Isolate Equalizing Valves a)    Close 85A (80 ft Air Lock)          7, b)    Close 85B    (80 ft Air Lock)        7 c)    Close 95A (95 ft Air Lock)          8 d)    Close 95B (95 ft Air Lock)          8 Location:                1  Piping Penetration Area 2  IVSW Control Panel - PAB 98 ft.      El.
3  Gallery above Piping Penetration Area 4  MCC 26 AA and BB - PAB 98 ft. El.
5  PACS/PACV Panels - PAB 98 ft. El.
6  Spray Pump Area - PAB 68 ft. El.
7  Personnel Air Lock - Fan House 80 ft.      El.
8  Equipment Hatch Air Lock - MO Bldg 95 ft.        El.
  "  The SM should initial those lines which it      is permissible to isolate.
The NP0 should initial    each valve as he properly positions it. The CRS can previously position some MOVs.        If he does so.
he should initial    the appropriate right hand column entry.
                                            - END-16 of 16
 
a Entergy                      Procedure Use Is:
0 Continuous Control Copy:
Nuclear Northeast        O Reference      Effective Date:
O3 Information 2-E-2, Revision: 0 FAULTED STEAMI(GEN EBATOR ISOLATION Approved By:
m Proced6e Sponsor, RPO/ D Team P Procedure Owner EDITORIAL REVISION
 
A. PURPOSE This procedure provides actions to identify and isolate a faulted steam generator.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:
: 1) 2-E-O, REACTOR TRIP OR SAFETY INJECTION,  Step 13, with the following symptoms:
: a. Any SG pressure decreasing in an uncontrolled manner.
: b. Any SG completely depressurized.
: 2)  2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT. Step 2, 2-ECA-3.1, SGTR WITH LOSS'OF REACTOR COOLANT  - SUBCOOLED RECOVERY DESIRED, Step 11, and 2-ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT  - SATURATED RECOVERY DESIRED, Step 4, with the following  symptoms and/or conditions:
: a. Any SG pressure decreasing in an uncontrolled manner.
: b. Any SG completely depressurized.
: c. Faulted SG isolation not verified.
: 3) 2-FR-H.5, RESPONSE TO STEAM GENERATOR LOW LEVEL,    Step 3,  when the affected SG is identified as faulted.
: 4)  Foldout page of other procedures whenever a faulted SG is identified.
: 5) 2-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, foldout page, if any SG pressure increases.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if    either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                          - OR -
o Containment pressure greater than 4 psig.
1 of 4
 
2-E-2                      FAULTED STEAM GENERATOR ISOLATION                              REV. 0 Number:
 
==Title:==
Revision Number:
* CAUTION                                                      *
* o At least one SG must be maintained available for RCS cooldown.                                *
* o Any faulted SG or secondary break should remain isolated during                              *
* subsequent recovery actions unless needed for RCS cooldown.
* o FRPs should NOT be implemented prior to completion of 2-E-O, REACTOR                          *
* TRIP OR SAFETY INJECTION, ATTACHMENT 1. AUTOMATIC ACTION VERIFICATION.                        *
        *
* t  *  *  *  * *  *  *  *
* f
: 1. Check MSIVs  - CLOSED                    Manually close valves.
: 2. Check If Any SG Secondary Pressure Boundary Is Intact:
: a. Check pressures in all SGs  -        a. IF all SG pressures decreasing ANY STABLE OR INCREASING                    in an uncontrolled manner, THEN go to 2-ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 1.
                                                      *    *  *  * *
* ft  * *  * * * *
* ft *  *
* ft *
* CAUTI ON
* Radiation levels and harsh environmen t conditions should be evaluated prior to performing local actions.
                                                    *    *  .  .
* ft *  * .  * * . * *  . .  , ft  ft f
: 3. Identify Faulted SG(s):
: a. Check pressures in all SGs  -        a. Search for initiating break:
o ANY SG PRESSURE DECREASING              o Main steamlines IN AN UNCONTROLLED MANNER o Main feedlines
                            - OR -
o Other secondary piping o ANY SG COMPLETELY DEPRESSURIZED                          Go to Step 5.
2 of 4
* CAUTION                                    *
* If  the turbine-driven AFW pump is  the only available source of feed flow,  *
* steam supply to the turbine-driven AFW pump must be maintained from one
* SG.
: 4.      Isolate Faulted SG(s):                  Manually close valves. IF valves can NOT be closed. THEN dispatch o Isolate main feedline                NPO to attempt to locally close valves or associated block valves.
o Isolate AFW flow o Dispatch NPO to close steam supply header valves to turbine-driven AFW pump from faulted SG(s):
o MS-41 (SG 22) o MS-42 (SG 23) o Verify SG atmospheric steam dumps - CLOSED o Verify SG blowdown isolation valves - CLOSED o Locally isolate the following lines from faulted SG(s):
o Steam traps upstream of MSIVs o MSIV bypass valves 3 of 4
: 5. Check CST Level    GREATER THAN        Switch to city water supply:
2 FT
: a. Open city water header, isolation valve:
o FCV-1205A
: b. Open AFW pump suction valves as necessary:
o PCV-1187 o PCV-1188 o PCV-1189
: 6. Check Secondary Radiation:
: a. Request periodic activity samples of all SGs
: b. Check unisolated secondary radiation monitors:
o Main steamline radiation recorder (R-28. R-29, R-30, and R-31) o Condenser air ejector radiation recorder (R-45) o SG blowdown radiation recorder (R-49)
: c. Secondary radiation  - NORMAL      c. Go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 7. Go To 2-E-1., LOSS OF REACTOR OR SECONDARY COOLANT, Step I
                                    -END-4 of 4
 
Procedure Use Is: Control Copy:
---Entergy                  E2 Continuous Nuclear Northeast      O Reference      Effective Date: 7 r-ae Tex-n 0 Information ruarPon 2-E-3, Revision: 0 STEAM GENE8AILTUBE RUPTURE Approved By:
Procedure Sponsor, RPO/p,              Date Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number:
2-E-3                        STEAM GENERATOR TUBE RUPTURE                  REV. 0 A. PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:
: 1) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 14, when condenser air ejector radiation, SG blowdown radiation or steamline radiation is abnormal.
: 2) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 26, 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 8, 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 6, 2-ECA-2.1. UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, Step 5, and 2-FR-H.3. RESPONSE TO STEAM GENERATOR HIGH LEVEL, Step 8, when secondary radiation is abnormal.
: 3) 2-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 21, 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 3, 2-ES-i.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 5, 2-ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 5, 2-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 5, 2-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 5, 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 12, 2-ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT - SATURATED RECOVERY DESIRED, Step 5, and 2-ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 6, when a SG narrow range level increases in an uncontrolled manner.
: 4) 2-ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 3, 4, and 5 when pressurizer pressure control is restored.
: 5) Any foldout page that has E-3 transition criteria whenever any SG level increases in an uncontrolled manner or any SG has abnormal radiation.
1 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than IE5 R/hr.
                        - OR -
o Containment pressure greater than 4 psig.
2 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
dr CAUTION dr FRPs should NOT! be implemented prior to completion of 2-E-O, REACTOR TRIP                                            dr OR SAFETY INJECTION. ATTACHMENT 1, AUTOMATIC ACTION VERIFICATION.                                                    dr
  *
* a..      *    * * *    *  *  *  * * *
* a  a a    a a a  *  *  * *    * *  *
* a *  * *  * *  * * * *
* 0 1.      Check If        RCPs Should Be Stopped:
: a. SI pumps        -  AT LEAST ONE RUNNING            a. Go to Step 2.
: b. RCS subcooling based on core                        b. Go to Step 2.
exit TCs - LESS THAN 23°F (30°F FOR ADVERSE CONTAINMENT)
: c. Stop all RCPs a  *
* a  *
* a
* a  *    *
* a *  *
* a  *
* a  **    a m ta  d*
* a
* a  *
* a *
* 11.
CAUTION                                                        dr
* Radiation levels and harsh environment conditions should be evaluated dr prior to performing local actions.
  *1 a  *
* a
* a a  a
* a  a  * *  *
* a  *
* a
* a  *  *  *
* a *
* a  a a  a  a
* a  a
* a a *
: 2.        Identify Ruptured SG(s):                                  Continue with Steps 7 through 12.
WHEN ruptured SG(s) identified, o Unexpected increase in any SG                            THEN do Steps 3 through 6.
level                                                OBSERVE CAUTIONS PRIOR TO STEP 3.
                              -  OR -
o High radiation from any SG steamline:
o  R-28    (SG    21) o  R-29    (SG    22) o  R-30    (SG    23) o  R-31    (SG    24)
                              -  OR -
o High radiation from any SG sample 3 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
FNumber:
2-E-3 Tite:
STEAM GENERATOR TUBE RUPTURE Revision Number:
REV. 0
                                              * *. a
                                                  .  *. .. a  * *
* CAUTION
* o If the turbine-driven AFW pump is the only available source of feed
* flow, steam supply to the turbine-driven AFW pump should be maintained
* from one SG.
* o At least one SG must be maintained available for RCS cooldown.
: 3.      Isolate Flow From Ruptured SG(s):
: a. Adjust ruptured SG(s) atmospheric steam dump controller setpoint to 74%,
1030 psig.
: b. Check ruptured SG(s)                  b. WHEN ruptured SG pressure less atmospheric steam dump    CLOSED        than 1030 psig, THEN verify ruptured SG atmospheric steam dump closed. IF NOT closed, THEN place controller in manual and close valve. IF valve can NOT be closed, THEN locally isolate open valve.
This Step continued on the next page.
4 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33Z FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number
 
==Title:==
Revision Number:
2-E-3                      .STEAM GENERATOR TUBE RUPTURE                      REV. 0
: c. Check 22 AND 23 SGs    INTACT      c. Perform the following:
: 1) IF at least one motor-driven AFW pump running, THEN manually trip.
turbine-driven AFW pump.
: 2)  IF turbine-driven AFW pump was NOT tripped, THEN:
a)  Locally isolate steam supply from ruptured SG(s) to turbine-driven AFW pump:
o MS-41 (SG 22) o MS-42 (SG 23)
: 3)  IF turbine-driven AFW pump was tripped, THEN:
a)  Locally isolate steam supply from ruptured SG to turbine-driven AFW pump:
o MS-41 (SG 22) o MS-42 (SG 23) b)  WHEN local isolation is complete, THEN restart turbine-driven AFW pump as necessary.
: d. Verify blowdown isolation          d. Manually close valve(s).
valve(s) from ruptured SG(s)
CLOSED
: e. Dispatch NPO to:
o Close steam traps upstream of ruptured SG(s) MSIV o Verify ruptured SG(s) MSIV bypass valve - CLOSED This Step continued on the next page.
5 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. S1 REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs. THEN manually start SI system pumps AND go to 2-ECA-3.i, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800  801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[    2-E-3 Number:
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                        REV. 0 Revision Number:
: f. Close ruptured SG(s) MSIV(s)      f. Perform the following:
: 1) Close all remaining MSIVs.
IF valves can NOT be closed, THEN locally close per 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS.
: 2)  Verify following valves closed:
o Turbine stop valves.
o Condenser steam dump valves.
o Moisture separator reheater valves.
o Dispatch NPO to close:
o 21 MBFP stop valve MS-7 o 22 MBFP stop valve MS-7-i o Air ejector stop valve MS-8 o Gland steam regulator stop valves
: 3) Use intact SG(s) atmospheric steam dump valve for steam dump.
ILF any ruptured SG can NOT be isolated from at least one intact SG, THEN go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
6 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20. IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is .decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply..
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEP                ACTION/EXPECTED RESPONSE                                                        RESPONSE NOT
  *  *    *      *  *
* ft  *z  *    *  *    *  *  *    *
* r  ft    *  *
* ft  *      ,* ft        **ft  ft      r
* t  ft    ft  ft  ft  ft ft    tf
  -                                                                              CAUTION                                                                                          f ft
* IF any ruptured SG is faulted, feed flow to that SG should-remain
* isolated during subsequent recovery actions unless needed for RCS cooldown.
t  t  f      t  t    t  t ft  ft    t  t  f    t ft    t  t    t  ft    t  t  ft            f      t  f  t        t f t      t    t t    t  t  ft  t  ft ft    ft
: 4.          Check Ruptured SG~s)                        Level:
: a. Narrow range level - GREATER                                              a. Maintain feed flow to ruptured THAN 10% (27% FOR ADVERSE                                                        SG until level greater than CONTAINMENT)                                                                    10% (27% FOR ADVERSE CONTAINMENT).
Continue with Step 5.                                OBSERVE CAUTION PRIOR TO STEP 5.                                  WHEN ruptured SG level greater than 10% (27% FOR ADVERSE CONTAINMENT), THEN stop feed flow to ruptured SG(s).
: b. Stop feed flow to ruptured SG(s)
  *k CAUTION Isolation of the Ruptured SG(s) should be completed by closing the MSIV(s), the SG Atmospheric(s) and the Turbine-driven AFW Pump Steam Supply before continuing to Step 5.                                                                                                                                      dr ft  ft  ft    ft  ft  ft  ft  ft  ft  ft  ft  ft  ft    "  ft  ft  ft  ft  ft  ft  ft    ft  ft  ft  ft  ft      ft  ft  ft ft  ft  ft ft  ft  ft  ft ft  ft        ft
: 5.          Check Ruptured SG(s) Pressure -                                                  Go to 2-ECA-3.1. SGTR WITH LOSS GREATER THAN 440 PSIG                                                            OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
7 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26) 2.-    SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST-level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:  1 2-E-3                            STEAM GENERATOR TUBE RUPTURE                        REV. 0
* CAUTION
* o IF RCPs are NOT running, the following steps may cause a false 2-F-0.4, INTEGRITY STATUS TREE, indication for the ruptured loop.        Disregard the ruptured Ioop T-cold indication until after performing Step 28.
o To prevent main steamline isolation,      steam dump to condenser should NOT
* exceed 0.5 E6 lbs/hr per SG.
o After an operator-induced cooldown in Step 6 is        begun, the continuous action for RCP Trip Criteria no longer applies.
i
: 6. Initiate RCS Cooldown:
: a. Determine required core exit temperature:
RUPTURED SG PRESSURE              CORE EXIT TEMPERATURE (PSIG)                OF (ADVERSE CONTAINMENT OF)
Greater than OR Equal to 1100                          519 (513) 1050                          513 (507) 1025                          510 (504) 1000                          507 (501) 975                          504 (497) 950                          500 (494) 900                          494 (487) 850                          487 (480) 800                          479 (472) 750                          471 (464) 700                          463 (456) 650                          454 (447) 600                          445 (438) 550                          435 (428) 500                          424 (416) 440                          409 (401)
This Step continued on the next page.
8 of .42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            O-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP    ACTION/EXPECTED RESPONSEi                RESPONSE NTOBTAINEDt
: b. Dump steam to condenser from        b. Manually or locally dump steam intact SG(s) at maximum rate,            at maximum rate from intact NOT to exceed 0.5 E6 lbs/hr              SG(s):
per intact SG:
o Use SG atmospheric steam
: 1) Check condenser - AVAILABLE              dump:
: 2)  Place steam dump controller            o Refer to 2-SOP-ESP-OO1, switch to manual and adjust                LOCAL EQUIPMENT OPERATION for zero output.                          AND COMPENSATORY ACTIONS for local operation as
: 3)  Transfer condenser steam                  necessary.
dump to pressure control mode and adjust manual                o Use turbine-driven AFW pump.
switch as necessary.
IF no intact SG available, THEN perform the following:
o Use faulted SG.
                                                            - OR -
o Go to"2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
: c. Core exit TCs - LESS THAN            c. Continue with Step 7. WHEN REQUIRED TEMPERATURE                      core exit TCs less than required temperature, THEN do Steps 6d and 6e.
: d. Stop RCS cooldown
: e. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE 9 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800  801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 7. Check Intact SG Levels:
: a. Narrow range level - GREATER      a. Maintain total feed flow THAN 10% (27% FOR ADVERSE            greater than 400 gpm until CONTAINMENT)                          narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain      b. IF narrow range level in any narrow range level between 14%        intact SG continues to (27% FOR ADVERSE CONTAINMENT)        increase in an uncontrolled and 50%                              manner, THEN stop RCS cooldown AND return to Step 1.
10 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (.26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[ SNumber :
2-E-3  .
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                                                RevisionREV. Number:
0
          *  *  *    * **  *
* a * *  *  *  *  *  *  *  * *  *  * *    *
* a * *    * *  *  *  * *  *  *    *  *  *    *  *
* CAUTION
* IF any PRZR PORV opens because of high PRZR pressure, Step 8b should be
* repeated after pressure decreases to less than the PORV setpoint.
          *  *,  *    *  *  * *1 * *
* a.  * *    *  *  *  .*  *
* r*  *    * * *  , * *  *  *  * *  *  *    *  *    *  .  *  *
      @    8.      Check PRZR PORVs And Block Valves:
: a. Power to block valves -                              a. Restore power to block valves AVAILABLE                                                  by closing the following breakers as necessary:
o MCC 26B/1H (MOV-535) o MCC 26A/1H (MOV-536)
: b. PORVs -. CLOSED                                      b. IF PRZR pressure less than 2335 psig, THEN manually close
                                                                                  *PORVs.
IF any valve can NOT be closed, THEN manually close its block valve.
IF block valve can NOT be closed, THEN go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
: c. Block valves -'AT          LEAST ONE                c. Open one block valve unless it OPEN                                                      was closed to isolate an open PORV.
11 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[  2-E-3 Number:
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                    REV. 0j Revision Number:
* I
        -*                                  CAUTION
* o If offsite power is  lost after SI reset, manual action may be required
* to restart safeguards equipment.
        "  o Overriding breaker anti-pump/lockout may require placing control switches to TRIP or may require Containment Spray Reset
* o Placing key switches to DEFEAT will prevent auto SI actuation.
: 9. Reset SI:
: a. Check all CCW pumps - RUNNING      a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1 o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2):
o Train A o Train B
: e. Verify Train A AND B - RESET      e. Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o SIA-1 o SIM-i o SIA-2 o SIM-2 12 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step I:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49),    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF'any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2,'FAULTED STEAM GENERATOR ISOLATION, Step I.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFN SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 10. Reset Containment Isolation Phase A And Phase B:
: a. Place IVSW switches to OPEN on SN panel:
o 1410 o 1413 o SOV-3518 o SOV-3519
: b. Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: c. Verify personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: d. Place control switches for all remaining Phase A isolation valves to CLOSE on SN panel
: e. One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B
: f. Verify Train A AND B  - RESET    f. IF signal does NOT reset,  THEN:
: 1) Place key switches to BYPASS.
: 2) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset, THEN reset relays CA1 AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
This Step continued on the next.page.
13 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based. on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step I.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
r[ Number:
2-E-3
 
==Title:==
STEAM GENERATOR TUBE RUPTURE Revision Number:
REV. 0 STP      ACTION/EXPECTED  RESPONSE  "          RESPONSE NOT OBTAINEDI
: g. Check Phase B - ACTUATED          g. Go To Step 11.
: h. Containment pressure - LESS        h. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig, THEN do Steps 10i through 10k.
: 2)  Continue with Step 11.
: i. One At A Time, Depress Containment Spray Reset Pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: j. One at a time, depress Phase B reset buttons:
o CI Phase B Train A o CI Phase B Train B
: k. Verify Train A AND B - RESET        k. Verify Relays reset (Top of Safeguards Initiation Racks 1-2 AND 2-2):
o  S1 o  S2 o  CB1 o  CB2
: 11. Establish Instrument Air To Containment:
: a. Open PCV-1228                      a. Verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAI o CA2 14 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFI SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
SNumber:
2-E-3
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                          REV. 0 Revision Number:  1 CAUTION RCS pressure should be monitored.            If RCS pressure decreases in an uncontrolled manner to less than 320 psig (340 psig FOR ADVERSE CONTAINMENT), the RHR pumps must be manually restarted to supply water to the RCS.
* 12..      Check If RHR Pumps Should Be Stopped-:
: a. RCS pressure - GREATER THAN            a. Go to Step 13. OBSERVE NOTE 320 PSIG (340 PSIG FOR ADVERSE              PRIOR TO STEP 13.
CONTAINMENT)
: b. Stop RHR pumps and place, in AUTO 15 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI TerminationStep 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[Number:
2-E-3
 
==Title:==
STEAM GENERATOR TUBE RUPTURE evision Number:
REV. 0
  "                                        CAUTION                                        *
* If RWST level decreases to less than 15 ft, charging pumps that are                  *
* started or running should be monitored for loss of suction which may
  "  result in pump damage.
: 13. Establish Chargino Flow:
: a. Charging pumps'- AT LEAST ONE        a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN go to Step 14.
: b. Align charging pump suction to RWST:
: 1) Open charging pump suction valve from RWST:
o LCV-112B
: 2)  Close charging pump suction valve from VCT:
o LCV-112C
: 3) Place RCS Makeup Control switch to STOP
: c. Establish maximum flow:
: 1) Start additional    charging pump(s)
: 2)  Verify speed controllers in MANUAL
: 3)  Open HCV-142 as necessary and adjust charging pump speed controllers for maximum flow 16 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return
    .to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
14ý    Check If    RCS Cooldown Should Be Stopped:
: a. Core exit TCs - LESS THAN          a. Do NOT proceed until core exit REQUIRED TEMPERATURE FROM              TCs less than required TABLE ON STEP 6a                      temperature.
: b. Stop RCS cooldown
: c. Maintain core exit TCs - LESS 15.
THAN REQUIRED TEMPERATUREFROM TABLE ON STEP 6a Check Ruptured SG(s) Pressure            IF pressure continues to decrease I
STABLE OR INCREASING                    to less than 250 psid above the pressure of the intact SG(s) used for cooldown, THEN go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
: 16. Check RCS Subcooling Based On          Go to 2-ECA-3.1, SGTR WITH LOSS Core Exit TCs - GREATER THAN            OF REACTOR COOLANT - SUBCOOLED VALUE OBTAINED FROM TABLE:              RECOVERY DESIRED, Step 1.
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400            72 (103) 401  - 800            56 (69) 801  - 1200          43  (50) 1201  - 2500          39  (46) 17 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20. IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step I:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
TF ACI ONEPCE
........                          REESPO                    NSE NOT OBTAINEDI'
: 17. Depressurize RCS To Minimize Break Flow And Refill PRZR:
: a. Normal PRZR spray    - AVAILABLE      a. Go to Step 18. OBSERVE AND EFFECTIVE                            CAUTIONS AND NOTE PRIOR TO STEP 18.
: b. Spray PRZR with maximum available spray until ANY of the following conditions satisfied:
o BOTH of the following:
: 1) RCS pressure - LESS THAN RUPTURED SG PRESSURE
: 2)  PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
                            - OR -
o PRZR level - GREATER THAN 71% (65% FOR ADVERSE CONTAINMENT)
OR -
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS, PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  -  400            52 (83) 401  -  800            36 (49) 801  -  1200            23 (30) 1201  -  2500            19 (26)
This Step continued on the next page.
18 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs. THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEP        ACTION/EXPECTED RESPONSE              RESPONSE NOT
: c. Close spray valve(s):
: 1) Normal  spray valves                1) Stop ANY RCP(s) required to stop spray flow.              i
: 2) Auxiliary spray valve              2) Isolate auxiliary spray line:
o Energize AND manually close charging line isolation valves:
o MOV-205 (At MCC 26AA)
                                                                  - OR -
o MOV-226 (At MCC 26BB)
AND MOV-227 (At MCC 26AA)
: d. Go to Step 20. OBSERVE CAUTION PRIOR TO STEP 20 CAUTION ft o The PRT may rupture IF a PRZR PORV is used to depressurize the RCS.
This may result in abnormal containment conditions.
o Cycling of the PRZR PORV should be minimized.
ft                                                                              ft NOTE The upper head region may void during RCS depressurization IF RCPs are NOT running. This will result in a rapidly increasing PRZR level.
: 18. DeDressurize RCS UsinQ PRZR PORV To Minimize Break Flow And Refill PRZR:
This Step continued on the next page.
19 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1.      SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: a. PRZR PORV  - AT LEAST ONE        a. Establish auxiliary spray:
AVAILABLE
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2)  Secure all but one charging pump and reduce speed to minimum flow.
: 3)  Close charging line flow control valve:
o HCV-142
: 4)  Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B 6):Open auxiliary spray valve:
o 212
: 7)  Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray established, THEN return to Step 17b.
IF auxiliary spray can NOT be established, THEN go to 2-ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 1.
This Step continued' on the next page.
20 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP    ACTION/EXPECTED RESPONSEi                RESPONSE NOT OBTAINEDI
: b. Open one PRZR PORV until ANY of the following conditions satisfied:
o BOTH of the following:
: 1) RCS pressure - LESS THAN RUPTURED SG PRESSURE
: 2)  PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT).
OR -
o PRZR level - GREATER THAN 71% (65% FOR ADVERSE CONTAINMENT)
                    - OR -
o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400              52 (83) 401 - 800              36 (49) 801 - 1200            23 (30) 1201 - 2500            19 (26)
: c. Close PRZR PORV                      c. Close PORV block valve.
21 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination.Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:
2-E-3                    STEAM GENERATOR TUBE RUPTURE                        REV. 0
: 19. Check RCS Pressure -  INCREASING      Close PRZR PORV block valve.
IF pressure continues to decrease. THE___Nperform the following:
: a. Monitor following conditions for indication of leakage from PRZR PORV:
o PRT temperature.
o PRT pressure.
o PRT level.
o PORV downstream temperature.
o Acoustic monitors.
: b. Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
22 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFI  SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
umber:              Title                                                                      Revision Number:1 2-E-3                                  STEAM GENERATOR TUBE RUPTURE                              REV. 0 t
CAUTION SI MUST BE TERMINATED when termination criteria are satisfied to prevent                              11 IW overfilling the ruptured SG(s).
: 20.      Check If SI Flow Should Be Terminated:
: a. RCS subcooling based on core                  a. Go to 2-ECA-3.1. SGTR WITH exit TCs - GREATER THAN VALUE                        LOSS OF REACTOR COOLANT -
OBTAINED FROM TABLE:                              SUBCOOLED RECOVERY DESIRED, Step 1.
WR RCS PRESSURE              RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400                    52  (83) 401 - 800                    36  (49) 801 - 1200                  23  (30) 1201 - 2500                    19  (26)
: b. Secondary heat sink:                          b. IF neither condition satisfied, THEN go to o Total feed flow to SG(s)                        2-ECA-3.1, SGTR WITH LOSS OF GREATER THAN 400 GPM                            REACTOR COOLANT - SUBCOOLED AVAILABLE                                      RECOVERY DESIRED, Step 1.
                              - OR    -
o Narrow range level in at least one intact SG -
GREATER THAN 10% (27% FOR ADVERSE CONTAINMENT)
: c. RCS pressure    - STABLE OR                  c. Go to 2-ECA-3.1. SGTR WITH INCREASING                                          LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
: d. PRZR level - GREATER THAN 14%                  d. Return to Step 5. OBSERVE (33% FOR ADVERSE CONTAINMENT)                      CAUTION PRIOR TO STEP 5.
23 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-].3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3,'STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:
2-E-3                    STEAM GENERATOR TUBE RUPTURE      REV. 0
: 21. Stop SI Pumps And Place In Auto 24 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SIsystem pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800  801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP      ACTION/EXPECTED RESPONSE IiR            ESPO.NSE NOT OBTAINED.
NOTE ATTACHMENT 1 provides a list  of 480V equipment load ratings.
: 22. Establish Charginq Flow:
: a. Charging pumps  - AT LEAST ONE      a. Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
o  MOV-250A,  MCC 26AA,  A2 o  MOV-250C,  MCC 26AA,  B2 o  MOV-250B,  MCC 26BB,  L3 o  MOV-250D,  MCC 26BB,  M3
                                                                - OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
o  241A o  241B o  241C o  241D
: 2) Start charging pump(s)      as necessary.
: b. Establish charging flow as necessary:
: 1) Verify speed controller in MANUAL
: 2) Adjust charging pump speed 25 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
2-E-3                      STEAM GENERATOR TUBE RUPTURE                      REV. 0
: 23. Verify S1 System Flow Not Required:
: a. RCS subcooling based on core        a. Manually start SI system pumps exit TCs - GREATER THAN VALUE          as necessary. Go to OBTAINED FROM TABLE:                  2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
WR RCS PRESSURE      RCS SUBCOOLING °F (PSIG)      (ADVERSE CONTAINMENI 0 - 400            52 (83) 401 - 800            36 (49) 801 - 1200            23 (30) 1201 - 2500            19 (26)
: b. PRZR level    GREATER THAN 14%      b. Control charging flow to (33% FOR ADVERSE CONTAINMENT)          maintain PRZR level. IF PRZR level can NOT be maintained, THEN manually start SI system pumps as necessary. Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
26 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14%.(33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[  2-E-3 Number:
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                      REV. 0 Revision Number: 1
: 24. Check If Letdown Can Be Established:
: a. PRZR level - GREATER THAN 28%      a. Continue with Step 25. WHEN (47% FOR ADVERSE CONTAINMENT)        level increases to greater than 28% (47% for ADVERSE CONTAINMENT). THEN do Steps 24b through 24d.
: b. CCW pumps  - ANY RUNNING          b. Perform the following:
: 1) Check for adequate power to run one CCW pump:
o Any 480V bus supplying CCW pump energized from offsite power.
                                                                  - OR -
o Load on any running diesel generator less than 1775 KW.
IF NOT, THEN go to Step 25.
: 2) Start one CCW pump.
IF no CCW pump can be started, THEN go to Step 25.
This Step continued on the next page.
27 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs. THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)    .52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return-to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number  :                    STEAM GENERATOR TUBE RUPTURE                Revision Number:
2-E- STAM GNERTORTUBERUPUREREV.                                  0 r            watar n"im s - ANY urarira                        r  Parfnrm tho  fnllnwinn-RUNNING ON NON-ESSENTIAL HEADER
: 1) Check for adequate power to run one service water pump on non-essential header:
o Any 480V bus energized from offsite power.
                                                              -OR  -
o Load on any running diesel generator less than 1725 KW.
IF NOT,  THEN go to Step 24d.
: 2)  Start one service water pump on non-essential header.
: d. Establish letdown:                  d. Establish excess letdown:
: 1) Close letdown orifice stops:        1) Establish CCW flow through excess letdown heat o 200A                                  exchanger by opening CCW o 200B                                  valves:
o 200C o Inlet valves 791,798
: 2) Open letdown line isolation            o Outlet valves 793,796 valves 201 and 202
: 2)  Position excess letdown
: 3) Place letdown flow control            diversion valve 215 to valves 200 A B C switch to              NORMAL to direct flow to REMOTE                                the VCT.
: 4) Open letdownstop valve              3)  Verify seal water return LCV 459 and return to AUTO            containment isolation valve 222 open.
: 5) Place low pressure letdown backpressure controller            4)  Verify excess letdown flow PCV-135 in MANUAL and                  control valve HCV-123 adjust to 75 percent open              closed.
: 6) Open letdown orifice stops          5) Open excess letdown to establish desired flow:              isolation stop valve 213.
o 200A,  75 gpm                    6)  Slowly open HCV-123 to o 200B,  45 gpm                      warmup the excess letdown o 200C. 75 gpm                        heat exchanger.
: 7) Set PCV-135 to maintain            7) Establish desired excess pressure between 225 psig              letdown flow using HCV-123.
and 275 psig
: 8) Maintain ex-cess letdown
: 8) Place PCV-135 in AUTO                  heat exchanger outlet temperature less than 1950F.
28 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP      ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
: 25. Check VCT Makeup Control System:      Adjust controls as necessary.
: a. Makeup set for greater than RCS boron concentration
: b. Place RCS makeup control switch to START
: 26. Check Charging Pump Suction -        Align suction to VCT:
ALIGNED TO VCT
: a. Open charging pump suction valve from VCT and return to AUTO:
o LCV-112C
: b. Close charging pump suction valve from RWST and return to AUTO:
o LCV-112B
                                                                                *r CAUTION Radiation levels and harsh environment conditions should be evaluated
* prior to performing local actions.
: 27. Check If SI Accumulators Should Be Isolated:
: a. RCS pressure - LESS THAN          a. Continue with Step 28. WHEN 1000 PSIG                              RCS pressure less than 1000 psig, THEN perform steps 27b, 27c, 27d and 27e.
This Step continued on the next page.
29 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    -LESS  THAN. VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400  .401-800      801-1200    120072500 RCS SUBCOOLING OF (ADVERSE)    52 (83)    36 (49)      23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP    ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED
: b. Check both the following:            b. Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
o RCS subcooling based on core            SUBCOOLED RECOVERY DESIRED, exit TCs - GREATER THAN                Step 1.
VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 - 400            52 (83) 401 - 800              36 (49) 801 - 1200            23 (30) 1201 - 2500            19 (26) o PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: c. Locally restore power to isolation valves:
0  894A (MCC 26A) 0  894C (MCC 26A) 0  894B (MCC 26B) 0  894D (MCC 26B)
This Step continued on the next page.
30 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: d. Close all SI accumulator        d. Vent any unisolated isolation valves                  accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B
                                          .o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943
: e. Open all SI accumulator isolation valve breakers 31 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs. THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level  decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
2-E-3                                    STEAM GENERATOR TUBE RUPTURE                                REV. 0 Number:
 
==Title:==
Revision Number:
        *  *  *    * *  *  * *  * *  *  *
* a * * * *  * *~  *  * * * *  * * *  * *  *  * .* *  *  *  * -ft  ~*
* i CAUTION
        @t RCS and ruptured SG(s) pressures must be maintained less than the ruptured SG(s) atmospheric steam dump setpoint.                                                          *t
: 28.        Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondary Leakane:
: a. Perform appropriate action(s) from table:
RUPTURED SG(s)                INCREASING            DECREASING            OFFSCALE LEVEL                                                          HIGH PRZR LEVEL o    Increase RCS          Increase RCS      o    Increase RCS LESS THAN 28%                  Makeup Flow            Makeup Flow            Makeup Flow (47% FOR ADVERSE CONTAINMENT)                o    Depressurize                              o  Maintain RCS And RCS Using                                    Ruptured SG(s)
Step 28b                                      Pressures Equal BETWEEN 28% (47%                Depressurize          Turn On                Maintain RCS And FOR ADVERSE                    RCS Using              PRZR                    Ruptured SG(s)
CONTAINMENT)                    Step 28b              Heaters                Pressures Equal AND 50%
BETWEEN                    o  Depressurize          Turn On                Maintain RCS And 50% And                        RCS Using              PRZR                    Ruptured SG(s) 71% (65%                        Step 28b              Heaters                Pressures Equal FOR ADVERSE CONTAINMENT)                o  Decrease RCS Makeup Flow GREATER THAN 71%                Decrease RCS          Turn On                Maintain RCS And (65% FOR ADVERSE              Makeup Flow            PRZR                    Ruptured SG(s)
CONTAINMENT)                                          Heaters                Pressures Equal This Step continued on the next page.
32 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step I.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[    2-E-3 S
Number:
STEAM GENERATOR TUBE RUPTURE STitle:
REV. 0 Revision Number:
STP    ACTION/EXPECTED RESPONSE          IRESPONSE NOT OBTAINED
: b. Use normal PRZR spray per        b. IF letdown is in service,  THEN Step 28a                              use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2)  Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4)  Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray can NOT be used, THEN Use one PRZR PORV.
33 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination.Step 20. IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
029. Check If Containment Spray Should Be Stopped:
: a. Spray pumps - RUNNING              a. Go to Step 30.
: b. Containment pressure - LESS        b. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig, THEN do Steps 29c through 29f.
: 2) Continue with Step 30.
OBSERVE CAUTION PRIOR TO STEP 30.
: c. One at a. time, depress containment spray reset pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: d. Containment area radiation        d. Perform the following:
NORMAL
: 1) WHEN containment spray has o R-25,  R-26                            been in service for 3.5 hours, THEN do Steps o R-41,  R-42                            29e and 29f.
o R-2,  R-7                          2) Go to Step 30. OBSERVE CAUTION PRIOR TO STEP 30.
: e. Stop containment spray pumps and place in AUTO
: f. Close containment spray pump discharge valves:
o MOV-866A o MOV-866B o MOV-866C o MOV-866D 34 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1.      SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED,.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG-pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
 
lNumber:
2-E-3
 
==Title:==
STEAM GENERATOR TUBE RUPTURE ACTION/EXPECTED RESNumE              R  PONSE NOT OBTAfNEDI ReviREV. Nu 0 I NOTE ATTACHMENT 1 provides a list    of 480V equipment load ratings.
@30. Check Status Of 480V Busses:
: a. All 480V busses -  ENERGIZED BY    a. Try to restore  offsite power OFFSITE POWER                          to 480V busses  per 2-AOP-138KV-1,  LOSS OF POWER TO 6.9KV BUS 5  AND/OR 6.
IF necessary, THEN manually load the following equipment on the 480V busses:
o MCCs:
o MCC 24A o MCC 27A o MCC 29A 0 Direct Support Facilities personnel to align lighting to PAB LIGHTING TRANSFORMER 23 ALTERNATE POWER SUPPLY TO TSC bus per 2-SOP-27.1.5.
480 VOLT SYSTEM, as necessary.
o Start one cable tunnel exhaust fan.
o IF load on 22 or 23 diesel generator less than 1875 KW, THEN verify radiation monitors R-43/R-44 in service and start PAB ventilation fans.
o Locally start one 480V switchgear room exhaust fan.
o IF necessary, defeat fan interlock using bypass key.
This Step continued on the next page.
35 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based, on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Go to Step 31.
: b. Manually load the following equipment on the 480V busses:
o All MCCs as necessary except.
MCC 28 and MCC 28A o All lighting as necessary o One cable tunnel exhaust fan o Verify radiation monitors R-43/R-44 in service and start PAB ventilation fans o Locally start one 480V switchgear room exhaust fan o IF necessary, defeat fan interlock using bypass key.
: 31. Check If Diesel Generators Should Be Stopped:
: a. Verify 480V busses - ENERGIZED. a. Try to restore offsite.power BY OFFSITE POWER                    to 480V busses per 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
: b. Locally stop any unloaded diesel generator(s) and place in standby
: 32. Minimize Secondary System Contamination:
o Isolate boiler blowdown o Isolate condenser overboarding o Isolate makeup to CST
: 33. Turn On PRZR Heaters As Necessary To Saturate PRZR Water At RuDtured SG(s) Pressure 36 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs. THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft,    switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[1Number:
2-E-3
 
==Title:==
STEAM GENERATOR TUBE RUPTURE                      REV. 0 Revision Number:
: 34. Check RCP Cooling - NORMAL:            IF all seal cooling has NOT been lost, THEN establish normal
: a. RCP CCW system alarms - CLEARED      cooling to RCPs. Refer to the following as necessary:
: b. RCP seal injection flow -
BETWEEN 6 GPM AND 10 GPM PER        o 2-SOP-1.3, REACTOR COOLANT PUMP RCP                                    STARTUP AND SHUTDOWN.
o 2-SOP-3.1. CHARGING, SEAL WATER, AND LETDOWN CONTROL.
: 35. Check If RCP Seal Return Flow Should Be Established:
: a. RCP thermal barrier AP              a. Go to Step 36. OBSERVE POSITIVE                                CAUTION AND NOTE PRIOR TO STEP 36.
: b. CCW pumps    - AT LEAST ONE          b. Go to Step 36. OBSERVE RUNNING                                  CAUTION AND NOTE PRIOR TO STEP 36.
: c. Establish seal    return flow:
: 1) Check No. 1 seal return              1) Manually open valves.
valves - OPEN:
o  261A o  261B o  261C o  261D
: 2)  Open seal return containment isolation valve:
o MOV-222 37 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1.
SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based. on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
 
i CAUTION
* If RCP seal cooling had previously been lost, the affected RCP(s)                    should
* NOT be started prior to a status evaluation.                                                      t NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
036.      Check RCP Status:
: a. 24 RCP    RUNNING                    a. Start RCP(s) to provide normal PRZR spray as follows:
: 1) IF RVLIS natural circulation range indication less than 100%,
THEN perform the following:
o Increase PRZR level to greater than 62% (81% FOR ADVERSE CONTAINMENT).
o Increase RCS subcooling based on core exit TCs to greater than value obtained from table:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400              74  (105) 401 - 800                58  (71) 801 - 1200              45  (52) 1201 - 2500              41  (48)
This Step continued on the next page.
38 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20. IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT.)
o RCS subcooling based on core exit TCs    -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreas~ing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3.
TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
S 2-E-3                    STEAM GENERATOR TUBE RUPTURE                    REV. 0 SNumber:
 
==Title:==
Revision          Number:
o Use PRZR heaters, as necessary to saturate the pressurizer water.
: 2) IF containment sump level less than 42'10 112- AND containment conditions NOT adverse, THEN:
a)  Reset MCC 28 and MCC 28A.
b)  Establish conditions for starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
c)  Start 24 RCP.
d)  IF 24 RCP can NOT be started, THEN start RCP(s) as required to provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer to ATTACHMENT 2 to verify naturalcirculation.
IF natural circulation NOT verified, THEN increase dumping steam.
: b. Stop all RCP(s) NOT required to supply ONE PRZR spray path
: 37. Check If Source Ranqe Detectors Should Be Energized:
: a. Check intermediate range flux    a. Continue with Step 38. WHEN
          - LESS THAN IE-10 AMPS              flux less than IE-10 amps, THEN do Steps 37b and 37c.
: b. Verify source range detectors    b. Manually energize source range
          - ENERGIZED                        detectors.
: c. Transfer nuclear recorders to source range scale 39 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THANVALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown.,IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
SFTEP - ACTION/EXPECTED RESPONSEI              ,RESPONSE NOT OBTAINEDI
: 38. Shut Down Unnecessary  Plant Equipment:
o Circulating water pumps not requi red o Service water pumps not required o Evaluate secondary plant status and shut down equipment as required CAUTION An offsite dose evaluation should be completed prior to using 2-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN or 2-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP.
: 39. Go To Appropriate Post-SGTR Cooldown Method:
o Go to 2-ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step I
                    - OR -
o Go to 2-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 1
                    - OR -
o Go to 2-ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP.
Step 1
                                        - END-40 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14%.(33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE; Step 1.
 
ATTACHMENT 1                (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the following table to determine 480V eguipment load ratinqs:
121 DG          22DG              23 DG EQUIPMENT            BUS 5A      BUS 2A    BUS 3A    BUS 6A 21 SERVICE WATER PUMP      282 KW 22 SERVICE WATER PUMP                  282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP      282 KW 25 SERVICE WATER PUMP                  282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS                                        277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                      485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                        384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT        250 KW 22 FAN COOLER UNIT        250 KW 23 FAN COOLER UNIT                      250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                          250 KW 21 SI PUMP                316 KW 22 SI PUMP                              316 KW    316 KW 23 SI PUMP                                                    345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP 21 RHR PUMP 22 RHR PUMP 303 KW 350 KW 303 KW I
21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                              150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                                299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW                228 KW 23 CCW PUMP 21 LIGHTING TRAN! SFORMER              150 KW (N)            150 KW (E) 22 LIGHTING TRAN SFORMER                          225 KW 23 LIGHTING TRAN: SFORMER  225 KW TURBINE AUX OIL PUMP                                          112 KW STATION AIR COMPIRESSOR    93 KW
                                    -END-41 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20, IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1.1 SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based, on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23.(30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft. go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
LRevision                              Number:
2-E-3                        STEAM GENERATOR TUBE RUPTURE                          REV. 0
                                        .ATTACHMENT 2                  (Attachment page 1 of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The following conditions support or indicate natural            circulation flow:
o RCS subcooling based on core exit TCs          - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400              52  (83) 401  - 800              36  (49) 801  - 1200            23  (30) 1201  - 2500            19  (26) o SG pressures  - STABLE OR DECREASING o RCS hot leg temperatures      - STABLE OR DECREASING o Core exit TCs - STABLE OR DECREASING o RCS cold leg temperatures      - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                              -END-42 of 42
 
FOLDOUT PAGE FOR 2-E-3
: 1. SI REINITIATION CRITERIA:
Following SI Termination Step 20. IF EITHER condition listed below occurs, THEN manually start SI system pumps AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.
Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52.(83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. COLD LEG RECIRCULATION CRITERION:
IF RWST level decreases to less than 9.24 ft, go to 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Step 1.
: 4. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 5. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Procedure Use Is:    Control Copy:
Enter                    El Continuous Nuclear Northeast        O3 Reference        Effective Date: *4 7
[3 Information 2-ES-3.1, Revision: 0 POST-SGTR COC                      .USING BACKFILL Approved By:
i .
Procec6(e Sponsor, RPO/ D Team P Procedure Owner PARTIAL REVISION
 
A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a steam generator tube rupture. This recovery method depressurizes the ruptured SG(s) by draining it through the ruptured SG tube into the RCS.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is  entered from:
: 1) 2-E-3, STEAM GENERATOR TUBE RUPTURE,  Step 39, if plant staff selects backfill method.
: 2)  2-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 10, when blowdown is not available and plant staff selects backfill method.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                          -OR-o Containment pressure greater than 4 psig.
1 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to,2-E-2, FAULTED*STEAM GENERATOR ISOLATION.
Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[ 2-ES-3.1 Number:                  Tile:
POST-SGTR COOLDOWN USING BACKFILL                                          REV. 0 Revision Number:
* CAUTION
* Inadvertent criticality may occur following any natural circulation cooldown if the first RCP started is in the ruptured loop.
: 1.          Turn On PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured SG(s) Pressure ft CAUTION
        ¢t If RCP seal cooling had previously been lost, the affected RCP(s)                                      should            *z NOT be started prior to a status evaluation.
ft  ft  ft  ft ft ft ft ft ft ft ft  *
* ft ft ft ft ft  ft  ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft
* ft ft ft  ft    ft NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
(D 2.            Check RCP Status:
This Step continued on the next page.
2 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
[ 2-ES-3.1 Number:
SFTEP
 
==Title:==
POST-SGTR COOLDOWN USING BACKFILL iACTION/EXPECTED RESPONSE    i      iRESPONSE NOT OBTAINEDI REV. 0 IRevision Number: 1
: a. 24 RCP - RUNNING                  a. Start RCP(s) to provide normal PRZR spray as follows:
: 1) IF RVLIS natural circulation range indication less than 100%,
THEN perform the following:
o Increase PRZR level to greater than 62% (81% FOR ADVERSE CONTAINMENT).
o Increase RCS subcooling based on core exit TCs to greater than value obtained from table:
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0  -  400          74  (105) 401  -  800          58  (71) 801  -  1200          45  (52) 1201  -  2500          41  (48) o Use PRZR heaters, as necessary to saturate the pressurizer water.
This Step continued on the next page.
3 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system.
pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE    PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level, decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step ,I,.
 
[ 2-ES-3.1 Number:        Tilte:
POST-SGTR COOLDOWN USING BACKFILL                    REV. 0 Revision Number: 1
: 2) IF containment sump level less than 42'10 1/2" AND containment conditions NOT adverse. THEN:
a)  Reset MCC 28 and MCC 28A.
b) Establish conditions for starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
c) Start 24 RCP.
d)  IF 24 RCP can NOT be started, THEN start RCP(s) as required to.
provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer to ATTACHMENT 1 to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam.
: b. Stop all RCP(s) NOT required to supply ONE PRZR spray path 4 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as-necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED,. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED . I FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFI SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
*    *  *    *  *  * *  *  *  * *  *  *  * *  *  *  *  * * *  * *  * * * * * * * * * * *
* a * * * *
¢t CAUTION                                        *
* Radiation levels and harsh environment conditions should be evaluated                          *
"    prior to performing local actions.                                                            *
: 3.        Check If SI Accumulators Should Be Isolated:
: a. Check both the following:                      a. Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
o RCS subcooling based on core                      SUBCOOLED RECOVERY DESIRED.
exit TCs - GREATER THAN                        Step 1.
VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE              RCS SUBCOOLING OF (PSIG)            (ADVERSE CONTAINMENT) 0  - 400                52    (83) 401  - 800                36    (49) 801  - 1200                23  (30) 1201  - 2500                19  (26) o PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: b. Locally restore power to isolation valves:
0  894A  (MCC  26A) 0  894C  (MCC  26A) 0  894B  (MCC    26B) 0  894D  (MCC    26B)
This Step continued on the next page.
5 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500, RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLYSWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:
2-ES-3.1                  POST-SGTR COOLDOWN USING BACKFILL                      REV. 0 STE        ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED I
: c. Close all SI accumulator            c. Vent any unisolated-isolation valves                        accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN consult the TSC to determine contingency actions.
: d. Open all SI accumulator isolation, valve breakers 6 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
FNumber:
2-ES-3.1
 
==Title:==
POST-SGTR COOLDOWN USING BACKFILL                  REV. 0 Revision Number: 1
: 4. Verify Adequate Shutdown Margin:
: a. Sample ruptured SG(s)
: b. Sample RCS
: c. Shutdown margin from graphs        c. Borate as necessary.
book - ADEQUATE
: 5. Check Intact SG Levels:
: a. Narrow range level - GREATER      a. Maintain total feed flow THAN 10% (27% FOR ADVERSE            greater than 400 gpm until CONTAINMENT)                          narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain      b. IF narrow range level in any narrow range level, between 14%      intact SG continues to (27% FOR ADVERSE CONTAINMENT)        increase in an uncontrolled and 50%                              manner, THEN stop RCS cooldown AND go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
7 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start SI system.
pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST-level, decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number
 
==Title:==
[Revision Number:
2 -ES-3.1                  POST-SGTR COOLDOWN USING BACKFILL                      REV. 0 STP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should NOT be delayed.
: 6. Initiate RCS Cooldown To Cold Shutdown:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN 1O0°F/HR
: b. Use RHR System if  in service
: c. Dump steam to condenser from        c. Manually or locally dump steam intact SG(s):                            from intact SG(s):
: 1) Check condenser - AVAILABLE          o Use SG atmospheric steam dump:
: 2) Place steam dump controller switch to manual and adjust            o Refer to 2-SOP-ESP-O01, for zero output.                          LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3) Transfer condenser steam                  for local operation as dump to pressure control                  necessary.
mode and adjust manual setpoint as necessary.                          -  OR -
o Use turbine-driven AFW pump.
IF no intact SG available and RHR system NOT in service, THEN perform the following:
o Use faulted SG.
                                                                    -OR  -
o Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
8 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level    CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA; UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
SFTEP    ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI
: 7. Check Ruptured SG(s) Narrow RanQe      Refill ruptured SG to 73% (60%
Level    GREATER THAN 14% (27% FOR    FOR ADVERSECONTAINMENT) using ADVERSE CONTAINMENT)                  feed flow.      IF any of the following conditions occur, THEN stop feed flow to ruptured SG:
o Ruptured SG pressure decreases in an uncontrolled manner.
                                                          - OR -
o Ruptured SG pressure increases to 1000 psig.
                                                          - OR -
o Ruptured SG pressure decreases to 430 psig AN{D ruptured SG level greater than 10% (27% FOR ADVERSE CONTAINMENT).
: 8. Control Charging And Letdown Flow To Maintain PRZR Level:
: a. PRZR level - GREATER THAN 28%      a. Increase charging flow as (47% FOR ADVERSECONTAINMENT)            necessary. Go to Step 9.
OBSERVE NOTES PRIOR TO STEP 9.
: b. PRZR level - LESS THAN 71%        b. Decrease charging flow as (65% FOR ADVERSE CONTAINMENT)            necessary. Go to Step 10.
9 of 14
 
FOLDOUT PAGE FOR 2-ES-3.l
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system.
pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200 1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEP        ACTION/EXPECTED RESPONSE IIRESPONSE            NOT OBTAINEDI NOTE o The upper head region may void during RCS'depressurization if RCPs are NOT running. This will result in a rapidly increasing PRZR level.
o RCS depressurization may be stopped when RCS pressure decreases to less than 370 psig (280 psig FOR ADVERSE CONTAINMENT) to maintain adequate RCP number 1 seal differential pressure.
o RCS depressurization rate shoud be controlled to maintain PRZR level stable.
: 9. Depressurize RCS To Backfill  From Ruptured SG(s):
: a. Use normal PRZR spray              a. IF letdown is in service,  THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212 This Step continued on the next page.
10 of 14
 
FOLDOUT PAGE FOR 2-ES-3-1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEPACTION/EXPECTED RESPONSE                RSOS OTOTIE
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
: b. Turn on PRZR heaters as necessary
: c. Maintain RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE    RCS SUBCOOLING OF (PSIG)    (ADVERSE CONTAINMENT) 0  - 400          52  (83) 401  - 800          36  (49) 801  - 1200        23  (30) 1201  -  2500        19  (26)
: d. Maintain PRZR level  - STABLE 11 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system.
pumps as necessary AND.go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
NOTE 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,    should be referred to for plant alignment during cooldown.
: 10. Check If RHR System Can Be Placed In Service:
: a. Check both the following:            a. Go to Step 11.
o RCS temperature - LESS THAN 3500F o RCS pressure - LESS THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Place RHR System in service per 2-SOP-4.2.1. RESIDUAL HEAT REMOVAL SYSTEM 011. Check If  RCPs Must Be StoDDed:
: a. Check the following:                a. IF neither condition satisfied, THEN go to Step 12.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                    - OR -
o Number 1 seal return flow -
LESS THAN 0.2 GPM
: b. Stop affected RCP(s)
: 12. Check RCS Temperatures  -  LESS        Return to Step 4.
THAN 200°F 12 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 13. Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions
: b. Consult TSC
                                  -END-13 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system.
pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing
    *in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
ATTACHMENT 1              (Attachment page I of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The followinQ conditions suDDort or indicate natural circulation fl ow:
o RC.S subcooling based on core exit TCs        - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 -. 400            52 (83) 401 - 800                36 (49) 801 - 1200              23 (30) 1201 - 2500              19 (26) o SG pressures  -  STABLE OR DECREASING o RCS hot leg temperatures      - STABLE OR DECREASING o Core exit TCs    -  STABLE OR DECREASING o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                      .END-14 of 14
 
FOLDOUT PAGE FOR 2-ES-3.1
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Procedure Use Is: Control Copy:
SEntergy                      lZ Continuous Nuclear  Northeast
            %tie              O3 Reference      Effective Date: z/_/__
Tea,,.
o3 Information 1A Cell
                        .2-ES-3.2, Revision: 0 POST-SGTR COOLDOLN-USING BLOWDOWN Approved By:
Procedure Sponsor, RPO/
Team P Procedure Owner PARTIAL REVISION
 
[ 2-ES-3.2 Number:
 
==Title:==
POST-SGTR COOLDOWN USING BLOWDOWN                  REV. 0 Revision Number:
A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a steam generator tube rupture. This recovery method depressurizes the ruptured SG(s) by draining it using SG blowdown.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is    entered from 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 39,    if plant staff selects the blowdown method.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                                - OR -
o Containment pressure greater than 4 psig.
1 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
a  *    *  * * *  * *  *  *
* a * *  *  *
* a  *  *  * *  * *  *  *
* a *  *
* a a *
* a
* a a
* CAUTION
* An offsite dose evaluation should be completed prior to using this
"    procedure.
Q
: 1.        Turn On PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured SG(s) Pressure
* CAUTION If RCP sea] cooling had previously been lost, the affected RCP(s)                        should NOT be started prior to a status evaluation.
a
* a  a a  a .  *  *
* a a a  a  a  a a *
* a a  a a  a  a a  a *
* a  *
* a  *
* a  a a a*
NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
: 2.        Check RCP Status:
I This Step continued on the next page.
2 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500
-RCS SUBCOOLING °F (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STP        ACTION/EXPECTED RESPONSE IIRESPONSE              NOT OBTAINEDI
: a. 24 RCP.-  RUNNING                  a. Start RCP(s) to provide normal PRZR spray as follows:
: 1) IF RVLIS natural circulation range indication less than 100%.
THEN perform the following:
o Increase PRZR level to greater than 62% (81% FOR ADVERSE CONTAINMENT).
o Increase RCS subcooling based on core exit TCs to greater than value obtained from table:
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 - 400              74 (105) 401 - 800              58 (71) 801 - 1200            45 (52) 1201 - 2500            41 (48) o Use PRZR heaters, as necessary to saturate the pressurizer water.
This Step continue'd on the next page.
3 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 2) IF containment sump level less than 42'10 1/2" AND containment conditions NOT adverse. THEN:
a)  Reset MCC 28 and MCC 28A.
b) Establish conditions for starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
c)  Start 24 RCP.
d)  IF 24 RCP can NOT be started, THEN start RCP(s) as required to provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer to ATTACHMENT I to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam.
: b. Stop all RCP(s) NOT required to supply ONE PRZR spray path 4 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM-TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY IWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
CAUTION Radiation levels and harsh environment conditions should be evaluated prior to performing local actions.
: 3.      Check If SI Accumulators Should Be Isolated:
: a. Check both the following:                    a. Go to 2-ECA-3.1, SGTR WITH LOSS O.F REACTOR COOLANT -
o RCS subcooling based on core                  SUBCOOLED RECOVERY DESIRED, exit TCs - GREATER THAN                        Step 1.
VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE            RCS SUBCOOLING OF (PSIG)          (ADVERSE CONTAINMENT) 0 - 400                  52  (83) 401 - 800                  36  (49) 801 - 1200                23  (30) 1201 - 2500                19  (26) o PRZR level - GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: b. Locally restore power to isolation valves:
0 894A    (MCC  26A) 0 894C    (MCC  26A) 0 894B    (MCC  26B) 0 894D    (MCC  26B)
This Step continued on the next page.
5 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. A-FW-SUPPLY SWITCHOVER CRITERION:.
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: c. Close all SI accumulator        c. Vent any unisolated isolation valves                    accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o .1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN consult the TSC to determine contingency actions.
: d. Open all SI accumulator isolation valve breakers 6 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step I:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. KFW-SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
: 4. Verify Adeauate Shutdown Margin:
: a. Sample ruptured SG(s)
: b. Sample RCS
: c. Shutdown margin from graphs      c. Borate as necessary.
book - ADEQUATE
: 5. Check Intact SG Levels:
: a. Narrow range level - GREATER      a. Maintain total feed flow THAN 10% (27% FOR ADVERSE            greater than 400 gpm until CONTAINMENT)                        narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain    b. IF narrow range level in any narrow range level between 14%      intact SG continues to (27% FOR ADVERSE CONTAINMENT)        increase in an uncontrolled and 50%                              manner, THEN stop RCS cooldown AND go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
7 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. .. AFW-FSUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
NOTE Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should NOT be delayed.
: 6. Initiate RCS Cooldown To 350°F:
: a. 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 SG(s):                        from intact SG(s):
: 1) Check condenser  - AVAILABLE      o Use SG atmospheric steam dump:
: 2) Place steam dump controller switch to manual and adjust          o Refer to 2-SOP-ESP-O01, for zero output.                        LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3) Transfer condenser steam                for local operation as dump to pressure control                necessary.
mode and adjust manual setpoint as necessary.                        - OR -
o Use turbine-driven AFW pump.
IF no intact SG available, THEN perform the following:
o Use faulted SG.
                                                          - OR -
o Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
8 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. -AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
          ** * * *  *
* ft  * *
* I* *  *
* t  ft ft t ft ft    *
* f f ft ft t t f CAUTION i                                                                                          t RCS and ruptured SG(s) pressures must be maintained less than the t
ruptured SG(s) atmospheric steam dump setpoint.
: 7. Control RCS Pressure And Charqinq Flow To Minimize RCS-To-Secondarv LeakaQe:
: a. Perform appropriate action(s) from table:
RUPTURED SG(s)          INCREASING          DECREASING            OFFSCALE LEVEL                                                  HIGH PRZR LEVEL]
o Increase RCS        Increase RCS    o    Increase RCS LESS THAN 28%            Makeup Flow          Makeup Flow          Makeup Flow (47% FOR ADVERSE CONTAINMENT)          o Depressurize                        o    Maintain RCS And RCS Using                                  Ruptured SG(s)
Step 7b                                    Pressures Equal BETWEEN 28% (47%        Depressurize        Turn On              Maintain RCS And FOR ADVERSE              RCS Using            PRZR                  Ruptured SG(s)
CONTAINMENT)            Step 7b              Heaters              Pressures Equal AND 50%
BETWEEN                o Depressurize        Turn On              Maintain RCS And 50%    And              RCS Using            PRZR                  Ruptured SG(s) 71% (65%                Step 7b              Heaters              Pressures Equal FOR ADVERSE CONTAINMENT)          o Decrease RCS Makeup Flow GREATER THAN 71%        Decrease RCS        Turn On              Maintain RCS And (65% FOR ADVERSE        Makeup Flow          PRZR                  Ruptured SG(s)
CONTAINMENT)                                  Heaters              Pressures Equal This Step continued on the next page.
9 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN.VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW-SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: b. Use normal PRZR spray per        b. IF letdown is in service,  THEN Step 7a                            use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
10 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52,(83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing' in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AIW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
NOTE 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,      should be referred to for plant alignment during cooldown.
: 8. Check If  RCS Cooldown Should Be Stopped:
: a. RCS temperatures  - LESS THAN      a. Return to Step 4.
3500 F
: b. Stop RCS cooldown
: c. Maintain RCS Temperatures  -
LESS THAN 350°F
: 9. Check Ruptured SG(s) Narrow Range      Refill ruptured SG to 73% (60%
Level - GREATER THAN 14% (27% FOR      FOR ADVERSE CONTAINMENT) using ADVERSE CONTAINMENT)                  feed flow. IF any of the following conditions occur, THEN stop feed flow to ruptured SG:
o Ruptured SG pressure decreases in an uncontrolled manner.
OR -
o Ruptured SG pressure increases to 1000 psig.
                                                          - OR -
o Ruptured SG pressure decreases to 430 psig AND ruptured SG level greater than 10% (27% FOR ADVERSE CONTAINMENT).
11 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, goto 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE., Step 1.
 
STEP      ACTION/EXPECTED RESPONSE                REPNE    O  BTIE NOTE Blowdown from ruptured SG(s) may be stopped when RCS pressure decreases to less than 370 psig (280 psig FOR ADVERSE CONTAINMENT) to maintain adequate RCP number 1 seal differential pressure.
: 10. Establish Blowdown From Ruptured        Go to alternate post-SGTR cooldown procedure, 2-ES-3.1, POST-SGTR COOLDOWN USING
: a. Refer to 2-SOP-7.2, SECONDARY      BACKFILL, Step 1, or 2-ES-3.3.
BOILER BLOWDOWN PURIFICATION        POST-SGTR COOLDOWN USING STEAM SYSTEM, as necessary                DUMP, Step 1.
011. Control Charging And Letdown Flow To Maintain PRZR Level:
: a. PRZR level - GREATER THAN 28%      a. Increase charging flow as (47% FOR ADVERSE CONTAINMENT)          necessary. Go to Step 12.
OBSERVE NOTE PRIOR TO STEP 12.
: b. PRZR level - LESS THAN 71%          b. Decrease charging flow as (65% FOR ADVERSE CONTAINMENT)          necessary. Go to Step 13.
12 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown. IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
NOTE The upper head region may void during RCS depressurization if RCPs are NOT running. This will result in a rapidly increasing PRZR level.
: 12. DeDressurize RCS To Minimize RCS-To-Secondary Leakace:
: a. Use normal PRZR spray            a. IF letdown is in service,  THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
This Step continued on the next page.
13 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step I.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEPH ACTION/EXPECTED RESPONSEt                    RESPONSE NOT OBTAINEDl IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
: b. Turn on PRZR heaters as necessary
: c. Maintain RCS pressure at ruptured SG(s) pressure
: d. Maintain RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE          RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  - 400            52 (83) 401  -  800            36 (49) 801  -  1200            23 (30) 1201  -  2500            19 (26) 013. Check If      RCPs Must Be Stopped:
: a. Check the following:                  a. IF neither condition satisfied, THEN go to Step 14.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                      - OR -
o Number 1 seal return flow -
LESS THAN 0.2 GPM
: b. Stop affected RCP(s) 14 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
t 2-ES-3.2 Number:      ITitle:
POST-SGTR COOLDOWN USING BLOWDOWN              REV. 0 Revision Number: 1
: 14. Check If RHR System Can Be Placed In Service:
: a. Check both the following:          a. Return to Step 9.
o RCS temperature - LESS THAN 350OF o RCS pressure -LESS  THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Place RHR System in service per 2-SOP-4.2.1, RESIDUAL HEAT REMOVAL SYSTEM 15 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
: 15. Continue RCS Cooldown To Cold Shutdown:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN IO0°F/HR
: b. Use RHR System
: c. Dump steam to condenser from      c. Manually or locally dump steam intact SG(s)                        from intact SG(s):
o Use SG atmospheric steam dump:
o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
OR -
o Use turbine-driven AFW pump.
IF no intact SG available and RHR system NOT in service, THEN perform the following:
o Use faulted SG.
                                                      - OR -
o Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
: 16. Check RCS Temperatures - LESS        Return to Step 9.
THAN 200OF 16 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG          J0-400      401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 17. Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions
: b. Consult TSC
                                  -END-17 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
I.F EITHER condition listed below occurs, manually start.SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft,  switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
ATTACHMENT 1                (Attachment ,page 1 of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The following conditions support or indicate natural circulation flow:
o RCS subcooling based on core exit TCs      -  GREATER THAN VALUE OBTAINED FROM TABLE:
WR. RCS PRESSURE      RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT)
O  - 400              52 (83) 401  - 800              36 (49) 801  - 1200            23 (30) 1201    2500            19 (26) o SG pressures - STABLE OR DECREASING o RCS hot leg temperatures    -  STABLE OR DECREASING o Core exit TCs - STABLE OR DECREASING o RCS cold leg temperatures    - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                      -END-18 of 18
 
FOLDOUT PAGE FOR 2-ES-3.2
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AF W SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Procedure Use Is:    Control Copy:
SiPEntergy El Continuous Nuclear Northeast      o Reference          Effective Date: A/i 7 o Information 2-ES-3.3, Revision: 0 POST-SGTR                              3 STEAM DUMP Approved By:
Procedurqponsor, RPO/
Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number: 1 2-ES-3.3                  POST-SGTR COOLDOWN USING STEAM DUMP                  REV. 0 A. PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a steam generator tube rupture.      This recovery method depressurizes the ruptured SG(s) by dumping steam.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is    entered from:
: 1) 2-E-3, STEAM GENERATOR TUBE RUPTURE,    Step 39, if  plant staff selects steam dump method.
: 2)  2-ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, Step 10, when blowdown is not available and plant staff selects steam dump method.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if    either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
OR o Containment pressure greater than 4 psig.
1 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
 
  *  *  *  *  * * * *  * *
* ft * * * * * *  *  *  *  *  * * *  * * *  *  *  *
* ft * *  * * *  *
* CAUTION o Steam should NOT be released from any ruptured SG if                water may exist in
* its steamline.
* o An offsite dose evaluation should be completed prior to using this
* procedure.
: 1.        Turn On PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured SG(s) Pressure ft  *  *  * * * *  * *  * * *  * * * * *  *  *
* ft  * *
* ft *
* ft
* ft * *  * * *  * *  * *
* CAUTION t
If RCP seal cooling had previously been lost, the affected RCP(s)                    should NOT be started prior to a status evaluation.
NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional. RCPs to provide adequate spray flow.
: 2.        Check RCP Status:
This Step continued on the next page.
2 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go *to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT (
: a. 24 RCP - RUNNING                a. Start RCP(s) to provide normal PRZR spray as follows:
: 1) IF RVLIS natural circulation range indication less than 100%,
THEN perform the following:
o Increase PRZR level to greater than 62% (81% FOR ADVERSE CONTAINMENT).
o Increase RCS subcooling based on core exit TCs to greater than value obtained from table:
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 - 400            74  (105) 401 - 800            58  (71) 801 - 1200            45 (52) 1201 - 2500            41 (48) o Use PRZR heaters, as necessary to saturate the pressurizer water.
This Step continued on the next page.
3 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
 
STP    ACTION/EXPECTED RESPONSE            ESPONSE NOT OBTAINED Rli
: 2) IF containment sump level less than 42'10 1/2" AND containment conditions NOT adverse, THEN:
a)  Reset MCC 28 and MCC 28A.
b) Establish conditions for starting an RCP per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION.
c) Start 24 RCP.
d)  IF 24 RCP can NOT be started, THEN start RCP(s) as required to provide PRZR spray flow.
IF an RCP can NOT be started, THEN refer.to ATTACHMENT 1 to verify natural circulation.
IF natural circulation NOT verified, THEN increase dumping steam.
: b. Stop all RCP(s) NOT required to supply ONE PRZR spray path 4 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system' pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400 RCS SUBCOOLING OF (ADVERSE)  52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
CAUTION
"    Radiation levels and harsh environment conditions should be evaluated
"  prior to performing local actions.
                                                                                                    *W
: 3.      Check If SI Accumulators Should Be Isolated:
: a. Check both the following:                    a. Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
o RCS subcooling based on core                    SUBCOOLED RECOVERY DESIRED, exit TCs - GREATER THAN                        Step 1.
VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE            RCS SUBCOOLING OF .
(PSIG)          (ADVERSE CONTAINMENT) 0 - 400                52    (83) 401 - 800                  36    (49) 801 - 1200                23    (30) 1201 - 2500                  19  (26) o PRZR level        GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT)
: b. Locally restore power to isolation valves:
0 894A    (MCC  26A) 0  894C  (MCC  26A) 0  894B  (MCC  26B) 0 894D    (MCC  26B)
This Step continued on the next page.
5 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: c. Close all SI accumulator        c. Vent any unisolated isolation valves                    accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN consult the TSC to determine contingency actions.
: d. Open all SI accumulator isolation valve breakers 6 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o.PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. '--A-AW-SI9PVL-SWrIO-VER -CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG.level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3,. STEAM GENERATOR TUBE RUPTURE, Step 1.
: 4. Verify Adeauate Shutdown Margin:
: a. Sample ruptured SG(s)
: b. Sample RCS
: c. Shutdown margin from graphs        c. Borate as necessary.
book - ADEQUATE
: 5. Check Intact SG Levels:
: a. Narrow range level - GREATER      a. Maintain total feed flow THAN 10% (27% FOR ADVERSE            greater than 400 gpm until CONTAINMENT)                          narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain      b. IF narrow range level in any narrow range level between 14%        intact SG continues to (27% FOR ADVERSE CONTAINMENT)        increase in an uncontrolled and 50%                              manner, THEN stop RCS cooldown AND go to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
7 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1.      SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT    SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)  19 (26)
: 2.      SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3.    '-AW'SUPPLY-SWITCHOVER    CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4.      MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
FNumber:
2-ES-3.3 STEP
 
==Title:==
POST-SGTR COOLDOWN USING STEAM DUMP ACTON/EPECED RSPOSE                      ESPOSE    OT OTAIEDI REV. 0 Revision Number: 1 NOTE Since ruptured SG(s) may continue to depressurize to-less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should NOT be delayed.,
: 6. Initiate RCS Cooldown To 350°F:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN IO0°F/HR
: b. Dump steam to condenser from
: b. Manually or locally dump steam intact SG(s):                            from intact SG(s):
: 1) Check condenser - AVAILABLE          o Use SG atmospheric steam dump:
: 2) Place steam dump controller switch to manual and adjust            o Refer to 2-SOP-ESP-O01, for zero output.                        LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3) Transfer condenser steam                  for local operation as dump to pressure control                  necessary.
mode and adjust manual setpoint as necessary.                            OR -
o Use turbine-driven AFW pump.
IF no intact SG available, THEN perform the following:
o Use faulted SG.
                                                                - OR -
o Go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
8 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESSTHAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)    52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3.  -4"    UPPLY--SW-ITtNOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation. stabilize the plant AND return to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:
22-ES-3.3                  POST-SGTR COOLDOWN USING STEAM DUMP                REV. 0 CAUTION RCS and ruptured SG(s) pressures must be maintained less than the ruptured SG(s) atmospheric steam dump setpoint.
: 7. Control RCS Pressure And Charging Flow To Minimize RCS-To-Secondarv Leakage:
: a. Perform appropriate action(s) from table:
RUPTURED SG(s)      INCREASING        DECREASING        OFFSCALE LEVEL                                            HIGH PRZR LEVELI o  Increase RCS      Increase RCS  o  Increase RCS LESS THAN 28%          Makeup Flow        Makeup Flow      Makeup Flow (47% FOR ADVERSE CONTAINMENT)          o  Depressurize                      o Maintain RCS And RCS Using                          Ruptured SG(s)
Step 7b                            Pressures Equal BETWEEN 28% (47%        Depressurize      Turn On          Maintain RCS And FOR ADVERSE            RCS Using          PRZR            Ruptured SG(s)
CONTAINMENT)            Step 7b            Heaters          Pressures Equal AND 50%
BETWEEN              o  Depressurize      Turn On          Maintain RCS And 50% And                  RCS Using          PRZR            Ruptured SG(s) 71% (65%                Step 7b            Heaters          Pressures Equal FOR ADVERSE CONTAINMENT)          o  Decrease RCS Makeup Flow GREATER THAN 71%        Decrease RCS      Turn On          Maintain RCS And (65% FOR ADVERSE        Makeup Flow        PRZR            Ruptured SG(s)
CONTAINMENT)                                Heaters          Pressures Equal This Step continued on the next page.
9 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400  401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: b. Use normal PRZR spray per        b. IF letdown is in service,  THEN Step 7a                            use auxiliary spray:
: 1) Maintain RCP seal  injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
10 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400 RCS SUBCOOLING OF (ADVERSE)      52 (83)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner-or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3.                    -HOYER -CRITERION:
    --ATfW-SUPPLY-SPITPL IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3,.STEAM GENERATOR TUBE RUPTURE. Step 1.
 
Number:
 
==Title:==
Revision Number:
2-ES-3.3                    POST-SGTR COOLDOWN USING STEAM DUMP                      REV. 0 STEP        ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED NOTE 2-POP-3.3, PLANT COOLDOWN - HOT TO COLD SHUTDOWN,        should be referred to for plant alignment during cooldown.
: 8. Check If    RCS Cooldown Should Be Stopped:
: a. RCS temperatures - LESS THAN
: a. Return to Step 4.
3500F
: b. Stop RCS cooldown
: c. Maintain RCS temperatures -
LESS THAN 350°F
: 9.      Check Ruptured SG(s) Narrow Ranae        Refill ruptured SG to 73% (60%
Level - GREATER THAN 14% (27% FOR        FOR ADVERSE CONTAINMENT) using A'DVERSE CONTAINMENT)                    feed flow. IF any of the following conditions occur, THEN stop feed flow to ruptured SG:
o Ruptured SG pressure decreases in an uncontrolled manner.
                                                                  - OR  -
o Ruptured SG pressure increases to 1000 psig.
                                                                  - OR-o Ruptured SG pressure decreases to 430 psig AND ruptured SG level greater than 10% (27% FOR ADVERSE CONTAINMENT).
11 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. -ýA-FWSJPPLY-SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3. STEAM GENERATOR TUBE RUPTURE, Step 1.
 
Number:
 
==Title:==
Revision Number:
2-ES-3.3                          POST-SGTR COOLDOWN USING STEAM DUMP                            REV. 0 CAUTION
* Ruptured SG(s)        pressure may decrease rapidly when steam is          released.
NOTE Steam releases from ruptured SG(s) may be stopped when RCS pressure decreases to less than 370 psig (280 psig FOR ADVERSE CONTAINMENT) to maintain adequate RCP number I seal differential pressure.
: 10.      Dump Steam To Condenser From                  Dump steam using ruptured SG(s)
Ruptured SG(s):                                atmospheric steam dump.
o Locally operate MSIV bypass valves as necessary
: 11.        Control CharqinQ And Letdown Flow To Maintain PRZR Level:
: a. PRZR level - GREATER THAN 28%            a. Increase charging flow as (47% FOR ADVERSE CONTAINMENT)                necessary. Go to Step 12.
OBSERVE NOTE PRIOR TO STEP 12.
: b. PRZR level - LESS THAN 71%              b. Decrease charging flow as (65% FOR ADVERSE CONTAINMENT)                necessary. Go to Step 13.
12 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step I:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG              0-400  401-800    801-1200    1200-2500 RCS SUBCOOLING OF (ADVERSE)    52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed'for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized. and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3.    -AFW--SUPPtY -SWITCflOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
F 2-ES-3.3 Number:
 
==Title:==
POST-SGTR COOLDOWN USING STEAM DUMP                  REV. 0 Revision Number:
NOTE The upper head region may void during RCS depressurization if RCPs are NOT running. This will result in a rapidly increasing PRZR level.
: 12. Depressurize RCS To Minimize RCS-To-Secondary Leakage:
: a. Use normal PRZR spray              a. IF letdown is in service,  THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2) Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4) Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6) Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
This Step continued on the next page.
13 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  -  LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. .. AFW-lSUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft, switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
 
SNumber:
2 -ES-3.3    }
 
==Title:==
POST-SGTR ,COOLDOWN USING STEAM DUMP                    REV. 0 Revision Number:
STP      ACTION/EXPECTED      RESPONSE              RESPONSE NOT OBTAINED IF auxiliary spray can NOT be used, THEN use one PRZR PORV.
: b. Turn on PRZR heaters as necessary
: c. Maintain RCS pressure at ruptured SG(s) pressure
: d. Maintain RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE            RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  -  400            52  (83) 401    -  800            36  (49) 801    -  1200            23  (30) 1201    -  2500            19  (26)
: 13. Check If      RCPs Must Be Stopped:
: a. Check the following:                    a. IF neither condition satisfied, THEN go to Step 14.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                            - OR -
o Number 1 seal return flow LESS THAN 0.2 GPM
: b. Stop affected RCP(s) 14 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs      LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG                0-400  401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)      52 (83) 36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3.  -AfW--SUPPLY-SWI-TCIIOVER--CRITERION:
IF CST level decreases to.lessthan 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
: 14. Check If  RHR System Can Be Placed In Service:
: a. Check both the following:        a. Return to Step 9.
o RCS temperature - LESS THAN 3500 F o RCS pressure - LESS THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Place RHR System in service per 2-SOP-4.2.1. RESIDUAL HEAT REMOVAL SYSTEM 15 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED. Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs    LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400  401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION.
Step 1.
: 3. .. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 15. Continue RCS Cooldown To Cold Shutdown:
: a. Maintain cooldown rate in RCS cold legs -  LESS THAN IO0F/HR
: b. Use RHR System
: c. Dump steam to condenser from      c. Manually or locally dump steam intact SG(s)                          from intact SG(s):
o Use SG atmospheric steam dump:
o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
OR  -
o Use turbine-driven AFW pump.
IF no intact SG available and RHR system NOT in service, THEN perform 'the following:
o Use faulted SG.
OR  -
o Go to 2-ECA-3.1, SGTR WITH.
LOSS OF REACTOR COOLANT -
SUBCOOLED RECOVERY DESIRED, Step 1.
: 16. Check RCS Temperatures    LESS        Return to Step 9.
THAN 2000F 16 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE  - PSIG          0-400  401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)    19 (26)
: 2. SECONDARY INTEGRITY CRITERIA; UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an-uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
: 17. Evaluate Long Term Plant Status:
: a. Maintain cold shutdown conditions
: b. Consult TSC
                                  -END-17 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1. SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs - LESS THAN VALUE OBTAINED FROM TABLE RCS PRESSURE - PSIG            0-400    401-800    801-1200  1200-2500 RCS SUBCOOLING OF (ADVERSE)  52 (83)  36 (49)    23 (30)  19 (26)
: 2. SECONDARY  INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE; Step 1.
 
Number:
 
==Title:==
Revision Number:
2 -ES-3.3                  POST-SGTR COOLDOWN USING STEAM DUMP                    REV. 0 ATTACHMENT 1                (Attachment page I of 1)
NATURAL CIRCULATION VERIFICATION
: 1. The following conditions support or indicate natural circulation flow:
o RCS subcooling based on core exit TCs        GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE        RCS SUBCOOLING °F (PSIG)      (ADVERSE CONTAINMENT) 0  - 400            52 (83) 401  - 800            36 (49) 801  - 1200            23 (30) 1201  - 2500            19 (26) o SG pressures  - STABLE OR DECREASING o RCS hot leg temperatures    - STABLE OR DECREASING o Core exit TCs - STABLE OR DECREASING P RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE
                                              -END-18 of 18
 
FOLDOUT PAGE FOR 2-ES-3.3
: 1. SI REINITIATION CRITERIA:
IF EITHER condition listed below occurs, manually start SI system pumps as necessary AND go to 2-ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o PRZR level - CANNOT BE MAINTAINED GREATER THAN 14% (33% FOR ADVERSE CONTAINMENT) o RCS subcooling based on core exit TCs  - LESS THAN VALUE OBTAINED FROM TABLE
: 2. SECONDARY INTEGRITY CRITERIA:
UNLESS needed for RCS cooldown, IF any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated, go to 2-E-2. FAULTED STEAM GENERATOR ISOLATION, Step 1.
: 3. AFW SUPPLY SWITCHOVER CRITERION:
IF CST level decreases to less than 2 ft. switch to city water supply.
: 4. MULTIPLE TUBE RUPTURE CRITERIA:
IF any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation, stabilize the plant AND return to 2-E-3, STEAM GENERATOR TUBE RUPTURE. Step 1.
 
  "EnteWg-                          Procedure Use Is: Control Copy:
l] Continuous Nuclear Northeast                03 Reference      Effective Date:.
outc TegA, 13 Information 2-ECA-0.0, Revision: 2 LOSS OF!ALLAC POWER Approved By:
Procedure Spr6        r, RPO/!
Team P Procedure Owner            ,
PARTIAL REVISION
 
A. PURPOSE This procedure provides actions to respond to a loss of all AC power.
B. SYMPTOMS OR ENTRY CONDITIONS
: 1) The symptom of a loss of all AC power is the indication that all 480V busses are de-energized.
: 2) This procedure is entered from 2-E-O, REACTOR TRIP OR SAFETY.
INJECTION. Step 3, on the indication that all 480V busses are de-energized.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                          - OR -
o Containment pressure greater than 4 psig.
1 of 28
 
NOTE o Steps 1 and 2 are IMMEDIATE ACTION steps.
o CSF Status Trees should be monitored for information only. FRPs should NOT be implemented.
: 1. Verify Reactor Trip:                  Manually trip reactor.
o Reactor trip breakers  - OPEN o Neutron flux - DECREASING o Rod bottom lights  - LIT o Rod position indicators    AT ZERO
: 2. Verify Turbine Trip:
: a. All turbine stop valves            a. Manually trip turbine. IF CLOSED                                turbine will NOT trip, THEN close MSIVs.
IF MSIVs can NOT be closed, THEN manually run back turbine.
2 of 28
: 3. Check If  RCS Is Isolated:
: a. PRZR PORVs  - CLOSED              a. IFE PRZR pressure less than 2335 psig, THEN manually close PORVs.
: b. Letdown isolation valves -        b. Manually close valve.
CLOSED o  LCV-459 o  200A o  200B o  200C
: c. Excess letdown isolation valve    c. Manually close valve.
      - CLOSED o 213
: 4. Verify AFW Flow - GREATER THAN 400 GPM:
: a. Turbine-driven AFW pump -          a. Manually open steam supply RUNNING                              regulator valve:
o PCV-1139
: b. Manually align turbine-driven AFW pump FCVs as necessary
: c. Adjust steam supply speed control valve as necessary:
o HCV-1118 3 of 28
 
ACT.. I ON*            *            *    *    **      B        I. . I . . . . .
*r                                                                                        t dr CAUTION                                      t The load on the diesel generators should remain less than 1650 KW but may            W*
be increased to 2000 KW for a maximum of 2 hrs in any 24 hr period.                t
: 5.      Try To Restore Power to Any 480V Bus;
: a. Energize 480V bus with diesel generator:
: 1) Check diesel generator(s)          1) Emergency start diesel RUNNING                            generator(s):
a) Manually actuate SI.
: 2) Verify 480V bus                    2) Manually energize 480V bus AUTOMATICALLY ENERGIZED            from running diesel generator.
This Step continued on the next page.
4 of 28
 
IF 480V bus can NOT be energized from diesel generator(s), THEN perform the following:
a) Locally trip running diesel generator(s).
b) Contact Con Ed DO to determine if 138KV or 13.8KV power readily available.
c) IF outside power is NOT readily available, THEN perform the following:
: 1. Start Appendix R DG per:
o 2-SOP-27.6, UNIT 2 APPENDIX R DIESEL GENERATOR OPERATION
: 2. Dispatch NPO to black start a GT per:
o 2-SOP-27.5.3. BLACK START OF GAS TURBINE 1, 2,  OR 3.
: 3. Go to Step 6. OBSERVE CAUTIONS PRIOR TO STEP 6.
d) IF outside power is readily available, THEN attempt to manually energize 480V bus using the following:
o 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
o 2-AOP-480V-1,  LOSS OF 480V BUS.
This Step continued on the next page.
5 of 28
 
STEP    ACTION/EXPECTED RESPONSEI            RESPONSE NOT OBTAINEDI
: b. Check:480V busses - AT LEAST      b. Go to Step 6. OBSERVE ONE ENERGIZED:                        CAUTIONS PRIOR TO STEP 6.
o 2A AND 3A
                  - OR -
o 5A OR -
o 6A
: c. Start one service water pump on the essential header to support running diesel generator
: d. Return to procedure and step in effect and implement FRPs 6 of 28
 
STP      ACTION/EXPECTEO RESPOýSE]            RESPONSE NOT OBTAINED
* CAUTION
* o When power is restored to any 480V bus,  recovery actions should
* continue starting with Step 24.                                        *
* o If an SI signal exists or if an SI signal is actuated during this
* procedure, it should be reset (refer to Step 18b) to permit manual      *
  "    loading of equipment on a 480V bus.
* o If a diesel generator is started,, a service water pump should be
* started on the essential header to provide diesel generator cooling.
* o If a partial train (bus 2A or bus 3A) is-energized, safeguards
* equipment on the energized bus including RCP seal cooling should NOT be
* placed in PULLOUT or isolated.
: 6. Place Following Equipment Switches In PULLOUT Position:
o Containment spray pumps o  SI pumps o  FCUs o Motor-driven AFW pumps o  Turning gear oil pump o  Bearing oil pump o  Turbine auxiliary oil pump o  CCW pumps o  RHR pumps 7 of 28
 
STE
* AC  IN  EPC  E          * **    *          **** NO        **  *
* CAUTION
* Radiation levels and harsh environment          conditions should be evaluated
* prior to performing local actions.                                            t (D 7.      Disoatch Personnel To Locally Restore AC Power;
: a.      Emergency diesel  generator(s) per:
o 2-SOP-27.3.1.1, 21 EMERGENCY DIESEL GENERATOR MANUAL OPERATION o 2-SOP-27.3.1.2. 22 EMERGENCY DIESEL GENERATOR MANUAL OPERATION o 2-SOP-27.3.1.3, 23 EMERGENCY DIESEL GENERATOR MANUAL OPERATION This Step continued on the next page.
8 of 28
: b. Check 13.8KV feeder 13W92 -      b. IF 13.8KV feeder 13W92 can NOT ENERGIZED                            be energized, THEN perform the following:
: 1) Contact Con Ed DO to determine if IP3 13.8KV feeder 13W93 is available.
: 2)  IF IP3 13.8KV 13W93 is available, THEN attempt to restore power to 6.9KV via 52GT/BT per:
o 2-SOP-ESP-O01. LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3)  IF 13.8KV feeder 13W93 is NOT available OR 52GT/BT can NOT be closed, THEN start Appendix R DG per:
o 2-SOP-27.6, UNIT 2 APPENDIX R DIESEL GENERATOR OPERATION
: 4) IFEAppendix R DG can NOT be started, THEN perform the following as required:
a) Restore power to ASSS via IP3 Appendix R DG per:
o 2-AOI-27.1.9.2, PROVIDING APPENDIX R POWER FROM UNIT 3 b)  Black start a GT per 2-SOP-27.5.3, BLACK START OF GAS TURBINE 1, 2, OR 3 c) Contact Con Ed DO for available power alignment.
This Step continued on the next page.
9 of 28
: 5) Continue with Step 8. WHEN power source is available, THEN do Step 7c.
: c. Attempt to restore power to busses per the following while continuing with Step 8:
o 2-SOP-27.1.3, OPERATION OF 13.8KV SYSTEM o 2-SOP-27.1.4, 6900 VOLT SYSTEM.
o 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6.
o 2-AOP-13.8KV-1, LOSS OF POWER TO ANY 13.8KV BUS o 2-AOP-480V-1,  LOSS OF 480V BUS.
: 8. Dispatch Personnel To Locally Close Valves To Isolate RCP Seals And Place Valve Switches In CLOSED Position:
o RCP seal return isolation valve outside containment:
o MOV-222 o RCP seal injection isolation valves outside containment:
o  MOV-250A o  MOV-250B o  MOV-250C o  MOV-250D o RCP thermal barrier CCW return isolation valve outside containment:
o MOV-789 10 of 28
: 9. Check If CST Is Isolated From Hotwel I:
: a. Verify condenser hotwell          a. IF valve(s) open or position isolation valves - CLOSED:            not known, THEN dispatch personnel to locally close o  LCV-1128                          valve(s). IF valve(s) can NOT o  LCV-1128A                          be closed, THEN locally close o  LCV-1129                          associated isolation valve(s):
o CD-6 o CT-8                                o CT-7 for LCV-1128 and LCV-1128A.
o CD-5 for LCV-1129.
: b. Place condenser hotwell isolation valve controllers in MANUAL:
o LCV-1128 o LCV-1128A o LCV-1129
: 10. Check SG Status:                      Manually close valves.      IF valves can NOT be manually closed, THEN
: a. MSIVs  - CLOSED                  locally close valves.
: b. Main FW regulating and bypass      Locally close MSIVs as necessary valves - CLOSED                    per 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND
: c. Blowdown isolation valves  -      COMPENSATORY ACTIONS.
CLOSED 11 of 28
 
STE          *ESPO*
ACTION*EXPECTED                    *I          NOT OBT*INE*I t
CAUTION i
* A faulted or ruptured SG that is isolated should remain isolated.      Steam
* supply to the turbine-driven AFW pump must be maintained from at least
  "  one SG.
: 11. Check If    Any SG Is Faulted:
: a. Check pressures in all SGs -      a. Go to Step 12.
o ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
                      - OR -
o ANY SG COMPLETELY DEPRESSURIZED
: b. Isolate faulted SG(s):            b. Manually close valves. IF valves can NOT be closed, THEN o Isolate AFW flow                    dispatch NPO to attempt to locally close valves or o Dispatch NPO to close steam        associated block valves.
supply header valves to turbine-driven AFW pump from faulted SG(s):
o MS-41 (SG 22) o MS-42 (SG 23) o Verify SG atmospheric steam dumps - CLOSED 12 of 28
 
STP    ACTION/EXPECTED RESPONSE          l RESPONSE NOT OBTAINED[
: 12. Check If SG Tubes Are Intact:        Try to identify ruptured SG(s).
Continue with Step 13. OBSERVE o Main steamline radiation            CAUTION PRIOR TO STEP 13. WHEN recorder (R-28, R-29, R-30 and      ruptured SG(s) identified. THEN R-31) - NORMAL                      isolate ruptured SG(s):
o Condenser air ejector radiation    o Isolate AFW flow.
recorder (R-45)- NORMAL o Dispatch NPO to close steam o SG blowdown radiation recorder        supply header valves to (R-49) - NORMAL                      turbine-driven AFW pump from ruptured SG(s):
o NO SG LEVEL INCREASING IN AN UNCONTROLLED MANNER                  o MS-41 (SG  22) o MS-42 (SG  23) o Adjust ruptured SG(s) atmospheric steam dump controller setpoint to 74%,
1030 psig.
WHEN ruptured SG pressure less than 1030 psig, THEN verify ruptured SG atmospheric steam dump closed. IF NOT closed, THEN place controller in manual and close valve. IF valve can NOT be closed, THEN locally isolate open valve.
13 of 28
 
S,  ,    *
* f * * , * * .    *. * *. *.  .* * *    * *    * * * *  * * * * * * * * *  * *-
* t CAUTION City water for AFW pumps will be necessary if CST level decreases to less
* than 2 ft.
013. Check Intact SG Levels:
: a. Narrow range level - GREATER          a. Maintain maximum AFW flow THAN10% (27% FOR ADVERSE                    until narrow range level CONTAINMENT)                                greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control AFW flow to maintain          b. IF narrow range level in any narrow range level between 10%              SG continues to increase in an (27% FOR ADVERSE CONTAINMENT)              uncontrolled manner, THEN and 50%                                    isolate ruptured SG(s):
o Isolate AFW flow.
o Dispatch NPO to close steam supply header valves to turbine-driven AFW pump from ruptured SG(s):
o MS-41 (SG 22) o MS-42 (SG 23) o Adjust ruptured SG(s) atmospheric steam dump controller setpoint to 74%,
1030 psig.
WHEN ruptured SG pressure less than 1030 psig, THEN verify ruptured SG atmospheric steam dump closed. IF NOT closed, THEN place controller in manual and close valve. IF valve can NOT be closed, THEN locally isolate open valve.
14 of 28
 
STEP    ACTION/EXPECTED RESPNWSEI7 .......      RES7PONSE NOT OBTAINED'I
: 14. Check DC Bus Loads:
: a. Monitor DC power supply:
o Consult TSC and shed selected DC loads if nPr~ssarv tn *xt~nd  hat~t.rv 1ife
: 15. Check CST Level    - GREATER THAN      Switch to city water supply:
2 FT
: a. Open city water header isolation valve:
o FCV-1205A
: b. Open AFW pump suction valves as necessary; o PCV-1187 o PCV-1188 o PCV-1189 15 of 28
 
STE
* C* I N E*
* PC
* E REP*: * **                    NO  * * *      * *
* CAUTION t
o SG pressures should NOT be decreased to less than 110 psig to prevent injection of accumulator nitrogen into the RCS.
o SG narrow range level should be maintained greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one intact SG.      If level can NOT be maintained, SG depressurization should be stopped until level is restored in at least one SG.
NOTE o The SGs should be depressurized at a rate sufficient to maintain a cooldown rate in the RCS cold legs less than IO0F per hour. This will minimize RCS inventory loss while cooling the RCP seals in a controlled manner.
o PRZR level may be lost and reactor vessel upper head voiding may occur due to depressurization of SGs. Depressurization should NOT be stopped to prevent these occurrences.
: 16.      Depressurize Intact SGs To 210 psic:
: a. Check SG narrow range levels  -    a. Perform the following:
GREATER THAN-10% (27% FOR ADVERSE CONTAINMENT) in at            1) Maintain maximum AFW'flow least one SG                              until narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: 2) Continue with Step 17.
WHEN narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG, THEN do Steps 16b through 16e.
This Step continued on the next page.
16 of 28
 
STP    ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI
: b. Manually dump steam using SG      b. Locally dump steam using SG atmospheric steam dumps to              atmospheric steam dumps:
maintain cooldown rate in RCS cold legs - LESS THAN 100°F/HR          o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
: c. Check RCS cold leg                c. Perform the following:
temperatures - GREATER THAN 3250 F                                  1) Control SG atmospheric steam dumps to stop SG depressurization.
: 2) Go to Step 17.
: d. Check SG pressures  - LESS THAN    d. Continue with Step 17. WHEN 210 PSIG                                SG pressures decrease to less than 210 psig, THEN do Step 16e.
: e. Manually control SG                e. Locally control SG atmospheric atmospheric steam dumps to              steam dumps to maintain SG maintain SG pressures at                pressures at 210 psig:
210 psig o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
: 17. Check Reactor Subcritical:            Control SG atmospheric steam dumps to stop SG depressurization o Intermediate range channels -        and allow RCS to heat up.
ZERO OR NEGATIVE STARTUP RATE o Source range channels - ZERO OR NEGATIVE STARTUP RATE 17 of 28
* CAUTION                                    *
* Placing key switches to DEFEAT will prevent auto SI actuation.
NOTE Depressurization of SGs will result in SI actuation.      SI should be reset to permit manual loading of equipment on 480V bus.
: 18. Check SI Sional Status:
: a. S1 - HAS BEEN ACTUATED            a. Go to Step 22. WHEN SI is actuated, THEN do Steps 18b, 19, 20 and 21.
: b. Reset SI:
: 1) Check all CCW pumps  -            1) Place non-running CCW pumps RUNNING                              CCR control switches in PULLOUT.
: 2)  Place controls for main AND bypass feedwater regulating valves to CLOSE
: 3) Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1
                      - AND -
o Train B SIA-2
: 4)  One at a time. depress Safety Injection reset buttons (Panel SB-2):
o Train A o Train B
: 5) Verify Train A AND B - RESET      5) Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o  SIA-1 o  SIM-I o  SIA-2 o  SIM-2 18 of 28
 
STEP    ACTION/EXPECTED RESPONSE              RESPONSE NOT OBTAINED
: 19. Verify Containment Isolation Phase A:
: a. Phase A - ACTUATED                a. Manually actuate phase A.
o Train A master relay CAI (above rack E) o Train B master relay CA2 (above rack F)
: b. Phase A valves  - CLOSED          b. Manually close valves. IF valves can NOT be manually closed, THEN locally close valves.
: c. IVSW valves - OPEN:                c. Manually open valves.
o 1410 o 1413 o SOV-3518 o SOV-3519
: d. WCP valves  - OPEN:              d. Manually open valves.
o  PCV 1238 o  PCV 1239 o  PCV  1240 o  PCV  1241
: e. Place personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel 19 of 28
: 20. Verify Containment Ventilation Isolation:
: a. Containment purge valves        a. Manually close valves.
CLOSED:
IF valves can NOT be closed, o  FCV-1170                        THEN close valves from fan o  FCV-1171                        room.
o  FCV-1172 o  FCV-1173                        IF valves can NOT be closed, THEN dispatch operator and HP personnel to close outside valves by isolating instrument air:
o FCV-1171,  IA-780 o FCV-1173,  IA-779
: b. Containment pressure relief      b. Manually close valves.
valves - CLOSED:
IF valves can NOT be closed, o PCV-1190                          THEN close valves from fan o PCV-1191                          room.
o PCV-1192 IF valves can NOT be closed, THEN dispatch operator AND HP personnel to close outside valves by isolating instrument air:
o PCV-1191,  IA-777 o PCV-1192,  IA-778 IF containment pressure relief can NOT be isolated, THEN locally close the following valves (Fan House 88 ft. el):
o UH-1013, Pressure Relief Fan Inlet Stop o UH-1014, Pressure Relief Fan Outlet stop 20 of 28
 
STEP    ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED
: 21. Check Containment Pressure - HAS    Perform the following:
REMAINED LESS THAN 24 PSIG
: a. Verify containment spray signal actuated. lI NOT, THEN manually actuate.
: b. Verify containment isolation Phase B valves closed.
IF NOT,  THEN manually close valves.
IF valves can NOT be manually closed, THEN locally close valves.
: c. Verify  IVSW isolation valves open:
o  7864 o  7865 o  7866 o  7867
: d. One at a time, depress Containment Spray Reset Pushbuttons:
o Spray SYS Reset Train.A o Spray SYS Reset Train B
: 22. Check Core Exit TCs - LESS THAN      IF Core Exit temperatures greater 12000 F                            than 1200°F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, Step 1.
21 of 28
 
STP    ACTION/EXPECTED RESPONSE..        J RESPONSE NOT OBTAINEDI
: 23. Check If  AC Power Is Restored:
: a. Check 480V busses  - AT LEAST      a. Continue to control RCS ONE ENERGIZED                        conditions and monitor plant status:
o 2A AND 3A
: 1) Check status of local
                  - OR -                        actions:
o 5A                                    o AC power restoration.
o RCP seal isolation.
                  - OR -                        o DC power supply.
o 6A                                  2) Check status of auxiliary boration systems:
o BAST temperature greater than 155 0 F.
IF temperature less than 155 0 F, request TSC to provide emergency power supply for boric acid heat trace to prevent crystallization.
: 3)  Check status of spent fuel cooling:
o Spent fuel pit level greater than low level alarm.
IF level less than low level alarm, THEN dispatch NPO to makeup to the spent fuel pit as necessary.
: 4) Open doors on all control room cabinets.
: 5)  Dispatch NPO to open AFW pump room roll-up door.
: 6)  Return to Step 11. OBSERVE CAUTION PRIOR TO STEP 11.
22 of 28
: 24. Stabilize SG Pressures:
: a. Manually control SG                a. Locally control SG atmospheric atmospheric steam dumps              steam dumps:
o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
* CAUTION                                    *
* The loads placed on the energized 480V bus should NOT exceed the capacity  *
* of the power source.
NOTE ATTACHMENT 2 provides a list of 480V equipment    load ratings.
: 25. Verify Service Water System Operation:
: a. Verify at least one pump -        a. Manually start pump.
RUNNING ON ESSENTIAL HEADER
: b. Service water valves from          b. Locally open valves as diesel generator - OPEN              necessary.
23 of 28
 
STEP      ACTION/EXPECTED RESPONSEI            RESPONSE NOT OBTAINEDI.....
: 26. Verify Following Equipment Loaded    Manually load equipment as On Eneraized 480V Bus:              necessary.
o Bus 5A:
: a. MCCs:
o MCC 26A o MCC 29A
: b. 21 Battery Charger in service
: c. 21 Static Inverter on alternate power supply per 2-SOP-27.1.6, INSTRUMENT BUS, DC DISTRIBUTION SYSTEM AND PA SYSTEM INVERTER
: d. 23 Static Inverter on alternate power supply  per 2-SOP-27.1.6 o Bus 2A:
: a. MCCs:
o MCC 24 o MCC 24A
: b. 22 Battery Charger in service
: c. 22 Static Inverter on alternate power supply per 2-SOP-27.1.6
: d. PA System Inverter on alternate power supply  per 2-SOP-27.1.6 This Step continued on the next page.
24 of 28
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.O                        LOSS OF ALL AC POWER          REV. 2 STEACTION/EXPECTEO        RESPOq,ý1I          RESPONSE NOT OBTAINE)t o Bus 3A:
: a. MCCs:
o MCC 26C o MCC 211
: b. 23 Battery Charger in service o Bus 6A:
: a. MCCs:
o MCC 26B o MCC 27A
: b. 24 Battery Charger in service
: c. 24 Static Inverter on alternate power supply per 2-SOP-27.1.6 25 Of 28
 
STEP        ACTION/EXPECTED RESPONSE                  RESPONSE NOT OBTAINED NOTE If RCP seal cooling was previously isolated, further cooling of the RCP seals will be established by natural circulation cooldown as directed in subsequent procedures.
: 27. Select Recovery    Procedure:
: a. Check RCS subcooling based on          a. Go to 2-ECA-0.2,    LOSS OF ALL core exit TCs - GREATER THAN                AC POWER RECOVERY WITH SI VALUE OBTAINED FROM TABLE:                  REQUIRED, Step 1.
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 - 400            52  (83) 401 - 800            36  (49) 801 - 1200            23  (30) 1201 - 2500            19  (26)
: b. Check PRZR level  - GREATER          b. Go to 2-ECA-O.2, LOSS OF ALL THAN 14% (33% FOR ADVERSE                  AC POWER RECOVERY WITH SI CONTAINMENT)                                REQUIRED, Step 1.
: c. Check if SI equipment -                c. Go to 2-ECA-O.1, LOSS OF ALL ACTUATED WITH RESULTANT                    AC POWER RECOVERY WITHOUT SI INJECTION FLOW UPON AC POWER                REQUIRED, Step 1.
RESTORATION
: d. Go to 2-ECA-O.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step I
                                            -END-26 of 28
 
ATTACHMENT I            (Attachment  page 1 of 1)
CONTAINMENT ISOLATION VALVES
: 1. The followino valves will close on Phase A isolation:
VALVE NAME                                          VALVE NUMBER(s)
CCW from excess letdown Hx                          796, 793 CCW to excess letdown Hx                            798, 791 Vent header from RCDT                              1786, 1787 Gas analyzer PRT                                    548, 549 Gas analyzer RCDT                                  1788, 1789 Letdown from regenerative HX                        201, 202 Letdown oriface control stop valves                200A, 200B, 200C Make-up to PRT                                      519, 552 Containment sump pumps to WDS - hold-up tank        1723, 1728 Instrument air to containment                      PCV-1228 RCDT to WDS - hold-up tank                          1702, 1705 SG blowdown and sampling system                    PCV-1214, 1214A PCV-1215, 1215A PCV-1216, 1216A PCV-1217, 1217A Radiation monitor return to containment            PCV-1234, 1235 PCV-1236, 1237 Accumulator samples                                956G, 956H Sample - pressurizer  steam                        956A, 956B Sample - pressurizer  liquid                      956C, 956D Sample - RCS loops                                  21, 22, 23 MOV-956E, 956F SJAE to containment                                1229, 1230 Hi-Rad sample system return to containment    sump  MOV-4399, 5132 Recirculation pump discharge sample line            MOV-990A, 990B Accumulator N2 Supply Line Stop                    863 2    The following valves will    close on Phase B isolation:
VALVE NAME                                            VALVE NUMBER(s)
Component cooling  to RCS pumps                        MOV-769, 797 Component cooling  from RCS thermal barrier return    MOV-789, FCV-625 Component cooling  from RCS motor bearing return      MOV-786, 784 Seal water return  containment isolation valve        MOV-222
                                      -END-27 of 28
 
ATTACHMENT 2.              (Attachment page I of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the following table to determine 480V equipment load ratings:
21 DG          22 DG            23 DG EQUIPMENT          BUS 5A    BUS 2A    BUS 3A    BUS 6A 21 SERVICE WATER PUMP    282 KW 22 SERVICE WATER PUMP                282 KW OR 282 KW 23 SERVICE WATER PUMP                                      282 KW 24 SERVICE WATER PUMP    282 KW 25 SERVICE WATER PUMP                282 KW OR 282 KW 26 SERVICE WATER PUMP                                      282 KW PRZR CONTROL HEATERS                                      277 KW 21 PRZR BU HEATERS                              554 KW 22 PRZR BU HEATERS                  485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                    384 KW 23 AFW PUMP                                              384 KW 21 FAN COOLER UNIT        250 KW 22 FAN COOLER UNIT        250 KW 23 FAN COOLER UNIT                  250 KW 24 FAN COOLER UNIT                              250 KW 25 FAN COOLER UNIT                                        250 KW 21 SI PUMP                316 KW 22 SI PUMP                          316 KW    316 KW 23 SI PUMP                                                345 KW 21 SPRAY PUMP            350 KW 22 SPRAY PUMP                                              350 KW 21 RHR PUMP                                    303 KW 22 RHR PUMP                                                303 KW 21 CHARGING PUMP          150 KW 22 CHARGING PUMP                                150 KW 23 CHARGING PUMP                                          150 KW 21 RECIRC PUMP            299 KW 22 RECIRC PUMP                                            299 KW 21 CCW PUMP              228 KW 22 CCW PUMP                          228 KW 23 CCW PUMP                                                228 KW 21 LIGHTING TRANSFORMER              150 KW (N)            150 KW CE) 22 LIGHTING TRANSFORMER                        225 KW 23 LIGHTING TRANSFORMER  225 KW TURBINE AUX OIL PUMP                                      112 KW STATION AIR COMPRESSOR    93 KW END 28 of 28
 
Procedure Use Is:  Control Copy:
Entergy                  0 Continuous Nuclear Northeast        O3 Reference        Effective Date: 4A107____
o3 Information 2-ECA-0.1, Revision: 0 LOSS OF ALL                      ER RECOVERY W1    J          hED Approved By:
Procedurec~ponsor, RPC Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.1I          LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED          REV. 0 A. PURPOSE This procedure provides actions to use normal operational systems to stabilize plant conditions following restoration of 480V power.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is    entered from 2-ECA-O.O,  LOSS OF ALL AC POWER, Step 27,  when 480V power is  restored and SI is not required.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if    either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                                - OR  -
o Containment pressure greater than 4 psig.
1 of 15
 
Number:
 
==Title:==
Revision Number:
2-ECA-0.1                LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED                          REV. 0
* CAUTION                                                *
          ,  IT  n  4ZT  i nnl  i e ,rteilt-tuf nrinr    fn  ngrfnrminn        ft-n0 nf thic
* procedure, it should be reset per Attachment 1 SI RESET to permit
* manual loading of equipment on a 480V bus.
* o Radiation levels and harsh environment conditions should be evaluated prior to performing local actions.
NOTE CSF Status Trees should be monitored for information only.                      FRPs should NOT be implemented prior to completion of Step 9.
: 1. Check RCP Seal    Isolation Status:
: a. RCP seal injection isolation                a. IF valves open or position not valves outside containment -                      known, THEN check charging CLOSED:                                            pump status:
0OMOV-250A                                        1) IF pump running,    THEN go to 0 MOV-250B                                              Step 2.
0 MOV-250C 0 MOV-250D                                        2) LF pump NOT running, THEN manually close valves before starting charging pump.
IF valves can NOT be manually closed, THEN locally close valves.
: b. RCP thermal barrier CCW return              b. IF valve open or position not isolation valve outside                            known, THEN check CCW pump containment - CLOSED:                              status:
o MOV-789                                          1) IF pump running,    THEN go to Step 2.
: 2) IF pump NOT running, THEN manually close valve.      IF valve can NOT be closed, THEN manually close CCW return flow control valve outside containment:
o FCV-625 2 of 15
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.1              LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED            REV. 0 STP        ACTiON/EXPECTED RESPONSEi                RESPONSE NOT OBTAINEDI
: 2. Check Containment Isolation            Perform the following:
Phase A - NOT ACTUATED
: a. Reset containment isolation Phase A:
: 1) Place IVSW switches to OPEN on SN panel o 1410 o 1413 o SOV 3518 o SOV 3519
: 2) Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: 3) Place personnel and equipment hatch solenoid control switches to INCIDENT on SM panel.
: 4) Place control switches for all Phase A isolation valves to CLOSE on SN panel.
: 5) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B This Step continued on the next page.
3 of 15
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.1          LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED              REV. 0 ACTIONEXPEC      EDEPNE                RESPONSE NOT OBTAINED'
: 6) Verify Train A and B reset.
IF signal does NOT reset, THEN:
a) Place key switches to BYPASS.
b) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset, THEN reset relays CA1 AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
: b. IF Phase B actuated,  THEN perform the following:
: 1) Reset Containment Spray.
: 2) Depress Phase B reset buttons.
: c. Establish instrument air to containment by opening isolation valve PCV-1228.
IF valve will NOT open, THEN verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAl o CA2 4 of 15
 
STEP          ACTION/EXPECTED RESPONSE                    RESPONSE NOT OBTAINED CAUTION
* The loads placed on the energized 480V bus should NOT exceed the capacity                    *
* of the power source.
: 3.      Manually Load Followinq Equipment On 480V Bus:
: a. Check instrument air                      a. Start one instrument air AVAILABLE                                    compressor.
: b. Start one CCW pump                      b. IF one CCW pump can NOT be started, THEN refer to 2-SOP-4.1.2 COMPONENT COOLING SYSTEM OPERATION to establish backup cooling to the following:
o Charging pumps o RHR pumps o SI pumps
: c. Check valve alignment and start charging pump:
: 1) Check valve alignment:                    1) Manually align valve as necessary. IF VCT NOT o,Charging pump suction                      available, THEN establish valve from VCT  - OPEN:                  suction from RWST:
o LCV-112C                                o Open suction valve from RWST:
o VCT makeup control system
                        - SET FOR AUTOMATIC                          o LCV-112B CONTROL AND GREATER THAN RCS BORON CONCENTRATION                  o Close suction valve from VCT:
o LCV-112C
: 2) Start one charging pump
: d. Start containment fan coolers as necessary
: e. Start one service water pump on non-essential header 5 of 15
 
Number:          ITitle:                                                            Revision Number:
2-ECA-O.1              LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED              REV.. 0 ACTION/EXPECTED RESPONSE1151                RESPONSE NOT, OBTAINED
: 4. Establish 55 qpm Charging Flow:
: a. Verify speed controller in MANUAL
: b. Adjust charging pump speed to establish 55 gpm flow
  . 5. Verify SI System Flow Not Required:
: a. RCS subcooling based on core            a. Go to 2-ECA-O.2. LOSS OF ALL exit TCs-    GREATER THAN VALUE            AC POWER RECOVERY WITH SI OBTAINED FROM TABLE:                        REQUIRED, Step 1.
WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  -  400          52  (83) 401  -  800          36  (49) 801  -  1200          23  (30) 1201  -  2500          19  (26)
: b. PRZR level - GREATER THAN 14%          b. Control charging flow to (33% FOR ADVERSE CONTAINMENT)              maintain PRZR level. IF PRZR level can NOT be maintained, THEN go to 2-ECA-0.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 1..
: 6. Check PRZR Level - GREATER THAN              Control charging flow as 28% (47% FOR ADVERSE CONTAINMENT)            necessary.
6 of 15
 
SNumber:
2-ECA-O.1
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED                                  REV. 0 Revision Number:
STP    ATINEPCTDRS          OS                    RSOS          NOT  OT    INU
* CAUTION o City water for AFW pumps will be necessary if CST level decreases to                                          *
* less than 2 ft.
* o If narrow range level decreases to less than 10% (27% FOR ADVERSE
* CONTAINMENT) and AFW flow is less than 400 gpm, the motor-driven AFW                                        *
* pumps should be manually loaded on 480V bus to supply water to the SGs.
* NOTE If motor-driven AFW pump operation is NOT required, pump switches should be maintained in PULLOUT to prevent automatic start.
( 7.      Check Intact SG Levels:
: a. Narrow range level - GREATER                    a. Maintain AFW flow greater than THAN 10% (27% FOR ADVERSE                              400 gpm until narrow range CONTAINMENT)                                            level greater than 10% (27%
FOR ADVERSE CONTAINMENT) in at
                                                                      .least one SG.
IF AFW flow NOT greater than 400 gpm, THEN:
: 1) Open AFW flow control valves as necessary.
: 2)  Start motor-driven AFW pumps as necessary.
: b. Control AFW flow to maintain narrow range level between 10%
(27% FOR ADVERSE CONTAINMENT) and 50%
7 of 15
 
[Number:
2-ECA-O.1
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED Revision Number:
REV.0 STEP    -    ACTION/EXPECTED RESPONSERESPONSE
: 8. Establish SG Pressure Control:
: a. Set each SG atmospheric steam dump controller to maintain existing SG pressure
: b. Place each SG atmospheric steam dump controller in automatic mode
: c. Locally return SG atmospheric steam dumps to remote control if necessary per 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
* CAUTION
* If an SI signal is actuated during this procedure after the SI pump switches have been placed in AUTO, procedure 2-ECA-O.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, should be performed.
: 9. Place Following Pump Switches In AUTO:
o SI pump o RHR pump o Containment spray pump 8 of 15
 
Number:        1
 
==Title:==
Revision Number:
2-ECA-O.1              LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED              REV. 0 ACTION/EXPECTED RESPONSE.                RESPONSE NOT OBTAINED
: 10. Check If Letdown Can Be Established:
: a. PRZR level - GREATER THAN 28%        a. Continue with Step 11. WHEN (47% FOR ADVERSE CONTAINMENT)            level increases to greater than 28% (47% FOR ADVERSE CONTAINMENT), THEN do Steps lOb and 10c.
: b. CCW pumps    - ANY RUNNING          b. Go to Step 11.
: c. Establish letdown:                  c. Establish excess letdown:
: 1) Close letdown orifice stops:          1) Establish CCW flow through excess letdown heat o 200A                                  exchanger by opening CCW o 200B                                  valves:
o 200C o Inlet valves 791,798
: 2)  Open letdown line isolation              o Outlet valves 793,796 valves 201 and 202
: 2) Position excess letdown
: 3)  Place letdown flow control              diversion valve 215 to valves 200 A B C switch to                NORMAL to direct flow to REMOTE                                  the VCT.
: 4)  Open letdown stop valve              3) Verify seal water return LCV 459 and return to AUTO                containment isolation valve 222 open.
: 5)  Place low pressure letdown backpressure controller              4)  Verify excess letdown flow PCV-135 in MANUAL and                    control valve HCV-123 adjust to 75 percent open                closed.
: 6)  Open letdown orifice stops            5) Open excess letdown to establish desired flow:                isolation stop valve 213.
o 200A, 75 gpm                        6)  Slowly open HCV-123 to o 200B, 45 gpm                          warmup the excess letdown o 200C, 75 gpm                          heat exchanger.
: 7) Set PCV-135 to maintain                7)  Establish desired excess pressure between 225 psig                letdown flow using HCV-123.
and 275 psig
: 8) Maintain excess letdown
: 8) Place PCV-135 in AUTO                      heat exchanger outlet temperature less than 195 0 F.
9 of 15
 
[2-ECA-O.1 Number:
STEP
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINEDI REV. 0 Revision Number:
: 11. Control Charaina And Letdown Flow To Maintain PRZR Level Between 28% (47% FOR ADVERSE CONTAINMENT)
And 50%
: 12. Establish PRZR Pressure Control:
: a. Check letdown - IN SERVICE          a. Use PRZR heaters and one PRZR PORV to maintain RCS pressure.
Go to Step 13.
: b. Check differential temperature      b. Use PRZR heaters and one PRZR between PRZR and auxiliary                PORV to maintain RCS pressure.
spray (TI-126)- LESS THAN 320°F          Go to Step 13.
: c. Use PRZR heaters and use auxiliary spray:
o Refer to 2-SOP-1.4, PRESSURIZER PRESSURE CONTROL 10 of 15
 
SACTION/EXPECTED RESPONEI                          RESPONSE NOT OBTAINED
: 13. Verify Natural Circulation:                          Increase dumping steam from intact SG(s)-
o RCS subcooling based on core exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE                    RCS SUBCOOLING OF (PSIG)            (ADVERSE CONTAINMENT) 0  - 400                    52 (83) 401    - 800                    36 (49) 801    - 1200                  23 (30) 1201        - 2500                  19 (26) o SG pressures            -    STABLE OR DECREASING o RCS hot leg temperatures                  -
STABLE OR DECREASING o Core exit TCs              -  STABLE OR DECREASING o RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE
: 14. Check If        Source Range Detectors Sýhould RP Fn~rqi7Pd:
      .......      ..  ...... 7 .....
: a. Check intermediate range flux                      a. Continue with Step 15. WHEN
              - LESS THAN IE-10 AMPS                            flux less than IE-10 amps, THEN do Steps 14b and 14c.
: b. Verify source range detectors                      b. Manually energize source range ENERGIZED                                      detectors.
: c.      Transfer nuclear recorders to source range scale 11 of 15
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.1              LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED              REV. 0 STEP      ACTION/EXPECTED RESPONSE                    RESPONSE NOT OBTAINED I
: 15. Verify Adeauate Shutdown Margin:
: a. Sample RCS
: b. Shutdown margin from graphs              b. Borate as necessary.
book - ADEQUATE
: 16. Maintain Plant Conditions -
STABLE:
o RCS pressure o PRZR level o RCS temperature o Intact SG levels
: 17. Verify SI System Flow Not Required:
: a. RCS subcooling based on core          a. Go to 2-ECA-O.2, LOSS OF ALL exit TCs    - GREATER THAN VALUE          AC POWER RECOVERY WITH SI OBTAINED FROM TABLE:                        REQUIRED, Step 1.
WR RCS PRESSURE          RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0  -  400            52 (83) 401  -  800            36 (49) 801  -  1200          23  (30) 1201  -  2500          19 (26)
: b. PRZR level - GREATER THAN 14%          b. Control charging flow to (33% FOR ADVERSE CONTAINMENT)              maintain PRZR Level. IF PRZR level can NOT be maintained, THEN go to 2-ECA-O.2, LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED, Step 1.
12 of 15
 
Number:
2-ECA-O.1
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED      Rev REV. Nu 0 I STEP      ACTION/EXPECTED RESPONSE            RESPONSE NOT OBTAINED
: 18. Try To Restore Offsite Power To      Maintain plant conditions stable All AC Busses:                      .using 480V power.
o 2-SOP-27.1.3, OPERATION OF 13.8KV SYSTEM o 2-SOP-27.1.4,  6900 VOLT SYSTEM o 2-AOP-138KV-1, LOSS OF POWER TO 6.9KV BUS 5 AND/OR 6 o 2-AOP-480V-1, LOSS OF NORMAL POWER TO ANY 480V BUS
: 19. Go To 2-ES-0.2  NATURAL CIRCULATION COOLDOWN, Step 1
                                        -END-13 of 15
 
2-ECA-O.1                LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED                          REV. 0 ACTION/EXPECTED        RESPONSE                  RESPONSE NOT OBTAINED ATTACHMENT 1                    (Attachment  page 1 of 1)
SI RESET
    *  *  *  *  *  * *  * *  *  *  *  * * *  * * *  * *  *  *  *  * *  * * *  *  *  * * * * *  * 'i *  * *
    *t                                                CAUTION                                                  *
                                                                                                                *r
* Placing key switches to DEFEAT will prevent auto SI actuation.
I.      Reset SI:
a)  Check all CCW pumps          - RUNNING      a)    Place non-running CCW pumps CCR control switches in PULLOUT.
b)  Place controls for main AND bypass feedwater regulating valves to CLOSE c)  Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1
                              -  AND  -
o Train B SIA-2 d)  One at a time, depress Safety Injection reset buttons (Panel SB-2):
o Train A o Train B e)    Verify Train A AND B - RESET                e)    Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o SIA-1 o SIM-1 o SIA-2 o SIM-2
                                                      -END-14 of 15
 
2-ECA -0.1            LOSS OF ALL AC POWER RECOVERY WITHOUT SI-REQUIRED                  REV. 0 Number:        1
 
==Title:==
1 Revision  Number:
ATTACHMENT 2                (Attachment  page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the following table to d*ptprminp    4ARNV Pniiinmpnt  I nad rati ngs:
21 DG          22 DG              23 DG EQUIPMENT              BUS 5A    BUS 2A    BUS 3A      BUS 6A 21 SERVICE WATER PUMP            282 KW 22 SERVICE WATER PUMP                      282 KW OR 282 KW 23 SERVICE WATER PUMP                                              282 KW 24 SERVICE WATER PUMP            282 KW 25 SERVICE WATER PUMP                      282 KW OR 282 KW 26 SERVICE WATER PUMP                                              282 KW PRZR CONTROL HEATERS                                              277 KW 21 PRZR BU HEATERS                                    554 KW 22 PRZR BU HEATERS                          485 KW 23 PRZR BU HEATERS              485 KW 21 AFW PUMP                                            384 KW 23 AFW PUMP                                                        384 KW 21 FAN COOLER UNIT              250 KW 22 FAN COOLER UNIT              250 KW 23 FAN COOLER UNIT                          250 KW 24 FAN COOLER UNIT                                    250 KW 25 FAN COOLER UNIT                                                250 KW 21 SI PUMP                      316 KW 22 SI PUMP                                  316 KW    316 KW 23SI PUMP                                                          345 KW 21 SPRAY PUMP                    350 KW 22 SPRAY PUMP                                                      350 KW 21 RHR PUMP 22 RHR PUMP 303 KW 303 KW I
21 CHARGING PUMP                150 KW 22 CHARGING PUMP                                      150 KW 23 CHARGING PUMP                                                  150 KW, 21 RECIRC PUMP                  299 KW 22 RECIRC PUMP                                                    299 KW 21 CCW PUMP                      228 KW 22 CCW PUMP                                228 KW 23 CCW PUMP                                                        228 KW 21 LIGHTING TRANSFORMER                    150 KW (N)            150 KW (E) 22 LIGHTING TRANSFORMER                                225 KW 23 LIGHTING TRANSFORMER          225 KW TURBINE AUX OIL PUMP                                              112 KW STATION AIR COMPRESSOR            93 KW
                                                  -END-15 of 15
 
Procedure Use Is: Control Copy:
SEntergy                      0 Continuous Nuclear Northeast      IJ Reference      Effective Date: 4/',(16 7 n Information 2-ECA-0.2, Revision: 0 LOSS OF ALLACRQOWER RECOVERY Approved By:
Procedure4%ponsor, RP(
Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.2            LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED          REV. 0 A. PURPOSE This procedure provides actions to use engineered safeguards systems to recover plant conditions following restoration of 480V power.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from:
: 1) 2-ECA-O.O, LOSS OF ALL AC POWER,  Step 27, when 480V power is restored and SI is required.
: 2)  2-ECA-O.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REOUIRED, Step 5 and 17, if SI is required or any time after performing Step 9 if SI is actuated.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if  either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                              - OR  -
o Containment pressure greater than 4 psig.
I of 13
 
Number:
 
==Title:==
Revision Number:1 2-ECA-O.2              LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED            REV. 0 a *a a  *
* CAUTION Placing key switches to DEFEAT will prevent auto SI actuation.
NOTE CSF Status Trees should be monitored for information only. FRPs should NOT be implemented prior to completion of Step 11.
: 1. Check SI Signal Status - RESET        Reset SI:
: a. Check all CCW pumps running.
IF NOT, THEN place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE.
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1
                                                                - AND o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2):
o Train A o Train B
: e. Verify Train A AND B reset.
IF NOT, THEN verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o  SIA-1 o  SIM-1 o  SIA-2 o  SIM-2 2 of 13
 
2-ECA-0.2            LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED              REV. 0 Number:      fTitle:                                                        Revision Number:
: 2. Check RCP Thermal Barrier CCW Isolation Status:
: a. CCW pumps - ALL STOPPED            a. Go to Step 3.
: b. CCW return isolation valve        b. Manually isolate CCW to RCP outside containment - CLOSED:        thermal  barriers:
o MOV-789                            o Close CCW return isolation valve outside containment:
o MOV-789
                                                                - OR -
o Close CCW return flow control valve outside containment:
o FCV-625
: 3. Check RWST Level  - GREATER THAN      Establish cold leg recirculation:
9.24 FT
: a. Perform 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1
: b. Go to Step 5. OBSERVE CAUTION PRIOR TO STEP 5.
3 of 13
 
Number:
 
==Title:==
Revision Number: 1 2-ECA-o.2            LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED          REV. 0      j
: 4. Manually Align Valves To Establish SI Injection Mode:
: a. Verify SI pump suction valve      a. Manually open valve.
from RWST - OPEN:
o MOV-1810
: b. Align SI System valves:
: 1) Open RHR Hx CCW outlet valves:
o MOV-822A o MOV-822B "2)  Open RHR Hx outlet valves:
o MOV-746 o MOV-747 4 of 13
 
Number:
 
==Title:==
Revision Number:1 2-ECA-O.2                        LOSS OF ALL AC POWER RECOVERY WITH Sl REQUIRED                                REV. 0      j STE                ACTION/EXPECTED RESPONSE.                          RESPONSE NOT OBTAINED.
CAUTION o The loads placed on the energized 480V bus should NOT exceed the t
capacity of the power source.
II o Radiation levels and harsh environment                    conditions should be evaluated II
                .prior to performing local actions.
* ft  *    *
* ft * *  * *
* ft ft ft *
* ft ft  ft ft ft  ft ft ft ft ft ft ft *
* ft ft *
* ft ft ft ft  ft ft
: 5.        Manually Load Following Equipment On 480V Bus:
: a. CCW pump                                      a. IF one CCW pump can NOT be started, THEN refer to 2-SOP-4.1.2 COMPONENT COOLING SYSTEM OPERATION to establish backup cooling to the following:
o Charging pumps o RHR pumps o SI pumps
: b. RHR pump
: c. SI pump This Step continued on the next page.
5 of 13
 
2-ECA-O.2              LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED            REV. 0 Number:        ITitle:                                                        Revision Number: 1 STEP      ACTION/EXPECTED RESPONSE              REPNSE NOT OTIE
: d. Containment Fan Coolers:
: 1) Start fan coolers
: 2)  NORM OUT valves - OPEN            2) Manually open valve(s).
IF any normal outlet valve on any fan cooler can NOT be opened, THEN perform the following:
a)  Notify TSC which containment fan cooler(s) are NOT, available.
b) Go to Step 5d3).
: 3) TCV-1104 and TCV-1105 -          3) Manually open valve(s).
BOTH OPEN
: e. Service water pump on essential header
: f. 21 Instrument air compressor 6 of 13
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.2                        LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED                          REV. 0 CAUTION
        *W t
o City water for AFW pumps will be necessary if                        CST level decreases to less than 2 ft.
* o If SG narrow range level decreases to less than 10% (27% FOR ADVERSE
* CONTAINMENT) and AFW flow is less than 400 gpm, the motor-driven AFW                                  Q
* pumps should be manually loaded on 480V bus to supply water to the SGs.                                Q
        *  *  *  * *    *  * *    *  * * * * * * *
* ft  *    * *  *  *  *  *  *  * * * * * * * *  *  *  *  *    *
* NOTE If motor-driven AFW pump operation is NOT required, pump switches should be maintained in PULLOUT to prevent automatic start.
0    6.        Check Intact SG Levels:
: a. Narrow range level - GREATER                  a. Maintain AFW flow greater than THAN 10% (27% FOR ADVERSE                          400 gpm until narrow range CONTAINMENT)                                        level greater than 10% (27%
FOR ADVERSE CONTAINMENT) in at least one SG.
IF AFW flow NOT greater than 400 gpm, THEN:
: 1) Open AFW flow control valves as necessary.
: 2)  Start motor-driven AFW pumps as necessary.
: b. Control AFW flow to maintain narrow range level between 10%
(27% FOR ADVERSE CONTAINMENT) and 50%
7 of 13
 
[  2-ECA-O.2 Number:
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED            REV. 0 Revision Number:
STEP      ACI  ONEPCE EPNERSOS O OBT INE
: 7. Verify Containment      Isolation Phase A:
: a. Phase A - ACTUATED                    a. Manually actuate phase A.
o Train A master relay CAI (above rack E) o Train B master relay CA2 (above rack F)
: b. Phase A valves - CLOSED              b. Manually close valves. IF valves can NOT be manually closed, THEN locally close valves.
: c. IVSW valves - OPEN:                  c. Manually open valves.
0  1410 0  1413 0  SOV-3518 0  SOV-3519
: d. WCP valves    - OPEN:                d. Manually open valves.
0  PCV  1238 0  PCV  1239 0  PCV  1240 0  PCV  1241
: e. Place personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: f. Dispatch NPO to periodically check:
: 1) IVSW tank:                            1) Direct NPO to fill or pressurize tank as o Level    - GREATER THAN 92%            necessary.
o Pressure    - GREATER THAN 57 PSIG
: 2) WCP header pressures -                2)  Direct NPO to verify GREATER THAN 52 PSIG                    station air backup OR N2 backup are aligned as
                                                            .necessary.
8 of 13
 
r2-ECA-0.2 Number:
 
==Title:==
LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED            REV. 0 Revision Number:
: 8. Verify Containment Ventilation Isolation:
: a. Containment purge valves          a. Manually close valves.
CLOSED:
IF valves can NOT be closed, o  FCV-1170                          THEN close valves from fan o  FCV-1171                          room.
o  FCV-1172 o  FCV-1173                          IF valves can NOT be closed, THEN dispatch operator and HP personnel to close outside valves by isolating instrument air:
o FCV-1171,  IA-780 o FCV-1173,  IA-779
: b. Containment pressure relief        b. Manually close valves.
valves - CLOSED:
IF valves can NOT be closed, o PCV-1190                            THEN close valves from fan o PCV-1191                            room.
o PCV-1192 IF valves can NOT be closed, THEN dispatch operator AND HP personnel to close outside valves by isolating instrument air:
o PCV-1191,  IA-777 o PCV-1192,  IA-778 IF containment pressure relief can NOT be isolated, THEN locally close the following valves (Fan House 88 ft. el):
o UH-1013, Pressure Relief Fan Inlet Stop o UH-1014, Pressure Relief Fan Outlet stop 9 of 13
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.2              LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED              REV. 0
  ~~ACTION/EXPECTED RESPOSE                        FRESPONSE NOT OBTAINEDI NOTE ATTACHMENT 1 provides a list  of Phase B valves.
: 9. Verify Containment Spray Not Reauired:
: a. Containment Pressure    HAS        a. Perform the following:
REMAINED LESS THAN 24 PSIG
: 1) Verify containment spray valves in proper emergency alignment:
o Spray pump discharge valves open:
o MOV-866A o MOV-866B o MOV-866C o MOV-8660 IF NOT, THEN manually align valves as necessary.
IF valves can NOT be manually aligned. THEN locally align valves.
: 2) Manually load containment spray pump on 480V bus.
: 3) Verify containment isolation Phase B valves
                                                          .closed.
IF NOT, THEN manually close valves.
IF valves can NOT be manually closed, THEN locally close valves.
: 4) Verify IVSW isolation valves open:
o  7864 o  7865 o  7866 o  7867
: 5) Go to Step 11.
10 of 13
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.2            LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED              REV. 0 STP        ACTION/EXPECTED RESPONSEI                RESPONSE NOT OBTAINEDI
: 10. Place Containment Spray Pump Switches In AUTO
: 11. Check RCP Seal  Isolation Status:
: a. RCP seal injection isolation        a. Locally close valves before valves outside containment -              starting charging pumps.
CLOSED:
o  MOV-250A o  MOV-250B o  MOV-250C o  MOV-250D
: 12. Go To 2-E-1 , LOSS OF REACTOR OR CSFrnNfARY flonlANT  Stpn 1
                                            - END -
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2-ECA-:.2            LOSS    ALL AC POWER RECOVERY WITH SI REQUIRED            REV.
ROF  0 ATTACHMENT 1            (Attachment page 1 of 1)
CONTAINMENT ISOLATION VALVES
: 1. The following valves will close on Phase A isolation:
VALVE NAME                                        VALVE NUMBER(s)
CCW from excess letdown Hx                        796, 793 CCW to excess letdown Hx                          798, 791 Vent header from RCDT                              1786, 1787 Gas analyzer PRT                                  548, 549 Gas analyzer RCDT                                  1788, 1789 Letdown from regenerative HX                      201, 202 Letdown oriface control stop valves                200A, 200B, 200C Make-up to PRT                                    519, 552 Containment sump pumps to WDS - hold-up tank      1723, 1728 Instrument air to containment                      PCV-1228 RCDT to WDS - hold-up tank                        1702, 1705 SG blowdown and sampling system                    .PCV-1214, 1214A PCV-1215, 1215A PCV-1216, 1216A PCV-1217, 1217A Radiation monitor return to containment            PCV-1234, 1235 PCV-1236, 1237 Accumulator samples                                956G, 956H Sample - pressurizer steam                        956A, 956B Sample    pressurizer liquid                      956C, 956D Sampl e - RCS loops                                21, 22, 23 MOV-956E, 956F SJAE to containment                                1229, 1230 Hi-Rad sample system return to containment sump    MOV-4399, 5132 Recirculation pump discharge sample line          MOV-990A, 990B Accumulator N2 Supply Line Stop                    863 2      The following valves will close on Phase B isolation:
VALVE NAME                                            VALVE NUMBER(s)
Component cooling  to RCS pumps                      MOV-769, 797 Component cooling    from RCS thermal barrier return  MOV-789, FCV-625 Component cooling  from RCS motor bearing return    MOV-786, 784 Seal water return  containment isolation valve      MOV-222
                                          -END-12 of 13
 
Number:
 
==Title:==
Revision Number:
2-ECA-O.2            LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED                  REV. 0 ATTACHMENT 2                (Attachment page 1 of 1) 480V EQUIPMENT LOAD RATINGS
: 1. Use the followinQ table to determine 480V eauiDment load ratings:
21 DG          22 DG              23 DG EQUIPMENT          BUS 5A    BUS 2A    BUS 3A      BUS 6A 21 SERVICE WATER PUMP      282 KW 22 SERVICE WATER PUMP                  282 KW OR 282 KW 23 SERVICE WATER PUMP                                        282 KW 24 SERVICE WATER PUMP      282 KW 25 SERVICE WATER PUMP                  282 KW OR 282 KW 26 SERVICE WATER PUMP                                        282 KW PRZR CONTROL HEATERS                                          277 KW 21 PRZR BU HEATERS                                554 KW 22 PRZR BU HEATERS                    485 KW 23 PRZR BU HEATERS        485 KW 21 AFW PUMP                                      384 KW 23 AFW PUMP                                                  384 KW 21 FAN COOLER UNIT        .250 KW 22 FAN COOLER UNIT          250 KW 23 FAN COOLER UNIT                    250 KW 24 FAN COOLER UNIT                                250 KW 25 FAN COOLER UNIT                                            250 KW 21 SI PUMP                  316 KW 22 SI PUMP                            316 KW    316 KW 23 SI PUMP                                                    345 KW 21 SPRAY PUMP              350 KW 22 SPRAY PUMP                                                350 KW 21 RHR PUMP                                      303 KW 22 RHR PUMP                                                  303 KW 21 CHARGING PUMP            150 KW 22 CHARGING PUMP                                  150 KW 23 CHARGING PUMP                                              150 KW 21 RECIRC PUMP              299 KW 22 RECIRC PUMP                                                299 KW 21 CCW PUMP                228 KW 22 CCW PUMP                            228 KW 23 CCW PUMP                                                  228 KW 21 LIGHTING TRANSFORMER                150 KW (N)            150 KW (E) 22 LIGHTING TRANSFORMER                          225 KW 23 LIGHTING TRANSFORMER    225 KW TURBINE AUX OIL PUMP                                          112 KW STATION AIR COMPRESSOR      93 KW
                                            -END-13 of 13
 
a-- Entergy                    Procedure Use Is:
R1 Continuous Control Copy:
Nucleaz Northeast natTea,,.
O Reference      Effective Date: 6/,407
                  ..4.
a*      o  Information Gel
                ! A-2-ECA-1.1, Revision: 0 LOSS OF EMERGENC-                  OLANT RECIRCULATION Approved By:
    ~42      -7 Procedke Sponsor, RPO/ I Team P Procedure Owner PARTIAL REVISION
 
Number:
 
==Title:==
Revision Number:
2-ECA-1.1                LOSS OF EMERGENCY COOLANT RECIRCULATION              REV. 0 A. PURPOSE This procedure provides actions to restore emergency coolant recirculation capability, to delay depletion of the RWST by adding makeup and reducing outflow, and to depressurize the RCS to minimize break flow.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is    entered from:
: 1) 2-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 16,  when cold leg recirculation capability cannot be verified.
: 2)  2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 9. when containment water level is insufficient to establish recirculation flow.
: 3) 2-ES-1.3. TRANSFER TO COLD LEG RECIRCULATION, ATTACHMENT 2, COLD LEG RECIRCULATION USING RHR PUMPS, Step 2, when at least one flow path from the sump cannot be established or maintained.
: 4) 2-ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 28,  when adequate recirculation flow cannot be maintained.
: 5)  2-ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 6, when a LOCA outside containment cannot be isolated.
C. ADVERSE CONTAINMENT CONDITIONS EOP values for adverse containment should be used if either of the following conditions exist:
o Containment radiation levels greater than 1E5 R/hr.
                                - OR -
o Containment pressure greater than 4 psig.
1 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-I c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
Number:
 
==Title:==
]Revision Number:
2-ECA-1.1                    LOSS OF EMERGENCY COOLANT RECIRCULATION                  REV. 0 CAUTION
* o If emergency coolant recirculation capability is restored during this
* procedure, further recovery actions should continue by returning to
* procedure and step in effect.
fft o Foldout page contains criteria to transition to 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1, whenever all trains of recirculation are affected by sump blockage.
o IF sump suction or RWST suction is    lost to any pump(s),  the pump(s) should be stopped:                                                                  *
        "    o RWST level less than 3.0 ft for SI,      RHR and charging pumps.                  f
* o RWST level less than 2.0 ft for containment spray pumps.
ft                                                                                        ft
: 1.      VERIFY Recirculation Trains NOT          IF both trains are affected such Affected Rv Sumn Rlockaae                that at least one train of recirculation flow can NOT be
: a. Indications of sump blockage          established or maintained, THEN may include:                          GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT
: 1) LOW HEAD INJECTION LINE LOW        CAUSED BY SUMP BLOCKAGE, Step 1.
FLOW alarm on panel SBF-1
: 2)  SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
: 3)  Indications of erratic or reduced flow
: 4) Abnormal sump level indication 2 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d)  Abnormal sump level indication
 
Number:
 
==Title:==
Revision Number:
2-ECA-1.1                LOSS OF EMERGENCY COOLANT RECIRCULATION                    REV. 0 STP        ACTION/EXPECTED RESPONSEI                RESPONSE NOTOBTAINEDI
: 2. Check Emergency Coolant                  Try to restore any recirculation Recirculation Enuioment    -            flowpath on at least one train.
AVAILABLE o Recirculation pump and flow path
                      -  OR o RHR pump and recirculation flow path
                        - OR -
o SI pump and recirculation flow path using:
o Recirculation pump OR -
o RHR pump
: 3. Verify Containment Fan Coolers -
IN SERVICE:
: a. Five fan coolers    RUNNING        a. Manually start fan cooler(s).
: b. NORM OUT valves    OPEN            b. Manually open valve(s).
IF any normal outlet valve on any fan cooler can NOT be opened, THEN perform the following:
: 1) Notify TSC which containment fan cooler(s) are NOT available.
: 2)  Go to Step 3c.
: c. TCV-1104 and TCV-1105 - BOTH        c. Manually open valve(s).
OPEN 3 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
STP        ACTION/EXPECTED rESPONSEI              RESPONSE NOT OBTAINEDI
* 4. Check RWST Level  - GREATER THAN      Go to step 26.
3.0 FT
: 5. Determine Containment Spray Requirements:
: a. Determine number of spray pumps required from table:
RWST            CONTAINMENT          FAN COOLERS RUNNING    SPRAY PUMPS LEVEL            PRESSURE            IN EMERGENCY MODE      REQUIRED Greater than 47 psig                                2 Greater            Between                    0, 1                2 than            2 psig and                2. 3,  4            1 9.24 ft            47 psig                      5                0 Less than 2 psig.                                  0 Greater than 47 psig                                2 Between            Between                      0                2 9.24 ft          2 psig and                1, 2,  3            1 and 2 ft            47 psig                    4,  5              0 Less than 2 psig                                  0 Less than              -                                          0 2 ft
: b. Spray pumps running    EQUAL TO    b. Manually operate spray pumps NUMBER REQUIRED                        and associated discharge valves as necessary.
4 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d)  Abnormal sump level indication
 
Number:              ITitle:                                                                          Revision Number:
2-ECA-1.1                        LOSS OF EMERGENCY COOLANT RECIRCULATION                                  REV. 0
                              ..    ..    ..... I.....
* REPOS      NOT
                                                                                    . OBTAINED.
* t" CAUTION                                                  t Radiation levels and harsh environment conditions should be evaluated prior to performing local actions.                                                                        t
: 6.      Add Makeup To RWST As Necessary:
: a. Align makeup to RWST per 2-SOP-10.1.1, SAFETY INJECTION ACCUMULATORS AND REFUELING WATER STORAGE TANK OPERATIONS CAUTION                                                    t City water for AFW pumps will be necessary if                      CST level decreases to less
* than 2 ft.                                                                                                *
* A  *    *  *  *
* A  * * *  * * *    * *  -    *  * * *    * *
* A  *  *  *  * * * *  * *  *  *  *  *  *
* 0    7.      Check Intact SG Levels:
: a. Narrow range level - GREATER                  a. Maintain total feed flow THAN 10%(27% FOR ADVERSE                          greater than 400 gpm until CONTAINMENT)                                      narrow range level greater than 10% (27% FOR ADVERSE CONTAINMENT) in at least one SG.
: b. Control feed flow to maintain                b. IF narrow range level in any narrow range level between 10%                    SG continues to increase, THEN (27% FOR ADVERSE CONTAINMENT)                    stop feed flow to that SG.
and 50%
5 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
Number:
 
==Title:==
Revision Number:
2-ECA-1.1                    LOSS OF EMERGENCY COOLANT RECIRCULATION                    REV. 0 STP    ACTION/EXPECTED RESPONSE l                  RESPONSE NOT OBTAINEDI
: 8. Initiate RCS Cooldown To Cold Shutdown:
: a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 0 F/HR
: b. Dump steam to condenser from            b. Manually or locally dump steam intact SG(s):                                from intact SG(s):
: 1) Check condenser      - AVAILABLE          o Use SG atmospheric steam dump:
: 2)  Place steam dump controller switch to manual and adjust                o Refer to 2-SOP-ESP-O01, for zero output.                              LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3)  Transfer condenser steam                      for local operation as dump to pressure control                      necessary.
mode and adjust manual setpoint as necessary.                              - OR -
o Use turbine-driven AFW pump.
IF no intact SG available, THEN use faulted SG.
: 9. Check SI System pump Status:                Go to Step 19.
o SI pumps      -  ANY RUNNING
                        -  OR -
o RHR pumps        ANY RUNNING IN SI MODE 6 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
CAUTION o If offsite power is lost after SI reset, manual action may be required to restart safeguards equipment.
o Overriding breaker anti-pump/lockout may require placing control switches to TRIP or may require Containment Spray Reset
* o Placing key switches to DEFEAT will prevent auto SI actuation.
10      Rese
* t    *I  If  Neces    *sary:**            *      *  *  *  *    * **        *  * *
: a. Check all CCW pumps                -  RUNNING      a. Place non-running CCW pumps CCR control switches in PULLOUT.
: b. Place controls for main AND bypass feedwater regulating valves to CLOSE
: c. Verify Automatic Safeguards Actuation key switches on Panel SB-2 in DEFEAT position:
o Train A SIA-1 o Train B SIA-2
: d. One at a time, depress Safety Injection reset buttons (Panel SB-2) o Train A o Train B
: e. Verify Train A AND B - RESET                        e. Verify Relays reset (Top of Safeguards Initiation Racks 1-1 AND 2-1):
o  SIA-1 o  SIM-1 o  SIA-2 o  SIM-2 7 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
[2-ECA-1.1 Number:      ITitle:
LOSS OF EMERGENCY COOLANT RECIRCULATION                REV. 0 Revision Number:
: 11. Establish One Train Of SI System Flow:
: a. SI pump - ONLY ONE RUNNING          a. Start or stop SI pumps to establish only one pump running.
: b. RCS pressure - LESS THAN            b. Stop RHR pumps. Go to Step 12.
320 PSIG (340 PSIG FOR ADVERSE CONTAINMENT)
: c. RHR pump - ONLY ONE RUNNING        c. Start or stop RHR pumps to establish only one pump running.
: 12. Verify No Backflow From RWST To Containment Sump:
: a. Containment sump valves    - ANY
: a. IF both containment sump OPEN:                                  valves closed. THEN go to Step 13. OBSERVE CAUTION o MOV-885A                            AND NOTE PRIOR TO STEP 13.
o MOV-885B
: b. Valve from RWST to RHR pump -      b. Manually close valve.
CLOSED o MOV-882 8 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage. THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-I
        ,c) Indications of erratic or reduced flow d)  Abnormal sump level  indication
 
[2-ECA-1.1 Number:
 
==Title:==
LOSS OF EMERGENCY COOLANT RECIRCULATION                              REV. 0 Revision Number: 1 S*                                                        CAUTION
* If RCP seal cooling had previously been lost, the affected RCP(s)                                should
* NOT be started prior to a status evaluation.
        *  *  *  *  *    *  *  * *  *  *r  *  * *  * *  *  *  *  * *  * *  *  * *  * * *  * * . * *  *  *  *  *
* NOTE RCPs should be run in the following order to provide normal PRZR spray:
RCP 24, RCP 23. Running 23 RCP may require starting additional RCPs to provide adequate spray flow.
: 13.        Check If An RCP Should Be Started:
: a. All RCPs        -  STOPPED                        a. Perform the following:
: 1) Stop all    but 24 RCP.
: 2)  IF 24 RCP already stopped.
THEN ONLY stop RCP(s) NOT required to provide PRZR spray.
: 3)  Go to Step 14.
: b. RCS subcooling based on core                        b. Go to Step 19.
exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE                    RCS SUBCOOLING OF (PSIG)                (ADVERSE CONTAINMENT) 0      400                  52  (83) 401    -800                      36  (49) 801    -1200                    23  (30) 1201      -2500                    19  (26)
This Step continued on the next page.
9 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
STP    ACTION/EXPECTED RESPONSEI              RESPONSE NOT OBTAINEDI
: c. Try to start 24 RCP:              c. IF 24 RCP can NOT be started, THEN start RCP(s) as required
: 1) Check containment                    to provide PRZR spray flow AND i conditions - NOT ADVERSE            go to Step 14.
: 2) Check containment sump level - LESS THAN 42'10 1/2"
: 3) Reset MCC 28 and MCC 28A
: 4)  Establish conditions for starting RCP(s) per 2-SOP-1.3, REACTOR COOLANT PUMP OPERATION
: 5) Start 24 RCP                                                        I 10 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION'LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d)  Abnormal sump level indication
 
ACheckIfN/EXCaBeTE RS
        *14.                          tT                PONiSnE    OBTAINED
*14. Check If SI Can Be Terminated:
: a. Check RVLIS indication:                  a. Go to Step 19.
o Natural circulation range -
GREATER THAN 60% IF NO RCP RUNNING OR -
o RCP running range - GREATER THAN 22% IF ONE RCP RUNNING
                      - OR  -
o RCP running range - GREATER THAN 29% IF TWO RCPs RUNNING
                      - OR -
o RCP running range - GREATER THAN 41% IF THREE RCPs RUNNING
                      - OR -
o RCP running range - GREATER THAN 60% IF FOUR RCPs RUNNING
: b. RCS subcooling based on core            b. Establish minimum SI flow to exit TCs - GREATER THAN VALUE              remove decay heat. Perform OBTAINED FROM TABLE:                        the following:
: 1) Determine minimum SI flow WR RCS PRESSURE            RCS SUBCOOLING OF          required from (PSIG)          (ADVERSE CONTAINMENT)          FIGURE ECA11-1.
0  -  400              102 (133)          2)  Establish minimum SI flow.
401  -  800              86 (99) 801  - 1200              73 (80)            3) Go to Step 19.
1201  -  2500              69 (76) 11 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow.from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-I c) Indications of erratic or reduced flow d) Abnormal sump level indication
: 15. Reset Containment Isolation Phase A And Phase B:
: a. Place IVSW switches to OPEN on SN panel:
o 1410 o 1413 o SOV-3518 o SOV-3519
: b. Place CNTMT RAD MON WCPS VALVES control switch to OPEN on SN panel
: c. Verify personnel AND equipment hatch solenoid control switches to INCIDENT on SM panel
: d. Place control switches for all remaining Phase A isolation valves to CLOSE on SN panel
: e. One at a time,  depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B
: f. Verify Train A AND B  - RESET    f. IF signal does NOT reset,  THEN:
: 1) Place key switches to BYPASS.
: 2) One at a time, depress Phase A reset buttons:
o CI Phase A Train A o CI Phase A Train B IF signal can NOT be reset, THEN reset relays CA1 AND CA2 on top of Safeguards Initiation Racks 1-2 AND 2-2.
This Step continued on the next page.
12 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
STP    ACTION/EXPECTED, RESPONSEI            RESPONSE NOT OBTAINEDI
: g. Check Phase B - ACTUATED          g. Go To Step 16.
: h. Containment pressure - LESS        h. Perform the following:
THAN 17 PSIG
: 1) WHEN containment pressure less than 17 psig, THEN do Steps 15i through 15k.
: 2) Continue with Step 16.
: i. One At.A Time. Depress Containment Spray Reset Pushbuttons:
o Spray SYS Reset Train A o Spray SYS Reset Train B
: j. One at a time,  depress Phase B reset buttons:
o CI Phase B Train A o CI Phase B Train B
: k. Verify Train A AND B - RESET      k. Verify Relays reset (Top Of
                                              *Safeguards Initiation Racks 1-2 AND 2-2):
o $1 o S2 o CB1 o CB2
: 16. Establish Instrument Air To Containment:
: a. Open PCV-1228                      a. Verify relays on top of Safeguards Initiation Racks 1-2 AND 2-2 are reset:
o CAI o CA2 13 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1 I. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
[2-ECA-1.1 Number:
0-7
 
==Title:==
LOSS OF EMERGENCY COOLANT RECIRCULATION ON/EXPECTED RES  NI              RESPONSE NOT OBTAINEDp" REV. 0 Revision Number: 1
: 17. Stop SI System Pumps And Place In AUTO:
o RHR pumps o SI pumps 14 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
INumber:Title:                                                                                                      Revision Number:
2-ECA-I.1                      LOSS OF EMERGENCY COOLANT RECIRCULATION                                                  REV. 0 CAUTION If RWST level decreases to less than 15 ft, charging pumps that are started or running should be monitored for loss of suction which may result in pump damage.
    *    *  *    *
* a *  * * *  *  * * * * * * *  * * *    *  *      *  *    *  *  *    *  *  *  *  *  *  *  *  *  *  * *
: 18.        Establish Charging Flow:
: a. Charging pumps - AT LEAST ONE            a.      Perform the following:
RUNNING
: 1) IF CCW flow to RCP(s) thermal barrier is lost, THEN isolate seal injection to affected RCP(s) before starting charging pumps:
o Locally energize AND close seal injection isolation valves:
o    MOV-250A,        MCC    26AA,      A2 o    MOV-250C,        MCC    26AA,. B2 o    MOV-250B,        MCC    26BB.      L3 o    MOV-250D,        MCC    26BB,      M3
                                                                                              -    OR -
o Locally close seal injection needle valves (51 ft. el, Piping Penetration Area):
o    241A o    241B o    241C o    241D
: 2)      Start one charging pump.
: b. Check RWST      -    LESS THAN 15 FT        b.      IF RWST level decreases to less than 15 ft, THEN do Step 18c.              Continue with Step 18d.
This Step continued on the next page.
15 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
I) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
: c. Try to add makeup to RCS from alternate source:
: 1) Realign makeup to VCT per 2-SOP-10.1.1, SAFETY INJECTION ACCUMULATORS AND REFUELING WATER STORAGE TANK OPERATIONS
: 2) Manually set blender controls to supply water to charging pump suction.
: d. Establish 55 gpm charging flow:
: 1) Verify speed controller in MANUAL
: 2) Adjust charging pump speed to establish 55 gpm flow 16 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        .c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
- *T E    rACTION/EXPECTED RESPONSE              RESPONSE NOT e19. Verify Adequate RCS Makeup Flow:
: a. Check RVLIS indication:          a. Increase RCS makeup flow to maintain RVLIS indication as o Natural circulation range -          necessary.
GREATER THAN 60% IF NO RCP RUNNING
_ OR -
o RCP running range - GREATER THAN 22% IF ONE RCP RUNNING
                      - OR -
o RCP running range - GREATER THAN 29% IF TWO RCPs RUNNING
                      - OR -
o RCP running range - GREATER THAN 41% IF THREE RCPs RUNNING
                      - OR -
o RCP running range - GREATER THAN 60% IF FOUR RCPs RUNNING
: b. Core exit TCs  - STABLE OR        b. Increase RCS makeup flow to DECREASING                            maintain TCs stable or decreasing.
17 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
[2-ECA-1.1 Number:
STP
 
==Title:==
LOSS OF EMERGENCY COOLANT RECIRCULATION CTION/XPETEDRSONS                      RE*IISPONS NOT OBTINE REV. 0 Revision Number: 1 NOTE The upper head region may void during RCS depressurization if RCPs are not running. This will result in a rapidly increasing PRZR level.
: 20. DeDressurize RCS To Decrease RCS Subcoolinn:
: a. RCS subcooling based on core        a. Go to Step 21.
exit TCs - GREATER THAN VALUE OBTAINED FROM TABLE:
WR RCS PRESSURE      RCS SUBCOOLING OF (PSIG)      (ADVERSE CONTAINMENT) 0 - 400          62  (93) 401 - 800            46  (59) 801 - 1200            33 (40) 1201 - 2500            29 (36)
This Step continued on the next page.
18 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        .c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
STE        ACTION/ExPECTED RESPONSEI          RESPONSE NOT OBTAINEDl
: b. Use normal PRZR spray          b. Use one PRZR PORV. IF RCS can NOT be depressurized using any PRZR PORV, THEN use auxiliary spray:
: 1) Maintain RCP seal injection 6 gpm to 10 gpm.
: 2)  Reduce charging pump speed to minimum flow.
: 3) Close charging line flow control valve:
o HCV-142
: 4)  Close the charging stop valves:
o 204A - Loop 22 o 204B - Loop 21
: 5) Close the pressurizer spray valves:
o PCV-455A o PCV-455B
: 6)  Open auxiliary spray valve:
o 212
: 7) Initiate spray slowly using HCV-142.
: 8) Adjust charging pump speed to increase spray flow.
This Step continued on the next page.
19 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-I b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
STP    ACTION/EXPECTED RESPONSEI                  RESPONSE NOT OBTAINEDl
: c. Depressurize RCS until either            c. If RCS subcooling less than of the following conditions                value obtained from table satisfied:                                  below. THEN increase RCS makeup flow as necessary to o PRZR level  -  GREATER THAN              restore subcooling:
71% (65% FOR ADVERSE CONTAINMENT)
WR RCS PRESSURE      RCS SUBCOOLING OF
                  - OR -                              (PSIG)      (ADVERSE CONTAINMENT) o RCS subcooling based on core                0 - 400          52 (83) exit TCs:                                401 - 800            36(49) 801 - 1200          23 (30)
BETWEEN VALUE OBTAINED FROM            1201 - 2500          19 (26)
FIRST TABLE WR RCS PRESSURE        RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400              52 (83) 401 - 800              36 (49) 801 - 1200              23 (30) 1201 - 2500              19 (26)
AND VALUE OBTAINED FROM SECOND TABLE WR RCS PRESSURE          RCS SUBCOOLING OF (PSIG)        (ADVERSE CONTAINMENT) 0 - 400              62 (93) 401 - 800              46 (59) 801 - 1200              33 (40) 1201 - 2500              29 (36)
: d. Stop RCS depressurization 20 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
[ Number:
2-ECA-1.1
 
==Title:==
LOSS OF EMERGENCY COOLANT RECIRCULATION Revision Number:
REV. 0 STP      ACTION/EXPECTED RESPONSE                REPNSO
                                      '  ý ]    ý    I REýSPONSE
                                                                ýNOTý
: 21. C~heck If RHR.System Should Be Placed In Service:
: a. Check both the following:            a. Go to Step 22.
o RCS temperatures    -  LESS THAN 350OF o RCS pressure - LESS THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Consult TSC to determine if RHR System should be placed in service
: 22. Check If SI Accumulators Should Be Isolated:
: a. At least two RCS hot leg              a. Continue with Step 23. WHEN temperatures - LESS THAN 350°F          at least two RCS hot leg temperatures less than 3500F, THEN do steps 22b through 22d
: b. Locally restore power to isolation valves:
0  894A  (MCC  26A) 0  894C  (MCC  26A) 0  894B  (MCC  26B) 0  894D  (MCC  26B)
This Step continued on the next page.
21 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT. CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
: c. Close all SI accumulator        c. Vent any unisolated isolation valves                  accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN consult the TSC to determine contingency actions.
: d. Open all SI accumulator isolation valve breakers 22 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
Number:
 
==Title:==
Revision Number:
2-ECA-1.1                LOSS OF EMERGENCY COOLANT RECIRCULATION                REV. 0
  @23. Check If RCPs Must Be Stopped:
: a. Check the following:                a. IF neither condition satisfied, THEN go to Step 24.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                        -  OR  -
o Number 1 seal return flow -
LESS THAN 0.2 GPM
: b. Stop affected RCP(s)
: 24. Check RCS Temperature    - GREATER    Go to Step 35.
THAN 200°F
: 25. Check RWST Level      LESS THAN        Return to Step 1.
3.0 FT
: 26. Stop Pumps Taking Suction From RWST And Place Switches In PULLOUT Position:
o RHR pumps o SI pumps o Charging pumps
: 27. Check RWST Level:
: a. RWST Level    -  LESS THAN 2.0 FT    a. Continue with Step 28. WHEN RWST level less than 2.0 ft, THEN stop containment spray pumps.
: b. Stop containment spray pumps 23 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal  sump level indication
* CAUTION                              *
* Radiation levels and harsh environment conditions should be evaluated *
* prior to performing local actions.                                    *
: 28. Try To Add Makeup To RCS From Alternate Source:
: a. Realign makeup to VCT per 2-SOP-10.1.1. SAFETY INJECTION ACCUMULATORS AND REFUELING WATER STORAGE TANK OPERATIONS
: b. Set blender controls to manually supply water to charging pump suction
: c. Start charging pumps
: d. Establish charging flow by adjusting charging pump speed controller as necessary 24 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        ,c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
Number:
 
==Title:==
Revision Number:1 2-ECA-1.1                  LOSS OF EMERGENCY COOLANT RECIRCULATION                  REV. 0 STP      ACTION/EXPECTED RESPONSE                RESPONSE NOT OBTAINED
* CAUTION To prevent main steamline isolation,    steam dump to condenser should NOT exceed 0.5 E6 lbs/hr per SG.
: 29. Check If All Intact SGs Should Be DeDressurized To 710 nsid:
: a. Check SG pressures - GREATER        a. Go to Step 30.
THAN 710 PSIG
: b. Dump steam to condenser at          b. Manually or locally dump steam maximum rate, NOT to exceed              at maximum rate from intact 0.5 E6 lbs/hr per intact SG:            SG(s):
: 1) Check condenser - AVAILABLE          o Use SG atmospheric steam dump:
: 2) Place steam dump controller switch to manual and adjust          o Refer to 2-SOP-ESP-O01, for zero output.                        LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS
: 3)  Transfer condenser steam                for local operation as dump to pressure control                necessary.
mode and adjust manual setpoint as necessary.              o Use turbine-driven AFW pump.
: c. Check SG pressures - LESS THAN
: c. Return to Step 29b.
710 PSIG
: d. Stop SG depressurization 25 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
I lNumber:
NumeTi        Title-    LOSS OF EMERGENCY COOLANT RECIRCULATION            Revi *REV. I Num STEP    ACTION/EXPECTED RESPONSE]                  NSE NOT OBTAINED I
: 30. DeDressurize All Intact SGs To Inject SI Accumulators As Necessary:
: a. Dump steam to condenser as          a. Manually or locally dump steam necessary to maintain                  from intact SG(s) as necessary appropriate RVLIS indication:          to maintain appropriate RVLIS o Natural circulation range -          indication:
AT 60% IF NO RCP RUNNING            o Use SG atmospheric steam dump:
                      -  OR -
o Refer to 2-SOP-ESP-O01, o RCP running range - AT 22%                LOCAL EQUIPMENT OPERATION IF ONE RCP RUNNING                      AND COMPENSATORY ACTIONS for local operation as
                      - OR -                            necessary.
o RCP running range - AT 29%          o Use turbine-driven AFW pump.
IF TWO RCPs RUNNING
                      -  OR -
o RCP running range - AT 41%
IF THREE RCPs RUNNING
                      -  OR -
o RCP running range - AT 60%
IF FOUR RCPs RUNNING
: b. Check SG pressures  - LESS THAN    b. Return to Step 30a.
110 PSIG
: c. Stop SG depressurization 26 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step .1.
: 1) Indications of sump blockage may include:
a)  LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b)  SI PUMP SUCTION LOW PRESS alarm on panel SBF-1
        .c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
F Number:
2-ECA-1.I
 
==Title:==
LOSS OF EMERGENCY COOLANT RECIRCULATION Revision Number:
REV. 0
: 31. Check If SI Accumulators Should Be Isolated:
: a. At least two RCS hot leg            a. Continue with Step 32. WHEN temperatures - LESS THAN 3500F        at least two RCS hot leg temperatures less than 350 0 F, THEN do Steps 31b through 31d.
: b. Locally restore power to isolation valves:
o  894A (MCC  26A) o  894C (MCC  26A) o  894B (MCC  26B) o  894D (MCC  26B)
: c. Close all SI accumulator            c. Vent any unisolated isolation valves                      accumulators:
: 1) Close nitrogen supply valve to accumulators: HCV-863.
o IF HCV-863 will NOT close THEN locally close the following nitrogen valves:
o 1809 o 1811A o 1811B This Step continued on the next page.
27 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal  sump level indication
 
Number:
 
==Title:==
Revision Number: 1 2-ECA-1.1                  LOSS OF EMERGENCY COOLANT RECIRCULATION                  REV. 0 I
STIEP7-m NOT OBTAINED ACTION/EXPECTED RESPONSE I          *
                                                    ---RESPONSE RESPONSE  NOT OBTAINED    F-
: 2) Open the following valves as necessary:
o Accumulator 21:
o 891A o HCV-943 o Accumulator 22:
o 891B o HCV-943 o Accumulator 23:
o 891C o HCV-943 o Accumulator 24:
o 891D o HCV-943 IF an accumulator can NOT be isolated or vented, THEN consult the TSC to determine contingency actions.
: d. Open all SI accumulator isolation valve breakers
: 32. Check If RCPs Must Be Stopped:
: a. Check the following:                a. IF neither condition satisfied, THEN go to Step 33.
o Number 1 seal differential pressure - LESS THAN 200 PSID
                          -  OR -
o Number 1 seal return flow -
LESS THAN 0.2 GPM
: b. Stop affected RCP(s) 28 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel  SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
 
Number:        Tile:                                                        Revision Number: 1 2-ECA-I,1              LOSS OF EMERGENCY COOLANT RECIRCULATION                REV. 0
: 33. Depressurize All Intact SGs To Atmospheric Pressure:
: a. Maintain cooldown rate in RCS cold legs -LESS  THAN 1000 F/HR
: b. Dump steam to condenser            b. Manually or locally dump steam from intact SG(s):
o Use SG atmospheric steam dump:
o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
o Use turbine-driven AFW pump.
: 34. Check If RHR System Should Be Placed In Service:
: a. Check both the following:          a. Return to Step 33.
o RCS temperature - LESS THAN 350°1F o RCS pressure - LESS THAN 370 PSIG (280 PSIG FOR ADVERSE CONTAINMENT)
: b. Consult TSC to determine if RHR System should be placed in service 29 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3. LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW. HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication
: 35. Maintain RCS Heat Removal:
: a. Use RHR System if  in service
: b. Dump steam to condenser from      b. Manually or locally dump steam intact SGs                            from intact SG(s):
o Use SG atmospheric steam dump:
o Refer to 2-SOP-ESP-O01, LOCAL EQUIPMENT OPERATION AND COMPENSATORY ACTIONS for local operation as necessary.
OR -
o Use turbine-driven AFW pump.
IF no intact SG available and RHR system NOT in service, THEN use faulted SG.
: 36. Check Containment Hydrogen Concentration:
: a. Obtain a hydrogen concentration measurement:
o Dispatch chemistry personnel to obtain sample
                - OR -
o Use H2-02 analyzer on Accident Assessment Panel
: b. Hydrogen concentration  - LESS    b. Consult TSC for additional THAN 3.0% IN DRY AIR                  recovery actions.
: 37. Consult TSC
                                    -END-30 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow from Containment to RCS can NOT be established OR maintained due to sump blockage, THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal  sump level indication
 
Number:
 
==Title:==
Revision Number:
2-ECA-1.1                LOSS OF EMERGENCY COOLANT RECIRCULATION                REV. 0 FIGURE ECA11-1 FLOW RATE (GPM) 700 600 500 400 300 200 1 %4-1 100 0
1 2    3 10 2    3 4  5 100 3 4 -44 5 6 7 8 9 1000 2  3  4  5 i 7 10000 TIME (MINUTES)
FIGURE ECA11-1, MINIMUM SI FLOW RATE VERSUS TIME AFTER TRIP
                                              -END-31 of 31
 
FOLDOUT PAGE FOR 2-ECA-1.1
: 1. LOSS OF EMERGENCY COOLANT RECIRCULATION:
: a. IF at any time recirculation flow.from Containment to RCS can NOT be established OR maintained due to sump blockage. THEN GO To 2-ECA-1.3, LOSS OF EMERGENCY RECIRCULATION COOLANT CAUSED BY SUMP BLOCKAGE, Step 1.
: 1) Indications of sump blockage may include:
a) LOW HEAD INJECTION LINE LOW FLOW alarm on panel SBF-1 b) SI PUMP SUCTION LOW PRESS alarm on panel SBF-1 c) Indications of erratic or reduced flow d) Abnormal sump level indication}}

Latest revision as of 14:49, 14 January 2025

Supplement to Reply to Request for Additional Information Regarding Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance
ML082820162
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/03/2008
From: Robert Walpole
Entergy Nuclear Indian Point 2
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
NL-08-154, TAC MD9214
Download: ML082820162 (734)
v • d • e


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