ML15142A394: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 38: Line 38:
* The task you are to perform is:
* The task you are to perform is:
Establish Alternate Charging Flow Path through A HPSI Header Unit 2
Establish Alternate Charging Flow Path through A HPSI Header Unit 2
                                                                      -
* The performance level to be used for this JPM is Perform,
* The performance level to be used for this JPM is Perform,
* This is not a time critical JPM.
* This is not a time critical JPM.
Line 279: Line 278:
JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:
JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:
* The task you are to perform is:          Emergency Borate Unit 2.
* The task you are to perform is:          Emergency Borate Unit 2.
                                                              -
* The performance level to be used for this JPM is Perform
* The performance level to be used for this JPM is Perform
* This is not a time critical JPM.
* This is not a time critical JPM.
Line 421: Line 419:
JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:
JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:
* The task you are to perform is:          Cool the Quench Tank Unit 2.
* The task you are to perform is:          Cool the Quench Tank Unit 2.
                                                                  -
* The performance level to be used for this JPM is Perform
* The performance level to be used for this JPM is Perform
* This is not a time critical JPM.
* This is not a time critical JPM.
Line 488: Line 485:
PERFORM the following:
PERFORM the following:
B. ENSURES V6300, VENT VALVE, is CLOSED.                                    SAT STANDARD:              ENSURES V6300, VENT VALVE, is CLOSED.
B. ENSURES V6300, VENT VALVE, is CLOSED.                                    SAT STANDARD:              ENSURES V6300, VENT VALVE, is CLOSED.
UNSAT EXAMINERS CUE:        Quench Tank pressure is 3 psi
UNSAT EXAMINERS CUE:        Quench Tank pressure is 3 psi 9
                                                          .
EXAMINERS CUE:        V6300, VENT VALVE indicates red light off green light on.
9 EXAMINERS CUE:        V6300, VENT VALVE indicates red light off green light on.
COMMENTS:
COMMENTS:
NRC 19A S-4 Simulator Page 8 of 15
NRC 19A S-4 Simulator Page 8 of 15
Line 1,223: Line 1,219:
Appendix H, Operation of the IA and I B Instrument Air Compressors, Section 1: Placing IA Instrument Air Compressor in Service.
Appendix H, Operation of the IA and I B Instrument Air Compressors, Section 1: Placing IA Instrument Air Compressor in Service.
STEP 1 :(1)    ENSURE the following Breakers are aligned as indicated.
STEP 1 :(1)    ENSURE the following Breakers are aligned as indicated.
Bkr 41324 (MCC 1A6)    - Instrument Air Compr. 1A ON
Bkr 41324 (MCC 1A6)    - Instrument Air Compr. 1A ON SAT STANDARD:      ENSURE Bkr 41324 ON.
                                                                  -
SAT STANDARD:      ENSURE Bkr 41324 ON.
EXAMINERS CUE:      Bkr 41324 pointer indicates to the 12 o-clock position.              UNSAT If the candidate wants to stop the JPM because thE..
EXAMINERS CUE:      Bkr 41324 pointer indicates to the 12 o-clock position.              UNSAT If the candidate wants to stop the JPM because thE..
procedure and the Breaker TAG nomenclature do no agree, tell him that the US has confirmed that it is th right breaker.
procedure and the Breaker TAG nomenclature do no agree, tell him that the US has confirmed that it is th right breaker.
EXAMINERS NOTE:    The breaker TAG reads: INSTR AIR COMPR IA COMMENTS:
EXAMINERS NOTE:    The breaker TAG reads: INSTR AIR COMPR IA COMMENTS:
STEP 2:(1)    ENSURE the following Breakers are aligned as indicated.
STEP 2:(1)    ENSURE the following Breakers are aligned as indicated.
Bkr 42434 (MCC lAB)    - lnstr Air Compr Cooler Fan ON
Bkr 42434 (MCC lAB)    - lnstr Air Compr Cooler Fan ON SAT STANDARD:      ENSURE Bkr 42434 ON.
                                                                    -
SAT STANDARD:      ENSURE Bkr 42434 ON.
EXAMINERS CUE:      Bkr 42434 pointer indicates to the 12 o-clock position.              UNSAT COMMENTS:
EXAMINERS CUE:      Bkr 42434 pointer indicates to the 12 o-clock position.              UNSAT COMMENTS:
STEP 3:(1)    ENSURE the following Breakers are aligned as indicated.
STEP 3:(1)    ENSURE the following Breakers are aligned as indicated.
Bkr 42435 (MCC lAB)      lnstr Air Compr Cool System Wtr Pp ON
Bkr 42435 (MCC lAB)      lnstr Air Compr Cool System Wtr Pp ON SAT STANDARD:      ENSURE Bkr 42435 ON.
                                                                          -
SAT STANDARD:      ENSURE Bkr 42435 ON.
EXAMINERS CUE:      Bkr 42435 pointer indicates to the 12 o-clock position.              UNSAT COMMENTS:
EXAMINERS CUE:      Bkr 42435 pointer indicates to the 12 o-clock position.              UNSAT COMMENTS:
NRC 19A P-2 Turbine Building Page 4 of 10
NRC 19A P-2 Turbine Building Page 4 of 10
Line 1,246: Line 1,236:
STEP 4:(2)    V13197        1A Instr Air Comp Jacket Inlet IsolOPEN                    CRITICAL STEP STANDARD:      ALIGN Vi 31 97 to OPEN.
STEP 4:(2)    V13197        1A Instr Air Comp Jacket Inlet IsolOPEN                    CRITICAL STEP STANDARD:      ALIGN Vi 31 97 to OPEN.
SAT EXAMINERS CUE:    V13197 is rotated counter clockwise to hard stop.
SAT EXAMINERS CUE:    V13197 is rotated counter clockwise to hard stop.
COMMENTS:                                                                                          UNSAT STEP 5:(2)    Vi 3201        1 A lnstr Air Comp Jacket Outlet Isol OPEN
COMMENTS:                                                                                          UNSAT STEP 5:(2)    Vi 3201        1 A lnstr Air Comp Jacket Outlet Isol OPEN STANDARD:    ALIGN Vi 3201 to OPEN.                                                                SAT EXAMINERS CUE:    VI 3201 is fully counter clockwise to hard stop.                      UNSAT EXAMINERS NOTE: VI 3201 is already/normally aligned OPEN.
                                                                  -
STANDARD:    ALIGN Vi 3201 to OPEN.                                                                SAT EXAMINERS CUE:    VI 3201 is fully counter clockwise to hard stop.                      UNSAT EXAMINERS NOTE: VI 3201 is already/normally aligned OPEN.
COMMENTS:
COMMENTS:
STEP 6:(2)    SH13383        Air Comprs Outlet Hdr Isol CLOSE
STEP 6:(2)    SH13383        Air Comprs Outlet Hdr Isol CLOSE
Line 1,261: Line 1,249:
NRC 19A P-2 Turbine Building Page 5 of 10
NRC 19A P-2 Turbine Building Page 5 of 10


JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 8:(2)  VI 3417      Air Compr Coolers Inlet from Recirc Pump lsol OPEN
JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 8:(2)  VI 3417      Air Compr Coolers Inlet from Recirc Pump lsol OPEN STANDARD:    ALIGN VI 3417 to OPEN.                                                              SAT EXAMINERS CUE:  VI 3417 is fully counter clockwise to hard stop.
                                                                        -
STANDARD:    ALIGN VI 3417 to OPEN.                                                              SAT EXAMINERS CUE:  VI 3417 is fully counter clockwise to hard stop.
UNSAT EXAMINERS NOTE: V13417 is aireadylnormally aligned OPEN.
UNSAT EXAMINERS NOTE: V13417 is aireadylnormally aligned OPEN.
COMMENTS:
COMMENTS:
Line 1,665: Line 1,651:
End of Section 2
End of Section 2


FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE RESPOND TO CCW EXCESSIVE ACTIVITY UNIT I
FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE RESPOND TO CCW EXCESSIVE ACTIVITY UNIT I NRC C-8 Unit I Control Room This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC 19AC-8 Unit 1 Control Room Page 1 of 10
                                      -
NRC C-8 Unit I Control Room This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC 19AC-8 Unit 1 Control Room Page 1 of 10


JOB PERFORMANCE MEASURE Task:              Respond to CCW Excessive Activity  Unit 1 Faulted JPM?        No Facility JPM #:    0821030 KIA:                008.K1 .04 3.3 / 3.3 Knowledge of the physical connection and/or cause-effect relationship between the COWS and the following systems: RCS, in order to determine sources(s) of RCS leakage into the COWS.
JOB PERFORMANCE MEASURE Task:              Respond to CCW Excessive Activity  Unit 1 Faulted JPM?        No Facility JPM #:    0821030 KIA:                008.K1 .04 3.3 / 3.3 Knowledge of the physical connection and/or cause-effect relationship between the COWS and the following systems: RCS, in order to determine sources(s) of RCS leakage into the COWS.
Line 1,677: Line 1,661:
==References:==
==References:==
* ONOP 1-0310030, Component Cooling Water Off Normal Operations
* ONOP 1-0310030, Component Cooling Water Off Normal Operations
                                                  -
* ONOP 1-031 0031, Component Cooling Water Excessive Activity
* ONOP 1-031 0031, Component Cooling Water Excessive Activity
* 1-APP-01-S-6, Annunciator Response Procedure Validation Time:  15 minutes                                      Time Critical:        No Tools/EquipmentlProcedures Needed:
* 1-APP-01-S-6, Annunciator Response Procedure Validation Time:  15 minutes                                      Time Critical:        No Tools/EquipmentlProcedures Needed:
a  ONOP 1-0310030, Component Cooling Water Off Normal Operations
a  ONOP 1-0310030, Component Cooling Water Off Normal Operations
                                                  -
* ONOP 1-0310031, Component Cooling Water Excessive Activity 1-APP-01-S-6, Annunciator Response Procedure Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
* ONOP 1-0310031, Component Cooling Water Excessive Activity 1-APP-01-S-6, Annunciator Response Procedure Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
* None Radiological Protection and RWP Requirements:
* None Radiological Protection and RWP Requirements:
Line 1,705: Line 1,687:
INITIATING CUES:
INITIATING CUES:
The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.
The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.
NRC 19A c-8 Unit 1 control Room Page 3 of 10
NRC 19A c-8 Unit 1 control Room Page 3 of 10


JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:
JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:
ONOP 1-0310030, Component Cooling Water Off Normal Operation
ONOP 1-0310030, Component Cooling Water Off Normal Operation Step 6.2 Subsequent Actions, Step 5.
 
Step 6.2 Subsequent Actions, Step 5.
CRITICAL STEP 1:(6.2.5.A.1)      abnormal level conditions exist in the CCW Surge Tank, Then            STEP perform the following:
CRITICAL STEP 1:(6.2.5.A.1)      abnormal level conditions exist in the CCW Surge Tank, Then            STEP perform the following:
A. High level in the CCW Surge Tank.
A. High level in the CCW Surge Tank.
Line 1,788: Line 1,767:
INITIATING CUES:
INITIATING CUES:
The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.
The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.
Page 10 of 10
Page 10 of 10


Line 1,853: Line 1,831:
This JPM is NOT TIME CRITICAL This is a FAULTED JPM
This JPM is NOT TIME CRITICAL This is a FAULTED JPM


REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Determine Shutdown Margin Criteria KA Statement:          2.1.43 Ability to use procedures to determine the effects on
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Determine Shutdown Margin Criteria KA Statement:          2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
                              -
reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
KA    IR:          RO    4.1, SRO    4.3
KA    IR:          RO    4.1, SRO    4.3


Line 1,892: Line 1,868:
ADMINISTRATIVE JPM A-i PAGE 4
ADMINISTRATIVE JPM A-i PAGE 4


NRC ADM JPM A-i STEP 4 (5A):  Determine Xenon worth from Figure A.4 and record on Data sheet 2.            CRITICAL STEP STANDARD:    2525 pcm 2600 pcm
NRC ADM JPM A-i STEP 4 (5A):  Determine Xenon worth from Figure A.4 and record on Data sheet 2.            CRITICAL STEP STANDARD:    2525 pcm 2600 pcm SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT STEP 5 (5B):  Record Reactivity Deviation on data sheet 2 SAT STANDARD:    Opcm EXAMINERS CUE: Reactor Engineering has provided a Reactivity                            UNSAT Deviation value of 0 pcm.
                        -
SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT STEP 5 (5B):  Record Reactivity Deviation on data sheet 2 SAT STANDARD:    Opcm EXAMINERS CUE: Reactor Engineering has provided a Reactivity                            UNSAT Deviation value of 0 pcm.
COMMENTS:
COMMENTS:
STEP 6 (SC):  Determine stuck rod worth using Figure B.4 and record on data sheet 2        CRITICAL STEP STANDARD:    1654 pcm  +/- 0 pcm SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT STEP 7 (5D & 6A):    Add lines 5A, SB, & SC and record on data sheet 2                    CRITICAL STEP STANDARD:    871 pcm 946 pcm
STEP 6 (SC):  Determine stuck rod worth using Figure B.4 and record on data sheet 2        CRITICAL STEP STANDARD:    1654 pcm  +/- 0 pcm SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT STEP 7 (5D & 6A):    Add lines 5A, SB, & SC and record on data sheet 2                    CRITICAL STEP STANDARD:    871 pcm 946 pcm SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT ST. LUCIE TRAINING DEPT.
                      -
SAT EXAMINERS CUE:        NONE COMMENTS:                                                                                        UNSAT ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM A-i PAGE 5
ADMINISTRATIVE JPM A-i PAGE 5


Line 1,939: Line 1,911:
C 0                a)                                      0          CI.
C 0                a)                                      0          CI.
I w° WZD    I LU 0                0 a)
I w° WZD    I LU 0                0 a)
C)                  4-ci
C)                  4-ci Wcca)
                                                                              <
Wcca)
Ith  -
Ith  -
C D
C D
Line 1,955: Line 1,925:
C 0
C 0
Eo            4                  a)
Eo            4                  a)
                                                                                        <
                                                .
CL)
CL)
                           -5 4-J  I (4
                           -5 4-J  I (4
I C CO 0
I C CO 0
Line 1,965: Line 1,932:
gQ)
gQ)
E 0
E 0
O
O I
                                                                    >
a)
I a)
Co z      -
Co z      -
Ea)        0 O4-                        -
Ea)        0 O4-                        -
Line 1,974: Line 1,940:
                 .3  4-J          -
                 .3  4-J          -
a) a)
a) a)
Z COcj c
Z COcj c
C) 4-CI) a)
C) 4-CI) a)
4-d            C) a)                            C) a)
4-d            C) a)                            C) a)
Line 1,991: Line 1,955:
     %1 0            0    >3
     %1 0            0    >3
: 0.      0 3            ><  C D  8 Z
: 0.      0 3            ><  C D  8 Z
OD    0)0 iN s)(D        C)    p                    Ill c      g  g          Oi                    zm o      00 CD
OD    0)0 iN s)(D        C)    p                    Ill c      g  g          Oi                    zm o      00 CD 0.
                    -
0.
 
CD.. -
CD.. -
         -      D          m WD                      CDZ&#xd8; c?xc                m m            w                    m w                              czm CD
         -      D          m WD                      CDZ&#xd8; c?xc                m m            w                    m w                              czm CD 01          HC
* 01          HC
                 +
                 +
: 0)  -
: 0)  -
0                        0 0
0                        0 0
              -
0 Q)      Ow          , ,1&#xf8;o    0      rn        0 0    CD
0 Q)      Ow          , ,1&#xf8;o    0      rn        0 0    CD
                     .          3o 0D                                          C) (
                     .          3o 0D                                          C) (
Line 2,007: Line 1,966:
                               .*3 D
                               .*3 D
c        Z 01-,
c        Z 01-,
* D        I C)
D        I C)
                        ,
C) o 0v  -a        0              0 tHUo                                    -4,
C) o 0v  -a        0              0 tHUo                                    -4,
                                 -U
                                 -U
                                 -U
                                 -U
* Cl)
* Cl)
                                            >
:5 F-UJ            :3-CD                                    C F
:5 F-UJ            :3-CD                                    C F
0                                      0.
0                                      0.
Line 2,103: Line 2,060:
(        )+[(          )x(          )]=
(        )+[(          )x(          )]=
Step 1 B      Step 1 C      Step ID      Time to Boil SAT STANDARD:      Step lB 16.8 SteplCl.17                                                                          UNSAT Step ID 4.44 Time to Boil 21.99 minutes (21.99 22 minutes is acceptable)
Step 1 B      Step 1 C      Step ID      Time to Boil SAT STANDARD:      Step lB 16.8 SteplCl.17                                                                          UNSAT Step ID 4.44 Time to Boil 21.99 minutes (21.99 22 minutes is acceptable)
                                                      -
EXAMINERS CUE:          NONE COMMENTS:
EXAMINERS CUE:          NONE COMMENTS:
STEP 9 (2):    H core shuffle or reload has NOT been completed, Then use the step 1 .E.
STEP 9 (2):    H core shuffle or reload has NOT been completed, Then use the step 1 .E.
Line 2,149: Line 2,105:
                           -                              3    i        (minutes)
                           -                              3    i        (minutes)
D.      Table 4 Additional volume of water above mid-loop.
D.      Table 4 Additional volume of water above mid-loop.
                          -
i.tl4    (100 ff
i.tl4    (100 ff
                                                                                             )
                                                                                             )
Line 2,176: Line 2,131:
                                                               .:--T--:                                        1 I          C)
                                                               .:--T--:                                        1 I          C)
                                                                     *...i..-..                                                  m 180                                                                                                            0          C
                                                                     *...i..-..                                                  m 180                                                                                                            0          C
                                                                            .
                                                                     .-+                                                         
                                                                     .-+                                                         
                                                                                                                             -1  I m
                                                                                                                             -1  I m
Line 2,182: Line 2,136:
                                                                                                             -U  >T1 I      z I      0
                                                                                                             -U  >T1 I      z I      0
                         -  ._,..                                                                              rn CD      C      0 CC  0      0 0
                         -  ._,..                                                                              rn CD      C      0 CC  0      0 0
                                                                                                            -.
m 1
m 1
                                                                                                                 ,  m      z
                                                                                                                 ,  m      z
Line 2,188: Line 2,141:
                                                             . ...4                    .                            z
                                                             . ...4                    .                            z
                                                     + .                  .+                                    a,  -4      0 1
                                                     + .                  .+                                    a,  -4      0 1
                                                                                                                    -
0              1 4  -
0              1 4  -
z 0          0 1
z 0          0 1
Line 2,194: Line 2,146:
r                                                                                >
r                                                                                >
I-20 0
I-20 0
02 4 6 10  12 14  16  18    20  22  24  26  28    30        32            34          36 38    40                      -D
02 4 6 10  12 14  16  18    20  22  24  26  28    30        32            34          36 38    40                      -D G)
                                                                                                                                >
G)
UNIT 1. 25000 EFPH                  C)
UNIT 1. 25000 EFPH                  C)
Time After S/D (Days)                                      PSL-2FSN-98-001                    0 (POPS1*O44Co3O.F242)
Time After S/D (Days)                                      PSL-2FSN-98-001                    0 (POPS1*O44Co3O.F242)
Line 2,206: Line 2,156:


REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)
KA Statement:          2.2.44 Ability to interpret control room indications to verify the status
KA Statement:          2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
                              -
and operation of a system, and understand how operator actions and directives affect plant and system conditions.
KA IR:            RO  = 4.2, SRO  = 4.4
KA IR:            RO  = 4.2, SRO  = 4.4


Line 2,309: Line 2,257:
     .3(.3CC03COQCCCC(.2CC03$2(.                        0    h..o.oCaCo(3ww                        1 CC-          (CrC..        CC*MCCCrCC$2UCC-J-.JCC$3$3(.-.CCO                                                                    fl1    F
     .3(.3CC03COQCCCC(.2CC03$2(.                        0    h..o.oCaCo(3ww                        1 CC-          (CrC..        CC*MCCCrCC$2UCC-J-.JCC$3$3(.-.CCO                                                                    fl1    F
(.2          Cr IC) Cr    0        .0. I- ( Ca (3) 133 3 (1 (.2 (.3 CC C.) (0 (.3 CC CC CC CO CC Cr .0. .0. (fl .6 0 Cr (. -3 13) -3 Cr .0. CC 30 CC 0 C.                    j( 0 0 0 CC CCC C.) CC                    CC 0
(.2          Cr IC) Cr    0        .0. I- ( Ca (3) 133 3 (1 (.2 (.3 CC C.) (0 (.3 CC CC CC CO CC Cr .0. .0. (fl .6 0 Cr (. -3 13) -3 Cr .0. CC 30 CC 0 C.                    j( 0 0 0 CC CCC C.) CC                    CC 0
14
14 0
                                                          -
0
                                                                                                                                                                                                                                                >
0 m
0 m
                                                                                                                                                                                                                                                >
CJ1CrUI          CrCrCrCr.6*.6UICrCrU1Cr,.6.CrCrCr...6..6.
CJ1CrUI          CrCrCrCr.6*.6UICrCrU1Cr,.6.CrCrCr...6..6.
2      I
2      I
Line 2,329: Line 2,273:
C n
C n
14 m
14 m
(31(31      .6.6CM          CrCrCr.6.6.6CrCrCrCrCr.6.6.6                                    ICCrCr      .6.6.6.6.6.6
(31(31      .6.6CM          CrCrCr.6.6.6CrCrCrCrCr.6.6.6                                    ICCrCr      .6.6.6.6.6.6
     *.6.k.6*.6 CrCrCr.6.6                                    CCCrCCC.6a.6 I- (        CO CO 13        (- 13 13 CD 13 F.          -3C- (-3 C- 13 (4 .3 I) 0        C- 13) 0 (CC C- CC CC Cr (3 C- Cr CC Cr (3 13) CC  C- CC (3 -4                  F-  I- 13 (3 3  13 (0                                                                                                                                                          2 (OCCCr0C)C                CCCCOC)1C                  rCaCrflCrCC                  C).CCCCCrCrCrCC(0CC0(30(0                                      1    -4 CC0132OCCCCCOC.20CC(00CCCC0                                                                                                                                                                                                          0...
     *.6.k.6*.6 CrCrCr.6.6                                    CCCrCCC.6a.6 I- (        CO CO 13        (- 13 13 CD 13 F.          -3C- (-3 C- 13 (4 .3 I) 0        C- 13) 0 (CC C- CC CC Cr (3 C- Cr CC Cr (3 13) CC  C- CC (3 -4                  F-  I- 13 (3 3  13 (0                                                                                                                                                          2 (OCCCr0C)C                CCCCOC)1C                  rCaCrflCrCC                  C).CCCCCrCrCrCC(0CC0(30(0                                      1    -4 CC0132OCCCCCOC.20CC(00CCCC0                                                                                                                                                                                                          0...
Line 2,348: Line 2,291:
O          CCOCCOI-      rCC rCC            I    W OCC              I CCO C
O          CCOCCOI-      rCC rCC            I    W OCC              I CCO C
0
0
    -
(
(
    .
0  JCCCCCDC      rCC  O          CCO 2      rCr02CrCCC      CC      CCC C                  C  CrW CCCCrWCC      CCr        0 C            CrCCCrUCO                                                                                    ICC 0                                                                                                    (0CC        OCCCC            $2CC13$2C            C2CC(3Ca0COaCOCCCr.303CCCCCa(.2COCaCCU                                          0          C C
0  JCCCCCDC      rCC  O          CCO 2      rCr02CrCCC      CC      CCC C                  C  CrW CCCCrWCC      CCr        0 C            CrCCCrUCO                                                                                    ICC 0                                                                                                    (0CC        OCCCC            $2CC13$2C            C2CC(3Ca0COaCOCCCr.303CCCCCa(.2COCaCCU                                          0          C C
0      C(30CrCCfr-CC)0aC-a*C                              rCot0C-CC-        CrCC                --                                      0                                                                                                .6 -J 0                                    0                            -
0      C(30CrCCfr-CC)0aC-a*C                              rCot0C-CC-        CrCC                --                                      0                                                                                                .6 -J 0                                    0                            -
Cr Ca Cr 3 CC (.3 (3 CC CC CC 0) CC                          Cr CC (3 0 0 Cr Cr                                                    CD (2. Cr CC CC 0 (.3 C 0 Ca (0 CC (CC 0 6.6.6 CC -J (.2 0Ca$3 z
Cr Ca Cr 3 CC (.3 (3 CC CC CC 0) CC                          Cr CC (3 0 0 Cr Cr                                                    CD (2. Cr CC CC 0 (.3 C 0 Ca (0 CC (CC 0 6.6.6 CC -J (.2 0Ca$3 z
2CCF Cr-JCrCrCC
2CCF Cr-JCrCrCC 0                                        CrOJC CDOCOF-a                              CJ CCJ-3                    -.3          CCCC(-          OOCOCCCC.J(3Cr-JCr$3COWaCOCM.3-JCC(30CO COCCW(CC                                                                                      CC                      CCC,IOCCC        r        C    03 CCWCCCCJCCCCC2CrW 0
    $
0                                        CrOJC CDOCOF-a                              CJ CCJ-3                    -.3          CCCC(-          OOCOCCCC.J(3Cr-JCr$3COWaCOCM.3-JCC(30CO COCCW(CC                                                                                      CC                      CCC,IOCCC        r        C    03 CCWCCCCJCCCCC2CrW 0
C                                    .3            0 -JO$3CCCC            .)                                  02C C
C                                    .3            0 -JO$3CCCC            .)                                  02C C
0  r-JMOCC0(3COCC--JWCrF-30t.Ct.C                                                                                              -I 0&deg;CD0.J0Cr(              -*JC-              .4.6          -.3(00)        OCrCCM$3C                    CCOCrCCCrCD$2C)0CO.6OC*000IC30 CCCC.-JC00                (0Ca00CCCC z
0  r-JMOCC0(3COCC--JWCrF-30t.Ct.C                                                                                              -I 0&deg;CD0.J0Cr(              -*JC-              .4.6          -.3(00)        OCrCCM$3C                    CCOCrCCCrCD$2C)0CO.6OC*000IC30 CCCC.-JC00                (0Ca00CCCC z
Line 2,365: Line 2,304:
42B                                  REACTOR ENGINEERING PERIODIC                                                  Attachment to:
42B                                  REACTOR ENGINEERING PERIODIC                                                  Attachment to:
PRQCbL)UK NV.:                              TESTS, CHECKS AND CALIBRATIONS                                                    48 of 64 OPERATING SURVEILLANCE PROCEDURE O-OSP-64.O1                                              ST. LUCIE PLANT ATTACHMENT 1, DATA SHEET I PERIODIC SURVEILLANCE OF INCORE DETECTOR SYSTEM Tahi. of 611ad bidWidual
PRQCbL)UK NV.:                              TESTS, CHECKS AND CALIBRATIONS                                                    48 of 64 OPERATING SURVEILLANCE PROCEDURE O-OSP-64.O1                                              ST. LUCIE PLANT ATTACHMENT 1, DATA SHEET I PERIODIC SURVEILLANCE OF INCORE DETECTOR SYSTEM Tahi. of 611ad bidWidual
                                                                                     .,w,I Group I            Level              DOPS                Core              Data of      Cycle/Exposure (EFPH)          #
                                                                                     .,w,I Group I            Level              DOPS                Core              Data of      Cycle/Exposure (EFPH)          #
(String)                              PID              Location            Failure            (if Known) 33                3                131                R-13            12/21101    13    .bandoned-B0C13          7 33                4                132                R-13            12121/01    13    Abandoned- SOC 13          8 34                1                133                T-13            05/17/97    10    Abandoned- SOC 10          9 34                2                134                7-13            05/17/97    10    Abandoned- SOC 10          10 34                3                135                7-13            05/17/97    10    Abandoned- BOG 10          11 34                4                136                T-13            05/17197    10    Abandoned- SOC 10          12 30                                  117                E-13            07/28/09    18            Low Signal        13 30                                  118                E-13            07/28/09    18            Low SIgnal        14 30                                  119                E-13            07/28/09    18            Low Signal        15 30              4                120                E-13            07/28/09    18            Low Signal        16 143                                                    r-ic.          -r-CDI4Y                ii.eJ      IlcL W 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 FOR INFORMA71ON ONLY
(String)                              PID              Location            Failure            (if Known) 33                3                131                R-13            12/21101    13    .bandoned-B0C13          7 33                4                132                R-13            12121/01    13    Abandoned- SOC 13          8 34                1                133                T-13            05/17/97    10    Abandoned- SOC 10          9 34                2                134                7-13            05/17/97    10    Abandoned- SOC 10          10 34                3                135                7-13            05/17/97    10    Abandoned- BOG 10          11 34                4                136                T-13            05/17197    10    Abandoned- SOC 10          12 30                                  117                E-13            07/28/09    18            Low Signal        13 30                                  118                E-13            07/28/09    18            Low SIgnal        14 30                                  119                E-13            07/28/09    18            Low Signal        15 30              4                120                E-13            07/28/09    18            Low Signal        16 143                                                    r-ic.          -r-CDI4Y                ii.eJ      IlcL W 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 FOR INFORMA71ON ONLY This document Is not controlled. Befor. using this substitute form It must be verified              Administratively OOS for observation to contain at least the same minimum infojmation as the original.
* This document Is not controlled. Befor. using this substitute form It must be verified              Administratively OOS for observation to contain at least the same minimum infojmation as the original.
Date V.r1fledJJj1jL. Initials S Da ShaM I
Date V.r1fledJJj1jL. Initials S Da ShaM I


Line 2,416: Line 2,353:
EVALUATE the total number of failed detectors against the criteria listed in Figure D.6, lncore Operating Status Table.
EVALUATE the total number of failed detectors against the criteria listed in Figure D.6, lncore Operating Status Table.
i! the criteria of Figure D.6, lncore Operating Status, is NOT met, Then the incore detector system is NOT operable.
i! the criteria of Figure D.6, lncore Operating Status, is NOT met, Then the incore detector system is NOT operable.
                                                                                              -
A.      PERFORM the following to monitor LHR using the Excore Detector System.
A.      PERFORM the following to monitor LHR using the Excore Detector System.
: 1.      PROCEED to Section 6.3, Monitoring LHR Using the Excore Detection system.
: 1.      PROCEED to Section 6.3, Monitoring LHR Using the Excore Detection system.
Line 2,458: Line 2,394:
This is NOT a TIME CRITICAL JPM This is a Non-Faulted JPM
This is NOT a TIME CRITICAL JPM This is a Non-Faulted JPM


REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA KA Statement:    2.3.7 Ability to comply with radiation work permit requirements
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA KA Statement:    2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
 
during normal or abnormal conditions.
KA IR:          RO  = 3.5, SRO  = 3.6
KA IR:          RO  = 3.5, SRO  = 3.6


Line 2,508: Line 2,442:


FLORIDA POWER & LIGHT                  - PSL                              HPS-7 LOCATION:                                            CHARGING PUMPS EL. -.5 FT.-
FLORIDA POWER & LIGHT                  - PSL                              HPS-7 LOCATION:                                            CHARGING PUMPS EL. -.5 FT.-
GRAVE DANGER VERY HIGH RAD AREA (C) CONTAMINATEDAREA DATE                                81509                                                              (P) HOT IARTICLE AREA
GRAVE DANGER VERY HIGH RAD AREA (C) CONTAMINATEDAREA DATE                                81509                                                              (P) HOT IARTICLE AREA (L) LOCKED HIGH RAI) AREA TIME:                                  u                        (H) HIGH RAD AREA                      (S) SPECIFICS RWP REQUIRED RPT PRINT                          J. Swift                      (R) RAI)L.vrIoN AREA                    (B) lII COVERAGE REQUIREI)
        .
(L) LOCKED HIGH RAI) AREA TIME:                                  u                        (H) HIGH RAD AREA                      (S) SPECIFICS RWP REQUIRED RPT PRINT                          J. Swift                      (R) RAI)L.vrIoN AREA                    (B) lII COVERAGE REQUIREI)
RPT SIGNATURE:___________ lI                                                            I.Y AREA RWP /U                                                          lI)iLGHLY(ONIAMINVIEI) AREA          jUL MDA                        dpm INSTRUMENT TYPE / ft R020/3603                                  INSTRUMENT TYPE / ft                                      1 dm        Hot Part INSTRUMENT TYPE/ft L-177/21829                                  INSTRUMENT TYPE/ft                                  No orohearea YN ii/_ci.                                      SNIEARSIN IWM /100 CM2                                                N/A      N/A 1  <1K    7        6      <1K/            ii    <1K/      16    N/A/          21    N/A/    26  N/A/            13    N/A      N/A 27  N/A  /          C    N/A        N/A 2  <1K    /        7    1.9K /            12    <1K7      17    N/A/          22    N/A/
RPT SIGNATURE:___________ lI                                                            I.Y AREA RWP /U                                                          lI)iLGHLY(ONIAMINVIEI) AREA          jUL MDA                        dpm INSTRUMENT TYPE / ft R020/3603                                  INSTRUMENT TYPE / ft                                      1 dm        Hot Part INSTRUMENT TYPE/ft L-177/21829                                  INSTRUMENT TYPE/ft                                  No orohearea YN ii/_ci.                                      SNIEARSIN IWM /100 CM2                                                N/A      N/A 1  <1K    7        6      <1K/            ii    <1K/      16    N/A/          21    N/A/    26  N/A/            13    N/A      N/A 27  N/A  /          C    N/A        N/A 2  <1K    /        7    1.9K /            12    <1K7      17    N/A/          22    N/A/
N/A      N/A
N/A      N/A
Line 2,651: Line 2,583:
COMMENTS:
COMMENTS:
STEP 6 (2):  State Watch Office Notification                                                  CRITICAL STEP A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).
STEP 6 (2):  State Watch Office Notification                                                  CRITICAL STEP A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).
SAT 1 Airborne Threat Abbreviated State Notification Prepare
SAT 1 Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:
 
State Notification Form by filling out the following:
* Lines 1 through 6                                                              UNSAT
* Lines 1 through 6                                                              UNSAT
* Line 11 STANDARD:
* Line 11 STANDARD:
Line 2,663: Line 2,593:
: l. A. LJTHISISADRILL                                            B. []THISISANEMERGENCY UNSAT STANDARD:          Checks A EXAMINERS CUE:                NONE EXAMINERS NOTE:                Per EPIP-08, Attachment IA step 1, drill, exercises or tests, each message shall be checked this is a drill COMMENTS:
: l. A. LJTHISISADRILL                                            B. []THISISANEMERGENCY UNSAT STANDARD:          Checks A EXAMINERS CUE:                NONE EXAMINERS NOTE:                Per EPIP-08, Attachment IA step 1, drill, exercises or tests, each message shall be checked this is a drill COMMENTS:
STEP 8 (Line 2):                                                                                      CRITICAL STEP
STEP 8 (Line 2):                                                                                      CRITICAL STEP
: 2. A. Date II                  B, Ci1ct Tine.                  C. Reputed by (Nanie D. Message Nunber:                      E. Reputed fron: Cotrd Rn Lisc EOF SAT F IiliaI / Ne CI8ssiflceti1 OR              Updt8 roation UNSAT STANDARD:          A. Todays Date B. Time contact made left blank at this time
: 2. A. Date II                  B, Ci1ct Tine.                  C. Reputed by (Nanie D. Message Nunber:                      E. Reputed fron: Cotrd Rn Lisc EOF SAT F IiliaI / Ne CI8ssiflceti1 OR              Updt8 roation UNSAT STANDARD:          A. Todays Date B. Time contact made left blank at this time C. Applicants name D. Message # I E. Control Room F. Initial / New Classification EXAMINERS CUE:                  NONE EXAMINERS NOTE:                Part B Contact time must be within 15 minutes of the emergency classification time EXAMINERS NOTE:                Contact time shall be filled in when contact is made with the state. This is noted in Step 17.
 
C. Applicants name D. Message # I E. Control Room F. Initial / New Classification EXAMINERS CUE:                  NONE EXAMINERS NOTE:                Part B Contact time must be within 15 minutes of the emergency classification time EXAMINERS NOTE:                Contact time shall be filled in when contact is made with the state. This is noted in Step 17.
COMMENTS:
COMMENTS:
ST. LUCIE TRAINING DEPT.
ST. LUCIE TRAINING DEPT.
Line 2,738: Line 2,666:
: 0. D Turfcey Point Unit 3                  E. Q Turfey Point Unit 4 Nor z3ai.
: 0. D Turfcey Point Unit 3                  E. Q Turfey Point Unit 4 Nor z3ai.
4,    Emergency Classification:          A. t6 ltlcatlon of Unusual Event                  8. DAlert C. C Site Area Emergency                          0. Q General Emergency 5.. A. Emeroencv Declaration:                      B.    [] Erneroencv Termination:            Date:    /    I        Time:
4,    Emergency Classification:          A. t6 ltlcatlon of Unusual Event                  8. DAlert C. C Site Area Emergency                          0. Q General Emergency 5.. A. Emeroencv Declaration:                      B.    [] Erneroencv Termination:            Date:    /    I        Time:
                                                                                                                                                      <-
: 6. Reason for Emercency Declaration:              A. BEAL Number            C
: 6. Reason for Emercency Declaration:              A. BEAL Number            C
                                                                                     /
                                                                                     /
Line 2,772: Line 2,699:
Form PSL-F070                    EPIP-08, Off-Site Notifications and Protective Action Recommendations                        Approval Date: 05/15/09
Form PSL-F070                    EPIP-08, Off-Site Notifications and Protective Action Recommendations                        Approval Date: 05/15/09


EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFP-1
EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFP-1 REVISION NO.:          PROCEDURE TITLE:                          PAE*
                                                          -
 
REVISION NO.:          PROCEDURE TITLE:                          PAE*
RESPONSE TO SECURITY EVENTS            of 27 PROCEDURE NO.:
RESPONSE TO SECURITY EVENTS            of 27 PROCEDURE NO.:
ONP-72.01                            ST. LUCIE PLANT 6.0    OPERATOR ACTIONS INSTRUCTIONS                        CONTINGENCY ACTIONS
ONP-72.01                            ST. LUCIE PLANT 6.0    OPERATOR ACTIONS INSTRUCTIONS                        CONTINGENCY ACTIONS
Line 2,788: Line 2,712:
C. DON headset attached to Control Room Security hotline phone.
C. DON headset attached to Control Room Security hotline phone.
: 3. if the Aircraft has impacted the plant site, Then REFER TO EDMG-01, Guideline for Responding to Large Area Fire or Explosion Involving Multiple Fire Zones, AND EDMG-02, Major Loss of Plant Control Systems Initial Response.
: 3. if the Aircraft has impacted the plant site, Then REFER TO EDMG-01, Guideline for Responding to Large Area Fire or Explosion Involving Multiple Fire Zones, AND EDMG-02, Major Loss of Plant Control Systems Initial Response.
                            -
4.)    IMPLEMENT Security Checklist in J      accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.
4.)    IMPLEMENT Security Checklist in J      accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.
: 5. jf the Security Event is a LAND BASED Threat, Then GO TO Appendix A, Response to LAND BASED Threat.
: 5. jf the Security Event is a LAND BASED Threat, Then GO TO Appendix A, Response to LAND BASED Threat.
Line 2,818: Line 2,741:
((3)      Off-Site Notifications NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is        required.
((3)      Off-Site Notifications NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is        required.
A.    &sect;2    Make an accelerated notification to the NRC in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.
A.    &sect;2    Make an accelerated notification to the NRC in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.
B. Airborne Threat Make an abbreviated State Notification in
B. Airborne Threat Make an abbreviated State Notification in accordance with EPIP-08.
                                          -
accordance with EPIP-08.
: 3.      ERO Activation NOTE The PSL    Conference    Bridge  can  be used to communicate with the ERO at an alternate location. Refer to the PSL Emergency Response Directory (ERD) for the phone number and password.
: 3.      ERO Activation NOTE The PSL    Conference    Bridge  can  be used to communicate with the ERO at an alternate location. Refer to the PSL Emergency Response Directory (ERD) for the phone number and password.
A.      Normal business hours      -
A.      Normal business hours      -
: 1.      Delay activation of the Emergency Response Facilities or direct ERO personnel to an alternate location.
: 1.      Delay activation of the Emergency Response Facilities or direct ERO personnel to an alternate location.
: 2.      Request off-site responders to go to EOF I alternate facility per EPIP-03, Attachment 4.
: 2.      Request off-site responders to go to EOF I alternate facility per EPIP-03, Attachment 4.
B.      Off-normal hours based on site accessibility, consider
B.      Off-normal hours based on site accessibility, consider directing ERO personnel to report to the EOF or alternate location.
                                            -
directing ERO personnel to report to the EOF or alternate location.


REVISION NO.:          PROCEDURE TITLE:                                      PAGE:
REVISION NO.:          PROCEDURE TITLE:                                      PAGE:
Line 2,836: Line 2,755:
NOTE
NOTE
           &#xb6; 1. Completion of this checklist requires the following Attachments (all from EPIP-08):
           &#xb6; 1. Completion of this checklist requires the following Attachments (all from EPIP-08):
Attachment I    Florida Nuclear Plant Emergency Notification Form Attachment 1A Directions for Completing the Florida Nuclear Plant
Attachment I    Florida Nuclear Plant Emergency Notification Form Attachment 1A Directions for Completing the Florida Nuclear Plant Emergency Notification Form Attachment 2    Determination of Protective Action Recommendations (PARs)
 
Attachment 3    NRC Reactor Plant Event Notification Worksheet Attachment 3A Directions for Completing the NRC Reactor Plant Event Notification Worksheet
Emergency Notification Form Attachment 2    Determination of Protective Action Recommendations (PARs)
Attachment 3    NRC Reactor Plant Event Notification Worksheet Attachment 3A Directions for Completing the NRC Reactor Plant
 
Event Notification Worksheet
: 2. Checklist Part 1 is for State Watch Office notification.
: 2. Checklist Part 1 is for State Watch Office notification.
: 3. Checklist Part 2 is for NRC notification.
: 3. Checklist Part 2 is for NRC notification.
Line 2,847: Line 2,762:
if Security Event, Then go to Step 3.A.1 .a NRC Notification or N/A.
if Security Event, Then go to Step 3.A.1 .a NRC Notification or N/A.
ui 2)      State Watch Office Notification A.      Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).
ui 2)      State Watch Office Notification A.      Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).
Airborne Threat Abbreviated State Notification Prepare
Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:
 
State Notification Form by filling out the following:
* Lines I through 6
* Lines I through 6
* Linell OR
* Linell OR
Line 2,855: Line 2,768:
REVISION NO.:            PROCEDURE TITLE:                                          PAGE:
REVISION NO.:            PROCEDURE TITLE:                                          PAGE:
20                OFF-SITE NOTIFICATIONS AND PROTECTIVE 2 0 of 56 PROCEDURE NO.:                      ACTION RECOMMENDATIONS EPIP-08                                ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 2 of 6)
20                OFF-SITE NOTIFICATIONS AND PROTECTIVE 2 0 of 56 PROCEDURE NO.:                      ACTION RECOMMENDATIONS EPIP-08                                ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 2 of 6)
: 2.              (continued)                                                              INITIAL All other Security and Non-Security Events Prepare the
: 2.              (continued)                                                              INITIAL All other Security and Non-Security Events Prepare the State Notification Form in accordance with Attachment IA, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.
                                                                      -
State Notification Form in accordance with Attachment IA, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.
Emergency Coordinator (EC) approval.
Emergency Coordinator (EC) approval.
NOTE Primary notification method to the State Watch Office (SWO) is to use the Hot Ring Down (HRD) phone.
NOTE Primary notification method to the State Watch Office (SWO) is to use the Hot Ring Down (HRD) phone.
Line 2,874: Line 2,785:
REVISION NO.:            PROCEDURE TITLE:                                      PAGE; 20                OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:                      ACTION RECOMMENDATIONS                        *38 &deg; f EPIP-08                              ST. LUCIE PLANT
REVISION NO.:            PROCEDURE TITLE:                                      PAGE; 20                OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:                      ACTION RECOMMENDATIONS                        *38 &deg; f EPIP-08                              ST. LUCIE PLANT
                                         &#xb6;6 ATTACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 8)
                                         &#xb6;6 ATTACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 8)
ITEM ENTRY On-line Verification Check the appropriate boxes as the State Watch Office
ITEM ENTRY On-line Verification Check the appropriate boxes as the State Watch Office Florida Division of Emergency Management (DEM) requests that the Department of Health Bureau of Radiation Control, St. Lucie County Department of Public Safety and the Martin County Department of Emergency Management get on the line, prior to initiating the notification. All four agencies must be notified (includes Florida OEM) through tje SWO or alternate means.
                        -
Florida Division of Emergency Management (DEM) requests that the Department of Health Bureau of Radiation Control, St. Lucie County Department of Public Safety and the Martin County Department of Emergency Management get on the line, prior to initiating the notification. All four agencies must be notified (includes Florida OEM) through tje SWO or alternate means.
Check appropriate box for drill or actual emergency as the case may be. During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.
Check appropriate box for drill or actual emergency as the case may be. During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.
2A. Enter todays date.
2A. Enter todays date.
Line 2,935: Line 2,844:
: 4. Management Designee:
: 4. Management Designee:
: 5. Test Specialist: Walter Mead
: 5. Test Specialist: Walter Mead
: 6. Expected Plant Response: (Cool-down cycle procedural limits) Generator output is increased initially
: 6. Expected Plant Response: (Cool-down cycle procedural limits) Generator output is increased initially by 20 to 50 MWe (approximately 30 Mwe is recommended) which in turn cools the RCS by approximately 2 to 5 degrees respectively (2 to 3 degrees is recommended). The RCS cool-down increases neutron moderation, as the thermal neutron population increases so does fissioning and reactor power increases.
                                                        -
by 20 to 50 MWe (approximately 30 Mwe is recommended) which in turn cools the RCS by approximately 2 to 5 degrees respectively (2 to 3 degrees is recommended). The RCS cool-down increases neutron moderation, as the thermal neutron population increases so does fissioning and reactor power increases.
The AT power will be prevented from increasing by inserting the Lead Bank 5. (Heat-up cycle) The generator output will then be decreased by the same amount it was previously increased and the RCS allowed to return to the initial Tavg value. AT power will decrease unless the Lead Bank 5 is withdrawn to its initial position. Data is taken prior to the cool-down, at the end of the cool-down and at the end of the heat-up. The cycle is repeated if additional data is required. MTC is predicted to be 20.16 pcm/&deg;F.
The AT power will be prevented from increasing by inserting the Lead Bank 5. (Heat-up cycle) The generator output will then be decreased by the same amount it was previously increased and the RCS allowed to return to the initial Tavg value. AT power will decrease unless the Lead Bank 5 is withdrawn to its initial position. Data is taken prior to the cool-down, at the end of the cool-down and at the end of the heat-up. The cycle is repeated if additional data is required. MTC is predicted to be 20.16 pcm/&deg;F.
: 7. Criteria for Test Termination: SM discretion, Crew discretion, dropped rod, DEH problems, RPS or NI problems, Linear Heat Rate alarms, Unexplained reactivity excursion, or other plant transients requiring operator attention for control. Misaligned or dropped rods will be addressed by the CEA OffNormal procedure.
: 7. Criteria for Test Termination: SM discretion, Crew discretion, dropped rod, DEH problems, RPS or NI problems, Linear Heat Rate alarms, Unexplained reactivity excursion, or other plant transients requiring operator attention for control. Misaligned or dropped rods will be addressed by the CEA OffNormal procedure.
Line 2,951: Line 2,858:
: 1. System should be notified that generator output may vary up to plus or minus 20 MWe during performance of the MTC test, which begins at 0900 on 2/25/09. The duration of the actual test is expected to be approximately 2-3 hours, with a further 2-3 hours for data analysis.
: 1. System should be notified that generator output may vary up to plus or minus 20 MWe during performance of the MTC test, which begins at 0900 on 2/25/09. The duration of the actual test is expected to be approximately 2-3 hours, with a further 2-3 hours for data analysis.
: 2. Due to the existing ASI swing and marginal ASI stability at this time in core life, CEA insertion should be closely controlled to ensure that an excessive and divergent ASI swing does not occur.
: 2. Due to the existing ASI swing and marginal ASI stability at this time in core life, CEA insertion should be closely controlled to ensure that an excessive and divergent ASI swing does not occur.
.
Consequently, the following insertion guidance is recommended.
Consequently, the following insertion guidance is recommended.
: 3. Starling on Thursday, 2/19/09, begin slowly inserting the Lead Bank (using Manual Group Mode) toward 115 W/D, plus or minus 2. The insertion rate should not exceed one            every hour.
: 3. Starling on Thursday, 2/19/09, begin slowly inserting the Lead Bank (using Manual Group Mode) toward 115 W/D, plus or minus 2. The insertion rate should not exceed one            every hour.
Line 2,984: Line 2,890:
           .[                                                      9    I
           .[                                                      9    I
                                                                           )
                                                                           )
    -
0 CD 0
0 CD 0
0 0
0 0
N) 0 CD
N) 0 CD
  >  0
  >  0 Cl, 0 0
          .
Cl, 0 0
:::::::z:H:                                                        0 C?)
:::::::z:H:                                                        0 C?)
C)  0
C)  0
Line 3,004: Line 2,907:
N)
N)
:::::::J::::::..::
:::::::J::::::..::
C)
C) 0 (0
                  -
0 (0
                                          -        -    -  -  -
                         -                N)      N)    C)) C))
                         -                N)      N)    C)) C))
C            (Ti                C              o      0 CEA (inches withdrawn)
C            (Ti                C              o      0 CEA (inches withdrawn)
Line 3,014: Line 2,914:
00 0 8J 0 60 11 6% 0  90 iU 99 99 9 8% 6 6% LL 00 01 V 00 61    Z  6% 60 P 00 80 P 008 009 666
00 0 8J 0 60 11 6% 0  90 iU 99 99 9 8% 6 6% LL 00 01 V 00 61    Z  6% 60 P 00 80 P 008 009 666


                                                    -
                                            .---
:r
:r
* F
* F
Line 3,034: Line 2,932:
1*9.
1*9.
Wed 08:00 Wed 09:59  Wed 12:01        Wed 14:00  Wed 16:00    Wed 17:53      Wed 13:53 Wed 22:00 ThU 00:09 Thu 91:59  Thu 04:01 140 130 j
Wed 08:00 Wed 09:59  Wed 12:01        Wed 14:00  Wed 16:00    Wed 17:53      Wed 13:53 Wed 22:00 ThU 00:09 Thu 91:59  Thu 04:01 140 130 j
12
12 110 Wed 08:00 Wed 0959    Wed 12:01        Wed 14:00  Wed 16:00    Wed 17:59      Wed 19:5* Wed 22:00 Thu 00:00 Thu        flu 04:0) flu 08:00 Cose
 
110
:      %-:                            :
Wed 08:00 Wed 0959    Wed 12:01        Wed 14:00  Wed 16:00    Wed 17:59      Wed 19:5* Wed 22:00 Thu 00:00 Thu        flu 04:0) flu 08:00 Cose


Inter-Office Correspondence RE/PSL 09-005 TO:                  SM                                                          DATE: February 25, 2009 FROM:                B. M. Wlliams                                              DEPT: Reactor Engineering
Inter-Office Correspondence RE/PSL 09-005 TO:                  SM                                                          DATE: February 25, 2009 FROM:                B. M. Wlliams                                              DEPT: Reactor Engineering

Latest revision as of 11:32, 5 February 2020

Initial Exam 2009302 Draft Sim in Plant JPMs
ML15142A394
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 05/27/2010
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
Download: ML15142A394 (226)
v • d • e


Text

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE ESTABLISH ALTERNATE CHARGING FLOWPATH TO RCS THROUGH A HPSI HEADER UNIT 2 -

NRC SI Simulator This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A Si Simulator Page 1 of 9

JOB PERFORMANCE MEASURE Task: Align Charging flow through A HPSI header.

Faulted JPM? Yes Facility JPM #: Modified from 0821115 K/A: A4.01 3.5 / 3.2 Ability to manually operate and/or monitor in the control room charging pump and flow controls.

Task Standard:

This JPM is complete when the US is notified that Charging flow has been established through the A HPSI header using the 2C Charging pump lAW 2EOP-99 Appendix T.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

2-EOP-99, Appendix T, Alternate Charging Flow Path to RCS Through A HPSI Header Validation Time: 10 minutes Time Critical: No Tools/EguipmentlProcedures Needed:

2-EOP-99, Appendix T, Alternate Charging Flow Path to RCS Through A HPSI Header Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A Si Simulator Page 2 of 9

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is:

Establish Alternate Charging Flow Path through A HPSI Header Unit 2

  • The performance level to be used for this JPM is Perform,
  • This is not a time critical JPM.
  • You may use any approved reference materials normally available in the execution of this task, including logs.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

  • All simulator JPM steps, including communications, shall be performed for this JPM.

a You are to operate any plant equipment that is necessary for the completion of this JPM.

  • The simulator will provide the cues as you perform this JPM.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 2 was tripped from 100% power due to a problem with the Feedwater Regulating System.

The Crew has implemented 2-EOP-15, Functional Recovery, due to a dual event. The SNPO reported a pipe break in the charging header between V2429 and V2523. The 2B Charging pump is out of service.

INITIATING CUES:

You are the RCO. The US has directed you to line up Charging flow through the A HPSI header and the 2A Charging Pump per 2-EOP-99, Appendix T, Alternate Charging Flow Path to RCS Through A HPSI Header.

NRC i9A Si Simulator Page 3of9

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

2-EOP-99, Appendix T, Alternate Charging Flow Path to RCS Through A HPSI Header.

STEP 1:(1) ENSURE letdown is ISOLATED.

SAT STANDARD: VERIFY all letdown Isolation Valves CLOSED.

  • E)(AMINERYS CUE: All letdown isolation valves closed, Green light ON, UNSAT Red light OFF.

COMMENTS:

STEP 2:(2) PLACE ALL Charging Pump in STOP.

SAT STANDARD: VERIFY ALL Charging Pump control switches to STOP.

  • E)(AMINERS CUE: ALL charging Pumps are in STOP, Green light ON, Red UNSAT light OFF.

COMMENTS:

STEP 3:(3) PLACE 2A HPSI Pump in STOP. CRITICAL STEP STANDARD: POSITION 2A HPSI Pump switch in STOP.

SAT

  • E)(AMINERS CUE: 2A HPSI pump switch in STOP, Green light ON, Red light OFF. Annunciator R-40 alarms.

UNSAT COMMENTS:

STEP 4:(4) CLOSE V3656, HPSI Pump 2A Discharge Valve. CRITICAL STEP STANDARD: OBTAIN key #67, POSITION V3656 to CLOSED.

SAT

  • E)(fiMINERS CUE: V3656 indicates Green light ON, Red light OFF Annunciator Q-33 Alarms.

UNSAT COMMENTS:

NRC 19AS1 Simulator Page 4 of 9

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 5:(5.A) Locally OPEN V2340, Charging Pump Discharge to A HPSI Header Isolation. (located in 20 Charging Pump Room). CRITICAL STEP STANDARD: DIRECT SNPO to OPEN V2340.

SAT

  • E)(AMINERIS CUE: The SNPO Reports V2340 is OPEN.

COMMENTS: UNSAT STEP 6:(5.B) if desired to use ANY combination of Charging Pump, Then locally LOCK CRITICAL CLOSED V2429, Charging Pump Discharge Isolation. STEP STANDARD: DIRECT THE SNPO to locally LOCK CLOSED V2429. SAT

  • EXAMINERS CUE: The SNPO REPORTS that V2429 is LOCK CLOSED.

UNSAT EXAMINERS NOTE: Break is downstream of V2429 per the cue therefore V2429 is to be closed. Located in pipe penetration room at Penetration Number 27.

COMMENTS:

STEP 7:(5.D) Locally OPEN V3519, Charging Pump to A HPSI Hdr Isol (Located in A CRITICAL HPSI pump room). STEP STANDARD: DIRECT THE SNPO to locally OPEN V3519. SAT

  • E)(AMINERS CUE: The SNPO REPORTS that V3519 is OPEN.

UNSAT COMMENTS:

NRC 19A Si Simulator Page 5of9

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 8:(6) ENSURE Charging Pump(s) have a suction flowpath from ONE of the following sources: SAT Boric Acid Makeup Tank Refueling Water Tank UNSAT Volume Control Tank STANDARD: Verify Charging Pump Suction Flowpath.

  • E)(AMINERS CUE: Charging Pump Suction is from the Boric Acid Makeup Tank.

COMMENTS:

STEP 9:(7) ENSURE Charging Pump(s) have a discharge flowpath by OPENING at CRITICAL least ONE A HPSI Header Loop Isolation Valve: STEP HCV-3617 2A2 Cold Leg SAT HCV3627 2A1 Cold Leg HCV3637 2B1 Cold Leg HCV-3647 2B2 Cold Leg UNSAT STANDARD: POSITION Any ONE of the four valves to OPEN.

S CUE:

7

  • EXAMINER As any one of the four Valves is OPENED, indicate the Green light is OFF, Red light is ON.

COMMENTS:

STEP 1 O:(8) START Charging Pump(s) AS NECESSARY. FAULTED STEP STANDARD: POSITION the 2A Charging Pump to START.

SAT

  • EXAMINERS CUE: 2A Charging Pump indicates Green light OFF and Red light ON. Recirc Valve Indicates BOTH lights ON. 2A Charging pump red and green lights off. UNSAT EXAMINERS NOTE: 2A Charging pump trips 5 seconds after start signal.

Applicant should refer back to step 5.C for use of the 2C Charging pump.

COMMENTS:

NRC 19A Si Simulator Page 6 of 9

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 11 :(5.C) If desired to use ONLY the 2C Charging pump Then locally LOCK CLOSED V2338 2C Charging Pump Disc. To Common Disc. Header Isolation. SAT STANDARD: DIRECT THE SNPO to locally LOCK CLOSED V2338. UNSAT

  • E)(AMINERS CUE: SNPO reports V2338 is LOCKED CLOSED.

EXAMINERS NOTE: Closing V2338 is NOT critical due to all Charging Pumps have discharge check valves. V2439 (step 6) should remain closed due to the location of the break.

If V2439 is re-opened the 2C Charging pump will pump out the break, not into the RCS.

COMMENTS:

STEP 1 2:(8) START the 2C Charging pump AS NECESSARY CRITICAL STEP STANDARD: POSITION the 2C Charging Pump to START SAT

  • E)(,MINERS CUE: 2C Charging pump indicates red light ON green light OFF. Recirc, Valve indicates Green light ON red Light OFF. UNSAT
  • EXAMINERS CUE: As the Recirc valve closes, depending on which SI header Valve is opened, R-46,47, 56 or 57 Alarms and Loop Pressure PIA-3329,3319,3339 or 3349 indicates 1980 psig.

COMMENTS:

STEP 13:(9) VERIFY flow to the RCS by ANY of the following:

Pressurizer level rising SAT Indicated flow on applicable HPSI Loop Flow Indicator STANDARD: OBSERVE Pressurizer Level and HPSI flow for PROPER indication. UNSAT

  • E)(AMINERS CUE: Pressurizer Level is slowly RISING and applicable HPSI Loop Flow (Fl-3311) Indicates 44 gpm.

COMMENTS:

NRC 19A Si Simulator Page 7 of 9

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP (done): NOTIFY the US that charging flow has been established through the A High Pressure Safety Injection Header using the 2A Charging Pump.

STANDARD: NOTIFY the US that charging flow has been ESTABLISHED through the A High Pressure Safety Injection Header using the 2A Charging Pump.

EXAMINERS CUE: US ACKNOWLEDGES COMMENTS:

END OF TASK STOP TIME:

NRC 19A Si Simulator Page 8 of 9

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-88. UNFREEZE the Simulator.
2. SELECT the Lesson File Folder for JPM.
3. OPEN the Lesson File for 0821115 and EXECUTE the Lesson.
4. TRIGGER Step 1.
5. After Letdown isolates on high temperature, CLOSE all three Letdown valves and PLACE all Charging pumps in STOP.
6. Line up Emergency Boration by performing the following steps:

> START 2Aor2B BA Pump.

> CLOSE V2650, Tank 2A Recirc. Valve.

> CLOSE V2651, Tank 2B Recirc Valve.

> OPEN V2514, Emergency Borate.

7. The Simulator will automatically FREEZE after 2A Charging Pump recirc valve strokes full open. All SPTAs are performed by the scenario.
8. Ensure 2B Charging pump is in STOP and breaker is racked out.
9. STORE a temporary IC set if more than one student is to take the JPM. Note: The lesson will have to be stopped and then re-executed each time the temporary IC set is restored.
10. UNFREEZE the simulator when the student is ready.
11. TRIGGER STEP Open V2340 when directed to do so by the student.
12. TRIGGER STEP Close V2429 when directed to do so by the student.
13. TRIGGER STEP Close V2338 when directed to do so by the student.
14. TRIGGER STEP Open V351 9 when directed to do so by the student.

JPM 0821115/R12 Simulator or U2 control Room Page 9 of 9

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 2 was tripped from 100% power due to a problem with the Feedwater Regulating System.

The Crew has implemented 2-EOP15, Functional Recovery, due to a dual event. The SNPO reported a pipe break in the charging header between V2429 and V2523. The 2B Charging pump is out of service INITIATING CUES:

You are the RCO. The US has directed you to line up Charging flow through the A HPSI header and the 2A Charging Pump per 2-EOP-99, Appendix T, Alternate Charging Flow Path to RCS Through A HPSI Header.

Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES / FIGURES / TABLES I DATA 97 of 156 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX T ALTERNATE CHARGING FLOW PATH TO RCS THROUGH A HPSI HEADER (Page 1 of 2)

CAUTION Use of this Appendix indicates a condition where the normal charging flowpath to the RCS has become unavailable due to a component or piping failure. This lineup will render the 2A HPSI Pump inoperable and letdown will not be possible due to loss of cooling flow through the Regenerative Heat Exchanger.

LI 1. ENSUREletdown is ISOLATED.

El 2. PLACE ALL Charging Pumps in STOP.

El 3. PLACE 2A HPSI Pump in STOP.

LI 4. CLOSE V3656, HPSI Pump 2A Discharge Valve.

El 5. DISPATCH an operator to perform the following valve alignment:

El A. Locally OPEN V2340, Charging Pump Discharge to A HPSI Header Isolation. (located in 2C Charging Pump Room)

LI B. [f desired to use ANY combination of Charging Pumps, Then locally LOCK CLOSED V2429, Charging Pump Discharge Isolation.

LI C. [f desired to use ONLY the 2C Charging Pump, Then locally LOCK CLOSED V2338, 2C Charging Pump Disch. to Common Disch. Header Isolation.

El D. Locally OPEN V3519, Charging Pump to A HPSI Hdr Isol (Located in A HPSI pump room).

LI 6. ENSURE Charging Pump(s) have a suction flowpath from ONE of the following sources.

LI Boric Acid Makeup Tank LI Refueling Water Tank LI Volume Control Tank

REVISION NO.: PROCEDURE TITLE: PAGE:

36A APPENDICES I FIGURES / TABLES / DATA 98 of 156 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 APPENDIX T ALTERNATE CHARGING FLOW PATH TO RCS THROUGH A HPSI HEADER (Page 2 of2)

LI 7. ENSURE Charging Pump(s) have a discharge flowpath by OPENING at least ONE A HPSI Header Loop Isolation Valve.

LI HCV-3617 (2A2 Cold Leg)

El HCV-3627 (2A1 Cold Leg)

LI HCV-3637 (2B1 Cold Leg)

LI HCV-3647 (2B2 Cold Leg)

El 8. START Charging Pump(s) AS NECESSARY.

El 9. VERIFY flow to the RCS by ANY of the following:

El Pressurizer level rising Li Indicated flow on applicable HPSI Loop Flow Indicator END OF APPENDIX T

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE MANUALLY ACTUATE AFAS-1 UNIT 2 NRC S-2 Simulator This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A S-2 simulator Page 1 of 8

JOB PERFORMANCE MEASURE Task: 07009036, MANUALLY INITIATE AFAS Faulted JPM? Yes Facility JPM #: Modified from 0821077 KIA: 061 .A2.04 3.4 I 3.8 Ability to predict the impacts of the following malfunctions or operations on the AFW and based on these predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.

Task Standard:

This JPM is complete when the operator reports that AFW flow has been restored to the 2A SG from the 2A or 20 AFW Pump.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

None Validation Time: 5 minutes Time Critical: No ToolslEquipmentlProcedures Needed:

  • None Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A S-2 simulator Page 2 of 8

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

The task you are to perform is: ManuaNy Actuate AFAS-1, Unit 2 The performance level to be used for this JPM is Perform

  • This is not a time critical JPM.

You may use any approved reference materials normally available in the execution of this task, including logs.

  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

  • All simulator JPM steps, including communications, shall be performed for this JPM.
  • You are to operate any plant equipment that is necessary for the completion of this JPM.
  • The simulator will provide the cues as you perform this JPM.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

A Steam Generator Tube Rupture occurred in SG 2B. The 2B SG has been isolated lAW 2-EOP-99 Appendix R and the RCS is being cooled down and depressurized. AFW to SG 2A has just automatically isolated due to the Feedwater Header differential pressure between the Steam Generators.

INITIATING CUES:

The US has directed you to:

1. manually initiate AFAS-1 from RTGB-202
2. restore SG 2A level to 60-70% NR at approximately 300 gpm.

NRC 19A S-2 simulator Page 3 of 8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

STEP 1: Manually initiate AFAS-1 by placing all four AFAS-1 INITIATION SWITCHES CRITICAL on RTGB-202 to the MANUAL position. STEP STANDARD: PLACE all four AFAS-1 INITIATION SWITCHES on RTGB-202 to the SAT MANUAL position.

  • E)(AMINERS CUE: All four AFAS-1 Initiation Switches on RTGB-202 are UNSAT placed in the MANUAL position.

COMMENTS:

STEP 2: OBSERVE valves MV-09-9, Pump 2A Disch to SG 2A Valve and FAULTED MV-09-1 1, Pump 2C to SG 2A fails to OPEN. STEP AND OBSERVE zero flow on FI-09-2A or FR-O92A, Header A Flow & Pressure SAT and on FI-09-2C or FR-09-2C, Header C Flow & Pressure.

STANDARD: OBSERVE valves MV-09-9 and MV-09-1 1 FAIL TO STROKE OPEN. UNSAT OBSERVE NO FLOW on Fl(FR)-09-2A and FI(FR)-09-2C.

  • E)(AMINERS CUE: MV-09-9 and MV-09-11 INDICATE Red lights OFF, Green lights ON.

FI-09-2AIFR-09-2A indicates 44 gpm flow and FI-09-2CIFR-092C indicates 0 flow to the SG 2A.

COMMENTS:

NRC 19A S-2 smuIator Page 4 of 8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 3: THROTTLES valve MV-09-9, Pump 2A Disch to SG 2A Valve OR FAULTED MV-09-1 1, Pump 2C to SG 2A to 150 to 250 GPM. STEP STANDARD: POSITION the control switch for MV-09-9 or MV-09-1 1 to the open position. SAT

  • E)(AMINERS CUE: MV-09-9 or MV-09-11 indicates Green light OFF and Red light OFF, UNSAT EVALUATORS NOTE: When Applicant attempts to throttle open either MV-09-9 OR MV-09-11, MV-09-9 or MV-09-11 will open for 5 seconds then trip as indicated by loss of light indication.

When MV-09-9 or MV-09-1 I trips it will automatically clear the fault on the other valve allowing it to be throttled.

COMMENTS:

STEP 4: DETERMINES MV-09-9 OR MV 1 1 has tripped and throttles other valve CRITICAL (MV-09-9 OR MV-09-1 1). STEP STANDARD: THROTTLES MV-09-9 or MV-09-1 ito 150-250 GPM as indicated on Fl 2A/FR-09-2A or Fl-09-2C/FR-092C and restores SG 1A level between 60%

and 70% narrow range SAT

  • E)CAMINERS CUE: MV-09-1I shows Green and Red lights ON; UNSAT FR-09-2A OR Fl-09-2C indicates 200 gpm, SG 2A level is now 65% narrow range and STABLE.

EVALUATORS NOTE: Due to the length of time to restore normal SIG level on the simulator, after student has throttled flow to raise the level, STATE that SIG level is being RESTORED to between 60 % and 70% NR level.

COMMENTS:

NRC 19A S-2 simulator Page 5 of 8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP (done): Notify the US that AFAS-1 has been manually initiated and AFW flow has been re-established to the 2A SG using the 2A AFW pump or the 2C AFW Pump. Level in the 2A SG is being restored to normal level (60%-70% NR).

SAT STANDARD: NOTIFY the US that AFW flow has been RESTORED to the 2A SG using the 2A AFW pump (or2C AFW Pump) and level is returning to normal level (60%-

70% NR). UNSAT EXAMINERS CUE: US ACKNOWLEDGES.

COMMENTS:

END OF TASK STOP TIME:

NRC 19A S-2 simulator Page 6 of 8

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-80.
2. EXECUTE Scenario S2
3. UNFREEZE the Simulator for a few seconds, then FREEZE.
4. ENSURE step Valves Fail Close is triggered (remaining steps will Auto Trigger on candidates actions).
5. UNFREEZE the Simulator when the student is ready.

NRC 1 9A S-2 simulator Page 7 of 8

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

A Steam Generator Tube Rupture occurred in SG 2B. The 28 SG has been isolated lAW 2-EOP-99 Appendix R and the RCS is being cooled down and depressurized. AFW to SG 2A has just automatically isolated due to the Feedwater Header differential pressure between the Steam Generators.

INITIATING CUES:

The US has directed you to:

3. manually initiate AFAS-1 from RTGB-202
4. restore SG 2A level to 60-70% NR at approximately 300 gpm.

Page 8 of 8

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE EMERGENCY BORATE NRC S-3 Simulator This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A S-3 Simulator Page 1 of 10

JOB PERFORMANCE MEASURE Task: 07002650, EMERGENCY BORATE THE RCS Faulted JPM? YES Facility JPM #:

K/A: 004.A4.07 3.9 / 3.7 Ability to manually operate and/or monitor in the control room: Boration/dilution Duty Area(s): N/A Task Information: N/A Task Standard:

This JPM is complete when emergency boration actions are established.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 2-ONP-02.02, Emergency Boration Validation Time: 5 minutes Time Critical: No ToolslEguipmentlProcedures Needed:
  • 2-ONP-02.02, Emergency Boration Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:

a None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner:

Signature:

Comments NRC 19A S-3 Simulator Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is: Emergency Borate Unit 2.
  • The performance level to be used for this JPM is Perform
  • This is not a time critical JPM.
  • You may use any approved reference materials normally available in the execution of this task, including logs.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

  • All simulator JPM steps, including communications, shall be performed for this JPM.
  • You are to operate any plant equipment that is necessary for the completion of this JPM.
  • The simulator will provide the cues as you perform this JPM.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

A reactor trip on Unit 2 has just occurred following a 45-day run at 100% power. The unit has experienced an excess cooldown and Tcold is approaching 500°F.

INITIATING CUES:

You are the BRCO. The US has directed you to Emergency Borate lAW 2-ONP-02.02, Emergency Boration NRC 19A S-3 SmuIator Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

ENTER 2-ONP-02.02, Emergency Boration STEP 1(6.0.1) PLACE the Makeup Mode Selector switch in MANUAL.

STANDARD: POSITION Makeup Mode Selector Switch to MANUAL.

SAT

  • E)(AMINERS CUE: Makeup Mode Selector Switch is in MANUAL.

EVALUATOR NOTE: Iflwhen, SIAS actuates (at any time during this JPM), UNSAT direct the BRCO to continue with the Emergency Boration. The BOP will verify the SIAS.

COMMENTS:

STEP 2:(6.0.2) ENSURE V2525, Boron Load Control Valve, is CLOSED.

STANDARD: ENSURE V2525 is CLOSED.

SAT

  • E)(AMINERS CUE: V2525 shows Green light ON, Red light OFF.

COMMENTS: UNSAT STEP 3:(6.0.3) START 2A or 2B BA Pump.

STANDARD: POSITION 2A or 2B BAM Pump control switch to RUN.

SAT

  • E)(AMINERS CUE: BAM Pump (2A or 2B) started by candidate shows Green light OFF, Red light ON.

UNSAT EVALUATOR NOTE: Since the procedure doesnt specify which pump to run, either one is acceptable. Optimally, however, the candidate should start the pump associated with the Tech Spec designated BAM tank.

COMMENTS:

NRC 19A S-3 Simulator Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE (WKI IT STEP 4: (6.0.4) CLOSE V2650, Tank 2A Recirc. Valve.

STANDARD: POSITION V2650 control switch to CLOSE. SAT

  • EXAMINERS CUE: V2650 shows Green light ON, Red light OFF.

UNSAT COMMENTS:

STEP 5: (6.0.5) CLOSE V2651, Tank 2B Recirc Valve.

STANDARD: POSITION V2651 control switch to CLOSE. SAT

  • EXAMINERS CUE: V2651 shows Green light ON, Red light OFF.

UNSAT COMMENTS:

FAULTED STEP 6: (6.0.6) OPEN V2514 Emergency Borate. STEP STANDARD: POSITION V2514 control switch to OPEN and OBSERVE that valve does NOT open.

SAT

  • E)(AMINERS CUE: V2514 shows Green light OFF, Red light OFF and M 42 annunciates.

UNSAT EVALUATOR NOTE: Faulted step V2514 failed to open.

COMMENTS:

NRC 19A S-3 Simulator Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST 2-ONP-02.02, CONTINGENCY ACTION; If V2514 fails to open, PERFORM the following:

FAULTED STEP 7: (6.O.6.A.1) OPEN V2508, BA Gravity Feed B. STEP STANDARD: POSITION V2508 control switch to OPEN and OBSERVE V2508 does not SAT open.

  • E)(AMINERS CUE: V2508 shows Green light ON, Red light OFF. UNSAT EVALUATOR NOTE: Faulted step V2508 failed to open COMMENTS:

STEP 8: (6.O.6.A.2) OPEN V2509, BA Gravity Feed A. FAULTED STEP STANDARD: POSITION V2509 control switch to OPEN and OBSERVE V2509 does not open.

SAT

  • EXAMINERS CUE: V2509 shows Green light ON, Red light OFF.

EVALUATOR NOTE: Faulted step V2509 failed to open UNSAT COMMENTS:

STEP 9: (6.O.6.A.3) CLOSE V2501 VCT Outlet Valve. CRITICAL STEP STANDARD: Candidate realizes that V2501 should not be closed at this time because it will isolate the suction path to the charging pumps. Candidate leaves V2501 OPEN. SAT

  • E)(AMINERS CUE: V2501 shows Green light OFF, Red light ON; UNSAT COMMENTS:

NRC 19A S-3 Simulator Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 10: (6.0.6.B.1) the Boric Acid Makeup Tanks are unavailable or both Gravity CRITICAL Feed valves failed to open, THEN perform the following: STEP OPEN V2504 Refuel Water to Charging Pumps SAT STANDARD: OPENS V2504 UNSAT EXAMINERS CUE: V2504 shows Green light OFF, Red light ON.

COMMENTS:

STEP 11: (6.0.6.B.2) CLOSE V2501 VCT Outlet Valve CRITICAL STEP STANDARD: CLOSES V2501 VCT Outlet Valve EXAMINERS CUE: V2501 shows Green light ON, Red light OFF. SAT EVALUATOR NOTE: If SIAS occurs, V2501 closes.

COMMENTS: UNSAT STEP 12 (6.0.6.B.3): STOP the running BAM pumps STANDARD: PLACES the control switch for the BAM pump that was started in step 3 to the stop position. SAT EXAMINERS CUE: Previously running SAM pump indicates red light OFF green light ON.

U N SAT COMMENTS:

NRC 19A S-3 Simulator Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 13: (6.O.6.B.4) ENSURE V2508 BA Gravity Feed CLOSED SAT STANDARD: ENSURES V2508 BA Gravity Feed CLOSED UNSAT EXAMINERS CUE: V2508 shows Green light ON, Red light OFF.

COMMENTS:

STEP 14: (6.O.6.B.5) ENSURE V2509 BA Gravity Feed CLOSED STANDARD: ENSURES V2509 BA Gravity Feed CLOSED SAT EXAMINERS CUE: V2509 shows Green light ON, Red light OFF.

UNSAT COMMENTS:

STEP 15: (6.O.6.B.6) ENSURES V2514 Emergency Borate CLOSED STANDARD: ENSURES V2514 Emergency Borate CLOSED SAT EXAMINERS CUE: V2514 shows Green light OFF, Red light OFF.

EVALUATOR NOTE: Requires SNPO to locally ensure this valve is closed.

UNSAT COMMENTS:

END OF TASK STOP TIME:

NRC 19A S-3 Simuator Page 8 of 10

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-85.
2. EXECUTE S-3 Emergency Borate
3. UNFREEZE the Simulator.
4. ENSURE scenario auto executes.

NRC 19A S-3 Simulator Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

A reactor trip on Unit 2 has just occurred following a 45-day run at 100% power. The unit has experienced an excess cooldown and Tcold is approaching 500°F.

INITIATING CUES:

You are the BRCO. The US has directed you to Emergency Borate lAW 2-ONP-02.02, Emergency Boration Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

6A EMERGENCY BORATION PROCEDURE NO.:

6 of 9 2ONP-02.02 ST. LUCIE UNIT 2 6.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS NOTE

  • This Procedure may contain steps that could adversely affect reactivity.

ENSURE that proper consideration and appropriate briefings occur prior to performance of steps that could challenge reactivity.

  • An Operator Aid has been placed at RTGB-205 Panel M. Any revision to this section of the procedure shall verify the validity of the Operator Aid and, if changes are necessary, a Label Request shall be initiated to incorporate these changes on a new Operator Aid placard.
1. ¶i PLACE the Makeup Mode Selector switch in MANUAL.
2. ENSURE V2525, Boron Load Control Valve, is CLOSED.
3. START 2A or 2B BA Pump.
4. CLOSE V2650, Tank 2A Recirc. Valve.
5. CLOSE V2651, Tank 2B Recirc Valve.
6. OPEN V2514, Emergency Borate. 6.

A. If V251 4 fails to open, PERFORM the following:

1. OPEN V2508, BA Gravity Feed B.
2. OPEN V2509, BA Gravity Feed A.
3. CLOSE V2501 VCT Outlet Valve.

0)

REVISION NO.: PROCEDURE TITLE: PAGE:

6A EMERGENCY BORATION PROCEDURE NO.:

7 Of 9 2-ONP-02.02 ST. LUCIE UNIT 2 6.0 OPERATOR ACTIONS (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

6. (continued)

B. If the Boric Acid Makeup Tanks are unavailable or both Gravity Feed valves failed to open, Then perform the following:

1. OPEN V2504 Refuel Water to Charging Pumps.
2. CLOSE V2501 VCT Outlet Valve.
3. STOP the running BAM pumps.
4. ENSURE V2508 BA Gravity Feed B CLOSED.
5. ENSURE V2509 BA Gravity Feed A CLOSED.
6. ENSURE V2514 Emergency Borate CLOSED.

0)

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE COOL THE QUENCH TANK NRC S-4 Simulator This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC 19A S-4 Simulator Page 1 ofl5

JOB PERFORMANCE MEASURE Task: Cool the Quench Tank Faulted JPM? No Facility JPM #:

K/A: 007.Al.03 2.6/2.7 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limit(s) associated with operating the PRTS controls including: Monitoring quench tank temperature.

Task Standard:

This JPM is complete when the Quench tank has been cooled to within normal operating temperature.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 2-NOP-01 .07, Quench Tank Operation Validation Time: 15 minutes Time Critical: No ToolslEquipment/Procedures Needed:
  • 2-NOP01 .07, Quench Tank Operation Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A S-4 Simulator Page 2 of 15

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is: Cool the Quench Tank Unit 2.
  • The performance level to be used for this JPM is Perform
  • This is not a time critical JPM.
  • You may use any approved reference materials normally available in the execution of this task, including logs.

Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

  • All simulator JPM steps, including communications, shall be performed for this JPM.
  • You are to operate any plant equipment that is necessary for the completion of this JPM.
  • The simulator will provide the cues as you perform this JPM.

Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 2 has been operating at 100% power for 230 days. PORV 1474 has recently started weeping and as a result the Quench Tank temperature has risen above normal values.

INITIATING CUES:

The US has directed you to cool the Quench Tank lAW 2-NOP-Ol .07, Quench Tank Operation section 4.4, Lowering the Quench Tank Temperature by Feed and Bleed until the Quench Tank temperature is within normal operating temperature.

The Prerequisites and Initial Conditions of 2-NOP-Ol .07 are met.

NRC 19A S-4 Simulator Page 3 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

4.4 Lowering Quench Tank Temperature by Feed and Bleed STEP 1(4.4.1) ENSURE Section 2.0 Precautions and Limitations has been reviewed.

STANDARD: REVIEWS Section 2.0 paying particular attention to step 2.1.3: Cooling the Quench tank to less than 115°F could raise the possibility of PORV and SAT Pressurizer Safety Valve leakage.

EXAMINERS CUE: None. UNSAT COMMENTS:

STEP 2:(4.4.2) ENSURE Section 3.0 Prerequisites and Initial Conditions has been reviewed.

STANDARD: REVIEWS Section 3.0. Prerequisites and Initial Conditions SAT EXAMINERS CUE: Unit Supervisor has initialed all Section 3.0 COMMENTS: UNSAT STEP 3:(4.4.3) Lower Quench Tank Level to between 60% and 63% in accordance with Section 4.3, Lowering Quench Tank Level.

STANDARD: PERFORMS Section 4.3. Lowering Quench Tank Level. SAT EXAMINERS CUE: None UNSAT COMMENTS:

NRC 19A S-4 Simulator Page 4 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 4 (4.3.1) ENSURE Section 2.0 Precautions and Limitations has been reviewed.

STANDARD: REVIEWS Section 2.0 paying particular attention to step 2.1.3: Cooling the Quench tank to less than 115°F could raise the possibility of PORV and SAT Pressurizer Safety Valve leakage.

EXAMINERS CUE: None. UNSAT COMMENTS:

STEP 5:(4.3.2) ENSURE Section 3.0 Prerequisites and Initial Conditions has been reviewed.

STANDARD: REVIEWS Section 3.0. Prerequisites and Initial Conditions SAT E)(AMINERS CUE: Unit Supervisor has initialed all Section 3.0 COMMENTS: UNSAT STEP 6 (4.3.3) MONITOR the Reactor Drain Tank as Quench Tank is drained to ensure there is ample volume to hold the water drained from the Quench Tank.

STANDARD: MONITORS Reactor Drain Tank while draining the Quench Tank. SAT EXAMINERS CUE: None.

UNSAT COMMENTS:

STEP 7:(4.3.4) OPEN V6741, NITROGEN HEADER. RTGB-205. CRITICAL STEP STANDARD: POSITIONS V6741 to the OPEN Position EXAMINERS CUE: V6741 indicates Red light on Green light off SAT COMMENTS:

UNSAT NRC 19A S-4 Simulator Page 5 of 15

JOB PERFORMANCE MEASURE CHECKLIST STEP 8: (4.3.5) OPEN Vi 401, QUENCH TANK DRAIN. RTGB-203 CRITICAL STEP STANDARD: POSITIONS V1401, QUENCH TANK DRAIN to the OPEN position.

EXAMINERS CUE: Red light on and green light off V1401, SAT QUENCH TANK DRAIN.

UNSAT COMMENTS:

STEP 10: (4.3.6) IF the Quench Tank pressure lowers to less than 1 psig, THEN PERFORM the following SAT STANDARD: MONITORS Quench Tank pressure. If pressure lowers to less than 1 psig performs the following: UNSAT

8. IF necessary to maintain Quench Tank pressure, THEN EQUALIZE pressure between the Quench Tank and Reactor Drain Tank as follows:

(1) OPEN V1400, QUENCH TANK VENT. RTGB-203 (2) OPEN V6300, VENT VALVE. RTGB-205 EXAMINERS CUE: Quench Tank pressure is 1.5 psig.

EVALUATOR NOTE: Quench Tank pressure should NOT lower less than I psig during performance of this task.

COMMENTS:

NRC 19A S-4 Simulator Page 6 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 11: (4.3.6) IF the Quench Tank pressure lowers to less than 1 psig, THEN PERFORM the following SAT STANDARD: MONITORS Quench Tank pressure. If pressure is between 2 and 4 psig performs the following: UNSAT C. WHEN Quench Tank pressure returns to between 2 and 4 psig, THEN OPEN V1401, Quench Tank Drain. RTGB-203 EXAMINERS CUE: Quench Tank pressure is 1.5 psig.

EVALUATOR NOTE: Quench Tank pressure should NOT lower less than I psig during performance of this task.

COMMENTS:

STEP 12: (4.3.7) If Quench Tank initial level was greater than 70%, THEN VERIFY SAT Annunciator H-32, QUENCH TANK LEVEL HIGH I LOW, CLEAR when level is less than 70%

UNSAT STANDARD: MONITORS Quench Tank level, DETERMINES less than 70%.

EXAMINERS CUE: Quench Tank Level is 65%.

EXAMINERS NOTE: Initial level less than 70%, therefore step not applicable.

COMMENTS:

STEP 13: (4.3.8) WHEN Quench Tank level is between 60% and 70%, THEN CLOSE CRITICAL Vi 401, QUENCH TANK DRAIN. RTGB-203 STEP STANDARD: POSITIONS Vi 401, QUENCH TANK DRAIN to the CLOSE position. SAT EXAMINERS CUE: Quench Tank level is 61%

EXAMINERS CUE: V1401, QUENCH TANK DRAIN indicate red light off green UNSAT light on.

EXAMINERS NOTE: V1401, QUENCH TANK DRAIN will be closed when level is between 60-63% per Step 4.4.3 COMMENTS:

NRC 19A S-4 Simulator Page 7 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 14: (4.3.9) IF Quench Tank pressure is less than 2 psig, THEN ENSURE Vi 400, QUENCH TANK VENT, is CLOSED, RTGB-203 STANDARD: ENSURES Vi 400, QUENCH TANK VENT, is CLOSED. SAT EXAMINERS CUE: Quench Tank pressure is 3 psig. UNSAT COMMENTS:

STEP 15: (4.3.10) WHEN Quench Tank pressure is between 2 psig and 4 psig, THEN PERFORM the following: SAT A. ENSURES Vi400, QUENCH TANK VENT, is CLOSED.

UNSAT STANDARD: ENSURES Vi 400, QUENCH TANK VENT, is CLOSED.

EXAMINERS CUE: Quench Tank pressure is 3 psig EXAMINERS CUE: V1400, Quench Tank Vent indicates red light off green light on EXAMINERS NOTE: VI 400 was not opened, therefore step is not applicable.

COMMENTS:

STEP i6: (4.3.iO) WHEN Quench Tank pressure is between 2 psig and 4 psi, THEN 9

PERFORM the following:

B. ENSURES V6300, VENT VALVE, is CLOSED. SAT STANDARD: ENSURES V6300, VENT VALVE, is CLOSED.

UNSAT EXAMINERS CUE: Quench Tank pressure is 3 psi 9

EXAMINERS CUE: V6300, VENT VALVE indicates red light off green light on.

COMMENTS:

NRC 19A S-4 Simulator Page 8 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 17: (4.3.10) WHEN Quench Tank pressure is between 2 psig and 4 psig, THEN CRITICAL PERFORM the following: STEP C. CLOSE V6741, NITROGEN HEADER. SAT STANDARD: POSITIONS V6741, NITROGEN HEADER to the CLOSED position.

UNSAT EXAMINERS CUE: Quench Tank pressure is 3 psig.

EXAMINERS CUE: V6741, NITROGEN HEADER indicates red light off green light on.

COMMENTS:

STEP 18:(4.4.4)RAISE Quench Tank level to between 67% and 70% in accordance with Section 4.2, Raising Quench Tank Level.

STANDARD: PERFORMS Section 4.2. Raising Quench Tank Level. SAT EXAMINERS CUE: None UNSAT COMMENTS:

STEP 19(4.2.1) ENSURE Section 2.0 Precautions and Limitations has been reviewed.

STANDARD: REVIEWS Section 2.0 paying particular attention to step 2.1.3: Cooling the Quench tank to less than 115°F could raise the possibility of PORV and SAT Pressurizer Safety Valve leakage.

EXAMINERS CUE: None. UNSAT COMMENTS:

NRC 19A S-4 Simulator Page 9 of 15

JOB PERFORMANCE MEASURE PERFORMANCE - T STEP 20:(4.2.2)ENSURE Section 3.0 Prerequisites and Initial Conditions has been reviewed.

STANDARD: REVIEWS Section 3.0. Prerequisites and Initial Conditions SAT EXAMINERS CUE: Unit Supervisor has initialed all Section 3.0 COMMENTS: UNSAT STEP 21: (4.2.3) OPEN V1400, QUENCH TANK VENT. RTGB203 CRITICAL STEP STANDARD: POSITIONS Vi 400, QUENCH TANK VENT to the OPEN position.

EXAMINERS CUE: Red light on and green light off on SAT VI 400, QUENCH TANK VENT.

UNSAT COMMENTS:

STEP 22: (4.2.4) ENSURE HCV-i5-i, PRIMARY WATER TO CONTAINMENT, is OPEN. RTGB-206 STANDARD: CHECKS HCV-i5-i, PRIMARY WATER TO SAT CONTAINMENT is OPEN.

EXAMINERS CUE: Red light on and green light off on HCV- UNSAT 15-1, PRIMARY WATER TO CONTAINMENT.

COMMENTS:

NRC 19A S-4 Simulator Page 10 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 23: (4.2.5) OPEN HCV-15-2, PMW TO QUENCH TANK. CRITICAL RTGB-203 STEP STANDARD: POSITIONS HCV-1 5-2, PMW TO QUENCH TANK to the OPEN position.

SAT E)(AMINERS CUE: Red light on and green light off on HCV 15-2, PMWTO QUENCH TANK.

UNSAT COMMENTS:

STEP 24: (4.2.6) IF Quench Tank pressure reaches 14 psig, THEN PERFORM the following.

SAT A. CLOSE HCV-1 5-2, PMW TO QUENCH TANK.

B. WHEN EITHER of the following conditions exist,

  • Quench Tank pressure is lowered to between 1 and 4 psig OR UNSAT
  • Quench Tank level is lowered to 60% to 63%

THEN OPEN HCV-1 5-2, PMW TO QUENCH TANK.

STANDARD: MONITORS Quench Tank pressure.

EXAMINERS CUE: Quench Tank pressure is 3 psig EXAMINERS NOTE: Quench Tank should not reach these values so step should be not applicable.

COMMENTS:

NRC 19A S-4 Simulator Page 11 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 25: (4.2.7) IF Quench Tank initial level is less than 60%, THEN VERIFY SAT Annunciator H-32, QUENCH TANK LEVEL HIGH/LOW, CLEAR when level exceeds than 60%.

UNSAT STANDARD: MONITORS Quench Tank level, DETERMINES greater than 60%.

EXAMINERS CUE: Quench Tank Level is 61%.

EXAMINERS NOTE: Quench Tank will not be below this value so step should be not applicable.

COMMENTS:

STEP 26 (4.2.8): WHEN Quench Tank level has raised to between 60% and 70%, CRITICAL THEN CLOSE HCV-15-2. STEP STANDARD: POSITIONS HCV-15-2 to the CLOSED position.

SAT EXAMINERS CUE: Quench Tank Level is 69%

EXAMINERS CUE: HCV-15-2 indicates red light off green light on EXAMINERS NOTE: Per step 4.4.4, raise level to between 67% and 70%.

UNSAT COMMENTS:

STEP 27: (4.2.9) WHEN Quench Tank pressure is less than or equal to 4 psig, CRITICAL THEN CLOSE Vi 400, QUENCH TANK VENT. RTGB-203 STEP STANDARD: POSITIONS Vi400, QUENCH TANK VENT, to CLOSE.

SAT EXAMINERS CUE: Quench Tank pressure is 3 psig.

EXAMINERS CUE: V1400 indicates red light off green light on UNSAT COMMENTS:

NRC 19A S-4 Simulator Page 12 of 15

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 28: (4.2.10) IF Quench Tank pressure is less than 1 psig, THEN PERFORM the following.

SAT A. OPEN V6741, NITROGEN HEADER.

B. WHEN Quench Tank pressure is between 2 psig and 4 psig, THEN CLOSE V6741.

UNSAT STANDARD: MONITORS Quench Tank pressure.

EXAMINERS CUE: Quench Tank pressure is 3 psig EXAMINERS NOTE: Quench Tank should not reach these values so step should be not applicable.

COMMENTS:

STEP 29: (4.4.5) REPEAT the previous two steps until both of the following conditions are satisified. SAT

  • Quench Tank temperature is between 115°F and 120° F
  • Quench Tank level is between 60% and 70%

UNSAT STANDARD: MONITORS Quench Tank temperature and Level EXAMINERS CUE: Quench tank temperature indicates 115°F EXAMINERS CUE: Quench tank level indicates 68%

EXAMINERS NOTE: If performed on the simulator, Sections 4.4.3 and 4.4.4 may be performed numerous times until temperature is between 115°F and 120°F.

COMMENTS:

END OF TASK STOP TIME:

NRC 19A S-4 Simulator Page 13 of 15

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-86.
2. UNFREEZE the Simulator.
3. INITIAL Section 3.0 of 2-NOP01 .07, Prerequisites and Initial Conditions, as Unit Supervisor NRC 19A S-4 Simulator Page 14 of 15

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 2 has been operating at 100% power for 230 days. PORV 1474 has recently started weeping and as a result the Quench Tank temperature has risen above normal values.

INITIATING CUES:

The US has directed you to cool the Quench Tank lAW 2-NOP-Ol .07, Quench Tank Operation section 4.4, Lowering the Quench Tank Temperature by Feed and Bleed until the Quench Tank temperature is within normal operating temperature.

The Prerequisites and Initial Conditions of 2-NOP-Ol .07 are met.

Page 15 of 15

REVISION NO.: PROCEDURE TITLE: PAGE:

50 QUENCH TANK OPERATION 7 of 18 PROCEDURE NO.:

2-NOP-Ol .07 ST. LUCIE UNIT 2 4.2 Raising Quench Tank Level INITIAL

1. ENSURE Section 2.0 Precautions and Limitations, has been reviewed.
2. ENSURE Section 3.0, Prerequisites and Initial Conditions, has been reviewed.
3. OPEN V1400, QUENCH TANK VENT. RTGB-203
4. ENSURE HCV-1 5-i, PRIMARY WATER TO CONTAINMENT, is OPEN. RTGB-206
5. OPEN HCV-15-2, PMW TO QUENCH TANK. RTGB-203 NOTE
  • The following step may be repeated as necessary.
  • Annunciator H-16, QUENCH TANK PRESS HIGH, alarms at 15 psig.
  • Annunciator H-32, QUENCH TANK LEVEL HIGH/LOW alarms at 70%

(HIGH) and 60% (LOW).

6. IF Quench Tank pressure reaches 14 psig, THEN PERFORM the following:

A. CLOSE HCV-1 5-2, PMW TO QUENCH TANK.

B. WHEN Quench Tank pressure is lowered to between 1 and 4 psi

, THEN OPEN HCV-15-2. RTGB-203 9

7. IF Quench Tank initial level is less than 60%, THEN VERIFY annunciator H-32, QUENCH TANK LEVEL HIGH! LOW, CLEAR when level exceeds 60%.
8. WHEN Quench Tank level is between 60% and 70%, THEN CLOSE HCV-15-2, PMWTO QUENCH TANK. RTGB-203
9. WHEN Quench Tank pressure is less than or equal to 4 psig, THEN CLOSE Vi 400, QUENCH TANK VENT. RTGB-203

REVISION NO.: PROCEDURE TITLE: PAGE:

50 QUENCH TANK OPERATION 8 of 18 PROCEDURE NO.:

2-NOP-O107 ST. LUCIE UNIT 2 4.2 Raising Quench Tank Level (continued) INITIAL

10. IF Quench Tank Pressure is less than 1 psig, THEN PERFORM the following:

A. OPEN V6741, NITROGEN HEADER.

B. WHEN Quench Tank pressure is between 2 psig and 4 psig, THEN CLOSE V6741. (Section 7.1.3 Management Directive 1)

Performed By:

Print/Sign Initials Date Reviewed By:

Unit Supervisor (Print/Sign) Date

REVISION NO.: PROCEDURE TITLE: PAGE:

5C QUENCH TANK OPERATION 9 of 18 PROCEDURE NO.:

2-NOP-01 .07 ST. LUCIE UNIT 2 4.3 Lowering Quench Tank Level INITIAL

1. ENSURE Section 2.0 Precautions and Limitations, has been reviewed.
2. ENSURE Section 3.0, Prerequisites and Initial Conditions, has been reviewed.
3. MONITOR the Reactor Drain Tank as Quench Tank is drained to ensure there is ample volume to hold the water drained from the Quench Tank.
4. OPEN V6741, NITROGEN HEADER. RTGB-205
5. OPEN V1401, QUENCH TANK DRAIN. RTGB-203 NOTE
  • The following step may be repeated as necessary.
  • Annunciator H-32, QUENCH TANK LEVEL HIGH/LOW alarms at 70%

(HIGH) and 60% (LOW).

6. IF Quench Tank pressure lowers to less than 1 psig, THEN PERFORM the following:

A. CLOSE Vi 401, Quench Tank Drain. RTGB-203 B. IF necessary to maintain Quench Tank pressure, THEN EQUALIZE pressure between the Quench Tank and Reactor Drain Tank as follows:

(1) OPEN Vi 400, QUENCH TANK VENT. RTGB-203 (2) OPEN V6300, RDT VENT VALVE. RTGB-205 C. WHEN Quench Tank pressure returns to between 2 and 4 psig, THEN OPEN Vi 401, Quench Tank Drain. RTGB-203

7. IF Quench Tank initial level was greater than 70%, THEN VERIFY Annunciator H-32, QUENCH TANK LEVEL HIGH / LOW, CLEAR when level is less than 70%.
8. WHEN Quench Tank level is between 60% and 70%, THEN CLOSE Vi 401, QUENCH TANK DRAIN. RTGB-203
9. IF Quench Tank pressure is less than 2 psig, THEN ENSURE Vi 400, QUENCH TANK VENT, is CLOSED. RTGB-203

REVISION NO.: PROCEDURE TITLE: PAGE:

50 QUENCHTANKOPERATION 10 of 18 PROCEDURE NO.:

2-NOP-Ol .07 ST. LUCIE UNIT 2 4.3 Lowering Quench Tank Level (continued) INITIAL

10. WHEN Quench Tank pressure is between 2 psig and 4 psig, THEN PERFORM the following:

A. ENSURE Vi 400, QUENCH TANK VENT, is CLOSED.

B. ENSURE V6300, VENT VALVE, is CLOSED.

C. CLOSE V6741, NITROGEN HEADER.

(Section 7.1 .3 Management Directive 1)

Performed By:

Print/Sign Initials Date Reviewed By:

Unit Supervisor (Print/Sign) Date

REVISION NO.: PROCEDURE TITLE: PAGE:

5C QUENCH TANK OPERATION 11 of 18 PROCEDURE NO.:

2-NOP-O1.07 ST. LUCIE UNIT 2 4.4 Lowering Quench Tank Temperature by Feed and Bleed INITIAL

1. ENSURE Section 2.0 Precautions and Limitations, has been reviewed.
2. ENSURE Section 3.0, Prerequisites and Initial Conditions, has been reviewed.
3. LOWER Quench Tank level to between 60% and 63% in accordance with Section 4.3, Lowering Quench Tank Level.
4. RAISE Quench Tank level to between 67% and 70% in accordance with Section 4.2, Raising Quench Tank Level.
5. REPEAT the previous two steps until both of the following conditions are satisfied:
  • Quench Tank temperature is between 115°F and 120°F.
  • Quench Tank level is between 60% and 70%.

Performed By:

Print/Sign Initials Date Reviewed By:

Unit Supervisor (Print/Sign) Date

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE PLACE THE PRESSURIZER ON RECIRC.

NRC S-5 Simulator This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A S-5 Simulator Page 1 of 8

JOB PERFORMANCE MEASURE Task: Place the Pressurizer on Recirc.

Faulted JPM? YES Facility JPM #:

KIA: 01O.A2.02 3.9/3.9 Ability to predict the impacts of the following malfunctions or operations on the PZR PCS: and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray Valve Failures.

Task Standard:

This JPM is complete when the Reactor has been tripped and the 2B2 RCP has been stopped.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 2-GOP-i 01, Reactor Operating Guidelines During Steady State and Scheduled Load Changes Appendix A
  • 2-0120035, Pressurizer Pressure and Level Validation Time: 10 minutes Time Critical: No ToolslEquipmentlProcedures Needed:
  • 2-GOP-lOl, Reactor Operating Guidelines During Steady State and Scheduled Load Changes Appendix A Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner:

Signature:

Comments NRC 19A S-5 Simulator Page 2 of 8

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is: Place the Pressurizer on Recirc.

The performance level to be used for this JPM is Perform a This is not a time critical JPM.

s You may use any approved reference materials normally available in the execution of this task, including logs.

  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

a All simulator JPM steps, including communications, shall be performed for this JPM.

  • You are to operate any plant equipment that is necessary for the completion of this JPM.

a The simulator will provide the cues as you perform this JPM.

  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 2 is operating at 100%. 2A Heater drain pump has an oil leak and must be removed from service. The Unit Supervisor is preparing for a down power lAW 2GOP-123, Turbine Shutdown Full Load to Zero Load INITIATING CUES:

The US has directed you to place the Pressurizer on recirc lAW 2-GOP-i 01, Appendix A Pressurizer Recirculation Guidelines.

NRC 19A S-5 Simulator Page 3of8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

2-GOP-IOI Appendix A STEP l(i.A) PLACE all available Backup Heater Bank control switches to ON. CRITICAL STEP STANDARD: POSITION B-i, B-2, B-4, and B-6 to the ON position.

EXAMINERS CUE: B-I, B-2, 8-4, and B-6 indicate red light on green light off. SAT EXAMINERS NOTE: 8-3 and 8-5 are already energized.

UNSAT COMMENTS:

STEP 2:(i .B) Slowly REDUCE the AUTO setpoint on PlC-i i OOX or PlC-li OOY, the CRITICAL selected Pressurizer Pressure controller, to maintain normal operating STEP pressure.

STANDARD: SLOWLY reduces PlC-i iOOX setpoint to approximately 2220 psia SAT EXAMINERS CUE: PIC-IIOOX setpoint is 2220 psia.

EXAMINERS NOTE: PIC-IIOOX setpoint is required to be reduced to UNSAT approximately 2220 psia to maintain 2250 psia.

COMMENTS:

NRC 19A S-5 Simulator Page 4 of 8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 3:(1 .C) OBSERVE HIC-1 100, Pressurizer Spray output and PCV-1 I 00E / 11 00F, FAULTED Pressurizer Spray Valve position indication to verify Main Spray flow. STEP STANDARD: OBSERVES PCV-1 IOOE /1 100F, Pressurizer Spray Valves.

DETERMINES spray valves are opening further than required and Pressure SAT is rapidly lowering. Takes manual control of HIC-1 100 in attempt to close the spray valves. When PCV-1 1 OOE does not close, places the spray selector switch to the PCV-1IOOF position. UNSAT EXAMINERS CUE: PCV-IIOOE and PCV-1100F red light on green light off.

EXAMINERS CUE: When HIC-1100 taken to manual and setpoint lowered, PCV-1100F green light on red light off. PCV1100E red light on green light off.

EVALUATOR NOTE: PCV-1100E I hOOF, Pressurizer Spray Valves will start to open as indicated by red and green lights. Both valves will open fully. The applicant should take manual control of HIC-1100 and attempt to close the valves. Only PCV-IIOOF will close.

COMMENTS:

STEP 4: Trip the Reactor CRITICAL STEP STANDARD: TRIPS the Reactor prior to automatic TMLP trip setpoint of approximately 2050 psia. SAT EXAMINERS CUE: All CEAs indicate rod bottom lights illuminated.

EXAMINERS NOTE: Applicant should trip the Reactor no later than 214 RPS UNSAT TMLP PRE-TRIP setpoint of 2100 psia.

COMMENTS:

STEP 5: Starts 2B2 Rector Coolant Pump oil lift pumps.

STANDARD: POSITIONS 2B2 Reactor Coolant Pump oil lift pumps to the ON position. SAT EXAMINERS CUE: 2B2 Reactor Coolant Pump oil lift pumps indicate red light on green light off. UNSAT COMMENTS:

NRC 19A S-5 Simulator Page 5 of 8

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST CRITICAL STEP 6: Stop 2B2 Reactor Coolant Pump. STEP STANDARD: POSITION 2B2 Reactor Coolant Pump to the STOP position.

SAT EXAMINERS CUE: 2B2 Reactor Coolant Pump indicates green light on red light off. AMP meter indicates 0. UNSAT COMMENTS:

END OF TASK STOP TIME:

NRC 19A S-5 Simuator Page 6 of 8

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-i.
2. EXECUTE Scenario S-5 Place the Pressurizer on Recirc.
3. UNFREEZE the Simulator.
4. ENSURE step Sprays Full Open auto triggers at 2225 psia NRC WA S-5 Simulator Page 7 of 8

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 2 is operating at 100%. 2A Heater drain pump has an oil leak and must be removed from service. The Unit Supervisor is preparing for a down power lAW 2-GOP-i 23, Turbine Shutdown Full Load to Zero Load INITIATING CUES:

The US has directed you to place the Pressurizer on recirc lAW 2-GOP-ioi, Appendix A Pressurizer Recirculation Guidelines.

Page 8 of 8

REVISION NO.: PROCEDURE TITLE: PAGE:

9B REACTOR OPERATING GUIDELINES DURING STEADY 12 f 15 PROCEDURE NO.: STATE AND SCHEDULED LOAD CHANGES 2-GOP-i 01 ST. LUCIE UNIT 2 APPENDIX A PRESSURIZER RECIRCULATION GUIDELINES (Page 1 of 2)

NOTE

  • The purpose of placing the Pressurizer on recirculation is to keep the Pressurizer and RCS boron concentration within 25 ppm when changing RCS boron concentration.
  • From measured data, the estimated time in minutes to correct a greater than or equal to 25 ppm boron mismatch by operating 6 Backup Bank heaters may be determined as follows:

Time (in minutes) to correct mismatch = [(Pzr ppm - RCS ppm) 25 ppm] x 3

1. To place the Pressurizer on recirculation:

A. PLACE all available Backup Bank heater control switches to ON.

B. Slowly REDUCE the AUTO setpoint on PlC-li OOX or PlC-li OOY, the selected Pressurizer Pressure controller, to maintain normal operating pressure.

C. OBSERVE HIC-iiOO, Pressurizer Spray output and PCV-liOOE/1100F, Pressurizer Spray Valve position indication to verify Main Spray flow.

NOTE Normally, the required number of Backup Bank heaters in service is dependent upon:

1. The magnitude of thermal losses from the system, including leakage to the Quench Tank.
2. The number of heater elements out of service.

The normal configuration is to have enough Backup Bank heaters in service to keep the Proportional Bank heaters at approximately 50% output.

2. To take the Pressurizer off recirculation:

A. REMOVE the additional Backup Bank heaters from service one at a time by returning the control switch to AUTO.

B. ADJUST the AUTO setpoint on PlC-i 1 OOX or PlC-i 1 OOY, the selected Pressurizer Pressure controller, to maintain normal operating pressure.

REVISION NO.: PROCEDURE TITLE: PAGE:

26 PRESSURIZER PRESSURE AND LEVEL PROCEDURE NO.:

6 of 15 2-0120035 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

1. A. (continued) 1. A. (continued)
3. If both pressure channels are failed or automatic pressure control does NOT operate properly, Then operate spray controller in manual and energize or deenergize heaters as necessary.

NOTE Divergence of Spray Line Temperatures between 2B1 and 2B2 Spray lines may indicate a stuck open spray valve. The stuck open spray valve would have the spray line with the higher temperature approaching cold leg temperature.

B. Verify PCV 11 OOE, Spray Valve 2B2, B. ,lf either spray valve is OPEN,

fld PCV 11 OOF, Spray Valve 2B1, / Then perform the following

CLOSED by observing BOTH of the following:

1. CLOSED valve position PCV 11 OOE, Spray Valve indication. /2B2, is OPEN, Then PLACE the spray valve selector switch in PCV1100F.
2. TIA-1103, Spray Line 2B1 / 2. PCV 11 OOF, Spray Valve Temperature, and TIA-1104, 2B1, is OPEN, Then Spray Line 2B2 Temperature, PLACE the spray valve approximately equal. selector switch in PCV 1100E.

REVISION NO.: PROCEDURE TITLE: PAGE:

26 PRESSURIZER PRESSURE AND LEVEL PROCEDURE NO..

7 Of 15 2-01 20035 ST. LUCIE UNIT 2 7.2 Subsequent Operator Actions (continued)

INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued) fi. B. (continued) 13.ifpressure continues to decrease due to a failed open matn spray valve, Then consider performing the following:
  • Tripthereactorand

\-turbIne

  • Stop the RCP in the

( Jaffected loop.

PCV 11 OOE-2B2 RCP PCV1100F-2B1 RCP

4. if the RCP in the affected loop has been secured and pressure continues to decrease, Then consider securing both 2B1 and 2B2 RCPs.

C. Verify SE-02-03, and SE-02-04, C. If auxiliary spray valve(s) is Auxiliary Spray Valve(s), CLOSED. OPEN, Then:

1. Attempt to close using key switch.
2. If auxiliary spray valves will NOT close, Then stop all charging and isolate letdown. Refer to 2-ONP-02.03, Charging and Letdown.
3. Review AP 0010134, Component Cycles and Transients, for applicability when plant is stabilized.

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE RESPOND TO CONTROL ROOM OUTSIDE AIR INTAKE RADIATION ALARMS NRC S-6 Simulator This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A S-6 Simulator Page 1 of 16

JOB PERFORMANCE MEASURE Task: Respond to Control Room outside air intake radiation alarms.

Faulted JPM? YES Facility JPM #:

K/A: 072.A3.O1 2.9 / 3.1 Ability to monitor automatic operation of the ARM system including: Changes in ventilation alignment.

Task Standard:

This JPM is complete when Unit 2 control room ventilation has been lined up lAW 2-ONP-25.02, Ventilation Systems Appendix B.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 2-ONP-25,02, Ventilation Systems Validation Time: 15 minutes Time Critical: No ToolslEquipment/Procedures Needed:
  • 2-ONP-25.02, Ventilation Systems Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A S-6 Simulator Page 2 of 16

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

a The task you are to perform is: Respond to Control Room outside air intake radiation alarms.

  • The performance level to be used for this JPM is Perform
  • This is not a time critical JPM.
  • You may use any approved reference materials normally available in the execution of this task, including logs.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

SPECIFIC DIRECTIONS FOR SIMULATOR JPMs:

a All simulator JPM steps, including communications, shall be performed for this JPM.

  • You are to operate any plant equipment that is necessary for the completion of this JPM.

a The simulator will provide the cues as you perform this JPM.

  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 1 has experienced a LBLOCA. SIAS and CIAS have occurred, but a breach of the Containment is in progress. Unit 2 Control Room has Outside Air Intake Radiation Monitors are in high alarm INITIATING CUES:

The US has directed you to verify Control Room ventilation and restore an outside air intake lAW 2-ONP-25-02, Ventilation Systems Appendix B NRC 19A S-6 Simulator Page 3 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

ENTER 2-ONP-25.02, Ventilation Systems Appendix B STEP 1(1) CHECK the following system alignment:

One (1) HVE-13A Inlet Damper (D-17A) OPEN SAT STANDARD: CHECKS One (1) HVE-13A Inlet Damper(D-17A) to be OPEN.

UNSAT EXAMINERS CUE: HVE-13A Inlet Damper (D-17A) indicates red light ON green light OFF.

COMMENTS:

STEP 2:(1) CHECK the following system alignment:

One (1) HVE-13A Inlet Damper (D-18) OPEN SAT STANDARD: CHECKS One(1) HVE-13A Inlet Damper (D-18) to be OPEN.

UNSAT EXAMINERS CUE: HVE-13A Inlet Damper (D-18) indicates red light ON green light OFF.

COMMENTS:

STEP 3:(1) CHECK the following system alignment:

FCV-25-24, kitchen Exhaust Isolation Valve CLOSED SAT STANDARD: CHECKS FCV-25-24, kitchen Exhaust Isolation Valve to be CLOSED.

UNSAT EXAMINERS CUE: FCV-25-24, kitchen Exhaust Isolation Valve indicates red light OFF green light ON.

COMMENTS:

NRC 19A S-6 Simulator Page 4 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 4: (1) CHECK the following system alignment: FAULTED STEP FCV-25-16, North OAI Isolation Valve CLOSED SAT STANDARD: CHECKS FCV-25-16, North OAt Isolation Valve to be CLOSED.

DETERMINNES valve is open and POSITIONS FCV-25-16, North OAI Isolation Valve to CLOSED. UNSAT E)(AMINERS CUE: FCV-25-16, North OAI Isolation Valve indicates red light ON green light OFF.

EXAMINERS CUE: FCV-25-16, North OAI Isolation Valve indicates red light OFF green light ON (after repositioning).

COMMENTS:

STEP 5: (1) CHECK the following system alignment:

FCV-25-17, South OAt Isolation Valve CLOSED SAT STANDARD: CHECKS FCV-25-17, South OAt Isolation Valve CLOSED.

UNSAT EXAMINERS CUE: FCV-25-17, South OAI Isolation Valve indicates red light OFF green light ON.

COMMENTS:

STEP 6: (1) CHECK the following system alignment:

FCV-25-18, Toilet Exhaust Isolation Valve CLOSED SAT STANDARD: CHECKS FCV-25-18, Toilet Exhaust Isolation Valve to be CLOSED UNSAT EXAMINERS CUE: FCV-25-18, Toilet Exhaust Isolation valve indicates red light OFF green light ON.

COMMENTS:

NRC 19A S-6 Simulator Page 5 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 7: (1) CHECK the following system alignment:

One (1) Control Room Emergency Filter Fan (HVE-13A) START SAT STANDARD: CHECKS One (1) Control Room Emergency Filter Fan (HVE-1 3A) to be RUNNING.

UNSAT EVALUATOR CUE: Control Room Emergency Filter Fan (HVE-13A) indicates red light ON green light OFF.

COMMENTS:

STEP 8: (1) CHECK the following system alignment:

SAT One (1) HVE-1 3B Inlet Damper (D-1 7B) OPEN STANDARD: CHECKS One (1) HVE-i 3B Inlet Damper (D-1 7B) to OPEN UNSAT EXAMINERS CUE: HVE-13B Inlet Damper (D-17B) indicates red light ON green light OFF.

COMMENTS:

STEP 9: (1) CHECK the following system alignment:

One (1) HVE-1 3B Inlet Damper (D-1 9) OPEN STANDARD: CHECKS One (1) HVE-13B Inlet Damper (D-1 9) to be OPEN. SAT EXAMINERS CUE: HVE-13B Inlet Damper (D-19) indicates red light ON green light OFF. UNSAT EXAMNIERS NOTE: There are no controls for Damper D-19.

COMMENTS:

NRC 19A S-6 Simulator Page 6 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 10: (1) CHECK the following system alignment:

SAT FCV-25-25, kitchen Exhaust Isolation Valve CLOSED UNSAT STANDARD: CHECKS FCV-25-25, kitchen Exhaust Isolation Valve to be CLOSED EXAMINERS CUE: FCV-25-25, kitchen Exhaust Isolation Valve indicates red light OFF green light ON.

COMMENTS:

STEP 11: (1) CHECK the following system alignment: FAULTED STEP FCV-25-14, North OAI Isolation Valve CLOSED STANDARD: CHECKS FCV-25-14, North OAI Isolation Valve to be CLOSED SAT DETERMINES FCV-25-14 to be open and POSITIONS FCV-25-14, North OAI Isolation Valve to the CLOSED position.

EXAMINERS CUE: FCV-25-14, North OAI Isolation Valve indicates red light UNSAT ON green light OFF.

EXAMINERS CUE: FCV-25-14, North OAI Isolation Valve indicates red light OFF green light ON (after repositioning).

COMMENTS:

STEP 12 (1): CHECK the following system alignment:

FCV-25-1 5, South OAI Isolation Valve CLOSED SAT STANDARD: CHECKS FCV-25-15, South OAI Isolation Valve to be CLOSED EXAMINERS CUE: FCV-25-15, South OAI Isolation Valve indicates red light OFF green light ON UNSAT COMMENTS:

NRC 19A S-6 Simulator Page 7 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 13: (1) CHECK the following system alignment:

SAT FCV25-19, Toilet Exhaust Isolation Valve CLOSED STANDARD: CHECKS FCV-25i9, Toilet Exhaust Isolation Valve to be CLOSED UNSAT EXAMINERS CUE: FCV-25-19, Toilet Exhaust Isolation Valve indicates red light OFF green light ON.

COMMENTS:

STEP 14: (1) CHECK the following system alignment:

One (1) Control Room Emergency Filter Fan (HVE-13B) START SAT STANDARD: CHECKS Control Room Emergency Filter Fan (HVE13B) to be RUNNING.

UNSAT EXAMINERS CUE: Control Room Emergency Filter Fan (HVE-13B) indicate red light ON green light OFF.

COMMENTS:

STEP 15: (2) If a Control Room Emerg Filter Fan did NOT start, Then manually START the applicable fan:

  • HVE-1 3A.

SAT

  • HVE-13B.

STANDARD: DETERMINES both HVE-1 3A and HVE-1 3B are running.

UNSAT EXAMINERS CUE: HVE-13A and HVE-13B indicate red light ON and green light OFF.

COMMENTS:

NRC 19A S-6 Simulator Page 8 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 16: (3) If any damper failed to position properly, Then manually POSITION the CRITICAL damper, as indicated in step 1. STEP STANDARD: POSITION the following if not previously performed:

CLOSE FCV-25-16, North CAl Isolation Valve SAT CLOSE FCV-25-14, North CAl Isolation Valve EXAMINERS CUE: FCV-25-16, North OAI Isolation Valve indicates red light UNSAT OFF green light ON.

FCV-25-14, North OAI Isolation Valve indicates red light OFF green light ON.

EXAMINERS NOTE: HVE-138 Inlet Damper (0-19) indicates red light off green light on. There are no controls for Damper 0-19.

COMMENTS:

STEP 17: (4) STOP HVE-14, Cntr Rm Toilet Exhaust Fan.

STANDARD: POSITIONS HVE-14, Cntr Rm Toilet Exhaust Fan to the stopped position SAT EXAMINERS CUE: HVE-14 local switch position is in the down position.

EXAMINERS NOTE: HVE-14 is not modeled. UNSAT COMMENTS:

STEP 18: (5) STOP HVE-33, Kitchen Exhaust Fan.

SAT STANDARD: POSITIONS HVE-33, Kitchen Exhaust Fan to the stopped position EXAMINERS CUE: HVE-33, local switch position is in the down position UNSAT EXAMINERS NOTE: HVE-33 is not modeled.

COMMENTS:

NRC 19A S-6 Simulator Page 9 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 19: (6) If both Control Room CAl Radiation Monitors on any intake are inoperable, Then REFER TO Tech Spec 3.3.3.1.

SAT STANDARD: DETERMINES both Control Room OAI Radiation Monitors are operable.

EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 20: (7) CRITICAL NOTE STEP Due to changing environmental conditions during long term events, it may be necessary to repeat steps 7 & 8 to maintain the lowest possible dose.

SAT DETERMINE which Control Room CAl has the least amount of radiation:

  • North OAI
  • South CAl UNSAT STANDARD: MONITORS OAI on PC-Il or CAl RM 23s. DETERMINES lowest dose is South.

EXAMINERS CUE: South indicates south intake is not in alarm EXAMINERS NOTE: Applicant should refer to PC-Il or RM 23s OAI radiation monitors to determine which OAt has the lowest dose.

The South OAI should indicate the lowest dose due to Unit us North of Unit 2.

COMMENTS:

NRC 19A S-6 Simulator Page 10 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 21: (8.A) When the OAT with the lowest amount of radiation has been determined, CRITICAL Then PERFORM the following: STEP OPEN the FCV on the lowest reading side: SAT

  • FCV-25-14, North OAT Isolation Valve
  • FCV-25-15, South OAI Isolation Valve UNSAT STANDARD: POSITIONS FCV-25-15, South OAT Isolation Valve to OPEN EXAMINERS CUE: FCV-25-15, South OAI Isolation Valve indicate red light ON green light OFF. V-16 alarms.

EXAMINERS NOTE: Inching valve to Open.

COMMENTS:

STEP 22: (8.B) When the OAT with the lowest amount of radiation has been determined, CRITICAL Then PERFORM the following: STEP THROTTLE the FCV on the lowest reading side throttle: SAT

  • FCV-25-16, North OAT Isolation Valve
  • FCV-25-17, South OAT Isolation Valve UNSAT STANDARD: THROTTLES FCV-25-17, South OAT Isolation Valve EXAMINERS CUE: FCV-25-17, South OAl Isolation Valve indicates 450 CFM on Fl 25-18B.

COMMENTS:

NRC 19A S-6 Simulator Page 11 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 23: (8.0) When the OAI with the lowest amount of radiation has been determined, Then PERFORM the following:

THROTTLE Control Room ventilation return air as necessary. SAT

  • PLACE PDIC-25-23A1, Cont Room to Outside Li P to Man and ADJUST as necessary.
  • PLACE PDIC-25-23B1, Cont Room to Outside Li P to Man UNSAT and ADJUST as necessary.

STANDARD: PLACES PDIC-25-23B1, Cont Room to Outside Li P to MAN EXAMINERS CUE: PDIC-25-23B1, Cont Room to Outside Li P is in manual and adjusted to zero demand. No adjustment is required.

E)(AMINERS NOTE: No adjustment necessary due to current system conditions.

COMMENTS:

STEP 24: (8.D) MAINTIAN parameters:

SAT OAI FCV CONTROL FLOW FLOW INITIAL ROOM PRESS INDICATION RATE MIN UNSAT 450 scfm NORTH FCV-25-16 0.125 in. H2O Fl-25-18A 450 scfm SOUTH FCV-25-17 0.125 in. H2O Fl-25-18B STANDARD: MONITORS above parameters EXAMINERS CUE: NONE COMMENTS:

NRC 19A S-6 Simulator Page 12 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 25: (8.E) If Control Room pressure indication is erratic and the required pressure differential cant be verified, Then MAINTAIN outside air intake air flow rate between 440 to 450 SCFM. SAT STANDARD: MONITORS Control Room pressure indication. UNSAT EXAMINERS CUE: Control Room pressure indication is steady.

COMMENTS:

STEP 26: (9) Initiate a Data Sheet 30 to track wind direction on a (4) four hour frequency.

STANDARD: INITIATES Data Sheet 30 track wind direction.

SAT E)(AMINERS CUE: Other RCO will initiate Data Sheet 30.

COMMENTS: UNSAT STEP 27: (10) If wind directions changes 90 degrees or more, in (4) four hours, Then, RE-PERFORM steps 7 and 8 above. SAT STANDARD: MONITORS wind direction on Data Sheet 30 UNSAT EXAMINERS CUE: Other RCO will monitor wind direction COMMENTS:

NRC 19A S-6 Simulator Page 13 of 16

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 28: (11) If desired, Then STOP ONE of the following Control Room Emerg Filter Fans:

  • HVE-13B UNSAT STANDARD: Both fans left running.

EXAMINERS CUE: Unit Supervisor directs keeping both fans running.

EXAMINERS CUE: HVE-13A and HVE-13B indicate red light ON green light OFF.

COMMENTS:

STEP 29: (12.A & B) When initiating signals are CLEARED, Then PERFORM ALL of the following:

ENSURE both Control Room Emerg Filter Fans are secured and SAT their control switches are in auto.

  • HVE-13A
  • HVE-13B UNSAT RESTORE Normal System Alignment per 2-NOP-25.07.

STANDARD: DETERMINES current lineup needs to be maintained because release is still occurring.

EXAMINERS CUE: Unit I still has a Containment breach and release is still occurring.

COMMENTS:

END OF TASK STOP TIME:

NRC 19A S-6 Simulator Page 14 of 16

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-i.
2. EXECUTE S-6 RESPOND TO CR OAI RADIATION, ensure step CR Ventilation Failures are triggered.
3. UNFREEZE the simulator.
4. TRIGGER step CR CAl RAD and ACKNOWLEDGE PC-il alarm.
5. The last two steps will auto trigger on the candidates actions.
6. Scenario must be stopped and re-executed after each candidate.

NRC 19A S-6 Simulator Page 15 of 16

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit I has experienced a LBLOCA. SIAS and CIAS have occurred, but a breach of the Containment is in progress. Unit 2 Control Room has Outside Air Intake Radiation Monitors are in high alarm INITIATING CUES:

The US has directed you to verify Control Room ventilation and restore an outside air intake lAW 2-ONP-25-02, Ventilation Systems Appendix B Page 16 of 16

REVISION NO.: PROCEDURE TITLE: PAGE:

21 VENTILATION SYSTEMS PROCEDURE NO.:

28 of 33 2-ONP-25.02 ST. LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 1 of 3)

INITIAL CHECK the following system alignment:

A B REQUIRED HVAC PANEL TRAIN TRAIN STATUS One (1) HVE-13A Inlet Damper(D-17A) OPEN N/A One (1) HVE-13A Inlet Damper (D-18) OPEN N/A FCV-25-24, kitchen Exhaust Isolation Valve CLOSED N/A FCV-25-16, North OAI Isolation Valve CLOSED N/A FCV-25-1 7, South OAI Isolation Valve CLOSED N/A FCV-25-18, Toilet Exhaust Isolation Valve CLOSED N/A One (1) Control Room Emergency Filter Fan (HVE-13A) START N/A One (1) HVE-13B Inlet Damper(D-17B) OPEN N/A One (1) HVE-1 3B Inlet Damper (D-1 9) OPEN N/A FCV-25-25, kitchen Exhaust Isolation Valve CLOSED N/A FCV25-i4, North OAI Isolation Valve CLOSED N/A FCV-25-15, South OAI Isolation Valve CLOSED N/A FCV-25-19, Toilet Exhaust Isolation Valve CLOSED N/A One (1) Control Room Emergency Filter Fan (HVE-13B) START N/A

2. a Control Room Emerg Filter Fan did NOT start, Then manually START the applicable fan:
  • HVE-13A.
  • HVE-13B.
3. If any damper failed to position properly, Then manually POSITION the damper, as indicated in step 1.
4. STOP HVE-14, Cntr Rm Toilet Exhaust Fan.
5. STOP HVE-33, Kitchen Exhaust Fan.
6. If both Control Room OAI Radiation Monitors on any intake are inoperable, Then REFER TO Tech Spec 3.3.3.1.

REVISION NO.: PROCEDURE TITLE: PAGE:

21 VENTILATION SYSTEMS PROCEDURE NO.:

29 of 33 2-ONP-25.02 ST. LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 2 of 3)

NOTE

¶7,12 Due to changing environmental conditions during long term events, it may be necessary to repeat steps 7 & 8 to maintain the lowest possible dose.

INITIAL

7. DETERMINE which Control Room OAI has the least amount of radiation:
  • North OAI
  • South OAI
8. When the OAI with the lowest amount of radiation has been determined, Then PERFORM the following:

A. OPEN the FCV on the lowest reading side:

  • FCV-25-14, North OAI Isolation Valve
  • FCV-25-1 5, South OAl Isolation Valve B. THROTTLE the FCV on the lowest reading side throttle:
  • FCV-25-1 6, North OAl Isolation Valve
  • FCV-25-17, South OAI Isolation Valve C. THROTTLE Control Room ventilation return air as necessary.
  • PLACE PDIC-25-23A1, Cont Room to Outside AP to Man and ADJUST as necessary.
  • PLACE PDIC-25-23B1, Cont Room to Outside AP to Man and ADJUST as necessary.

N)

REVISION NO.: PROCEDURE TITLE: PAGE:

21 VENTILATION SYSTEMS PROCEDURE NO.:

30 of 33 2.ONP-25.02 ST. LUCIE UNIT 2 APPENDIX B CIAS AND CONTROL ROOM OAI HIGH RADIATION (Page 3 of 3)

8. (continued) INITIAL
0. MAINTAIN parameters:

CONTROL ROOM PRESS FLOW FLOW OAI FCV INITIAL MIN INDICATION RATE NORTH FCV-25-16 0.125 in. H 0

2 FI-25-18A 450 scfm SOUTH FCV-25-17 0.125 in. H 0

2 FI-25-18B 450 scfm E. If Control Room pressure indication is erratic and the required pressure differential cant be verified, Then MAINTAIN outside air intake air flow rate between 440 to 450 SCFM.

9. ¶Ji Initiate a Data Sheet 30 to track wind direction on a (4) four hour frequency.
10. ¶712 If wind directions changes 90 degrees or more, in (4) four hours, Then, RE-PERFORM steps 7 and 8 above.
11. ¶. HZ desired, Then STOP ONE of the following Control Room Emerg Filter Fans:
  • HVE13A
  • HVE-13B
12. When initiating signals are CLEARED, Then PERFORM ALL of the following:

A. ENSURE both Control Room Emerg Filter Fans are secured and their control switches are in auto.

  • HVE-13A
  • HVE-13B B. RESTORE Normal System Alignment per 2-NOP-25.07.

END OF APPENDIX B

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE ALIGN THE IC ICW PUMP TO THE IA ICW HEADER -

UNITI NRC P-I Unit I Intake Structure This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC P-i Unit 1 Intake Structure Page 1 of 10

JOB PERFORMANCE MEASURE Task: 07021020 - Perform local actions to align the IC ICW Pump the 1A ICW Header on Unit 1 Faulted JPM? No Facility JPM #: 0821093 KIA: 076,K4.06 2.8 / 3.2 Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: Service water train separation.

Task Standard:

This JPM is complete when the control when the 1C Intake Cooling Water pump has been aligned and started on the 1A ICW Header.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

1-NOP-21.03C, Section 4.1, Starting the IC ICW Pump on A Header with Header Pressurized Validation Time: 20 minutes Time Critical: No ToolslEquipmentlProcedures Needed:

1-NOP-21.03C, Section 4.1, Starting the 1C ICW Pump on A Header with Header Pressurized.

Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

None Radiological Protection and RWP Requirements:

None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC P-i Unit 1 Intake Structure Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

The task you are to perform is:

Perform local actions to align the 1C ICW Pump the 1A lOW Header on Unit 1

  • The performance level to be used for this JPM is Simulate
  • This is not a time critical JPM.
  • During the performance of the task, I will tell you which steps to simulate or discuss.
  • I will provide you with the appropriate cues for steps that are simulated or discussed.

a You may use any approved reference materials normally available in the execution of this task, including logs.

a Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power steady state conditions.

1. The 1A lOW Pump is to be taken out of service for routine maintenance.
2. The 10 lOW Pump is to be aligned and started on the 1A lOW Header during the anticipated two hours required to complete the maintenance in the 1A lOW Pump.
3. The AB Bus is electrically aligned to the 1A3 Bus.

INITIATING CUES:

You are the AN P0. The Unit Supervisor has directed you to perform the following in accordance with 1-NOP-21.030, Section 4.1:

1. Align the IC ICW Pump to supply the 1A lOW Header
2. Observe the starting on the 10 lOW Pump.

NOTE: All Prerequisites for 1-NOP-21.030, Section 4.1 are complete NRC P-i Unit 1 Intake Structure Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

1-NOP-21.03C, Section 4.1, Starting IC ICW Pump on A Header with Header Pressurized.

STEP 1:(4.O)

SAT NOTE Review of ATTACHMENT 1 prior to performance of this procedure is recommended UNSAT STANDARD: REVIEWS ATTACHMENT 1 EXAMINERS CUE: None COMMENTS:

NOTE CRITICAL

1. Proper CLOSED alignment of crosstie valve requires the valve indicator arrow STEP to lineup with the V notch on the indicator plate. (ATTACHMENT 1 Step 2)
2. System Performance Group/OSE shall be notified if crosstie valve is not SAT aligned properly.
3. If two lOW Pumps are electrically aligned AND operating on the same electrical bus while the unit is in Modes 1, 2 or 3 (SIAS NOT blocked), the UNSAT associated Off-Site Power source must be declared inoperable in accordance with Technical Specification. (Section 7.1 .3 Management Directive 3)

STEP (4.1.1) ENSURE Locked Closed SB21211, 1C ICW Pump Cross Tie Disch. to B Train Isol. (INTKJ9/N-41W-C)

STANDARD: UNLOCK, CLOSE, and LOCK SB21 211.

EXAMINERS CUE: SB21211 is UNLOCKED, pointer indicates CLOSED, handwheel is RELOCKED EVALUATORS NOTE: See Notes above:

1. Per note in the procedure, the proper CLOSED alignment of the crosstie valve requires the valve indicator arrow to line up with the V notch on the indicator plate.
2. N/AforthisJPM
3. Unit Supervisor is aware of Tech Spec. concern COMMENTS:

NRC P-i Unit 1 Intake Structure Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 2:(4.1 .2) ENSURE Locked Open SB21 165, 1C ICW Pump Crosstie Disch. to A Train Isol. (INTKI9/N-4/W-C)

STANDARD: UNLOCK, ENSURE OPEN, and LOCK SB21165.

SAT EXAMINERS CUE: S821165 is UNLOCKED, pointer indicates OPEN, handwheel is RELOCKED EXAMINERS NOTE: SB21165 may be already locked open depending on UNSAT plant conditions.

COMMENTS:

STEP 3:(4.1.3) ENSURE 1C ICW Pump motor lube oil level approximately at STANDSTILL level mark.

STANDARD: OBSERVE IC ICW Pump motor bearing sightglass for PROPER oil LEVEL.

SAT EXAMINERS CUE: Motor Oil level in upper and lower sightglass is 1/4 full EXAMINERS NOTE: If candidate starts to climb ladder to upper sightglass access door, give him the cue above for the upper UNSAT sightglass. The lower sightglass is also difficult to see via the access door. If candidate starts to go under the wall, give the cue above for the lower sightglass.

However, the candidate should discuss any safety above 6 requirements if he were to need to climb.

COMMENTS:

STEP 4:(4.1.4) VERIFY LOCKED OPEN SB21206, 1C ICW Pump Disch. Valve.

(INTK/1 815-41W-C)

STANDARD: VERIFY SB21206 is LOCKED OPEN.

SAT EXAMINERS CUE: SB21206 is LOCKED in the OPEN Position COMMENTS: UNSAT STEP 5:(4.1.5) CLOSE SH21204, P1-21-SC Isol. for 1C ICW Pp. Disch. Press.

(INTKJ23IN-3/W-C) CRITICAL STEP STANDARD: POSITION SH21204 to CLOSED.

SAT EXAMINERS CUE: 5H21204 is CLOSED (Valve handle perpendicular to pipe)

COMMENTS: UNSAT NRC P-i Unit 1 Intake Structure Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 6:(4.1 .6) CLOSE the local instrument isolation for PT-21-8A, A ICW Hdr. Pressure CRITICAL Transmitter. STEP STANDARD: POSITION the local instrument isolation for PT-218A to CLOSED. SAT EXAMINERS CUE: Local Instrument Isolation for PT-21-8A to CLOSED. If candidate wants to stop JPM because valve TAG and UNSAT procedure do not agree, inform him that the US has confirmed that it is the correct valve.

EVALUATORS NOTE: Valve handle should be perpendicular to the pipe.

Valve TAG reads: ICW Pump DISCH HDR Train A PRESS COMMENTS:

CAUTION Starting pump while it is rotating backwards could result in damage to the pump. SAT TTACHMENT 1 Step 1)

UNSAT STEP 7:(4.1.7) VERIFY the 1C ICW Pump shaft is not rotating backwards.

STANDARD: OBSERVE the 1C ICW Pump shaft.

EXAMINERS CUE: The IC ICW Pump shaft is stationary.

EVALUATORS NOTE: Per note in the procedure, starting the pump while it i rotating backwards could result in pump damage.

COMMENTS:

STEP 8:(4.1.8) START 1C ICW pump.

STANDARD: NOTIFY the Control Room that IC OW Pump is ready to START.

SAT EXAMINERS CUE: Control Room acknowledges makes plant announcement and REPORTS the IC ICW Pump has been Started. The IC ICW Pump is now running. UNSAT COMMENTS:

NRC P-i Unit 1 Intake Structure Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 9:(4.1.9) WHEN IC ICW Pump amps stabilize, THEN stop the 1A ICW pump and place the control switch to the PULL TO LOCK position.

STANDARD: None, this is a Control Room Step. SAT EXAMINERS CUE: Control Room makes announcement theyare securinglstopping the IA ICW Pump. UNSAT EXAMINERS CUE: Control Room informs you that the IA ICW Pump control switch is in PULL to LOCK (or Step 9 is complete).

COMMENTS:

STEP lO:(4.1.1O) VERIFY the 1A ICW Pump shaft comes to rest.

STANDARD: OBSERVE the 1A ICW Pump shaft.

SAT EXAMINERS CUE: The IA ICW Pump shaft is stationary.

UNSAT COMMENTS:

STEP 11:(4.1.11) SLOWLY OPEN 5H21204, Pl-21-5C lsol. CRITICAL STEP STANDARD: POSITION SH21204, Pl-21-5C Isolation valve, SLOWLY to OPEN.

SAT EXAMINERS CUE: SH21204 is SLOWLY positioned to fully counterclockwise.

If asked, local pressure indication, PI-21-5C, indicates UNSAT 41 psig and is stable.

COMMENTS:

NRC P-i Unit 1 Intake Structure Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 12:(4.1.12) Slowly OPEN the local instrument isolation for PT-21-8A, IA ICW PUMP CRITICAL DISCH HDR PRESS. STEP STANDARD: SLOWLY POSITION the local instrument isolation for PT-21-8A to OPEN. SAT EXAMINERS CUE: Local Instrument Isolation for PT-21-8A SLOWLY positioned parallel to the pipe. UNSAT EVALUATORS NOTE: Valve handle should be parallel to the pipe.

COMMENTS:

STEP 13:(4.1.13) OPEN SH54064, IC ICW Pump Acid Return ISOL. (INTK!171N-31W-C) CRITICAL STEP STANDARD: POSITION SH54064 to OPEN (valve handle parallel to the pipe)..

SAT EXAMINERS CUE: SH54064, IC ICW Pump Acid Return ISOL, is positioned parallel to the pipe.

UNSAT COMMENTS:

STEP 14:(4.l.14) CLOSE SH54062, 1A ICW PUMP ACID RETURN ISOL CRITICAL (INTKI1 7/N-3/W-C). STEP STANDARD: POSITION SH54062 to CLOSE (valve handle perpendicular to the pipe). SAT EXAMINERS CUE: SH54062, IA ICW Pump Acid Return ISOL, is positioned perpendicular to the pipe.. UNSAT COMMENTS:

STEP 15:(4.l.15) Independently VERIFY the following valve line-up:

. SH21204 Pl-21-5C ISOL (INTKI23/N-31W-C) OPEN SAT

. LOCAL INSTRUMENT VALVE FOR PT-21-8A (INTKI2OI4IW-C) OPEN UNSAT STANDARD: REQUEST NWE or Unit Supervisor to assign someone to perform IVs..

EXAMINERS CUE: IVs have been completed SAT.

COMMENTS:

NRC P-i Unit 1 Intake Structure Page 8 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 16:(Done) NOTIFY Control Room that the 1C ICW Pump is ALIGNED and SUPPLYING the 1A ICW Header in accordance with 1-NOP-21 .03C, Section 4.1.

SAT STANDARD: NOTIFY Control Room that the 1C ICW Pump is ALIGNED and SUPPLYING the 1A ICW Header UNSAT EXAMINERS CUE: UNIT SUPERVISOR ACKNOWLEDGES COMMENTS:

END OF TASK STOP TIME:

NRC P-i Unit 1 Intake Structure Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 1 is operating at 100% power steady state conditions.

1. The 1A lOW Pump is to be taken out of service for routine maintenance.
2. The 1C lOW Pump is to be aligned and started on the 1A ICW Header during the anticipated two hours required to complete the maintenance in the 1A ICW Pump.
3. The AB Bus is electrically aligned to the 1A3 Bus.

INITIATING CUES:

You are the ANPO. The Unit Supervisor has directed you to perform the following in accordance with 1-NOP-21.03C, Section 4.1:

1. Align the 1C lOW Pump to supply the 1A lOW Header
2. Observe the starting on the IC lOW Pump.

NOTE: All Prerequisites for 1-NOP-21.03C, Section 4.1 are complete Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

1C INTAKE COOLING WATER PUMP OPERATION 6 of 20 PROCEDURE NO.:

1-NOP-21.03C ST. LUCIE UNIT 1 4.0 INSTRUCTIONS INITIAL NOTE Review of ATTACHMENT 1 prior to performance of this procedure is recommended.

4.1 Starting I C ICW Pump on A Header with Header Pressurized NOTE

  • Proper CLOSED alignment of crosstie valve requires the valve indicator arrow to line up with the V notch on the indicator plate.

(ATTACHMENT 1 Step 2)

  • System Performance Group/OSE shall be notified if crosstie valve is not aligned properly.
  • If two ICW Pumps are electrically aligned AND operating on the same electrical bus while the unit is in Modes 1, 2 or 3 (SIAS NOT blocked), the associated Ott-Site Power Source must be declared inoperable in accordance with Technical Specifications. (Section 7.1.3 Management Directive 3)
1. ENSURE Locked Closed SB21 211, IC ICW PUMP CROSS TIE DISCH TO B TRAIN ISOL (INTK/9/N-4!W-C).
2. ENSURE Locked Open SB21165, 1C ICW PUMP CROSSTIE DISCH TO A TRAIN ISOL (INTK/9!N-4/W-C).
3. ENSURE 1 C ICW Pump motor lube oil level approximately at STANDSTILL level mark.
4. VERIFY LOCKED OPEN SB21206, 1C ICW PUMP DISCH ISOL (INTK!1 8/5-41W-C).
5. CLOSE SH21204, PI-21-5C ISOL (INTK/23/N-3/W-C).
6. CLOSE the local instrument isolation for PT-21-8A, 1A ICW PUMP DISCH HDR PRESS (INTK/20141W C).

CAUTION Starting pump while it is rotating backwards could result in damage to the pump. (ATTACHMENT 1 Step 1)

7. VERIFY 1 C ICW Pump shaft is NOT rotating backwards.

REVISION NO.: PROCEDURE TITLE: PAGE:

0 10 INTAKE COOLING WATER PUMP OPERATION 7 of 20 PROCEDURE NO.:

1 -NOP-21 .030 ST. LUCIE UNIT 1 41 Starting I C ICW Pump on A Header with Header Pressurized INITIAL (continued)

8. START 10 lOW PUMP.
9. WHEN 10 ICW Pump amps stabilize, THEN STOP 1A lOW Pump and PLACE control switch to PULL TO LOCK position.
10. VERIFY 1A 10W pump shaft comes to rest.

II. Slowly OPEN SH21204, Pl-21-5C ISOL.

12. Slowly OPEN the local instrument isolation for PT-21-8A, 1A ICW PUMP DISCH HDR PRESS.
13. OPEN SH54064, 10 lOW PUMP ACID RETURN ISOL (INTK/1 7!N-3/W-C).
14. CLOSE SH54062, 1A lOW PUMP ACID RETURN ISOL (INTK/1 7/N-3/W-C).
15. Independently VERIFY the following valve line-up:

Component Component . Position

. . Location . Verified By Number Description Required SH21204 P1-21-50 ISOL INTKI23/N-3/W-C OPEN LOCAL INSTRUMENT N/A INTKI2O/4/W-O OPEN VALVE FOR PT-21-8A Performed By:

Print/Sign Initials Date Performed By:

Print/Sign Initials Date Performed By:

Print/Sign Initials Date Verified By:

Print/Sign Initials Date

REVISION NO.: PROCEDURE TITLE: PAGE:

1C INTAKE COOLING WATER PUMP OPERATION 20 of 20 PROCEDURE NO.:

1-NOP-21.03C ST. LUCIE UNIT 1 ATTACHMENT I GENERAL INFORMATION (Page 1 of 1)

NOTE

  • This attachment provides additional background information to support and clarify notes, cautions or instructional steps in the body of the procedure.
  • Cross references are provided for relevant steps to specific items in this attachment.

I. Prior to starting and after securing an lOW Pump, the pump shaft should be checked to ensure it is not rotating backwards. Reverse rotation could result in pump damage when starting pump.

Reverse rotation is an indication that check valve degradation is occurring. A CR should be submitted if reverse rotation is observed.

2. Alignment of the lOW crosstie valves is critical in preventing flow diversion that would affect the lOW PUMP In Service Test (1ST) surveillance runs. Any flow diversion around the valve seat may result in an erroneous indication of lower developed head for the pump.

Each crosstie valve (SB21165 or SB21211) was marked with a V notch and arrow when apart and actual seat position visually verified.

System Performance Group/OSE should be notified if the V notch on the indicator plate and valve indicator arrow do not properly line up when the alignment requires the valve to be closed.

(Section 7.1.3 Management Directive 2)

3. The OW Pump discharge pressure gauges require isolation prior to starting the pump to prevent gauge damage. The gauge shall be unisolated after pump start.
4. Sodium Hypochlorite should be aligned to any running lOW PUMP.
5. The lOW pumps are Self Lube pumps.

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE ALIGN EMERGENCY COOLING WATER TO THE IA INSTRUMENT AIR COMPRESSOR AND START THE IA INSTRUMENT AIR COMPRESSOR NRC P.2 Unit I Turbine Building This JPM is NOT TIME CRITICAL This is a FAULTED JPM NRC 19A P-2 Turbine Building Page 1 of 10

JOB PERFORMANCE MEASURE Task: Align Emergency Cooling Water to the 1A Instrument Air Compressor Faulted JPM? No Facility JPM #: 0821068 K/A: 078.K1 .04 2.6 / 2.9 Knowledge of the physical connections and/or cause-effect relationship between the lAS and the following: cooling water to compressor.

Task Standard:

This JPM is complete when the Control Room has been notified that the 1A Instrument Air Compressor has been aligned to the Emergency Cooling System and that the 1A Compressor is running.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 1-EOP-99, Appendices/Figures/Tables/Data Sheets, Appendix H, Operation of the 1A and lB Instrument Air Compressors Validation Time: 25 minutes Time Critical: No ToolslEquipmentlProcedures Needed:
  • 1-EOP-99, Appendices/Figures/Tables/Data Sheets, Appendix H, Operation of the 1A and lB Instrument Air Compressors Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner:

Signature:

Comments NRC 19A P-2 Turbine Building Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is: Align Emergency Cooling Water to the 1A Instrument Air Compressor
  • The performance level to be used for this JPM is Simulate.
  • This is not a time critical JPM.
  • During the performance of the task, I will tell you which steps to simulate or discuss.

I will provide you with the appropriate cues for steps that are simulated or discussed.

  • You may use any approved reference materials normally available in the execution of this task, including logs.
  • Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

A loss of off-site power has been diagnosed and is in progress.

The 1A and lB TCW Pumps are de-energized.

INITIATING CUES:

You are the NPO.

The US has just directed you to perform the following lAW l-EOP-99, Appendices/Figures/Tables/Data Sheets, Appendix H, Operation of the 1A and lB Instrument Air Compressors.

1. Align the Emergency Cooling System to the 1A Instrument Air Compressor
2. Start the compressor NRC 19A P2 Turbine Building Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

Appendix H, Operation of the IA and I B Instrument Air Compressors, Section 1: Placing IA Instrument Air Compressor in Service.

STEP 1 :(1) ENSURE the following Breakers are aligned as indicated.

Bkr 41324 (MCC 1A6) - Instrument Air Compr. 1A ON SAT STANDARD: ENSURE Bkr 41324 ON.

EXAMINERS CUE: Bkr 41324 pointer indicates to the 12 o-clock position. UNSAT If the candidate wants to stop the JPM because thE..

procedure and the Breaker TAG nomenclature do no agree, tell him that the US has confirmed that it is th right breaker.

EXAMINERS NOTE: The breaker TAG reads: INSTR AIR COMPR IA COMMENTS:

STEP 2:(1) ENSURE the following Breakers are aligned as indicated.

Bkr 42434 (MCC lAB) - lnstr Air Compr Cooler Fan ON SAT STANDARD: ENSURE Bkr 42434 ON.

EXAMINERS CUE: Bkr 42434 pointer indicates to the 12 o-clock position. UNSAT COMMENTS:

STEP 3:(1) ENSURE the following Breakers are aligned as indicated.

Bkr 42435 (MCC lAB) lnstr Air Compr Cool System Wtr Pp ON SAT STANDARD: ENSURE Bkr 42435 ON.

EXAMINERS CUE: Bkr 42435 pointer indicates to the 12 o-clock position. UNSAT COMMENTS:

NRC 19A P-2 Turbine Building Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST

2. If TCW is NOT available, Then PERFORM the following:

A. ALIGN IA Instrument Air Compressor for emergency cooling and operation.

STEP 4:(2) V13197 1A Instr Air Comp Jacket Inlet IsolOPEN CRITICAL STEP STANDARD: ALIGN Vi 31 97 to OPEN.

SAT EXAMINERS CUE: V13197 is rotated counter clockwise to hard stop.

COMMENTS: UNSAT STEP 5:(2) Vi 3201 1 A lnstr Air Comp Jacket Outlet Isol OPEN STANDARD: ALIGN Vi 3201 to OPEN. SAT EXAMINERS CUE: VI 3201 is fully counter clockwise to hard stop. UNSAT EXAMINERS NOTE: VI 3201 is already/normally aligned OPEN.

COMMENTS:

STEP 6:(2) SH13383 Air Comprs Outlet Hdr Isol CLOSE

- CRITICAL STEP STANDARD: ALIGN SH13383 to CLOSE.

SAT EXAMINERS CUE: SH13383 is rotated so that the handle is perpendicular to the pipe.

EXAMINERS NOTE: Ladder required >6. Candidate should discuss usage UNSAT requirements and any PPE requirements that apply.

COMMENTS:

STEP 7:(2) SH13380 Air Comprs Inlet Hdr Isol - CLOSE CRITICAL STEP STANDARD: ALIGN SH13380 to CLOSE.

SAT EXAMINERS CUE: SH13380 is rotated so that the handle is perpendicular to the pipe.

EXAMINERS NOTE: Ladder required >6. Candidate should discuss usage UNSAT requirements and any PPE requirements that apply.

COMMENTS:

NRC 19A P-2 Turbine Building Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 8:(2) VI 3417 Air Compr Coolers Inlet from Recirc Pump lsol OPEN STANDARD: ALIGN VI 3417 to OPEN. SAT EXAMINERS CUE: VI 3417 is fully counter clockwise to hard stop.

UNSAT EXAMINERS NOTE: V13417 is aireadylnormally aligned OPEN.

COMMENTS:

STEP 9:(2) Vl 3420 Air Compr Coolers Inlet from Recirc Pump Iso! - OPEN STANDARD: ALIGN V13420 to OPEN.

SAT EXAMINERS CUE: V13420 is fully counter clockwise to hard stop.

EXAMINERS NOTE: V13420 is alreadylnormally aligned OPEN. UNSAT COMMENTS:

STEP 10:(2) V13424 1A Recirc Pump from Head Tank Iso! - OPEN STANDARD: ALIGN VI 3424 to OPEN.

SAT EXAMINERS CUE: VI 3424 is fully counter clockwise to hard stop.

EXAMINERS NOTE: V13424 is already/normally aligned OPEN. UNSAT COMMENTS:

STEP 11:(2) SH13419 Fan Cooler Inlet Isol OPEN

- CRITICAL STEP STANDARD: ALIGN SH13419 to OPEN.

SAT EXAMINERS CUE: SH13419 is rotated so that the handle is parallel to the pipe.

UNSAT COMMENTS:

NRC 19A P-2 Turbine Building Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 12:(2) 5H13418 1A Recirc Pump Disch Isol - OPEN CRITICAL STEP STANDARD: ALIGN SH13418 to OPEN.

SAT EXAMINERS CUE: SH13418 is rotated so that the handle is parallel to the pipe.

UNSAT COMMENTS:

STEP 13:(2) V18109 lnstr Air Rcvr Inlet from 1A Aftercooler Isol - OPEN SAT STANDARD: ENSURE V18109 is OPEN.

EXAMINERS CUE: VI 81 09 is rotated counter clockwise to hard stop. UNSAT COMMENTS:

STEP 14:(2) Vi 8586 1 C I 1 D lnstr Air Comps Disch Isol - CLOSE CRITICAL STEP STANDARD: ALIGN Vi 8586 to CLOSE.

SAT EXAMINERS CUE: VI 8586 is rotated clockwise to hard stop.

COMMENTS UNSAT STEP 15:(2.B.) ENSURE the Instrument Air Compressor Head Tank is at least % full.

STANDARD: ENSURE the tank is AT LEAST % FULL of water.

SAT EXAMINERS CUE: The Head Tank is FULL of water.

EVALUATORS NOTE: The candidate should be able to get the cue from the UNSAT actual head tank level. Provide this cue only if the actual head tank level is less than % full.

COMMENTS:

NRC 19A P-2 Turbine Building Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 16:(2.C) START the Emergency Cooling System Recirculation Pump. CRITICAL STEP STANDARD: DEPRESS the START pushbutton for the Inst. Air Comp. Water Pump and OBSERVE the Red indicating light is ILLUMINATED. SAT EXAMINERS CUE: Emergency Cooling Pump indicates Red light ON and Green light OFF. UNSAT COMMENTS:

STEP 17:(2.D) START the Emergency Cooling System Radiator Fan. CRITICAL STEP STANDARD: DEPRESS the START pushbutton for the Inst. Air Comp. Cooler Fan and OBSERVE the Red indicating light is ILLUMINATED. SAT EXAMINERS CUE: Emergency Cooling System Fan indicates Red light ON and Green light OFF. UNSAT EXAMINERS NOTE: Start button inside control box south of radiator.

COMMENTS:

STEP 18:(3) If TCW is available, Then ALIGN the 1A Instrument Air Compressor for normal cooling and operation.

STANDARD: DETERMINE that this step is NOT APPLICABLE. SAT EXAMINERS CUE: None UNSAT COMMENTS:

STEP 19:(4) Locally START the 1A Instrument Air Compressor. CRITICAL STEP STANDARD: POSITION the local control switch to RUN.

SAT EXAMINERS CUE: IA Instrument Air Compressor is RUNNING.

EXAMINERS NOTE: Control switch East of IA Instrument Air Compressor. UNSAT COMMENTS:

NRC 19A P-2 Turbine Building Page 8 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP (done): NOTIFY Unit 1 Control Room that the IA Instrument Air Compressor has been aligned to the Emergency Cooling System and that the 1A Compressor is RUNNING.

SAT STANDARD: NOTIFY Unit 1 Control Room that the IA Instrument Air Compressor has been aligned to the Emergency Cooling System and that the 1A Instrument Air Compressor is RUNNING. UNSAT EXAMINERS CUE: CONTROL ROOM ACKNOWLEDGES that the IA Air Compressor has been aligned to the Emergency Cooling System and is RUNNING.

COMMENTS:

END OF TASK STOP TIME:

NRC 19A P-2 Turbine Building Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

A loss of off-site power has been diagnosed and is in progress.

The 1A and lB TOW Pumps are de-energized.

INITIATING CUES:

You are the NPO.

The US has just directed you to perform the following lAW l-EOP-99, Appendices/Figures/Tables/Data Sheets, Appendix H, Operation of the lA and lB Instrument Air Compressors.

1. Align the Emergency Cooling System to the 1A Instrument Air Compressor
2. Start the compressor Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

39 \PPENDICES! FIGURES / TABLES! DATA SHEETS PROCEDURE NO.:

55 of 155 1-EOP-99 ST. LUCIE UNIT 1 APPENDIX H OPERATION OF THE IA AND lB INSTRUMENT AIR COMPRESSORS (Page 1 of 4)

Section 1: Placing IA Instrument Air Compressor in Service El I. ENSURE the following breakers are aligned as indicated.

Component ID Component Name POSITION (1)

Bkr41324(MCC 1A6) lnstrumentAirCompr. 1A ON Bkr 42434 (MCC lAB) lnstr Air Compr Cooler Fan ON Bkr 42435 (MCC lAB) lnstr Air Compr Cool System VVtr Pp ON El 2. TCW is NOT available, Then PERFORM the following:

El A. ALIGN 1A Instrument Air Compressor for emergency cooling and operation.

Component ID Component Name POSITION (1)

V13197 1A Instr Air Comp Jacket Inlet Isol OPEN Vi 3201 1A lnstr Air Comp Jacket Outlet Isol OPEN SH1 3383 Air Comprs Outlet Hdr 1501 CLOSE SH1 3380 Air Comprs Inlet Hdr Isol CLOSE V13417 Air Compr Coolers Inlet from Recirc Pump Isol OPEN V13420 Air Compr Coolers Inlet from Recirc Pump Isol OPEN V13424 1A Recirc Pump from Head Tank Isol OPEN SH13419 Fan Cooler Inlet Isol OPEN SH13418 1A Recirc Pump Disch Isol OPEN V18109 lnstr Air Rcvr Inlet from 1A Aftercooler Isol OPEN V18586 1/10 InstrAirComps Disch Isol CLOSE El B. ENSURE the Instrument Air Compressor Head Tank level is at least 3/4 full.

El C. START the Emergency Cooling System Recirculation Pump.

El D. START the Emergency Cooling System Radiator Fan.

REVISION NO.: PROCEDURE TITLE: PAGE:

39 \PPENDICES! FIGURES / TABLES I DATA SHEETS PROCEDURE NO.:

56 of 155 1-EOP-99 ST. LUCIE UNIT 1 APPENDIX H OPERATION OF THE IA AND lB INSTRUMENT AIR COMPRESSORS (Page 2 of4)

Section 1: Placing IA Instrument Air Compressor in Service (continued)

LI 3. If TOW is available, Then ALIGN 1A Instrument Air Compressor for normal cooling and operation:

Component ID Component Name POSITION ()

V13197 IA lnstr Air Comp Jacket Inlet lsol OPEN V13201 1A lnstrAirCompJacketOutlet Isol OPEN Vi 8109 Instr Air Rcvr Inlet from 1A Aftercooler Isol OPEN Vi8586 10/iD InstrAirComps Disch Isol CLOSE_

LI 4. Locally START the 1A Instrument Air Compressor.

LI 5. NOTIFY Unit 1 Control Room that 1A Instrument Air Compressor is running.

End of Section 1

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE BLEND TO THE VCT USING LOCAL CONTROL NRC P-3 Unit I RAB This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC WA P-3 Unit 1 RAB Page 1 oflO

JOB PERFORMANCE MEASURE Task: Blend to the VCT using local control Faulted JPM? No Facility JPM #:

004.K4.04 3.2 I 3.1 Knowledge of CVCS design features(s) and/or interlock(s) which provide for the following: Manual/automatic transfers of control.

Task Standard:

This JPM is complete when the VCT is being blended to the normal VCT level.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 1 -ONP-02.O1, Boron Concentration Control Validation Time: 25 minutes Time Critical: No Tools/EquipmentlProcedures Needed:
  • 1--ONP-02.O1, Boron Concentration Control Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A P-3 Unit 1 RAB Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

a The task you are to perform is to Blend to the VCT using Local Control.

  • The performance level to be used for this JPM is Simulate.

a This is not a time critical JPM.

During the performance of the task, I will tell you which steps to simulate or discuss.

  • I will provide you with the appropriate cues for steps that are simulated or discussed.
  • You may use any approved reference materials normally available in the execution of this task, including logs.

a Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 1 is at 100% power steady state.

1. FCV-2161, Boric Acid Makeup Isolation has failed to open.
2. The VCT level necessitates a blended makeup to bring level back to normal range.
3. RCS boron concentration is 879 PPM.
4. The 1A BAMT boron concentration is 5889 ppm
5. The lB BAMT boron concentration is 6120 ppm.

INITIATING CUES:

You are the SNPO.

The US has directed you to implement the SNPO actions of I -ONP-02.01, Boron Concentration Control Appendix A to:

1. Locally blend to the VCT to within normal operating level range using the I B BAMT.
a. Control room desires 30 gpm primary water flow and 5 gpm boric acid flow (a blend ratio of 6:1).

NRC 19A P-3 unit 1 RAB Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

Appendix A Local Operation Of Boron Concentration Control STEP 1 :(1) STATION an operator at the Boric Acid station and establish communication with the control room.

SAT STANDARD: COMMUNICATE with the control room when on station EXAMINERS CUE: Control room acknowledges you are on station anc UNSAT verifies communication.

COMMENTS:

STEP 2:(2) PLACE the Makeup Mode Selector switch in MANUAL STANDARD: VERIFIES with the control room the Makeup Mode Selector switch is in SAT manual.

EXAMINERS CUE: Control room acknowledges the Makeup Mode Selecto UNSAT switch is in manual.

COMMENTS:

STEP 3:(3) START IA or I B Boric Acid pump.

STANDARD: VERIFIES with the control room 1A or lB Boric Acid pump has beer SAT started.

EXAMINERS CUE: Control room acknowledges the lB Boric Acid pump ir UNSAT running.

COMMENTS:

NRC 19A P-3 Unit 1 RAB Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 4:(4) OPEN FCV-2161, Boric Acid Makeup Isolation SAT STANDARD: IDENTIFIES cue has stated FCV-2 161 has failed to open.

EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 5:(5) IF FCV-2161 fails to operate, Then DIRECT the operator to OPEN V2164, CRITICAL 8AM Pump Strainer Bypass Isol. STEP STANDARD: ROTATES V2164 fully counter clockwise to the open position. SAT EXAMNIERS NOTE: Initial cue stated FCV-2161 has failed to open. UNSAT EXAMINERS CUE: Control room directs V2164 to be opened.

EXAMINERS CUE: V2164 has been rotated fully counter clockwise COMMENTS:

STEP 6:(6) ENSURE V2514 is CLOSED SAT STANDARD: COMMUNICATES with control room to determine V2514 to be closed.

EXAMINERS NOTE: This is a Control room operated valve. UNSAT EXAMINERS CUE: Control room confirms V2514 is closed.

COMMENTS:

STEP 7:(7) ENSURE FCV-2210Y is CLOSED SAT STANDARD: COMMUNICATES with control room to determine FCV-2210Y to be closed.

EXAMINERS NOTE: This is a Control room operated valve. UNSAT EXAMINERS CUE: Control room confirms FCV-2210Y is closed.

COMMENTS:

NRC 19A P-3 Unit 1 RAB Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 8:(8) DIRECT the operator at the Boric Acid station to throttle V2174, EMERG CRITICAL Boration From BAM Pumps Disc Isol, OPEN to the calculated blend ratio. STEP SAT STANDARD: ROTATES Counter clockwise V2174 two(2) turns UNSAT EXAMINERS NOTE: Blend ratio is 30 gallons Primary water for every 5 gallons Boric acid. (6:1 as per cue)

EXAMINERS CUE: Control room directs V2174 to be opened 2 turns.

EXAMINERS CUE: V2174 has been turned counter clockwise two (2) turns.

COMMENTS:

STEP 9:(9) MONITOR FR-2210 for boric acid flow rate and ADJUST V2174 as necessary. SAT STANDARD: COMMUNICATES with control room to determine boric acid flow rate.

UNSAT EXAMINERS CUE: Control room states boric acid flow rate is 3 gpm.

EXAMINERS CUE: Control room directs V2174 opened an additional 1/2 turn.

COMMENTS:

NRC 19A P-3 Unit 1 RAB Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 1O:(9) MONITOR FR-2210 for boric acid flow rate and ADJUST V2174 as CRITICAL necessary STEP STANDARD: ROTATES V2174 counter clockwise an additional Y2 turn and SAT communicates with control room to determine boric acid flow rate.

DETERMINES 5 gpm is desired flow rate.

UNSAT EXAMINERS CUE: V2174 is turned counter clockwise an additional 1/2 turn and the Control room states boric acid flow is 5 gpm.

COMMENTS:

STEP 11:(1O) DIRECT the operator at the Boric Acid Station to throttle V2180, PMW to CRITICAL Charging Pumps Suct. Manual Isol, OPEN to the calculated blend ratio. STEP V2180 is located in the 1C Charging pump room.

SAT STANDARD: ROTATES V2180 counter clockwise 4 turns.

EXAMINERS CUE: Control room directs V2180 opened 4 turns. UNSAT EXAMINERS CUE: V2180 has been rotated counter clockwise 4 turns.

EXAMINERS NOTE: V2180 is a locked closed valve. Candidate should discuss actions required to manipulate V2180.

COMMENTS:

STEP 12:(11) Monitor FR-2210 for Reactor Makeup Water flow rate and ADJUST V2180 CRITICAL as necessary. STEP STANDARD: COMMUNICATES with control room to determine Reactor Makeup Water SAT flow rate.

DETERMINES 45 gpm is 15 gpm greater than the desired flow rate.

UNSAT EXAMINERS CUE: Control room states Reactor Makeup Water flow rate is 45 gpm.

EXAMINERS CUE: Control room directs V2180 closed I full turn.

COMMENTS:

NRC 19A P-3 Unit 1 RAB Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 13:(11) Monitor FR-2210 for Reactor Makeup Water flow rate and ADJUST V2180 CRITICAL as necessary. STEP STANDARD: ROTATES V2180 clockwise one(1) full turn and communicates with control SAT room to determine flow rate.

DETERMINES 30 gpm is the desired flow rate.

UNSAT EXAMINERS CUE: Control room states Reactor Makeup Water flow rate is 30 gpm.

COMMENTS:

STEP 14:(12) MONITOR for any abnormal change in Tave.

SAT STANDARD: COMMUNICATES with control room to determine acceptable blend and Tave.

UNSAT EXAMINERS CUE: Control room states no changes in Boric Acid flow or Reactor Makeup flow rates are needed at this time.

COMMENTS:

STEP 15:(13) MONITOR for any abnormal change in RCS Boron concentration.

SAT STANDARD: COMMUNICATES with control room to determine any change in RCS Boron concentration.

UNSAT EXAMINERS CUE: Control room states no changes in RCS Boron concentration.

COMMENTS NRC 19A P-3 Unit 1 RAB Page 8 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 16:(14.) DIRECT the operator to adjust V2174 and V2180 as required to maintain the VCT in the normal band and plant conditions stable.

SAT STANDARD: COMMUNICATES with the control room to determine acceptability of current flow rates.

UNSAT EXAMINERS CUE: Control room states no changes are needed as this time.

COMMENTS:

END OF TASK STOP TIME:

NRC 19A P-3 Unit 1 RAB Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 1 is at 100% power steady state.

1. FCV-2161, Boric Acid Makeup Isolation has failed to open.
2. The VCT level necessitates a blended makeup to bring level back to normal range.
3. RCS boron concentration is 879 PPM.
4. The 1A BAMT boron concentration is 5889 ppm
5. The lB BAMT boron concentration is 6120 ppm.

INITIATING CUES:

You are the SN PC.

The US has directed you to implement the SNPO actions of 1-ONP-02.01, Boron Concentration Control Appendix A to:

1. Locally blend to the VCT to within normal operating level range using the 1 B BAMT.
b. Control room desires 30 gpm primary water flow and 5 gpm boric acid flow (a blend ratio of 6:1).

Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

5B BORON CONCENTRATION CONTROL PROCEDURE NO.:

14 of 16 1-ONP-02.O1 ST. LUCIE UNIT 1 APPENDIX A LOCAL OPERATION OF BORON CONCENTRATION CONTROL (Page 1 ofi)

1. Station an operator at the Boric Acid station and establish communication with the control room.
2. ¶1 PLACE the Makeup Mode Selector switch in MANUAL.
3. START lAor lB Boric Acid pump.
4. OPEN FCV-2161, Boric Acid Makeup Isol.
5. If FCV-2161 fails to operate, Then DIRECT the operator to OPEN V2164, BAM Pump Strainer Bypass Isol.
6. ENSURE V2514 is CLOSED.
7. ENSURE FCV-2210Y is CLOSED.

CAUTION

  • V21 74 provides a direct Boric Acid flow path to the Charging pump suction at 20 gpm.
  • V21 80 provides a direct Primary Water flow path to the Charging pump suction.
8. DIRECT the operator at the Boric Acid station to throttle V2174, EMERG Boration From BAM Pumps Disch Isol, OPEN to the calculated blend ratio.
9. MONITOR FR-2210 for boric acid flow rate and ADJUST V2174 as necessary.
10. DIRECT the operator at the Boric Acid Station to throttle V2180, PMW to Charging Pumps Suct Manual lsol, OPEN to the calculated blend ratio. V2180 is located in the 1C Charging pump room.
11. MONITOR FR-2210 for Reactor Makeup Water flow rate and ADJUST V2180 as necessary.
12. MONITOR for any abnormal change in Tave.
13. MONITOR for any abnormal change in RCS Boron concentration.
14. DIRECT the operator to adjust V21 74 and V21 80 as required to maintain the VCT in the normal band and plant conditions stable.

END OF APPENDIX A

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE ENERGIZE 4.16 KV BUS 1B3 FROM UNIT 2 VIA SBO CROSS-TIE BREAKER UNIT I -

NRC C-7 Unit I Control Room This JPM is TIME CRITICAL This is a NON-FAULTED JPM NRC 19A C-7 Unit 1 Control Room Page 1 of 10

JOB PERFORMANCE MEASURE Task: Energize 1B3 4.16KV Bus from Unit 2 during station blackout using SBO crosstie breaker on Unit 1.

Faulted JPM? No Facility JPM #: 0821 121T K/A: 062.A4.01 3.3/3.1 Ability to manually operate and/or monitor in the control room: all breakers (including available switchyard).

Task Standard:

This JPM is complete when 4.16 KV Bus 1B3 is energized from Unit 2 via the SBO crosstie breaker.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • 1-EOP-99, Appendix V, Receiving AC Power from Unit 2 Using SBO Crosstie Validation Time: 10 minutes Time Critical: YES ToolslEquipmentlProcedures Needed:
  • 1 -EOP-99, Appendix V, Receiving AC Power from Unit 2 Using SBO Crosstie Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radioloqical Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A C-7 Unit 1 Control Room Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

a The task you are to perform is:

Energize 1B3 4.16KV Bus from Unit 2 during station blackout using 580 crosstie breaker on Unit 1.

  • The performance level to be used for this JPM is Simulate a This IS a time critical JPM.

a During the performance of the task, I will tell you which steps to simulate or discuss.

  • I will provide you with the appropriate cues for steps that are simulated or discussed.
  • You may use any approved reference materials normally available in the execution of this task, including logs.

a Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

St. Lucie has experienced a loss of offsite power due to electrical grid instability.

1. Unit 2 is stable in hot standby with both its 4.16 KV emergency buses powered from the emergency diesel generators.
2. Unit 1 is in a station blackout condition because 1A EDG is tagged out for maintenance and lB EDG cannot be started due to an unknown fault.
a. 1C AFW Pump is feeding both steam generators.
b. 1-EOP-99 Table 7 breaker alignment has been completed.

INITIATING CUES:

You are the Desk RCO.

The US has directed you to perform the following lAW 1-EOP-99, Appendix V, Receiving AC Power from Unit 2 Using SBO Crosstie:

1. Cross-tie the lAB and 2AB 4.16 KV Buses
2. Energize 4.16 KV Bus J.

(Portions of this JPM are TIME CRITICAL. Time starts when you have completed reading the Initiating cue).

NRC 19A C-7 Unit 1 Control Room Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

Appendix V, Receiving AC Power from Unit 2 Using SBO Crosstie, Section 1: Preparations for Crosstie STEP I :(1) SELECT the train that will be used to receive AC power from Unit 2.

SAT STANDARD: SELECT B Train (per Initiating Cue)

EXAMINERS CUE: None UNSAT COMMENTS:

STEP 2:(2) VERIFY Table 7, Vital Power Breaker Configuration / Station Blackout, has been completed. SAT STANDARD: VERIFY Table 7 breaker alignment is COMPLETED.

UNSAT EXAMINERS CUE: Table 7 breaker alignment has been COMPLETED (per Initiating Cue).

COMMENTS:

STEP 3:(3) DISPATCH an operator to locally PLACE the following NORMAL I CRITICAL ISOLATE switches in ISOLATE. STEP

  • Selected train EDG Output Breaker SAT
  • Selected train motor driven AFW pump STANDARD: DIRECT the SNPO to PLACE Breakers 1-20401 and 1-20412 UNSAT NORMAL/ISOLATE switches in ISOLATE.

EXAMINERS CUE: Annunciator A-56 received. Breaker 1-20401 green and red status lights are OFF.

Annunciator G-45 received. Breaker 1-20412 green and red status lights are OFF.

COMMENTS:

NRC 19A C-7 unit i control Room Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 4:(4) PLACE the following COW Pumps in PULL TO LOCK:

CRITICAL

  • 1CCCWPump STEP
  • Selected train COW Pump SAT STANDARD: POSITION the 1 B and IC CCW Pumps control switches to PULL-TO-LOCK.

UNSAT EXAMINERS CUE: lB and IC CCW Pump Control switches are turned to the far left and the handles are pulled up to the locked position (as each is positioned)

COMMENTS:

STEP 5:(5) PLACE the selected train Containment Spray pump in STOP.

CRITICAL STEP STANDARD: POSITION the CNTMT Spray Pump 18 to STOP.

SAT EXAMINERS CUE: Containment spray pump lB in STOP (as positioned)

R-52 alarms UNSAT COMMENTS:

STEP 6:(6) PLACE the following Safety Injection Pumps in STOP: CRITICAL STEP

  • Selected train HPSI Pump
  • Selected train LPSI Pump SAT STANDARD: POSITIONS the lB HPSI and 18 LPSI pump control switches to STOP. UNSAT EXAMINERS CUE: lB HPSI control switch in STOP. R-56 alarms lB LPSI control switch in STOP. R-59 alarms COMMENTS:

NRC 19A C-7 unit i Control Room Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 7:(7) PLACE the following Charging Pumps in STOP: CRITICAL STEP

  • 1C Charging Pump
  • Selected train Charging Pump SAT STANDARD: POSITION the 1 B and 1 C Charging Pumps control switches to STOP.

UNSAT EXAMINERS CUE: lB and IC Charging Pump Control switches are in STOP (as each is positioned) (M-47 & M-48 alarm).

(Red lights OFF green lights ON)

COMMENTS:

STEP 8:(8) PLACE ALL RCP Oil Lift Pumps in OFF. CRITICAL STEP STANDARD: POSITION ALL RCP Oil Lift Pump control switches in Qf.

SAT EXAMINERS CUE: ALL RCP Oil Lift Pump control switches indicate Green lights ON, Red lights OFF.

UNSAT COMMENTS:

STEP 9:(9) PLACE the following ICW Pumps in PULL TO LOCK. CRITICAL STEP

  • 1CICWPump
  • Selected train ICW Pump SAT STANDARD: POSITION the lB and 1C ICW pump control switches to UNSAT PULL-TO-LOCK.

EXAMINERS CUE: lB and IC ICW Pump Control switches are turned to the far left and the handles are pulled up to the locked position (as each is positioned)

COMMENTS:

NRC 19A C-7 Unit 1 Control Room Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 10:(10) ENSURE further attempts to restore power to the selected train from a Unit 1 source are suspended while Unit to Unit CROSSTIE efforts are in SAT progress.

STANDARD: NOTIFY the US to SUSPEND attempts to restore while Unit to Unit crosstie UNSAT efforts is in progress.

EXAMINERS CUE: US Acknowledges.

COMMENTS:

Section 2: Receiving Power from Unit 2 STEP 11 :(1 .A) When Unit 2 is ready to supply power to Unit 1, Then PERFORM ALL of the following: CRITICAL STEP A. CLOSE the Unit I SBO crosstie breaker, 4160V SWGR lAB UNIT X TIE BKR (20501). SAT STANDARD: OBTAIN Key 40 and POSITION Breaker 1-20501 control switch to CLOSE.

UNSAT EXAMINERS CUE: Unit 2 reports READY to cross-tie.

If asked prior to closure, Bkr 1-20501 Amber light is LIT, After Breaker 1-20501 is closed, Bkr indicates Green light OFF, Red light ON. Ann B-I Alarms EVALUATOR NOTE: Student should verify that Unit 2 is ready to cross-tie before closing this breaker but this is not necessary to complete the Critical Step.

COMMENTS:

NRC 19A C-7 Unit 1 Control Room Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 12:(1.B) When Unit 2 is ready to supply power to Unit 1, Then PERFORM ALL of TIME CRITICAL the following: STEP B. REQUEST Unit 2 to close SBO crosstie breaker, 4.16 KV SWGR 2AB Unit X-TIE BKR (2-20501).

SAT STANDARD: REQUEST Unit 2 to CLOSE SBO breaker, 2-20501 EXAMINERS CUE: Unit 2 ACKNOWLEDGES and REPORTS that Breaker UNSAT 2-20501 is CLOSED.

Bkr 2-20501 indicates Green light OFF, Red light ON.

EVALUATORS NOTE: Record time Unit 2 closed Bkr 2-20501, minutes TU2CIose COMMENTS:

STEP 13:(1 .C) When Unit 2 is ready to supply power to Unit 1, Then PERFORM ALL of the following: SAT C. VERIFY the lAB 4.16 KV bus has power restored.

UNSAT STANDARD: VERIFY the lAB 4.16 KV bus is ENERGIZED.

EXAMINERS CUE: The lAB 4.16 KV bus is ENERGIZED If asked, VM-942 reads 4160 volts, 3 White Bus Voltage Lights are ON COMMENTS:

STEP 14:(2) ALIGN the selected train Vital 4.16 kV bus to the lAB 4.16 kV bus by CLOSING the TWO crosstie breakers: CRITICAL STEP lAB to 1B3 SAT

  • 1 AB-1 B3 (20504) CLOSED
  • 1 B3-1 AB (20409) CLOSED UNSAT STANDARD: POSITION Breaker 1-20504 and 1-20409 control switches to CLOSE.

EXAMINERS CUE: Breakers 1-20409 and 1-20504 indicate Green light OFF, Red light ON (as each is positioned)

COMMENTS:

NRC 19A C-7 Unit 1 Control Room Page 8 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 15:(3) VERIFY the selected train Vital 4.16 kV bus has power restored.

STANDARD: VERIFY VM-964 INDICATES 4160 volts.

SAT EXAMINERS CUE: VM-964 indicates 4160 volts, 3 White Bus Voltage lights are ON UNSAT If asked, AM-942 and AM-935 indicate 20 amps (due to lB AFW Pump)

COMMENTS:

STEP (done): NOTIFY the US that the 1 B3 4160 KV Bus power has been RESTORED.

STANDARD: NOTIFY the US that the I B3 4160 KV Bus is ENERGIZED from Unit 2 via the SBO crosstie breaker in accordance with 1-EOP-99, Appendix V SAT EXAMINERS CUE: US ACKNOWLEDGES UNSAT COMMENTS:

END OF TASK STOP TIME:

TIME-CRITICAL CALCULATION:

Calculate 0 = iose Tb 20 T - START TIME: - = minutes = Critical time iose 20 Tu START Tsbo If Tb 0 >10 minutes, then Student fails this JPM.

NRC 19A C-7 Unit 1 Control Room Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

St. Lucie has experienced a loss of offsite power due to electrical grid instability.

1. Unit 2 is stable in hot standby with both its 4.16 KV emergency buses powered from the emergency diesel generators.
2. Unit 1 is in a station blackout condition because 1A EDG is tagged out for maintenance and 1 B EDG cannot be started due to an unknown fault.
a. 1-EOP-99 Table 7 breaker alignment has been completed.
b. 10 AFW Pump is feeding both steam generators.

INITIATING CUES:

You are the Desk RCO.

The US has directed you to perform the following lAW 1-EOP-99, Appendix V, Receiving AC Power from Unit 2 Using SBO Crosstie:

1. Cross-tie the lAB and 2AB 4.16 KV Buses
2. Energize 4.16 KV Bus 1B3 (Portions of this JPM are TIME CRITICAL. Time starts when you have completed reading the Initiating cue).

Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

39 PPENDICES I FIGURES / TABLES I DATA SHEETS PROCEDURE NO.:

99 of 155 1-EOP-99 ST. LUCIE UNIT 1 APPENDIX V RECEIVING AC POWER FROM UNIT 2 USING SBO CROSSTIE (Page 1 of7)

Section 1: Preparations for Crosstie LI 1. SELECT the train that will be used to receive AC power from Unit 2 (1).

A Train B Train NOTE All of the following factors should be considered:

  • The potential for recovering a Unit 1 AC power source
  • Equipment availability

LI 2. VERIFY Table 7, Vital Power Breaker Configuration I Station Blackout, has been completed.

LI 3. DISPATCH an operator to locally PLACE the following NORMAL I ISOLATE switches in ISOLATE:

LI Selected train EDG Output Breaker LI Selected train motor driven AFW Pump LI 4. PLACE the following CCW Pumps in PULL TO LOCK LI 1CCCWPump LI Selected train CCW Pump LI 5. PLACE the selected train Containment Spray Pump in STOP.

LI 6. PLACE the following Safety Injection Pumps in STOP:

LI Selected train HPSI Pump LI Selected train LPSI Pump LI 7. PLACE the following Charging Pumps in STOP:

LI 1C Charging Pump LI Selected train Charging Pump

REVISION NO.: PROCEDURE TITLE: PAGE:

39 PPENDICES / FIGURES / TABLES / DATA SHEETS PROCEDURE NO.:

100 of 155 1-EOP-99 ST. LUCIE UNIT 1 APPENDIX V RECEIVING AC POWER FROM UNIT 2 USING SBO CROSSTIE (Page 2 of 7)

Section 1: Preparations for Crosstie (continued)

El 8. PLACE ALL RCP Oil Lift Pumps in OFF.

0 9. PLACE the following ICW Pumps in PULL TO LOCK:

U 1CICW Pump El Selected train ICW Pump El 1O.ENSURE further attempts to restore power to the selected train from a Unit 1 source are suspended while Unit to Unit crosstie efforts are in progress.

End of Section 1

REVISION NO.: PROCEDURE TITLE: PAGE:

39 \PPENDICES I FIGURES I TABLES / DATA SHEETS PROCEDURE NO.:

101 of 155 1-EOP-99 ST. LUCIE UNIT 1 APPENDIX V RECEIVING AC POWER FROM UNIT 2 USING SBO CROSSTIE (Page 3 of 7)

Section 2: Receiving Power from Unit 2 EJ 1. When Unit 2 is ready to supply power to Unit 1 Then PERFORM ALL of the following:

LI A. CLOSE the Unit 1 SBO crosstie breaker, 4160V SWGR lAB UNIT X-TIE BKR (20501).

LI B. REQUEST Unit 2 CLOSE their SBO crosstie breaker, 4160V SWGR 2AB UNIT X-TIE BKR (2-20501).

LI C. VERIFY the lAB 4.16 KV bus has power restored.

LI 2. ALIGN the selected train Vital 4.16 KV bus to the lAB 4.16 KV bus by CLOSING the TWO crosstie breakers:

1ABto1A3() 1ABto1B3()

1 AB-1 A3 (20505) 1 AB-1 B3 (20504) 1A3-1AB (20208) 1B3-1AB (20409)

LI 3. VERIFY the selected train Vital 4.16 KV bus has power restored.

LI 4. [f TWO Unit 2 EDGs are RUNNING, Then GO TO Section 3, Restoring Loads With TWO Unit 2 EDGs Running.

LI 5. [f only ONE Unit 2 EDG is RUNNING, Then GO TO Section 4, Restoring Loads With ONE Unit 2 EDG Running.

LI 6. If Unit 2 has Offsite Power, Then GO TO Section 5, Restoring Loads With Unit 2 Offsite Power.

End of Section 2

FPL St. Lucie Nuclear Plant JOB PERFORMANCE MEASURE RESPOND TO CCW EXCESSIVE ACTIVITY UNIT I NRC C-8 Unit I Control Room This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM NRC 19AC-8 Unit 1 Control Room Page 1 of 10

JOB PERFORMANCE MEASURE Task: Respond to CCW Excessive Activity Unit 1 Faulted JPM? No Facility JPM #: 0821030 KIA: 008.K1 .04 3.3 / 3.3 Knowledge of the physical connection and/or cause-effect relationship between the COWS and the following systems: RCS, in order to determine sources(s) of RCS leakage into the COWS.

Task Standard:

This JPM is complete when the US has been informed that the Pressurizer Steam Space Sample Heat Exchanger has been isolated.

Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

  • ONOP 1-0310030, Component Cooling Water Off Normal Operations
  • ONOP 1-031 0031, Component Cooling Water Excessive Activity
  • 1-APP-01-S-6, Annunciator Response Procedure Validation Time: 15 minutes Time Critical: No Tools/EquipmentlProcedures Needed:

a ONOP 1-0310030, Component Cooling Water Off Normal Operations

  • ONOP 1-0310031, Component Cooling Water Excessive Activity 1-APP-01-S-6, Annunciator Response Procedure Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
  • None Radiological Protection and RWP Requirements:
  • None Candidate:

Name Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC 19A c-8 Unit 1 Control Room Page 2 of 10

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

  • The task you are to perform is: Respond to CCW Excessive Activity Unit I
  • The performance level to be used for this JPM is Simulate a This is not a time critical JPM.
  • During the performance of the task, I will tell you which steps to simulate or discuss.
  • I will provide you with the appropriate cues for steps that are simulated or discussed.

a You may use any approved reference materials normally available in the execution of this task, including logs.

a Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power, steady state conditions, MOL.

1. Annunciator S-6 (CCW SURGE TANK LEVEL HIGH/COMPARTMENT A LEVEL LOW) has illuminated.
2. A SNPO was dispatched to locally investigate the CCW Surge Tank.
a. He reports that level is greater than 4 feet (sightglass full) and
b. LCV-14-1, Demin Water to Surge Tank, is closed with no make-up flow indicated.
3. All operator actions of 1-ARP-01-S6 have been carried out.

INITIATING CUES:

The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.

NRC 19A c-8 Unit 1 control Room Page 3 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST START TIME:

ONOP 1-0310030, Component Cooling Water Off Normal Operation Step 6.2 Subsequent Actions, Step 5.

CRITICAL STEP 1:(6.2.5.A.1) abnormal level conditions exist in the CCW Surge Tank, Then STEP perform the following:

A. High level in the CCW Surge Tank.

1. Check the CCW Radiation Monitors (Channel 56 & 57) for abnormal trends. If high radiation is indicated, refer to ONOP 1-0310031, Component Cooling Water Excessive Activity.

SAT STANDARD: OBSERVE channels 56 & 57 for trends.

UNSAT E)(AMINERS CUE: Channel 56 reads 2.8 e 6 iJCiImI and channel 57 reads 3.8 e6 pCi/mI. Both are trending up but not in alarm.

EXAMINERS NOTE: At this point, the Student must refer to ONP 1-0310031, Component Cooling Water Excessive Activity COMMENTS:

ONOP 1-031 0031, Component Cooling Water Excessive Activity.

Step 7.2 Subsequent Actions STEP 2:(7.2.1) Notify Health Physics and Chemistry Department of CCW excessive activity.

STANDARD: CONTACT the Chemistry and HP Technicians and INFORM them that there SAT is excessive activity in the COW system.

EXAMINERS CUE: CHEMISTRY and HP TECHNICIANS NOTIFIED UNSAT COMMENTS:

NRC 19A C-8 Unit 1 Control Room Page 4 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 3:(7.2.2) Determine the primary leak rate per 1 -OSP-01 .03, Reactor Coolant System Inventory Balance.

STANDARD: N/A. SAT EXAMINERS CUE: The Unit Supervisor reports that OSP-01.03, Reactor UNSAT Coolant System Inventory Balance, has been performed and the leak rate is 0.5 GPM.

COMMENTS:

STEP 4:(7.2.3) H the plant is in Mode 3 through 6 (SIAS BLOCKED), Th perform safety function status check of the LOW Mode Off-Normal Procedure for the current plant condition.

SAT STANDARD: DETERMINE step is NOT APPLICABLE Unit is in Mode 1 EXAMINERS CUE: Acknowledge that the step is not applicable. UNSAT COMMENTS:

Inspect the following components for RCS leakage:

STEP 5:(7.2.4.A) Verify RCS inleakage from the RCP(s) seal cooler is NOT occurring by the following:

1. NO unexplained increase in RCP lower seal temperature. SAT STANDARD: Verify no unexplained INCREASE in any RCP lower cavity seal temperature UNSAT EXAMINERS CUE: Lower seal cavity temperatures indicate 100°F to 115°F COMMENTS:

NRC 19A C-8 Unit 1 Control Room Page 5 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 6:(7.2.4.A.2) Verify RCS inleakage from the RCP(s) seal cooler is NOT occurring by the following:

2. DOS Computer Points are NOT in alarm SAT
  • 33X193_A, 1A1 ROP CL Tube Lk Vlv Cls/Pwr FA
  • 33X293 A, 1A2 RCP CL Tube Lk Vlv CIs/Pwr FA
  • 33X1 94A, 1 Bi RCP CL Tube Lk Vlv Cls/Pwr FA. UNSAT
  • 33X294_A, 1 B2 RCP CL Tube Lk Vlv Ols/Pwr FA STANDARD: VERIFY DOS computer points are NOT in alarm by checking either the alarm screen or RCP displays.

EXAMINERS CUE: No RCP DCS computer points are in alarm.

COMMENTS:

STEP 7: (7.2.4.B) Verify the outlet temperature of the sample heat exchangers (HX) does CRITICAL NOT indicate possible leakage. STEP STANDARD: CONTACT the SNPO and give directions to CHECK the outlet temperatures on the sample heat exchangers for ABNORMAL SAT values.

EXAMINERS CUE: SNPO REPORTS Pressurizer Steam Space Sample heat UNSAT exchanger return temperature is approximately 130°F, all others are <90°F.

COMMENTS:

CONTINGENCY ACTIONS.

STEP 8: (7.2.4.B) If a sample heat exchanger indicates possible leakage, Then go to Appendix A, Isolation of the Sample Heat Exchangers.

STANDARD: GO TO Appendix A and DETERMINE IC Sample Heat Exchanger SAT (Pressurizer Steam Space) requires isolation.

EXAMINERS CUE: NONE UNSAT COMMENTS:

NRC 19A C-8 Unit 1 Control Room Page 6 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST APPENDIX A, ISOLATION OF THE SAMPLE HEAT EXCHANGERS, IC SAMPLE HEAT EXCHANGER (PRESSURIZER STEAM SPACE.

STEP 9:(3.A.1) If the 1C Sample Heat Exchanger is suspected of causing the increase in CRITICAL CCW activity, Then isolate the heat exchanger by the following: STEP

1. Close V5202, Pressurizer Steam Space Sample (RTGB 106). SAT STANDARD: POSITION V5202 handswitch to CLOSE UNSAT EXAMINERS CUE: Green light is ON, Red light is OFF COMMENTS:

STEP 10:(3.A.2) If the IC Sample Heat Exchanger is suspected of causing the increase in CRITICAL CCW activity, Then isolate the heat exchanger by the following: STEP

2. Close V5205, Pressurizer Steam Space Sample (RTGB 106). SAT STANDARD: POSITION V5205 handswitch to CLOSE UNSAT EXAMINERS CUE: Green light is ON, Red light is OFF COMMENTS:

STEP I 1(3.A.3) If the 10 Sample Heat Exchanger is suspected of causing the increase in CRITICAL 00W activity, ]J isolate the heat exchanger by the following: STEP

3. Close V05007, 1C Sample HX Outlet Isol. SAT STANDARD: CONTACT the SNPO to CLOSE V05007 UNSAT EXAMINERS CUE: SNPO reports V05007 CLOSED.

COMMENTS:

NRC 19A C-8 Unit 1 Control Room Page 7 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP 1 2:(3.A.4) j[ the 10 Sample Heat Exchanger is suspected of causing the CRITICAL increase in CCW activity, Then isolate the heat exchanger by the STEP following:

SAT

4. Close Vi 4506, 10 Sample HX Inlet IsoI.

STANDARD: CONTACT the SNPO to CLOSE Vi 4506 UNSAT EXAMINERS CUE: SNPO reports V14506 CLOSED COMMENTS:

STEP 1 3:(3.A.5) the 10 Sample Heat Exchanger is suspected of causing the increase in CRITICAL CCW activity, Then isolate the heat exchanger by the following: STEP

5. Close 14502, IC Sample HX Outlet Isol. SAT STANDARD: CONTACT the SNPO to CLOSE Vi 4502 UNSAT EXAMINERS CUE: SNPO reports V14502 CLOSED COMMENTS:

STEP 1 4:(3.A.6) If the 10 Sample Heat Exchanger is suspected of causing the increase in CCW activity, Then isolate the heat exchanger by the following:

6. Continue to monitor trends after HX has been isolated to verify leak has SAT stopped. Contact SNPO to determine Pressurizer Steam Space outlet tern perature.

UNSAT STANDARD: Monitor CCW Radiation Monitor (Channels 56 & 57) to VERIFY leak has been ISOLATED. Contact SNPO to determine Pressurizer Steam Space outlet temperature.

EXAMINERS CUE: CCW Radiation Monitor (Channels 56 & 57) have stabalized. SNPO REPORTS Pressurizer Steam Space Sample heat exchanger return temperature is approximately 120°F and lowering.

COMMENTS:

NRC 19A C-8 Unit 1 control Room Page 8 of 10

JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STEP (done): Notify the US that the 1C Sample Heat Exchanger has been isolated.

STANDARD: NOTIFY the US that the 1 C Sample Heat Exchanger has been ISOLATED SAT EXAMINERS CUE: US AKNOWLEDGES COMMENTS: UNSAT END OF TASK STOP TIME:

NRC 19A C-8 Unit 1 Control Room Page 9 of 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

Unit 1 is operating at 100% power, steady state conditions, MOL.

1. Annunciator S-6 (COW SURGE TANK LEVEL HIGH/COMPARTMENT A LEVEL LOW) has illuminated.
2. A SNPO was dispatched to locally investigate the CCW Surge Tank.
a. He reports that level is greater than 4 feet (sightglass full) and
b. LCV-1 4-1, Demin Water to Surge Tank, is closed with no make-up flow indicated.
3. All operator actions of 1-ARP-01-S6 have been carried out.

INITIATING CUES:

The US has directed you to perform the actions required by ONOP 1-031 0030, Component Cooling Water Off Normal Operation, to determine the cause for the high Surge Tank level.

Page 10 of 10

REVISION NO.: PROCEDURE TITLE: PAGE:

40 COMPONENT COOLING WATER

- 18 f 23 PROCEDURE NO.: OFF-NORMAL OPERATION 1-0310030 ST. LUCIE UNIT 1 6.2 Subsequent Action (continued)

NOTE CCW Surge Tank vent (RCV-1 4-1) diverts from atmosphere to the Chemical Drain Tank on high radioactivity in the CCW System.

5. If abnormal level conditions exist in the CCW Surge Tank, Then PERFORM the following:

A. HighLevel in the CCW Surge Tank.

/1E)CHECK the CCW Radiation Monitors (Channel 56 & 57) for

( Jabnormal trends. If high radiation is indicated, REFER to ONOP 1-0310031, Component Cooling Water Excessive Activity.

2. CHECK the CCW Surge Tank Makeup Flow meter (FQ-1 4-14) for flow. If makeup flow is indicated, CLOSE Vi 4100, Makeup lsol, and VERIFY V14101, Alternate Makeup Supply, is closed.
3. Evaluate S!G Blowdown Sample Heat Exchangers as a source of in leakage.

B. Low Level in the CCW Surge Tank

1. CHECK the CCW Surge Tank Makeup Flow Meter (FQ-1 4-1 4) for flow:
a. If no flow is indicated:
1. VERIFY LCV-i4-i, CCW Surge Tank Fill Valve, and V14i00, Makeup Isol, are open.
2. VERIFY a Demin Water Pump is running.

CAUTION Use the fire system as a makeup source only as a last resort.

b. If flow is indicated:
1. COMMENCE a visual search of the CCW System for evidence of leakage.
2. REFER to Appendix A to aid in the leak search.
3. ISOLATE the leak, if possible.

REVISION NO.: PROCEDURE TITLE: PAGE:

22 COMPONENT COOLING WATER EXCESSIVE 6 0 f 19 PROCEDURE NO.: ACTIVITY 1-031 0031 ST. LUCIE UNIT 1 7.2 Subsequent Operator Actions INSTRUCTIONS CONTINGENCY ACTIONS

1. Notify Health Physics and Chemistry Department of CCW excessive activity.
2. Determine the primary leak rate per 1 -OSP-01 .03, Reactor Coolant System Inventory Balance.
3. If plant is in Mode 3 though 6 (SIAS Blocked), Then perform safety function status check of Low Mode Off-Normal Procedure for current plant condition.
4. Inspect the following components for 4.

indication of RCS inleakage:

A. Verify RCS inleakage from the A. If RCP seal cooler leakage is RCP(s) seal cooler is NOT occurring indicated, Then:

by the following:

1. NO unexplained increase in RCP 1. Monitor RCP seal cavity lower seal temperature. temperature per ONOP 1-0120034 (Reactor Coolant Pump Off-Normal).
2. DCS Computer Points are NOT 2. [1 DCS Computer Points in alarm: 33X1 93_A, 33X293A, 33X1 94_A or 33X294_A
  • 33X1 93_A, 1AI RCP CL are in alarm, Then ensure Tube Lk Vlv Cls / Pwr FA the Hx Iso!. Valve has been closed and GO TO ONOP
  • 33X293_A, 1A2 RCP CL 1-0120034 (Reactor Tube Lk Vlv CIs / Pwr FA Coolant Pump Off-Normal).
  • 33X194A, 1B1 RCPCL Tube Lk Vlv CIs / Pwr FA
  • 33X294A, 1A2 RCP CL Tube Lk Vlv CIs! Pwr FA

REVISION NO.: PROCEDURE TITLE: PAGE:

22 COMPONENT COOLING WATER EXCESSIVE 10 f 19 PROCEDURE NO.: ACTIVITY 1-0310031 ST. LUCIE UNIT 1 APPENDIX A ISOLATION OF THE SAMPLE HEAT EXCHANGERS (Page 2 of2)

3. 1C SAMPLE HEAT EXCHANGER (PRESSURIZER STEAM SPACE)

A. [f the 1 C Sample Heat Exchanger is suspected of causing the increase in CCW activity, Then isolate the heat exchanger by the following:

1. Close V5202, Przr. Steam Space Sample (RTGB-106).
2. Close V5205, Przr. Steam Space Sample (RTGB-106).
3. Close V05007, 10 Sample Hx Outlet Isol.
4. Close V14506, 10 Sample Hx Inlet Isol.
5. Close Vi 4502, 10 Sample Hx Outlet Isol.
6. Continue to monitor trends after Hx has been isolated to verify leak has been stopped.
4. 1 D SAMPLE HEAT EXCHANGER (SHUTDOWN COOLING)

A. H the 1 D Sample Heat Exchanger is suspected of causing the increase in COW activity, Then isolate the heat exchanger by the following:

1. Close V0501 0, 1 D Sample Hx Inlet from SITs Isol.
2. Close V5127, 1D Sample Hx Inlet from 1A LPSI Pump Disch. Isol.
3. Close V5130, 1D Sample Hx Inlet from HPSI Pumps Mm-flow Isol.
4. Close V51 61, 1 D Sample Hx Inlet from SDC Suct. Isol.
5. Close V050i 1, 1 D Sample Hx Outlet Isol.
6. Close Vi4505, 1D Sample Hx Inlet Isol.
7. Close V14501, 1D Sample Hx Outlet Isol.
8. Continue to monitor trends after Hx has been isolated to verify leak has been stopped.

END OF APPENDIX A

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-I Determine Shutdown Margin Criteria (RO/SRO)

This JPM is NOT TIME CRITICAL This is a FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Determine Shutdown Margin Criteria KA Statement: 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

KA IR: RO 4.1, SRO 4.3

References:

  • Unit 2 Plant Physics Curves
  • 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical)

Name Validation Time: 15 minutes Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 2

NRC ADM JPM A-i REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Determine Shutdown Margin Criteria Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 was at 100% power for 120 days, 3143 EFPH. An automatic reactor / turbine trip just occurred.

  • CEA 8 did not drop and is at 132 withdrawn.
  • Current RCS temperature is 532°F.
  • RCS Cb is 962 ppm (at 0400).
  • Current time is 0500.
  • Reactor Engineering has provided a Reactivity Deviation value of 0 pcm.

Prerequisites/Precautions/Limitations of 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical) are complete Initiating Cue You are directed to verify shutdown margin for the current plant conditions and to determine corrective actions if any apply.

EXAMINERS NOTE: This SDM calculation was conducted using 3143 EFPH.

Figures A.4, BA, B.5, B.6, & B] from the PSL Unit 2 Cycle 18 Plant Curve Book (PSL-ENG-SEFJ-09-008 Rev. 0), dated 05/18/09, were used to perform this calculation. Ensure the same revisions are given to the applicants for performance of this JPM. Reactor Engineering has provided a Reactivity Deviation value of 0 pcm (Data sheet 2 step 5B).

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 3

NRC ADM JPM A-i START TIME:

DATA SHEET 2 STEP 1 (1&2): Prerequisites & Precautions/Limitations complete SAT STANDARD: All complete EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 2 (3): Record current plant conditions on data sheet 2 STANDARD: SAT

3. Current Plant Conditions:

Date TOPIy Time .LLI:&C Mode 3 UNSAT Temperature 53, °F Core Burnup 3j 13 EFPH (DCS)

EXAMINERS CUE: NONE COMMENTS:

STEP 3 (4): Record target plant conditions on data sheet 2 STANDARD: SAT

4. Target Plant Conditions A. Surveillance time interval (Enter 0 if calculating for UNSAT current conditions) Hours B. Minimum expected RCS Temperature during the surveillance interval EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 4

NRC ADM JPM A-i STEP 4 (5A): Determine Xenon worth from Figure A.4 and record on Data sheet 2. CRITICAL STEP STANDARD: 2525 pcm 2600 pcm SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 5 (5B): Record Reactivity Deviation on data sheet 2 SAT STANDARD: Opcm EXAMINERS CUE: Reactor Engineering has provided a Reactivity UNSAT Deviation value of 0 pcm.

COMMENTS:

STEP 6 (SC): Determine stuck rod worth using Figure B.4 and record on data sheet 2 CRITICAL STEP STANDARD: 1654 pcm +/- 0 pcm SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 7 (5D & 6A): Add lines 5A, SB, & SC and record on data sheet 2 CRITICAL STEP STANDARD: 871 pcm 946 pcm SAT EXAMINERS CUE: NONE COMMENTS: UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 5

NRC ADM JPM A-i STEP 8 (68): Determine boron worth using Figure B.5 and record on data sheet 2 CRITICAL STEP STANDARD: 8.01 pcm/ppm 8.04 pcm/ppm SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 9 (6C): Divide line 6A by 68 CRITICAL STEP STANDARD: 108.70 ppm 117.70 ppm SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 10 (6D): Determine Shutdown Boron Concentration using figures B.6 or B.7 CRITICAL (preferably B.7) and record on data sheet 2. STEP STANDARD: 1130 ppm - 1150 ppm SAT EXAMINERS CUE: NONE UNSAT COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 6

NRC ADM JPM A-i STEP 11 (6E): Add lines 6C & 6D and record on data sheet 2 CRITICAL STEP STANDARD: 1021 ppm -1032 ppm EXAMINERS CUE: NONE SAT COMMENTS:

U NSAT STEP 12 (7A): Enter present RCS boron concentration.

STANDARD: Given as 962 ppm SAT EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 13 (7B): Determine if Shutdown Margin is adequate CRITICAL STEP STANDARD: Determines SDM not met for current plant conditions and that immediate Emergency Boration is required per Technical Specifictions.

SAT COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 7

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 was at 100% power for 120 days, 3143 EFPH. An automatic reactor / turbine trip just occurred.

  • CEA 8 did not drop and is at 132 withdrawn.
  • Current RCS temperature is 532°F.
  • RCS Cb is 962 ppm.(at 0400(
  • Current time is 0500.
  • Reactor Engineering has provided a Reactivity Deviation value of 0 pcm.

Prerequisites/Precautions/Limitations of 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin; Modes 2, 3, 4, and 5 (Subcritical) are complete Initiating Cue You are directed to verify shutdown margin for the current plant conditions and to determine corrective actions if any apply.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-i PAGE 8

c) 0 z

0 C) 0 0

C) 0 r41 0-ui C,

T 0

I 01 H 0

0 I C

LLJ4-z U)

LU -

a) 0 o a) w

.IuJa)

C 0 a) 0 CI.

I w° WZD I LU 0 0 a)

C) 4-ci Wcca)

Ith -

C D

a 5

CD P a) 0 a) a) 5 0 4- C) 0

..I 0

a) CoQ) 0

_00 00 4-U) 0 a) a) C) Co +

C) a) .-

0 E CD LU 0 0 0 c-S U)

> a)

G) 0 *0 +

C 0

Eo 4 a)

CL)

-5 4-J I (4

I C CO 0

Xa)

EC z

gQ)

E 0

O I

a)

Co z -

Ea) 0 O4- -

a

.0

.3 4-J -

a) a)

Z COcj c

C) 4-CI) a)

4-d C) a) C) a)

a) a) 0 CD CD C.) C) z 2

i)

C., U)

a) m Zc, 0 Z

m > Cl) z Ufll_AQ a 0 -l 0

0 CD-,W 3m 0 a 3

Z

-3 m WH 0.

C(O W mcv C) CO 0 0

%1 0 0 >3

0. 0 3 >< C D 8 Z

OD 0)0 iN s)(D C) p Ill c g g Oi zm o 00 CD 0.

CD.. -

- D m WD CDZØ c?xc m m w m w czm CD 01 HC

+

0) -

0 0 0

0 Q) Ow , ,1øo 0 rn 0 0 CD

. 3o 0D C) (

c :01 CD

.*3 D

c Z 01-,

D I C)

C) o 0v -a 0 0 tHUo -4,

-U

-U

  • Cl)
5 F-UJ :3-CD C F

0 0.

<. F 0

CD :3- C)0 1_ C) 0)

CD CD CD CD D

5-CD w CD CD CD C) 0 -i CD CD CD 0 :5 3- :3 0) 0 23 C,
5 o_ w 0 0) a
0. WZ F -I cT >

0 00 :5 Cn

5 C) :5:5 0) W D.

-I-. 0 o i CD F- Cl) - C, CD C, 0 o

-o CD CD CD CD :3 -.

ni 0 CD ,- 0 4 CD C, z C, 0

> CD C  !. 3 CD C, C 0 CD >

,, 0 CD 0)0 CD :3 -4 0)0 F CD C, 1 C 1 CD H CD

=1 - F-C, 3 Cl,

-l CD 5 CD 0

0) - :5 x
0. CD rn CD D.CD C,, 0 In

-I -t -l m C) CD ,-.- 1%,

In CD I,

-l CD CD)

C *0 CD 0 Cl) 0 ID 0) 0 CD 0)

F- r CD F-CD --.0 CD

5. C DC CD - 0)

CD

-I CD CD CD C C) mo p

  • F-CD 0 :3.

CD H

3 0

0) CD
5 CD C) :5 C CD C, 1 v.j CD CD CD

-o 0.

CD F-

-I,

r w -o 0

-I 0

3 CD 0.

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING A-2 This JPM is NOT TIME CRITICAL This is a NON-FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING KA Statement: 2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

KA#: 3.9/4.2

References:

1-0440030 Shutdown Cooling Off-Normal Candidate:

Name Validation Time: 15 minutes Start Time:

Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 2

NRC ADM JPM A-2 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE TIME TO BOIL AND THE MAKEUP FOR BOIL OFF ON LOSS OF SHUTDOWN COOLING Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit I is in a Refueling outage preparing to lift the Reactor Vessel head. You have just begun your shift.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the following using 1-0440030, Shutdown Cooling Off-Normal:

1. Time boiling will occur
2. Flow to makeup for Boil-Off lAW 1-0440030, Shutdown Cooling Off-Normal.

Given:

  • RCS temperature is 95°F
  • RCS level is 35 feet.
  • The Unit was tripped on Oct. 18, at 0000
  • Current date I time is Oct. 22, 0110 ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 3

NRC ADM JPM A-2 START TIME:

DATA SHEET I STEP 1 (1A): Record the following information SAT RCS Temperature UNSAT STANDARD: Records 95°F EXAMINERS CUE: NONE COMMENTS:

STEP 2 (1A): Record the following information Vessel/Cavity Level SAT STANDARD: Records 35 ft. UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 3 (1A): Record the following information Time since shutdown (hours) SAT STANDARD: Records 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> (97 - 97.17)

UNSAT EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 4

NRC ADM JPM A-2 STEP 4 (IA): Record the following information Time Shutdown Cooling Lost SAT STANDARD: 0100 UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 5 (1 B): Table 2 Time to Boil at Mid-Loop CRITICAL STEP EXAMINERS NOTE

. Temperature between columns, select higher temperature

. Time since shutdown between rows, select the lesser time SAT STANDARD: 16.8 minutes UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 6 (1C): Table 3Additional Time to Boil /100 ft 3 CRITICAL STE P EXAMINERS NOTE

. Temperature between columns, select higher temperature

. Time since shutdown between rows, select the lesser time SAT STANDARD: 1.17 minutes UNSAT EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 5

NRC ADM JPM A-2 STEP 7 (1 D): Table 4 Additional volume of water above mid-loop CRITICAL STEP STANDARD: 4.44 (100 ft) 3 SAT EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 8 (1 E): PERFORM the following equation to determine the Corrected Time to Boil CRITICAL as follows: STEP

( )+[( )x( )]=

Step 1 B Step 1 C Step ID Time to Boil SAT STANDARD: Step lB 16.8 SteplCl.17 UNSAT Step ID 4.44 Time to Boil 21.99 minutes (21.99 22 minutes is acceptable)

EXAMINERS CUE: NONE COMMENTS:

STEP 9 (2): H core shuffle or reload has NOT been completed, Then use the step 1 .E.

Time to Boil value in step 4.

STANDARD: Based on cue of Reactor Vessel head being removed, determines step i.E is SAT applicable.

EXAMINERS CUE: NONE UNSAT COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 6

NRC ADM JPM A-2 STEP 10 (3): [1 core shuffle or reload has been completed, Then PERFORM the following equation to adjust the time to boil and use this value in step 4.

STANDARD: Determines core shuffle I reload has NOT been complete. SAT EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 11(4): Determine time boiling will occur CRITICAL STEP

+ =

Time SDC Lost Time to Boil Time Boiling Will Occur SAT STANDARD: Time SDC Lost 0100 Time to Boil 21.99 (22 minutes is acceptable)

Time Boiling Will Occur 0122 (0121 0122)

UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 12: Determine Flow To Makeup For Boil-Off CRITICAL STEP STANDARD: Using Figure 1 determines 65 gpm (64-66) makeup for boil-off.

EXAMINERS CUE: NONE EXAMINERS NOTE: This step may be performed at any time SAT COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 7

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is in a Refueling outage preparing to lift the Reactor Vessel head. You have just begun your shift.

A loss of shutdown cooling occurs.

Initiating Cue The US has directed you to determine the following using 1-0440030, Shutdown Cooling Off-Normal:

1. Time boiling will occur
2. Flow to makeup for Boil-Off lAW 1-0440030, Shutdown Cooling Off-Normal.

Given:

  • RCS temperature is 95°F
  • RCS level is 35 feet.
  • The Unit was tripped on Oct. 18, at 0000
  • Current date I time is Oct. 22, 0110 ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-2 PAGE 8

LEVISION NO.: PROCEDURE 1TILE: PAGE:

36B SHUTDOWN COOLING OFF-NORMAL ROCEDURE NO.: 35 of 36 1-0440030 ST. LUCIE UNIT I DATA SHEET I ESTIMATED TIME TO CORE BOILING AND REQUIRED SHUTDOWN COOLING RESTORATION (Page I of 2)

§ Determine the corrected Time to Core Boiling by performing the following:

A. Record the following information RCS Temperature Vessel/Cavity Level c Time since shutdown (hours) i Time Shutdown Cooling Lost Cl b p B. Table 2 Time to Boil at Mid-Loop

- c., 8 (minutes)

C. Table 3 Additional Time to Boil 1100 ft

- 3 i (minutes)

D. Table 4 Additional volume of water above mid-loop.

i.tl4 (100 ff

)

3 E. PERFORM the following equation to determine the Corrected Time to Boil as follows: a1,qj it

( L(I. )+[( Ill )x( i )j= minutes Step I B Step IC Step ID Time to Boil core shuffle or reload has NOT been completed, use the step I.E. Time I to1! Boil value In step 4.

2.,

3. r ] core shuffle or reload has been completed, Thç PERFORM the following equation to adjust the time to boil and use this value In step 4.

xI.35=

Time to boil step I.E Time to Boil

42 a REVISION NO.: PROCEDURE TITLE: -4 PAGE:

38B SHUTDOWN COOLING OFF-NORMAL PROCEDURE NO.:

36 f 36 1-0440030 ST. LUCIE UNIT I DATA SHEET I ESTIMATED TIME TO CORE BOILING AND REQUIRED SHUTDOWN COOLING RESTORATION (Page 2 of 2)

L Determine time boiling will occur.

Z2..

Time SDC Lost + Time to Boil Time Boiling Will Occur ii 0S2i b172..

Performed by: I I I RCO Date Verlfiedby: I I I US Date END OF DATA SHEET I

m 0

C) Co m 0 o c z

  • () z Ma keup Flow For Boiloff 0 o Z 260 op c.

0 240 e

-D 220 -

0 C.)

m 200 *

.:--T--: 1 I C)

  • ...i..-.. m 180 0 C

.-+

-1 I m

-l I 0 0 t Cl)

-U >T1 I z I 0

- ._,.. rn CD C 0 CC 0 0 0

m 1

, m z

.__._J_ .-- o- C C)

. ...4 . z

+ . .+ a, -4 0 1

0 1 4 -

z 0 0 1

.- ___.._______i_.._._._..._.__._.._.

r >

I-20 0

02 4 6 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 -D G)

UNIT 1. 25000 EFPH C)

Time After S/D (Days) PSL-2FSN-98-001 0 (POPS1*O44Co3O.F242)

(.3.

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-3 Monitoring Linear Heat Rate Using Incore Detectors (DCS)

(RO/SRO)

This JPM is NOT TIME CRITICAL This is a FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)

KA Statement: 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

KA IR: RO = 4.2, SRO = 4.4

References:

  • NOP-1 00.03, Monitoring Linear Heat Rate
  • 2-NOP-102.01, Distributed Control System (DOS) Operations
  • FSAR 13.8.1.2, Incore Detectors
  • 2-ARP-01-L-16, Linear Heat Rate/Incores
  • Equipment Out of Service Log
  • 0-OSP-64.01, Reactor Engineering Periodic Tests, Checks, and Calibrations Operating Surveillance Procedure Candidate:

Name Validation Time: 25 minutes Start Time: Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 2

NRC ADM JPM A-3 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Monitoring Linear Heat Rate Using Incore Detectors (DCS)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions

1. Unit 2 is at 100% power
2. Annunciator L- 16 is in alarm. The ARP has been pulled with the following actions completed:
a. Reactor Engineering has been notified.
b. 0-NOP-100.03, Monitoring Linear Heat Rate, has been referred to and the Prerequisites, Precautions, Limitations, and Initial Conditions of NOP-1 00.03, have been completed.

NOTE: The flux log will be printed as part of step 6.2.1 Initiating Cue The Unit Supervisor has directed you to perform NOP-1 00.03, Monitoring Linear Heat Rate, starting with step 6.2.1.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 3

NRC ADM JPM A-3 START TIME:

NOP-1 00.03 Monitoring Linear Heat Rate CRITICAL STEP 1(6.2.1): Obtain a Flux Log from the DCS STEP A. From the Main Menu ACCESS the Process Reports B. PRINT SAT STANDARD: Candidate touches Print Demand Log and log prints out EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 2 (6.2.2): Determine which incore detectors are failed or abnormal STANDARD: Notes failed detectors at locations 26, 30, 33, 34, & 43 (detector #1)

SAT EXAMINERS CUE: NONE EXAMINERS NOTE: A Failed or Abnormal Detector will be indicated UNSAT by one of 3 colors: Black, White or Red on the Incore Display. #43 (detector #1) is an add itionallnew failed detector and is RED on the DCS display. An abnormally low flux indicated on the hard copy flux log is also indication of a failed detector.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 4

NRC ADM JPM A-3 STEP 3 (6.2.3): Compare failed detectors to Equipment Out of Service Log (OOS), Figure D,6, Incore Operating Status. CRITICAL STEP STANDARD: Determines there is one (1) additional failed detector location (string 43 detector #1)

SAT EXAMINERS CUE: Make available the hardcopy Equipment Out of Service Log.

UNSAT EXAMINERS NOTE: May compare to either Figure D.6 or to Data Sheet I of O-OSP-64.OI (both are in OOS log book).

COMMENTS:

STEP 4 (6.24): Add additional/new failed detectors to the total CRITICAL STANDARD: Additional failed detector(s) added to the Equipment Out of Service STEP Log (OOS).

EXAMINERS CUE: NONE SAT EXAMINERS NOTE: This may be accomplished by adding to Attachment I, Data Sheet I of O-OSP-64.OI, or by UNSAT annotating the appropriate block on Figure 0.6 or both (both are in OOS log book).

COMMENTS:

STEP 5 (6.2.5): Evaluate the total number of failed detectors against criteria on Figure D.6.

STANDARD: Determines that there are 21 upper detectors and 22 lower detectors SAT still operable in the affected quadrant and that this is greater than the minimums of 4 operable in the upper, 4 in the lower and a total of 10 for that quadrant UNSAT EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 5

NRC ADM JPM A-3 STEP 6 (6.2.6): If criteria on Figure D.6 is not met, the Incore detector system is NOT Operable STANDARD: Determines Incore System is Operable EXAMINERS CUE: After operability determination, the Unit SAT Supervisor directs you to remove new failed detector(s) from SCAN in DCS using 2-NOP-102.01, Distributive Control System (DCS) UNSAT Operations, step 6.3.

EXAMINERS NOTE: This is not a Tech Spec operability, but is an operability requirement of FSAR 13.8.1.2.

COMMENTS:

2-NOP-1 02.01 Distributed Control System (DCS) Operations STEP 7 (6.3.1): Select INCORE from Main menu STANDARD: INCORE selected SAT EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 8 (6.3.2): Select the Incore Group with the failed detector STANDARD: Correct Incore group (#43) selected EXAMINERS CUE: NONE SAT COMMENTS:

UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 6

NRC ADM JPM A-3 STEP 9 (6.3.3): Select DEL FROM SCAN button for the failed detector CRITICAL STANDARD: DEL SCAN button turns black for detector #1 of string 43 STEP EXAMINERS CUE: NONE SAT COMMENTS:

UNSAT STEP 10 (6.3.4): SELECT the Input Box on the pop-up screen.

STANDARD: Input Box Selected for detector #1 of string #43 EXAMINERS CUE: NONE SAT EXAMINERS NOTE: Input Box is above the DEL SCAN button.

UNSAT COMMENTS:

STEP 1 1 (6.3.5): Enter zero (0) in the Input Box and then PRESS Enter.

CRITICAL STANDARD: The Flux value will now be shown in pink on a black background and STEP a small black box with a pink letter 0 will now appear next to the Flux value. Annunciator L-16 clears.

EXAMINERS CUE: NONE SAT EXAMINERS NOTE: When the DEL SCAN button is colored light blue, the lncore detector will have been deleted and the UNSAT DCS will no longer evaluate the incore. When a zero (0) is manually entered, this will positively indicate that the Incore detector was taken out of service and that value will be stored in the log term historian.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 7

NRC ADM JPM A-3 STEP 12 (6.3.6): Ensure the Flux value now indicates zero (0)

STANDARD: Flux value indicates zero (0) for detector #1 at string location #43 SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 13 (6.3.6): SELECT CLOSE to return to the main Incore screen STANDARD: Incore string #43 detector #1 will show a black box in the upper left quad.

SAT EXAMINERS CUE: NONE EXAMINERS NONE: Black box indicates the detector has been UNSAT removed from scan.

COMMENTS:

STEP 14 (6.3.6): Document change to lncore Detector status on Data Sheet 1 STANDARD: Failed detector recorded on Datasheet 1 EXAMINERS CUE: The US directs tha another operator will provide Independent Verification (IV) on Data Sheet I Examiner may

. SAT need to cue examinee that this is the END of the JPM.

EXAMINERS NOTE: Since no specific direction is given, there may be UNSAT a wide variety of wording that would meet the intent of recording this change on data sheet I COMMENTS:

END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 8

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions

1. Unit 2 is at 100% power
2. The Prerequisites, Precautions, Limitations, and Initial Conditions of NOP-100.03, Monitoring Linear Heat Rate, have been completed Initiating Cue The Unit Supervisor has directed you to perform NOP-1 00.03, Monitoring Linear Heat Rate, starting with step 6.2.1.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-3 PAGE 9

1

-U I 0

C C 132 CC) (-2 (.3 (.3 (-3 (C) (-3 (- 3 fr I- I- C- (.3 (- (.3 (.3 Cr CC Cr CC Cr Cr h h 03 03 (.3 (3 02 02 (.2 (2 (.2 (.2 (-3 $3 C) CC (.3 (-3 >

Cr 02 13) (0 CC -J CC UI C.) 133 0 Cr (3 133 0 (0 CC -J CC Cr C.) 132 0 CC CC -J CC Cr (.3 (.2 0 30 CC -2 CC Cr 0 CC (I

r.3 cc 0

0 01 CrCr (.CCrCJI Cru,CrCra,a CrCCCrCCCrCrCJlCr.h..a. .a 0 .h..h.a..b. (JCCrCr.S 2 C rCrCrCr.h.&.b.Cr

(.* OO3$3CtCCCr$3

.3

-U 0$303(3O0-.ICCCCC-.IO .h.h.

C 0 rt.3-.J 13OCCCCC-C0th(-1OM30t.2tO(-CC-.J -JCfl?.3COCOOC.3 0....

30O( .b.Wt3 .ICCCCCrCrCC pOOCfl03CCI-tO

(.3 (0 (-3 -J 13) $3 (- (- CC (- CC 0 CM Cr CC 0 CC (.3 0 0 0 (fi (.1 CC (0 0) fr (.3 CC CC b 0 (. (a I Cr CC 3 CC CD (0 (. 13) t (.2 (0 (3 CC 0 0 0 (.3 (- -3 .0. CM CC (.3 0 (.3 -3 (31 CC CO fr I-. CO (.1 (-3 13) -.3 (0 133 )a x CC 0 .3 .6 I -3 .0. CC CC .6 1 CC) (S CD CO (.3 (fl (. CD 0 (0 (.3 0 .3 CC --3

.3(.3CC03COQCCCC(.2CC03$2(. 0 h..o.oCaCo(3ww 1 CC- (CrC.. CC*MCCCrCC$2UCC-J-.JCC$3$3(.-.CCO fl1 F

(.2 Cr IC) Cr 0 .0. I- ( Ca (3) 133 3 (1 (.2 (.3 CC C.) (0 (.3 CC CC CC CO CC Cr .0. .0. (fl .6 0 Cr (. -3 13) -3 Cr .0. CC 30 CC 0 C. j( 0 0 0 CC CCC C.) CC CC 0

14 0

0 m

CJ1CrUI CrCrCrCr.6*.6UICrCrU1Cr,.6.CrCrCr...6..6.

2 I

.6 *.6.6.6.6.6CrCrCr.6 CrCrCrCr.6* Cr Cr01 (30, (-Cl.), OOlC)* $3$3$2O(-$23IC)-J(3CO$3(C)IC)30W$2CrCCU1(3 0 (3CrCCCr3C.3C0$2(3CC)C0CC(-.($2(-3(.2$3-JC-(3(3CMCCCr(3

-(,C(0CrCr 1

(3Cr02WO°OCOO°°I-2(-°a.60°0CC0O(3I-Q(-(.2(. 0,...

132(3CC.6aU(.3CC0(.2CrQCr00$3(3(.C(.3CC(3MO CCl(3C0 0

  • Cr CrCr.6CCCCWCrCC(-(3.6.6(3(3fr-CD(-2$2-JCO(

11 C-3Cr1

(.3OCCCC03 C

0 CC(3CCCM 003Cr UICC03..3 CC (ata°aCCCC°(3p) CrJ0W0M.6$2OCC-)CCCrCr(..(3$3eOCO

(.2 o F- CC 0) -3 CC CC C.) CC Cr .6 0 Cr 02 0 (31 .3 0 03 CO IC) IC X 0 C- CC .6 .6 CC Cr -4 CC Cr CC CC (3 0 CC) -3 0 CC 02 CO CC (.3 0 0 .j (.2 0 0 C .6 02 CC) -2 (.2 0 (0 CC 0 C.) CC) CC (.3 .6 0 CC -3 CC) C.) CO (-3 fl. .6 -J CC IC) C) 13 .4 CC .6 (.3 CD (.3 CC 13) CC .6 CC) CC Cr Cr -l C 03 0 ( C.C CC Ca x 0 - CC F- C.) (3 (4 (32 (-3 0 0 fl. 0 .6 CC CO .6 CC C- CC (.2 CC CD C- C.) () I- -3 (0 C.) (0 CD 0 0 (- F- C- CC C-C. CC Cr CC -3 (.3 -3 0 0 CC .0. (0 Cr Cl) C Ix r

fib F

C n

14 m

(31(31 .6.6CM CrCrCr.6.6.6CrCrCrCrCr.6.6.6 ICCrCr .6.6.6.6.6.6

  • .6.k.6*.6 CrCrCr.6.6 CCCrCCC.6a.6 I- ( CO CO 13 (- 13 13 CD 13 F. -3C- (-3 C- 13 (4 .3 I) 0 C- 13) 0 (CC C- CC CC Cr (3 C- Cr CC Cr (3 13) CC C- CC (3 -4 F- I- 13 (3 3 13 (0 2 (OCCCr0C)C CCCCOC)1C rCaCrflCrCC C).CCCCCrCrCrCC(0CC0(30(0 1 -4 CC0132OCCCCCOC.20CC(00CCCC0 0...

CCMaCr$3( C.JCCCSC -2.0. (.2F-°aCCCr°$3$3OCrW WCrC.J-4WF0t.3CC0Cr-JCCCC.6CCCrOCCC-A C

0 rCCCC-.)CO CrC-JCrCC.J 0 Cr fl I CO. Cr (0 13 1.) C (4 Cr CM 0 Cr C.) C,.

0 CD 13 .0. CC) CC Cr CC 0 0 0 CC CC 3 . 0 C C.C CC .6 (C) 3 (C) CC (.C (CC 13 0 0 0 13) CC .6 CC CC CC 3 I C-.

J0 -3W0CC0-30(3-300CC0(- CC 1 4.OCCIC)IJC r C C

0 C.)FCCOCC

-J.6-)CC-JCD $3-J$3(-0$2 C-M(-3 0 -

1 C

0 C-JMCr.3CC 34C 0 0 0 0 0 CC CC 13 Cr C- CC (.4 CC (.3 1) (.2 CC C- CD CO CC CC CO CC I- (.3 (0 (C)

CD 0 13 CC CC CO C CC) 0 (0 CO C- Cr (0 3) .6 .0. 0 .3 CC Cr C.) I- (5) 13 I- (.3 -3 (.3 Cr C- CC Cr CC a CM CC .6 -J 0 .0. .6 C- 0 (0 Cr (C) CC (0 CC C- (C) CD .6 .6 CC .6 (0 (0 0 a 0 IC) (.3 .6 13 CD .3 (.3 Cr CC) CC 2

14

-I 2

0 pJ CC Cr .8.8 Cr Cr Cr Cr .0. .0 .6 .6 Cr Cr Cr Cr Cr .6 .6 .8 (31 Cr Cr .6 .0. .6 .6.6.8 .8

.0. .6.6 CO .6 .8 .6 Cr Cr Cr .6 .6.6 Cr Cr CC Cr .8 .8 .6.6 (-3 (C) 0 -3 F CO (.2 (0 CD 13 13 13 (0 13 .3 C- (-3 13 13 3 CCC CC (.2 13 CC (.3 13 Cr CC Cr C- Cr CC Cr (C) CC C- C- CC -

.8Cr CrC CrC C

O CCOCCOI- rCC rCC I W OCC I CCO C

0

(

0 JCCCCCDC rCC O CCO 2 rCr02CrCCC CC CCC C C CrW CCCCrWCC CCr 0 C CrCCCrUCO ICC 0 (0CC OCCCC $2CC13$2C C2CC(3Ca0COaCOCCCr.303CCCCCa(.2COCaCCU 0 C C

0 C(30CrCCfr-CC)0aC-a*C rCot0C-CC- CrCC -- 0 .6 -J 0 0 -

Cr Ca Cr 3 CC (.3 (3 CC CC CC 0) CC Cr CC (3 0 0 Cr Cr CD (2. Cr CC CC 0 (.3 C 0 Ca (0 CC (CC 0 6.6.6 CC -J (.2 0Ca$3 z

2CCF Cr-JCrCrCC 0 CrOJC CDOCOF-a CJ CCJ-3 -.3 CCCC(- OOCOCCCC.J(3Cr-JCr$3COWaCOCM.3-JCC(30CO COCCW(CC CC CCC,IOCCC r C 03 CCWCCCCJCCCCC2CrW 0

C .3 0 -JO$3CCCC .) 02C C

0 r-JMOCC0(3COCC--JWCrF-30t.Ct.C -I 0°CD0.J0Cr( -*JC- .4.6 -.3(00) OCrCCM$3C CCOCrCCCrCD$2C)0CO.6OC*000IC30 CCCC.-JC00 (0Ca00CCCC z

0 0

-Ti M

ifr IISION NO.: PROCEDURE TITLE: PAGE:

42B REACTOR ENGINEERING PERIODIC Attachment to:

PRQCbL)UK NV.: TESTS, CHECKS AND CALIBRATIONS 48 of 64 OPERATING SURVEILLANCE PROCEDURE O-OSP-64.O1 ST. LUCIE PLANT ATTACHMENT 1, DATA SHEET I PERIODIC SURVEILLANCE OF INCORE DETECTOR SYSTEM Tahi. of 611ad bidWidual

.,w,I Group I Level DOPS Core Data of Cycle/Exposure (EFPH) #

(String) PID Location Failure (if Known) 33 3 131 R-13 12/21101 13 .bandoned-B0C13 7 33 4 132 R-13 12121/01 13 Abandoned- SOC 13 8 34 1 133 T-13 05/17/97 10 Abandoned- SOC 10 9 34 2 134 7-13 05/17/97 10 Abandoned- SOC 10 10 34 3 135 7-13 05/17/97 10 Abandoned- BOG 10 11 34 4 136 T-13 05/17197 10 Abandoned- SOC 10 12 30 117 E-13 07/28/09 18 Low Signal 13 30 118 E-13 07/28/09 18 Low SIgnal 14 30 119 E-13 07/28/09 18 Low Signal 15 30 4 120 E-13 07/28/09 18 Low Signal 16 143 r-ic. -r-CDI4Y ii.eJ IlcL W 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 FOR INFORMA71ON ONLY This document Is not controlled. Befor. using this substitute form It must be verified Administratively OOS for observation to contain at least the same minimum infojmation as the original.

Date V.r1fledJJj1jL. Initials S Da ShaM I

A3 P4NSLIIJer I4ey Unit 2 Cycle 18 Figure D.6, Incore Operating Status pg 20(2 0

Quadrant I II Is 13 8 12 I0 S

Quadrant 3 1S0 PreparEd by: 44j Date f/

Notes: 1. North Is it the top of the paws.

2. ShadIng Indicatis a faII.d detector.
3. Cor. map currant is of: 11i3Q$

Verified by: Date f)L.gj F

,t3 A ivsv.tr EVISION NO.: PROCEDURE TITLE: PAGE:

8A DISTRIBUTED CONTROL SYSTEM (DCS)

- 8 of 8 PROCEDURE NO.: OPERATIONS 2-NOP-102.Ol ST. LUCIE UNIT 2 DATA SHEET I CHANGE OF DCS DATA (Page 1 of 1)

Parameter As Found As Left Initial IV Date Time cs PID IS rAI S(A) MtP)

L 14

-c,.,.. ccM/

ri -W /3

)r Jé:j Reason Parameter was changed:

Reviewed By:

US/SM S 2 OPS DATE_____________

DCC Procedure DOCN NOP-1 02.01 SYS COM comoleted TM END OF DATA SHEET I

REVISION: PROCEDURE TITLE: PANEL I ANNUNCIATOR RESPONSE PROCEDURE L PROCEDURE NO: W1NDOW:

2-ARP-01-L16 ST. LUCIE UNIT 2 16 ANNUNCIATOR PANEL L 12345678 9 10 11 12 13 14 15 LINEAR HEAT 17 18 19 20 21 22 23 24 RATE I INCORES 2526 27 28 29 30 31 32 3334 35 36 37 38 39 40 41 42 43 44 45 46 47 48 LI 6 DEVICE: LOCATION: SETPOINT:

DCS Incore Monitor Device Control Room Various ALARM CONFIRMATiON:

1 Process Alarm located on the DCS system bar is blinking red on the Operators or Engineering workstation.

2. DCS Incore Map OPERATOR ACTIONS:
1. Print Process Report Flux Data Log
2. NOTIFY Reactor Engineering.
3. Refer to 0-NOP-1 00.03, Monitoring Linear Heat Rate.

CAUSES: Detector neutron volts exceeds the high alarm limit (HAL), for greater than 10 seconds.

REFERENCES:

1. PC/M 02042
2. CWD 2998-8-327 Sheet 1550

REVIQN NO.: PROCEDURE TITLE: PAGE:

5A MONITORING LINEAR HEAT RATE PROCEDURE NO.:

7 of 10 NOP-1 00.03 ST. LUCIE PLANT Monitoring Linear Heat Rate Using the lncore Detection System OBTAIN a Flux Log from the DCS by performing the following:

From the Main Menu ACCESS the Process Reports.

PRINT A Failed or Abnormal Detector wW tfciicated by one of 3 colors: Black, White or Red on the Incore Display.

DETERMINE which incore detectors in the flux log are failed or abnormal.

COMPARE the number of failed detectors and their locations to the list of failed incore detectors maintained in the Equipment Out of Service (OOS)

Figure D.6, lncore Operating Status.

j[ any detectors are discovered as failed in addition to those identified in Figure D.6, Then ADD the additional failed detector to the total.

EVALUATE the total number of failed detectors against the criteria listed in Figure D.6, lncore Operating Status Table.

i! the criteria of Figure D.6, lncore Operating Status, is NOT met, Then the incore detector system is NOT operable.

A. PERFORM the following to monitor LHR using the Excore Detector System.

1. PROCEED to Section 6.3, Monitoring LHR Using the Excore Detection system.
2. REFER to Technical Specifications 3.2.1, immediately ADVISE the Shift Manager and contact Reactor Engineering.
7. VERIFY fewer than 2 self-powered incore detectors are in alarm. (11 NOTE An asterisk next to the detector reading on the flux log indicates that detector has exceeded its alarm setpoint.

A. If two or more detectors are in alarm, Then NOTIFY Reactor Engineering and l&C Department.

B. If four or more detectors are in alarm, Then INITIATE corrective action within 15 minutes to reduce LHR to within limits (less than 4 detectors in alarm) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in accordance with Technical Specification 3.2.1.

REVISION NO.: PROCEDURE TITLE: PAGE:

8A DISTRIBUTED CONTROL SYSTEM (DCS)

- 9 of 81 PROCEDURE NO.: OPERATIONS 2-NOP-102.O1 ST. LUCIE UNIT 2 6 Deleting an Incore Detector From the Main Menu, SELECT the Incore button.

SELECT the Incore group that contains the detector you wish to delete.

SELECT the DEL FROM SCAN button located at the bottom of the pop-up

) screen for the selected detector.

f9( The DEL FROM SCAN button will now turn black indicating that the

&../ detector has been deleted from scan.

SELECT the input box of the pop-up screen above the DEL FROM SCAN button.

(s ENTER a zero (0) in the Input Box and then PRESS the Enter key.

When the DEL FROM SCAN butto-blored light blue, the Incore detector will have been deleted and the DS will no longer evaluate the incore.

When a zero (0) is manually entered, this will positively indicate that the Incore detector was taken out of service and that yalue will be stored in the log-term historian.

. The Flux value will now be shown in pink on a black background and a small black box with a pink letter 0 will now appear next to the Flux value. This indicates that a manual value has been entered.

ENSURE that the Flux Value now indicates zero (0).

SELECT Close to return to the main Incore screen On the main lncore screen, the Incore string will now show a black box in the upper left quad indicating that at least one (1) of the detectors has been deleted from scan.

Use Datasheet I of this procedure to document the change to the lncore Detector.

END OF SECTION 6.3

13.8.1 .1.2 Surveillance Requirements Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown on Table 13,8.1-2.

Each of the above seismic monitoring instruments actuated during a seismic event (greater than or equal to O.Olg) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

Plant operating restrictions associated with the Incore Detectors were removed from the facility Technical Specifications by License Amendment No. 136 and NRC Safety Evaluation Report issued June 6, 1995.

The operability of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The NRC Safety Evaluation Report issued June 6, 1995 with Technical Specification License Amendment #136 removing the incore detector operating restrictions from the Technical Specifications and placing them in the UFSAR recommends that any safety evaluation to reduce the minimum number of operable incore detectors address certain issues. These issues are specified below:

1) How an inadvertent loading of a fuel assembly into an improper location will be detected;
2) How the validity of the tilt estimates will be ensured;
3) How adequate core coverage will be maintained;
4) How the measurement uncertainties will be assured and why the added uncertainties are adequate to guarantee that measured peak linear heat rates, peak pin powers radial peaking factors, and azimuthal power tilts will meet Technical Specification limits; and
5) How the incore detector system will be restored to full (or nearly full) service before the beginning of each cycle.

13.8.1.2.1 Limiting Conditions for Operation

1. The incore detection system shall be operable using the BEACON code with:
a. The minimum requirement for detector availability at the beginning of each cycle is 75% for startup testing misload verification. For the rest of the cycle 50% detector availability is needed, and 13.8-2 Amendment No. 22 (05/07)

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM A-4 EVALUATE SURVEY MAP DATA (RO/SRO)

This is NOT a TIME CRITICAL JPM This is a Non-Faulted JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA KA Statement: 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

KA IR: RO = 3.5, SRO = 3.6

References:

HPP-20, Area Radiation and Contamination Surveys RWP 09-0002 Routine Maintenance ask Candidate:

Name Validation Time: 20 minutes StartTime:

Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A4 PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE SURVEY MAP DATA Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task and the cue sheet that I provided to you.

Initial Conditions You are an extra Unit 1 Reactor Operator. All three Charging Pumps have been identified as having an issue with the motor. You have been assigned to perform an inspection tour of all three Charging Pumps.

Initiating Cue Evaluate the attached survey map for the areas you will be touring, the ROUTINE MAINTENANCE RWP, and determine:

1. The expected required postings for charging pump rooms 1A, lB & 1C in accordance with HPP-20, Area Radiation and Contamination Surveys.
2. Whether the Operations Routine Maintenance RWP can be used for this tour.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 3

START TIME:

STEP 1: Determines the posting for Charging pump room 1A is expected to be High CRITICAL Radiation Area STEP STANDARD: HIGH RADIATION AREA SAT EXAMINERS CUE:

EXAMINERS NOTE: A specific RWP is not wrong, but not necessary because the Routine Maintenance RWP allows entry UNSAT into contaminated and HRA (after HP HRA brief).

EXAMINERS NOTE: The candidate may state a HOT SPOT posting is necessary. This is acceptable per HPP-20 step 6.6.3 stating that the component should be posted, therefore is not part of the CRITICAL nature of this step.

COMMENTS:

STEP 2: Determines the posting for Charging pump room 1 B is expected to be CRITICAL Radiation Area and Contaminated Area STEP STANDARD: RADIATION AREA AND CONTAMINATED AREA SAT EXAMINERS CUE: NONE COMMENTS: UNSAT STEP 3: Determines the posting for Charging pump room 1C is expected to be CRITICAL Radiation Area STEP STANDARD: RADIATION AREA SAT EXAMINERS CUE: NONE EXAMINERS NOTE: The candidate may state a HOT SPOT posting is UNSAT necessary, but this would be incorrect because this reading does not meet the criteria for a HOT SPOT.

However, this is not part of the CRITICAL nature of this step because HPP-20 step 6.6.3 states the HOT SPOT should be posted.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 4

STEP 4: Determines that Operations ROUTINE MAINTENANCE RWP will be CRITICAL sufficient for this tour. STEP STANDARD: OPERATIONS ROUTINE MAINTENANCE RWP WILL BE SUFFICIENT SAT EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: RWP 09-0002 Task #2 allows entry into contaminated and HRA (after HP brief) as long as RWP dosimetry alarm limits are not exceeded.

COMMENTS:

STOP TIME:

ST. LUCTE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 5

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task and the cue sheet that I provided to you.

Initial Conditions You are an extra Unit 1 Reactor Operator. All three Charging Pumps have been identified as having an issue with the motor. You have been assigned to perform an inspection tour of all three Charging Pumps.

Initiating Cue Evaluate the attached survey map for the areas you will be touring, the ROUTINE MAINTENANCE RWP, and determine:

3. The expected required postings for charging pump rooms IA, 1 B & 1 C.
1. Whether the Operations Routine Maintenance RWP can be used for this tour.

ST. LIJCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 6

FLORIDA POWER & LIGHT - PSL HPS-7 LOCATION: CHARGING PUMPS EL. -.5 FT.-

GRAVE DANGER VERY HIGH RAD AREA (C) CONTAMINATEDAREA DATE 81509 (P) HOT IARTICLE AREA (L) LOCKED HIGH RAI) AREA TIME: u (H) HIGH RAD AREA (S) SPECIFICS RWP REQUIRED RPT PRINT J. Swift (R) RAI)L.vrIoN AREA (B) lII COVERAGE REQUIREI)

RPT SIGNATURE:___________ lI I.Y AREA RWP /U lI)iLGHLY(ONIAMINVIEI) AREA jUL MDA dpm INSTRUMENT TYPE / ft R020/3603 INSTRUMENT TYPE / ft 1 dm Hot Part INSTRUMENT TYPE/ft L-177/21829 INSTRUMENT TYPE/ft No orohearea YN ii/_ci. SNIEARSIN IWM /100 CM2 N/A N/A 1 <1K 7 6 <1K/ ii <1K/ 16 N/A/ 21 N/A/ 26 N/A/ 13 N/A N/A 27 N/A / C N/A N/A 2 <1K / 7 1.9K / 12 <1K7 17 N/A/ 22 N/A/

N/A N/A

/ 1.5K/ <1K/ N/A/

3 <1K 8 13 [8 N/A/ 23 N/A/ 28

<1K / 1.1K / <1K/ N/A/ N/A/ N/A /

4 9 14 9 24 29 F N/A N/A

/ N/A N/A/ N/A /

5 <1 K j <1 K/

15 / 20 25 N/A/ G N/A N/A LEGENIT Geneta( Area Dose Rates Reviewed By:

  • (Soritact Dose Rate Q smear Location B. Gold .1JJe 8-15-04 A Neution Doce Rate intent;I It DDE)

PrInt Name SIgnature Date E Bela Radiation in rnRudiIIi Radiation / (ontanti riated I3ciundry Charging Pump Room A Charging Pump Room B Charging Pump Room C S I OPS DATE Exposure Received Completing Survey:___________ mrern, I)OCT SURVEY REMARKS: DOCN HPS-7 SYS 1-IP COM P ITM

This Page Intentionally left blank ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-4 PAGE 8

REVISION NO.: PROCEDURE TITLE: PAGE:

28 AREA RADIATION AND CONTAMINATION 1 0f 37 PROCEDURE NO SURVEYS HPP-20 ST LUCIE PLANT 6.1 General (continued)

3. Record information on survey maps and forms as soon as practical. Survey nomenclature on maps and forms should be as follows:

A. Num ers reiienting mrem/hr general area dose rate are underlined for gamma, boxed for beta, within a triangle for neutron.

B. Numbers representing mrem/hr contact dose rate are indicated by an asterisk or star next to numbers underlined, boxed or within a triangle, as appropriate.

C. Levels of removable contamination in dpm/1 00cm 2 should be indicated by circled numbers for smear locations.

D. Units of Rem/hr or additional pertinent nomenclature shall be clearly td

4. Postings and updating should be noted on the survey maps and forms before the maps are approved. Outdoor postings should be checked for proper colors and fading due to sun.
5. Personnel performing surveys are responsible for:

A. Initiating radiological controls as indicated by the survey results.

B. Completing and signing the survey forms prior to the end of the shift, if time permits. -

re C. Routing th h Physics Shift Supervisor for review and appro ,çI 0 4

b M D. Placing thc 7 npleted surveys box during non-outage opc U. k17 E. Notifying t ..,visor when changes to postings were made.

6. A Health Physics Shift Supervisor is responsible for reviewing and approving the adequacy of completed survey forms.

A. Copies of approved surveys shall be available for plant personnel to review prior to entering the RCA.

END OF SECTION 6.1

REVISION NO.: PROCEDURE TITLE: PAGE:

28 AREA RADIATION AND CONTAMINATION 17 0 f 37 PROCEDURE NO.: SURVEYS HPP-20 ST. LUCIE PLANT 6.6 Requirements Based on Survey Results

1. Radiation Areas A. §1,3 Any area, accessible to individuals, in which radiation levels could resu I receiving a dose equivalent in excess o mr I hou at 12 inches (30 cm) from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, RADIATION AREA.

B. §1,2,3 Any area, accessible to individuals, in which radiation levels could resuJUnanjndjvjj _receia,ir9_ajise equivalent in excess o 00 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at che 0 cm) from the radiation sourc oF?F6Th any u ace that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, HIGH RADIATION AREA, SPECIFIC RWP REQUIRED. Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.

C. Any area, accessible to individuals, in which radiation levels could resuJ aR-indiALidIIjjyPiVing dpse egujyant in excess of ,000 m in 1 hrur at 12 inches (30 gfrom the radiation sou or from any surfaciThat the raiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, LOCKED HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED. Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.

D. §1,2,3 Any area, accessible to individuals, in which radiation levels ul n indivi eiving an absorbed dose in xcess for 50 s in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at meter from the radiation so ce any su e radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, GRAVE DANGER, VERY HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED. Additionally, the area shall have access control requirements established in accordance with 10 CFR 20.

2. Surveys, postings and placards are not required in overhead areas, unless made accessible by ladders or scaffolding.

REVISION NO.: PROCEDURE TITLE: PAGE; 28 AREA RADIATION AND CONTAMINATION PROCEDURENO.: SURVEYS *8 f 37 HPP-20 ST. LUCIE PLANT 6.6 Requirements Based on Survey Results (continued)

NOTE

  • ¶5,8 Hot Spot stickers shall not be stuck directly on stainless steel components. Some adhesives contain halogens (i.e., chlorides) that may degrade the component. Alternate means of Hot Spot postings are to be utilized to identify Hot Spots. The recommended method is to affix the Hot Spot sticker to a yellow plastic CAUTION sign attached to the component with Rad rope or ribbon.
  • Hot Spots need be identifIed for areas ! routinely accessed or for areas accessed only during outages, unless otherwise directed by RP Supervision.

(__;---- ---------

3. § A component or item having a contact reading greater than 100 mrem/hr and more than 5 times the general area radiation levels (i.e. 30 cm from contact) should be posted as a HOT SPOT. The Hot Spot Log updated monthly upon completion of the comPrehe_,,d
4. § The boundary o the Radiation Controlled Area 5Wmaintained at less than 2 mrem/hr. If the radiation levels outside the RCA are found to be greater than 2 mrem/hr, barricade and post the area and take action to reduce the radiation levels to less than 2 mrem/hr.
5. Contamination A. §3 Any area containing removable surface contamination in excess of 1000 dpm/lOOcm 2 beta/gamma or 20 dpm/lOOcm 2 alpha shall be posted as a Contaminated Area.

B. Any area containing remi1WUriace conraminatioTh excess of 100,000 2 beta / gamma should be posted as a Highly Contaminated dpm/lOOcm Area.

C. Exits from contaminated areas require as a minimum, a single step-off pad placed on the CLEAN side of the access point for the area.

D. Areas in which contamination exists over a major portion of the area in excess of 100,000 dpm/lOOcm 2 may require a double step-off pad.

E. Replace step-off pads between areas of higher and lower contamination levels at a frequency determined by contamination surveys.

F. Restricted areas established in the controlled area shall be surveyed and posted in accordance with the requirements of 6.6.1 above.

END OF SECTION 6.6

St. Lucie Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT RWP

Title:

Radiation Protection, Nuclear Operations, Security, Chemistry: Entry Jnt RWP No.: 09-0002 Rev. 02 The Radiation Controlled Area and Reactor Auxiliary Bldg.

1.16 Task: ROUTINE MAINTENANCE

(!!!(!

Comments: Unit I & 2 RAB I RCA RWP Type: JOB ROUTINE RWP Status: BeEin Date: Close On Date:

ACTIVE 3/412009 Prepared By: Job Supervisor:

ALARA ID: Stay Time Alarm(hh:mm):

Estlinatéd Dose: 4,201 mrem Estimated Hours: 246,556.00 Chirp Rate:

Actual Dose: 2,630 mrem Actual Hours: 140,822.08 Buildlngs J Elevations Rooms Jnit I & 2 RAB I RCA 1l Areas ALL AREAS

)escrlptlon (alue !il General Area Contamination Levels <1K G/A dpm /100 cm2 General Area Gamma Level <1 G/A mREM/HR Task Description Status 1 RP Dept: Job Coverage, Surveys, Inspections. Source Check / Calibrate Survey Instr. Active 2 Operations Dept: Clearances, Tags, Surveillances and Inspections. Active 3 Security: Walkdowns, Inspections, Patrols. Active 4 Chemistry Dept: Sampling and Analysis. Active 5 Operations Dept (Trainees): Clearances, Tags, Surveillances and Inspections. Active 6 RP Dept (Trainees) Active 7 Chemistry De t (Trainees) 4ctive Requirement Groups Requirement Descriptions N/A V

Instructions I:

Instructions 2:

Instructions 3:

Anorover Title SUPERVISOR SEXTON, ALAN B 03/06/2009 N/A 10/29/2009 1:36:55PM Page 1 of I

St. Lucle Nuclear Power Plant FPL St. Lucie RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 09-0002 02 Task Descriotlon; RP Dept: Job Coverage, Surveys, Inspections. Source Check / Task Status: Active Calibrate Survey Instr.

1.16 Task; ROUTINE MAINTENANCE ALABA ID: Stay Time AIarm(hh:mm: 16:00 Estimate Dose; 1,928.00 Estimate Hours: 53,205.00 Chlro Rate:

Hi-Rad: Yes Hot Particle: Yes Locked HI-Rad: No Hi-Contamination; Yes Low Gamma Dose (mrem) Low Gamma Rate (mrem/hr) HIh Gamma Dose (mrem) HIh Gamma Rate (mrem/hr) 12,00 300.00 Low Beta Dose Low Beta Dose HIh Beta Dose H12h Beta Rate Low Neutron Dose. Low Neutron Dose H12h Neutron Dose HIh Neutron Rate a

Requirement Groups Requirement Descriptions DOSIMETRY PAM) Required to be worn in NRAs. ..

GENERAL INSTRUCTIONS tefer to HPP- 15 for hot particle area work. W/B scan with RO-2 or equivalent (open vindow) shall be done at 2 hr intervals when in HPAs. Use HPP-3.3 form.

)bserve & obey ALL RP postings & verbal instructions. Utilize low dose waiting areas.

PROTECTIVE CLOTHING P will determine PC re uirements based on radiological conditions in work areas.

InstructIons 1: This RWP is to be used for routine shift work including source check and calibration of survey instrumentation.

  • pJJs shall provide their own surveys, radiological job coverage. *Utilize RP procedures to provide radiological coverage. Contact RPSS to obtain appropriate procedures. Contact RPSS to discuss / resolve issues as needed.

InstructIons 2: *Sign in and out on Form HPP-30. 14 while working with Neutron sources.

InstructIons 3: ALARA HOLDPOINTS: In case of an EPL) alarm leave area immediately and report to RP at RCA control point.

are authorized to enter a NRA but are not to exceed the RWP EPD dose rate setpolnt of 300 mrem/hr.

N/A V I 0t29t2009 1:37:02PM Page 7 of 7

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT A-5 This JPM is TIME CRITICAL (portions)

This is a NON-FAULTED JPM

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT KA Statement: 2.4.28 Knowledge of procedures relating to security event (non safeguards information)

KA#: 3.2/4.1

References:

ONP-72.O1, Response to Security Events EPIP-Ol, Classification of Emergencies EPIP-02, Duties and Responsibilities of the Emergency Coordinator EPIP-08, Off-Site Notifications and Protective Action Recommendations Candidate:

Name Validation Time: 20 minutes StartTime:

Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 2

NRC ADM JPM A5 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at 0815, you as the Shift Manager, receives a validated NRC Headquarters phone call to report an Airborne Threat.

The estimated time to site arrival is 0855.

A track of interest is verified by the NRC due to anomalous flight activity. The Airborne Threat has been validated with the NRC Headquarters Operations Center.

Initiating Cue The Unit 2 Unit Supervisor directs you the Shift Manager to:

1. Perform Step 6.0.4 in accordance with ONP-72.01, Response to Security Events
  • For any required documentation of time, use current clock time.

Portions of this JPM are time critical ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 3

NRC ADM JPM A-5 START TIME:

ONP-72.O1, Response to Security Events STEP 1 (6.0.4): IMPLEMENT Security Checklist in accordance with EPIP-02, Duties and SAT Responsibilities of the Emergency Coordinator.

STANDARD: Refers to EPIP-02. Duties and Responsibilities of the Emergency UNSAT Coordinator Security Checklist.

EXAMINERS CUE: NONE EXAMINERS NOTE: Start time for time critical step____________

COMMENTS:

EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 2 (5.2.1.C): Determine Threat SAT Informational Airborne Threat (greater than 30 minutes)

Verify the Control Rooms are implementing ONP-72.01, Appendix D. UNSAT

  • Unit 1
  • Unit 2 STANDARD: Informs the Control Rooms to implement ONP-72,01 Appendix D EXAMINERS CUE: Control Rooms have been notified COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 4

NRC ADM JPM A-5 NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is not required. SAT STEP 3 (5.2.2): Off Site Notifications UNSAT A. Make an accelerated notification to the NRC in accordance with EPIP 08, Off-site Notifications and Protective Action Recommendations.

STANDARD: Determines from cue threat has been validated and NRC notification NOT required.

EXAMINERS CUE: NONE COMMENTS:

STEP 4 (5.2.2): Off Site Notifications and Protective Action Recommendations B. Airborne Threat Make an abbreviated State Notification in

- SAT accordance with EPIP-08.

STANDARD: Refers to EPIP-08 and commences filling out the State Notification form. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: If asked for shift communicator, state the shift communicator is not available at this time.

COMM ENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 5

NRC ADM JPM A-5 EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM SAT STEP 5(1): If Security Event, Then go to Step 3.A.1.a NRC Notification or N/A.

UNSAT STANDARD: Determines step is N/A due to validation of threat as per cue.

EXAMINERS CUE: NONE EXAMINERS NOTE: A potential exists for the candidate to make an accelerated NRC phone call. Step 3.A.1 .b will direct the candidate to the next step.

COMMENTS:

STEP 6 (2): State Watch Office Notification CRITICAL STEP A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).

SAT 1 Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:

  • Lines 1 through 6 UNSAT
  • Line 11 STANDARD:

EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 6

NRC ADM JPM A-5 ATTACHMENT I FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM SAT STEP 7 (Line 1):

l. A. LJTHISISADRILL B. []THISISANEMERGENCY UNSAT STANDARD: Checks A EXAMINERS CUE: NONE EXAMINERS NOTE: Per EPIP-08, Attachment IA step 1, drill, exercises or tests, each message shall be checked this is a drill COMMENTS:

STEP 8 (Line 2): CRITICAL STEP

2. A. Date II B, Ci1ct Tine. C. Reputed by (Nanie D. Message Nunber: E. Reputed fron: Cotrd Rn Lisc EOF SAT F IiliaI / Ne CI8ssiflceti1 OR Updt8 roation UNSAT STANDARD: A. Todays Date B. Time contact made left blank at this time C. Applicants name D. Message # I E. Control Room F. Initial / New Classification EXAMINERS CUE: NONE EXAMINERS NOTE: Part B Contact time must be within 15 minutes of the emergency classification time EXAMINERS NOTE: Contact time shall be filled in when contact is made with the state. This is noted in Step 17.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 7

NRC ADM JPM A-5 STEP 9 (Line 3): CRITICAL STEP 3 Sta: A. Crystal River Ult 3 St Lucie Urt 1 C Q St. Lube Ut 2 D. Q Turkey Point Unit 3 E. 0 Turkey Point Unit 4 SAT STANDARD: C, St. Lucie Unit 2 (St. Lucie Unit 1 is acceptable, but not both) UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: EPIP Attachment IA step 3 requires only one affected unit be selected (either one can be selected but not both).

COMMENTS:

STEP 10 (Line 4): CRITICAL STEP 4* &nc Classif cation: A. Notification of Unusual Event 8 C, C Site kea Eergericy D, Q General Emergency SAT STANDARD: A, Unusual Event UNSAT EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 8

NRC ADM JPM A-5 STEP 11 (Line 5): TIME CRITICAL STEP 5* k ErqcyLdara5o: B, Ecy rmili: nate ii SAT STANDARD: A, Emergency Declaration, current date and time UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: This is the time emergency declaration is made.

EXAMINERS NOTE: STOP TIME for Time Critical Action This time must less than 15 minutes from the time in step 1. Also START TIME for second critical time.

COMMENTS:

STEP 12 (Line 6): CRITICAL STEP 6,* A. EAL OR .

Jesrpt:

SAT STANDARD: A. EAL Number 21 .A (Validated notification from NRC providing information of an aircraft threat). UNSAT EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 9

NRC ADM JPM A-5 STEP 13 (Line 11): CRITICAL STEP 11, UTILITY PROTECTIVE ACTION RECOMMENUATIONS FOR THE PUBUC:

A. El No utility recommended actions at this time. SAT B. El The utility recommends the folling prective actis:

Evacuate Sectors Shelter Sectors No Action Sectos UNSAT Evacuate Zones. OR 0 2 Shelter Zones: 2 5 510 AND consider issuance of potassium iodide (KI STANDARD: A. No utility protective action recommendations for the public.

EXAMINERS CUE: NONE COMMENTS:

EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM SAT STEP 14 (Appendix A, 2.A.2): State Watch Office Notification A. Prepare the Florida Nuclear Plant Emergency Notification Form UNSAT (form similar to Attachment 1).

2. All other Security and Non-Security Events Prepare the State Notification Form in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

STANDARD: Determines this step is N/A EXAMINERS CUE: NONE COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 10

NRC ADM JPM A-5 EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A CRITICAL NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP STEP 15 (A 2.B): Emergency Coordinator (EC) approval.

ATTACHMENT I FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM SAT (Line 15) 15, Date ii Iinie: UNSAT Message Received By. tarne:________________________________ Date. I / Thie:

STANDARD: Documents approval including date and time.

EXAMINERS CUE: NONE COMMENTS:

EPIP-08, Off-Site Notifications and Protective Action Recommendations Appendix A CRITICAL NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP STEP 16 (A 2.C): Using the State HOT RINGDOWN PHONE, dial 100 SAT STANDARD: Dials 100 on the State HOT RINGDOWN PHONE.

UNSAT EXAMINERS CUE: 100 has been dialed, the state watch office picks up the phone.

COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 11

NRC ADM JPM A-5 STEP 17 (A.2.D): TIME Hold down the button on the handset while talking. This must be CRITICAL done each time you talk. Release the button in order to listen. STEP When the State Duty Officer answers, announce:

This is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)] with an SAT emergency message. Contact Time is I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy. UNSAT STANDARD: Communicates message. States the contact time as the current time.

EXAMINERS CUE: Answer as the State Watch Office EXAMINERS NOTE: Contact time above is Stop time for time critical step. This time must be less than 15 minutes from the time listed in step 11.

EXAMINERS NOTE: Upon completion of communication, terminate the task.

COMMENTS:

END OF TASK ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 12

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at 0815, you as the Shift Manager, receives a validated NRC Headquarters phone call to report an Airborne Threat.

The estimated time to site arrival is 0855.

A track of interest is verified by the NRC due to anomalous flight activity. The Airborne Threat has been validated with the NRC Headquarters Operations Center.

Initiating Cue The Unit 2 Unit Supervisor directs you the Shift Manager to:

1. Perform Step 6.0.4 in accordance with ONP-72.01, Response to Security Events
  • For any required documentation of time, use current clock time.

Portions of this JPM are time critical ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM A-5 PAGE 13

ATTACHMENT 1 14-9 J%

FLORIDA NUCLEAR PLANT EMERGENCY NoTIF1CAtON FORM (Page 1 of 1)

On4ine Venfication: Q SWPIDEM C DOHJBC C St. Lucie County/Ft. Pierce C Marlin County

1. A. H 4 ISISADRILL B. C THIS IS AN EMERGENCY
2. A. Date B.
  • Contact Time: C. Reported by (Name) (Jrcti C 4

(Yk3 D. Message Number E. Reportedfrom: ntroIRoocn CTSC DEOF F. 1nitlaI! New Glassiflcallon OR [1 Update Notification Ie1c 1I U,

  • k 3 Site: A. D CystaI River UnIt 3 B. St. Lucia Unit 1 C. Lucia Unit 2

/ 0- 2 4

LJA11

0. D Turfcey Point Unit 3 E. Q Turfey Point Unit 4 Nor z3ai.

4, Emergency Classification: A. t6 ltlcatlon of Unusual Event 8. DAlert C. C Site Area Emergency 0. Q General Emergency 5.. A. Emeroencv Declaration: B. [] Erneroencv Termination: Date: / I Time:

6. Reason for Emercency Declaration: A. BEAL Number C

/

2 4 OR B. C

Description:

7. Additional Information or ljodate: A. Q None OR B. Q

Description:

$ Weather Data: A. Wind direction from degrees B. Downwind Sectors Affected:

9. Release Status: A. DNone(Gotoltemll) B. Din progress C. QHasoccurred,butstopped(Gotoltem.11)
10. Release Significance Catecrory (at the Site Boundary):

Under evaluation.

B.Q Release within normal operating limits ( 3.5 E-1 Cl/sec noble gas, 4.6 E*5 Cl/sec iodIne)

C.D Non.Slgnificant Fraction of PAG Range (release Is> normal limits and <500 mrem TEDE and 1000 mrem CDE)

D.C PAG Range ( 500 mrem TEDE or 1000 mrem CDE)

E.D Uquld release (no actions required)

11. UTILITY PROTECTIVE ACTION RECOMMENDATIONS FOR THE PUBLIC:

A. No utility recommended actions at this time.

B. Q The utility recommends the following protective actions:

Evacuate Sectors Shelter Sectors No Action Sectors Evacuate Zones: OR 0.- 2 Shelter Zones: 2 5 510 AND consider Issuance of potassium Iodide (Kl)

If form is completed In the Control Room, go to Item 15. If completed in the TSC or EOF, Continue with Item 12.

12. Plant Conditions: A. Reactor Shutdown? Q Yes Q No B. Core Adequately Cooled? C Yes C No C. Containment Intact? []Yes Q No 0. Core Condition: I] Stable [)Degrading
13. WeaTher Data: A.
  • Wind Speed mph B. Stability Class
14. Additional Release Information: A. Q N/A OR Read this statement I hour pro)ected doses as follows:

Distance Projected Thyroid Dose (CDE) for 1 Hour Prolected Total Dose (TEDE) for 1 Hour 1 MIle (Site Boundary) B. mrem 2 MIles 0.

mrem E. mrnm 5 Miles F. mrem __ mrem 10 Miles H. mrem mrnn,

15. (Do Not Read) EC or RM Approval Signature: Time:

Messaoe Received Bv Name:______________________________ Time:

Items are evaluated for NRC Performance IndIcators (P1s)

Form PSL-F070 EPIP-08, Off-Site Notifications and Protective Action Recommendations Approval Date: 05/15/09

EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFP-1 REVISION NO.: PROCEDURE TITLE: PAE*

RESPONSE TO SECURITY EVENTS of 27 PROCEDURE NO.:

ONP-72.01 ST. LUCIE PLANT 6.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

1. VALIDATE the authenticity of any Airborne Threat by calling NRC Headquarters Operations Center. USE the NRC ENS telephone or a commercial line to call 301-816-5100.
2. If any of the following conditions exist:
  • Security Department reports ARMED intruders are within the Protected Area fence.
  • IMMINENT Aircraft Threat (less than 5 minutes arrival time).
  • An Aircraft has impacted inside the Protected Area Fence.

Then PERFORM the following:

A. TRIP Unit 1 Reactor.

B. TRIP Unit 2 Reactor.

C. DON headset attached to Control Room Security hotline phone.

3. if the Aircraft has impacted the plant site, Then REFER TO EDMG-01, Guideline for Responding to Large Area Fire or Explosion Involving Multiple Fire Zones, AND EDMG-02, Major Loss of Plant Control Systems Initial Response.

4.) IMPLEMENT Security Checklist in J accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

5. jf the Security Event is a LAND BASED Threat, Then GO TO Appendix A, Response to LAND BASED Threat.

EXEMPT FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR §2.390

REVISION NO.: PROCEDURE TITLE: PAGE; 28 DUTIES AND RESPONSIBILITIES OF THE 15 of 47 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 52 Security Checklist INITIAL Date: I /

NOTE is This to be used for Actual Events or Credible Threats.

1. Determine Threat CAUTION
  • Plant page announcements must take in to account the current conditions (e.g., severe weather). Ensure the E-Plan announcements do NOT conflict with Security-related announcements.
  • Movement of plant personnel, including site evacuation, must take into account the current conditions and safety of personnel.

NOTE The Operations Shift Manager Selects the personnel required to remain in the Control Room in order to perform the actions of this procedure.

A. Imminent Airborne Threat (less than 5 minutes)

1. Verify the Control Rooms are implementing ONP-72.01, Appendix B.
  • Uniti
  • Unit2 B. Probable Airborne Threat (5 to 30 minutes)
1. Verify the Control Rooms are implementing ONP-72.O1, Appendix C.
  • Uniti
  • Unit2 Informational Airborne Threat (greater than 30 minutes)

I. Verify the Control Rooms are implementing ONP-72.01, Appendix D.

  • Uniti
  • Unit2

rEVISION NO.: PROCEDURE TITLE: PAGE; 28 DUTIES AND RESPONSIBILITIES OF THE 16 ° f 7 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.2 Security Checklist (continued) INITIAL

1. (continued)

D. Land-Based Threat

1. Verify the Control Rooms are implementing ONP-72.O1, Appendix A.
  • Uniti
  • Unit2

((3) Off-Site Notifications NOTE If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is required.

A. §2 Make an accelerated notification to the NRC in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.

B. Airborne Threat Make an abbreviated State Notification in accordance with EPIP-08.

3. ERO Activation NOTE The PSL Conference Bridge can be used to communicate with the ERO at an alternate location. Refer to the PSL Emergency Response Directory (ERD) for the phone number and password.

A. Normal business hours -

1. Delay activation of the Emergency Response Facilities or direct ERO personnel to an alternate location.
2. Request off-site responders to go to EOF I alternate facility per EPIP-03, Attachment 4.

B. Off-normal hours based on site accessibility, consider directing ERO personnel to report to the EOF or alternate location.

REVISION NO.: PROCEDURE TITLE: PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE of 56 PROCEDURE NO.: ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 1 of 6)

INITIAL CAUTION

  • § Notification of State and local agencies shall be made as soon as practicable within 15 minutes of declaration of an Emergency Class.

. ¶ A new Florida Nuclear Plant Emergency NotificaUon Form shall be completed for all updates.

NOTE

¶ 1. Completion of this checklist requires the following Attachments (all from EPIP-08):

Attachment I Florida Nuclear Plant Emergency Notification Form Attachment 1A Directions for Completing the Florida Nuclear Plant Emergency Notification Form Attachment 2 Determination of Protective Action Recommendations (PARs)

Attachment 3 NRC Reactor Plant Event Notification Worksheet Attachment 3A Directions for Completing the NRC Reactor Plant Event Notification Worksheet

2. Checklist Part 1 is for State Watch Office notification.
3. Checklist Part 2 is for NRC notification.
4. Completion of this Appendix (A) may be delegated to the Shift Communicator.

if Security Event, Then go to Step 3.A.1 .a NRC Notification or N/A.

ui 2) State Watch Office Notification A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).

Airborne Threat Abbreviated State Notification Prepare State Notification Form by filling out the following:

  • Lines I through 6

REVISION NO.: PROCEDURE TITLE: PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE 2 0 of 56 PROCEDURE NO.: ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 2 of 6)

2. (continued) INITIAL All other Security and Non-Security Events Prepare the State Notification Form in accordance with Attachment IA, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

Emergency Coordinator (EC) approval.

NOTE Primary notification method to the State Watch Office (SWO) is to use the Hot Ring Down (HRD) phone.

2. If the HRD is out-of-service, alternate notification methods are provided in Section E, below.

C. Using the State HOT RING DOWN (HRD) Phone, dial 100.

D. Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen.

When the State Duty Officer answers, announce:

This is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)] with an emergency message. Contact Time is am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy.

Allow the Duty Officer to contact St. Lucie County, Martin County and the Bureau of Radiation Control prior to transmitting the information from the notification form. When the parties are on line, provide the information slowly (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

1. ¶15,17 All four off-site agencies have been notified:

A. Florida Department of Emergency Management (DEM)

B. Florida Department of Health, Bureau of Radiation Control (DOH / BRC)

C. St. Lucie County Department of Public Safety / Ft.

Pierce Control D. Martin County Department of Emergency Services

REVISION NO.: PROCEDURE TITLE: PAGE; 20 OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.: ACTION RECOMMENDATIONS *38 ° f EPIP-08 ST. LUCIE PLANT

¶6 ATTACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 8)

ITEM ENTRY On-line Verification Check the appropriate boxes as the State Watch Office Florida Division of Emergency Management (DEM) requests that the Department of Health Bureau of Radiation Control, St. Lucie County Department of Public Safety and the Martin County Department of Emergency Management get on the line, prior to initiating the notification. All four agencies must be notified (includes Florida OEM) through tje SWO or alternate means.

Check appropriate box for drill or actual emergency as the case may be. During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.

2A. Enter todays date.

28. Enter the time (using the official time, normally synchronized with ERDADS) when contact is made with the State Watch Office. For initial notification of classification, this shall be within 15 minutes of the Emergency Declaration time in item 5, 2C. Enter the name of the person making the notification call.

2D. Enter the message number beginning with #1 and following sequentially in all facilities (e.g., if the Control Room transmitted two messages the TSC would start with #3).

2E. Check the box for the facility from which the notification is being made.

2F. Check the box for Initial I New Classification or Update Notification.

Site Check the affected site I unit. Do not check more than one unit. For dual unit events such as the approach of a hurricane or loss of off-site power, the fact that the other unit is affected by the condition should be stated in the Additional Information or Update section.

4. Emergency Classification Check the box corresponding to current accident classification declared.

REVISION NO.: PROCEDURE TITLE: PAGE 20 OFF-SITE NOTIFICATIONS AND PROTECTIVE 39 °f 6 PROCEDURE NO.: ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT AT1ACHMENT IA DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 2 of 8)

NOTE When opening and closing an event in one notification:

  • On line 5, both box A and box B apply
  • Date(s) and times of declaration and termination are to be indicated
5. Emergency Declaration or Emergency Termination Enter the date and time when the current emergency classification was (A) declared OR (B) terminated.
6. Reason for Emergency Declaration A. Enter the Emergency Action Level (EAL) number as given in EPIP-Ol Attachment 2, EAL Descriptions for Florida Nuclear Plant Emergency Notification Form (St. Lucie Nuclear Plant).

OR B. Enter wording like that found in the EAL information in EPIP-Ol, Classification Of Emergencies. Wording should be brief yet descriptive enough for the off-site agencies to gain an understanding of the event. It should be clear from the incident description which EAL has necessitated the emergency declaration. Wording should be as non-technical as possible with no acronyms or abbreviations. This information should remain the same throughout update messages, unless there is a classification change.

7. Additional Information or Update Check A (None) if there is no information or B to provide additional information/clarification or reason for the update, for example:
  • A condition is occurring/occurred that would otherwise have resulted in the declaration of the same or lesser emergency classification.
  • Identify that both units are affected by the condition, e.g., due to a loss of off-site power or hurricane warning, etc.
  • Change Protective Action Recommendations (PARs)
  • Change in radiological conditions
  • Change in equipment status
  • Injuries
  • Termination of event

REVISION NO.: PROCEDURE TITLE: PAGE:

20 OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.: ACTION RECOMMENDATIONS 6 of 56 EPIP-08 ST. LUCIE PLANT 5.1 State and County Notification (continued)

3. B. (continued)
2. if one Unit is in a classified event and the other Unit enters into a more severe event in which a higher Emergency Class would apply, Then a new classification shall be declared and promptly, within the regulatory time limits, issued to the State, Counties and the NRC.

Abbreviated Notification Due to an Airborne Threat NOTE Concurrence for use of an abbreviated notification in response to an on-site airborne threat situation has been obtained from State and county officials.

If the site is under a potential or actual airborne threat, Then complete lines I through 6 and line II of the State Notification Form, obtain approval from the Emergency Coordinator or Recovery Manager and transmit the abbreviated notification to the State Watch Office.

END OF SECTION 5.1

REVISION NO.; JPROCEDURE TITLE; PAGE:

16 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

¶1 0 f 39 EPIP-Ol ST. LUCIE PLANT NOTE

  • Initiating Conditions / Emergency Action Levels are applicable to ill modes unless otherwise indicated.
  • The Emergency Coordinator should not wait until the applicable time (as stated in the Initiating Condition / Emergency Action Level) has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

5.2 Classifying the Event

1. ¶ A goal of fifteen (15) minutes should be used for assessing and classifying an emergency once indications (Emergency Action Levels (EAL5)) are available to Control Room Operators that an Initiating Condition (IC) has been met and/or exceeded.

This goal should allow time for determination of indications (leak rate, etc.) and detailed review of Attachment 1, Emergency Classification Table.

1. ¶a For EALs that are time-based, a prescribed assessment period is provided. It is to be acknowledged that the condition described in the EAL has been met if the stated time period has elapsed.

There is not an additional 15 minute assessment period.

Example EALs:

No main or auxiliary feedwater flow available for greater than 15 minutes when required for heat removal and Steam Generator levels are less than 40% wide range OR Uncontrolled fire within the Power Block lasting more than 10 minutes OR LOCA with initially successful ECCS and subsequent failure of containment heat removal systems for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

0 PPL UNIT 2 CYCLE 17, 300 PPM MTC TEST, February 25, 2009 Moderator Temperature Coefficient Determination - Infrequently Performed Test - Brief

1. Purpose of Test: The 300 ppm MTC test fulfills Technical Specification surveillance requirement 4.1.1.4.2.c. Determine the MTC is within the required limits At any Thermal Power, within 7 EFPD after reaching a Rated Thermal Power equilibrium boron concentration of 300 ppm. The MTC test is normally performed at lOO% rated thermal power. The Cycle 17 300 ppm MTC design predictions are for lOO%

rated thermal power. Power is allowed to drift slightly below 100% (99.5% by highest indication) just prior to the test to prevent exceeding 100% avg. AT power during the testing.

The acceptance criteria for the test results are as follows:

a. Less positive than +5 pcm/F at less than or equal to 70% of RATED THERMAL POWER,
b. Less positive than a linear ramp from +5 pcm/F at 70% of RATED THERMAL POWER to 0 pcm/F at 100% RATED THERMAL POWER, and
c. Less negative than 32 pcm/F (COLR limit) at RATED THERMAL POWER
d. With the MTC outside any of the above limits, be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2. Governing Procedure: This test is performed in accordance with specific instructions provided in Operating Procedure 3200051, At Power Determination of Moderator Temperature Coefficient and Power Coefficient.
3. Special Conditions: In accordance with OP 3200051, the requirements of Specification 3.1.3.6 (Regulating CEA Insertion Limits) will be suspended during the performance of the test.
4. Management Designee:
5. Test Specialist: Walter Mead
6. Expected Plant Response: (Cool-down cycle procedural limits) Generator output is increased initially by 20 to 50 MWe (approximately 30 Mwe is recommended) which in turn cools the RCS by approximately 2 to 5 degrees respectively (2 to 3 degrees is recommended). The RCS cool-down increases neutron moderation, as the thermal neutron population increases so does fissioning and reactor power increases.

The AT power will be prevented from increasing by inserting the Lead Bank 5. (Heat-up cycle) The generator output will then be decreased by the same amount it was previously increased and the RCS allowed to return to the initial Tavg value. AT power will decrease unless the Lead Bank 5 is withdrawn to its initial position. Data is taken prior to the cool-down, at the end of the cool-down and at the end of the heat-up. The cycle is repeated if additional data is required. MTC is predicted to be 20.16 pcm/°F.

7. Criteria for Test Termination: SM discretion, Crew discretion, dropped rod, DEH problems, RPS or NI problems, Linear Heat Rate alarms, Unexplained reactivity excursion, or other plant transients requiring operator attention for control. Misaligned or dropped rods will be addressed by the CEA OffNormal procedure.
8. Expected duration of the Test: Approximately two to three hours with two to three hours additional for data reduction/analysis.
9. Review Attachment 1 checklist of ADM-09. 12.
10. Post-Test: Rod recovery and ASI guidelines following the MTC test is covered by a separate memo issued at the successful completion of the MTC test and data reduction.

0 PL RE/PSL-09-003 To: SM/Night Orders Date: February 18, 2009 From: D. M. Williams Department: Reactor Engineering

Subject:

UNIT 2, CYCLE 17, 300 PPM MTC TEST Assuming that Unit 2 continues fuN power operation, the 300 PPM MTC test is currently scheduled for Wednesday, 2125/09, at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />. Detailed guidance is provided below for the set up and performance of the upcoming MTC test.

To facilitate proper performance of the MTC test, please ensure the following preparations are completed prior to the execution of Operating Procedure 3200051, At Power Determination of Moderator Temperature Coefficient and Power Coefficient:

1. System should be notified that generator output may vary up to plus or minus 20 MWe during performance of the MTC test, which begins at 0900 on 2/25/09. The duration of the actual test is expected to be approximately 2-3 hours, with a further 2-3 hours for data analysis.
2. Due to the existing ASI swing and marginal ASI stability at this time in core life, CEA insertion should be closely controlled to ensure that an excessive and divergent ASI swing does not occur.

Consequently, the following insertion guidance is recommended.

3. Starling on Thursday, 2/19/09, begin slowly inserting the Lead Bank (using Manual Group Mode) toward 115 W/D, plus or minus 2. The insertion rate should not exceed one every hour.

CEA insertion should begin at a time in the current ASI swing when power is moving toward the top of the core (ASI trending more negative).

4. Operations should plot measured ASI hourly on graph paper provided by Reactor Engineering.
5. As the Lead Bank is inserted ASI will begin to diverge from the current Full Power ESI of -0.06 RPS units and move toward the bottom of the core as CEAs are inserted. Continue CEA insertion at a rate of one step per hour until ASI reaches approximately +0.30 RPS Units. Atthis point, stop CEA insertion and allow ASI to swing. It is estimated that Group 5 will be able to inserted to near 125 during this first phase.
6. After ASI has turned and is heading toward the top of the core, recommence CEA insertion when ASI reaches between +0.10 and 0 RPS units and is heading toward the top of the core (i.e.

more negative).

7. If the CEA target height of 115 +/- 2 has not be reached by the time that ASI has again reached approximately +0.30 RPS units, then stop CEA insertion and again allow ASI to swing. When ASI is approximately +0.20 RPS units and is heading for the top of the core, recommence CEA insertion to 115.

0 Lfl 8. The ESI for the MTC test is estimated to be approximately +0.30 RPS units.

9. Reactor Engineering will monitor the ASI trend and may recommend additional guidance as necessary, based on actual plant conditions.
10. As CEAs are inserted monitor linear heat rate continuously via the incore detector system.
11. Insertion of the Lead Bank from 135 to 115 will add approximately 100 pcm of negative reactivity, which must be compensated for by additional dilution to maintain constant power.

G:\eng\RENGJNE\MTC\UNIT2\U2 Cycle 1 7\300ppm\U2C 17 300 PPM Night Orders.doc

12. The Lead Bank will be allowed to soak at 115 withdrawn in order to establish equillbrium test conditions. If the resulting ASI swings are sufficiently large and are predicted to not dampen out prior to the test, RE will provide guidance for half cycle dampening.
13. RCS Chemistry evolutions that could cause changes in RCS boron concentration, such as de lithiation or ion exchanger evolutions, should not be performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the beginning of the MTC test.
14. Prior to performing the test at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on 2/25/09, reactor power as indicated by the highest instrument reading should be allowed to drift down to approximately 99.5 %.
15. During the performance of the MTC test the Lead Bank will be inserted and withdrawn from the 115 W/D test position. This will further vary the ASI in approximately 0.6 RPSU swings about the newly established MTC test ESI.
16. ADM-09. 12, Conduct of Infrequently Performed Tests or Evolutions at St. Lucie will be completed prior to performing the test.
17. Separate guidance will be provided for post-MTC test CEA recovery and ASI control.

D. M. MlIiams Reactor Engineering W. D. Mead /

Reactor Eriginenng Distribution: M. Hicks (OPS/PSL) Night Order Book R. Scalone (WC/PSL)

P. Searfoorce (WCIPSL) J. Connor(ENG/PSL) J. Klauck (OPSIPSL)

A. Day (CHEM/PSI) M. Bladek (OPSIPSL) D. Huey (WCIPSL)

Lfl r4 G:\eng\RENGINE\MTC\UNIT2\U2 Cycle I 7\300ppm\U2CI 7 300 PPM Night Orders.doc

ASI (RPSU)

I t ppp 9 p pppop

zzz:z:zL::: +/-.:z N

0 0

CD 0 -D 0 CI) 0

.[ 9 I

)

0 CD 0

0 0

N) 0 CD

> 0 Cl, 0 0

z:H: 0 C?)

C) 0

-c CO C,, 0 0

a N)

N) 0 CD 0

0 I a

N)

-o.

C (0

C 0

0  ::::::::: :z:z::::

N)

J::::::..::

C) 0 (0

- N) N) C)) C))

C (Ti C o 0 CEA (inches withdrawn)

0 0U 00 0 rni 6% io 00 ou 99 T 98 0 P 0 9 6% 60 9 60 9 6

00 0 8J 0 60 11 6% 0 90 iU 99 99 9 8% 6 6% LL 00 01 V 00 61 Z 6% 60 P 00 80 P 008 009 666

r
  • F

..j .. F

. 1005 Wed 03.00 Wed 03:53 Wed 12:01 Wed 14:00 Wed 16:09 Wed 1750 Wed 19:59 Wed 2200 flu 00:00 flu 01:59 flu 04:01 Thu 06:00 as

.j.:

29.

.: ,::i::::::::::::ziz::z.zzzzL ::::::::::::: 26 Wed 08:00 Wed 01:59 Wed 22:01 Wed 14:00 Wed 12:00 Wed 17:59 Wed 23:59 Wed 22,00 Thu 00:00 lIna 01:59 flu 04:01 Thu 09:00
  • 600

.600

...1, .---... .400 rn ..-..

j

.200

.000 3.

Wed 08:00 Wed 09:59 Wed 12:91 WCd 14:90 Wed 16:00 Wed 17,5) Wed 1959 Wed 22:00 Thu 00:00 Thu 01:53 Thu 04:01 Thu 06:00 291.

290.5 230.

2*9.5 a.. * . .

1*9.

Wed 08:00 Wed 09:59 Wed 12:01 Wed 14:00 Wed 16:00 Wed 17:53 Wed 13:53 Wed 22:00 ThU 00:09 Thu 91:59 Thu 04:01 140 130 j

12 110 Wed 08:00 Wed 0959 Wed 12:01 Wed 14:00 Wed 16:00 Wed 17:59 Wed 19:5* Wed 22:00 Thu 00:00 Thu flu 04:0) flu 08:00 Cose

Inter-Office Correspondence RE/PSL 09-005 TO: SM DATE: February 25, 2009 FROM: B. M. Wlliams DEPT: Reactor Engineering

SUBJECT:

UNIT 2, CYCLE 17, POST 300 ppm MTC TEST CEA RECOVERY AND AS! GUIDANCE

1. Well done to Operations for the good performance demonstrated during the MTC test.
2. The value of MTC, as determined by this test, is 20.49 pcm/°F. The predicted value for this boron concentration is 20.16 pcml°F. The extrapolated 0 ppm value of MTC is calculated to be -24.62 pcm/°F. This is a satisfactory result and fulfills the requirements of Technical Specification 3.1.1.4.
3. Reactor power may be returned to the nominal 100% power level.
4. Begin withdrawing the Lead Bank 5 CEAs slowly as permitted by current AS! control practices. The withdrawal rate of the lead group should be gradual, not exceeding 1 step per hourwhile maintaining reactor power at the desired level through RCS boration. As the lead bank is withdrawn, continuous monitoring of the linear heat rate shall be accomplished via the incore alarms. It is recommended that CEA withdrawal commence when ASI is moving toward the bottom of the core (i.e. AS! is trending in the positive direction).

The Target CEA height for this time in core life is 134 withdrawn. It is recommended that as the Group 5 CEAs are withdrawn, the remaining CEAs be slowly worked in to 134. Alternately, the remaining CLAs

5. may be repositioned following the withdrawal of Group 5, if desired. Insertion of the remaining CEAs may assist in mitigating the ASI transient resulting from the withdrawal of Group 5.
6. As the Group 5 CEAs are withdrawn to 134, AS! will begin to diverge from its test target axial shape index of +0.3 RPS ASI units (asiu). As CEAs are moved out, the AS! will become increasingly negative and move toward the HFP ES! value of -0.06 RPS asiu. Monitor a plot of the AS!.
7. Withdrawal of the Lead Bank from 115 to 134 will add approximately 100 pcm of positive reactivity, which may need to be compensated for by boration to maintain constant reactor power
8. Once the HFP ES! value of -0.06 RPS asiu is achieved, the AS! should be controlled to the HFP ES! within the expanded transient band +/-0.2 RPS asiu, as follows. If Group 5 CEAs have not reached 134 withdrawn by the time the HFP ESI has been reached, then secure the withdrawal of Group 5 and determine which way the AS! will move naturally. If the AS! trend is to the bottom of the core (+ASI), continue to slowly withdraw Group 5 as permitted by AS! until 134 is achieved. If it is determined the ASI trend (-AS!) is toward the top of the core, wait for the ASI to turn before continuing the withdrawal of bank 5. Note: If the ASI continues to trend to the top of the core it may become necessary to temporarily insert Group 5 (or insert the other Groups if not already at 134) to keep the AS! within the expanded transient band and then resume Group 5 withdrawal after AS! has turned.

,Lk Dave Williams Engineer Walt Mead Reactor Engineer /

Reactor J K!auck (OPSJPSL)

Distribution: Night Order Book R. Scalone (WC/PSL)

D. Huey (WC/PSL) J. Connor (ENG/PSL) M. Hicks (OPS/PSL)

F, \caii \rengine\Rtc\imitl\MTC Recovery Ltr.doc

Retrieved from "https://kanterella.com/w/index.php?title=ML15142A394&oldid=2448479"