ML20135E716
| ML20135E716 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/03/1997 |
| From: | Hurley L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9703100128 | |
| Download: ML20135E716 (159) | |
Text
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UNITE 3 STATLJ
- t NUCLEAR REGULATORY COMMISSION REGION IV 611 RYAN PLAZA DRIVE, SUITE 400
/,
AR LlNGTON, TEXAS 76011-8064 l&R 3 1997 4
NOTE T0:
NRC Document Control Desk Mail Stop 0 5 D 24 FROM:
Laura Hurley, Licensing Assistant Operations Branch, Region IV
SUBJECT:
OPERATOR LICENSING EXAMINATIONS ASHINISTERED ON NOVEMBER 18 22, 1996 AT PALO VERDE NUCLEAR GENERATING STATIONS, UNITS 1, 2, AND 3 DOCKETS #50 528: 50 529; 50 530 On November 18 22, 1996, Operator Licensing Examinations were administered at the referenced facility. Attached you will find the following information for
)rocessing through NUDOCS and distribution to the NRC staff, including the NRC 3DR:
Item #1 -
a) Facility submitted outline and intial' exam submittal, designated for distribution under RIDS Code A070, b) As given operating examination, designated for distribution under R:0S Code A070,
' Item #2 -
Examinatior.,;eport with the as given written examination attached, designated for distribution under RIDS Code IE42.
If you have any questions, r ease contact Laura Hurley, Licensing Assistant, Operations Branch, Region li at (817) 860 8253,
[0 SooN O
$8 V
5.858Pp55,8p8 e
l gP H%q'g UNITE D STATES
/
NUCLEAR REGULATORY COMMISSION
.g RE0lON IV f
611 RYAN PLAZA DRIVE, SUITE 400
,'s,
/
AR LINGTON, TEXAS 760118064 MAR 3 1997 NOTE T0:
NRC Documtnt Control Desk Mail Stop 0 5 D 24 FROM:
Laura Hurley, Licensing Assistant Operations Branch, Region IV
SUBJECT:
OPERATOR LICENSING EXAMINATIONS ASHINISTERED ON NOVEMBER 18 22,.
1996. AT PALO VERDE NUCLEAR GENERATING STATIONS, UNITS 1, 2, AND 3 DOCKETS #50 528: 50 529; 50 530 On November 18 22, 1996, Operator Licensing Examinations were administered at the referenced facility. Attached you will find the following information for
)rocessing through NUDOCS and distribution to the NRC staff, including the NRC
)DR:
Item #1 -
a) Facility submitted outline and intial exam submittal, designated for distribution under RIDS Code A070.
b) As given operating examination, designated for distribution under RIDS Code A070.
Item #2 -
Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42.
If you have any questions, please contact Laura Hurley, Licensing Assistant.
Operations Branch, Region IV at (817) 860 8253.
4 4
0
a, Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: Standbv Op-Test No.:
Examiners:
Operators:
4 Objectives:
Evaluate the crew's response to a failure of the pressurizer pressure control system.
Evaluate the crew's response to a loss of nuclear cooling water.
Evaluate the crew's ability to %- an A'IWS condition.
Evaluate the crew in using the EOPs during a steam space LOCA.
Initial Conditions: 50% power, Middle of Cycle,36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> post trip recovery.
Turnover: Essential Auxiliary Feedwater pump 'B' is out of service for motor bearing replacement.
Pressurizer pressure instrument PT-100X is failed. Control selected to PT-100Y. Presious shiR halted power ascension at 50% for turnover. Dilution rate was 60 gpm,400P-9ZZ05, Power Operations, is in progress at step 5.3.38. ARer tumover raise power level to 100% in accordance with 400P-9ZZ05, Appendix D allows 10% per hour.
Event Malf. No.
Event Event Description No.
Type
- 0 N/R Raise power level.
I CV14B 1
Pressurizer pressure PT-100Y fails low.
2 CC01A C
Ioss of Nuclear Cooling Water, cross-tic Essential Cooling Water to Nuclear Cooling Water, loss ofletdown.
CP03:
C NCNP01B 3
TC)1 I
Main Turbine EliC failure results in turbine runback.
CAE C
Reactor fails to autorratically trip.
4 RV02:
M Pressurizer safety 5 alve sticks open 10%
RCEPSV200 CP05:
C
'A' high pressure sathy injection pump fails to automatically start.
SIAP02 AV01:
C Steam Generator fi economizer valve sticks 5% open.
SGNFVill2 AV04:
SGNFV1112
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor O
,\\
Examiner Standards Rev.8 i
j
1 Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: Standbv Event No: 0 Page 1 of_[
l Event
Description:
Raise Power Level then place 'B' Main Feed in senice.
Time Position Applicant's Actions or Behavior CRS Direct actions for power increase per 400P-9ZZ05, Power Operations from step 5.3.38.
Monitor power ascension ramprate via OAP or Appendix J.
i inform chemistry of power increase.
PO Dilute the RCS at the appropriate rate and amount to support power increase within allowable lindth.
Monitor power ascension ramprate to be within established limits (9% per hour).
2 SO Increase turbine load using load limit or load set controls.
Maintain T, within +3'F of T,a.
Monitor circulating water temperatures.
Adjust feedwater dP across economizer valves as necessary. Monitor feeding and steaming rates on SGs.
Examiner Standards Rev.8
=__.-
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:_ Standbv Event No: 1 Page 1 of__1 3
Event
Description:
Pressurizer Pressure Instrument PT-100Y Fails low Time Position Applicant's Actions or Behavior CRS Direct operator response to B04 alarm 4A01B, "PZR PRESS HI-LO".
Contact maintenance for repairs.
PO Diagnose problem as PT-100Y fail low.
Take action with other channel not available:
Plaec RCN-PIC-100 in manual.
Increase output to maintain pressure.
j restore heater operation.
e Monitor to proper system operation.
SO Monitor control boards.
I Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: Standby Event No: 2 Page 1 of _1 I
Event
Description:
Loss of Nuclear Cooling Water, Crosstic Essential Cooling Water, Loss ofletdown.
Time Position Applicant's Actions or Behavior CRS Direct operator response to B04 and B07 alarms.
attempt start standby pump.
e Diagnose loss of Nuclear Cooling Water.
Direct operator actions from 40AO-9ZZPO, Loss of Cooling Water, section 4.0 Check for no NC system leaks.
Perform Appendix A, Cross-Connect EW to NC.
Ensure only one charging pump running.
Direct operator actions for less of Letdown per 40AO-9ZZ05.
SO Respond 13 B07 alarms 7A07A and 7A078.
Start the standby nuclear cooling water pump.
Diagnose loss of nuclear cooling water.
Direct auxiliary operator to investigate.
Note: either PO, SO or both may perform EW to NC crosstic actions.
PO/SO Perform actions to crosstic Essential Cooling Water to Nuclear Cooling Water using Train A.
Ensure Spray Pond A pump running.
Ensure Essential Cooling Water pump A o. ning.
Ensure both nuclear cooling water pumps are in " Pull-To-lock" e Close NCN-UV-99.
Open EWA-UV-145 and EWA-UV-65.
Ensure no more than one ncrmal chiller NC outlet valve is open.
Direct an auxiliary operator to unlock and throttle EWA-IICV-53 until all RCP low NC flow alarms clear on B04.
PO Perform actions for Loss ofletdown per 40AO-9ZZ05.
ensure only one charging pump running.
e prepare for extended loss ofletdown.
e Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: Standby Event No: 3 Page 1 of 1
4 Event
Description:
Main Turbine EHC Failure, ATWS Time Position Applicant's Actions or Behavior CRS Deternune need to manually trip reactor due to trip setpoints being exceeded Direct actions to trip reactor.
Manual trip pushbattons.
Open breakets LO3 and L10 on B01.
PO Diagnose failure of reactor to trip.
Attempt manual reactor trip.
PO Open breakers LO3 and LIO on B01.
Close breakers LO3 and LIO after reactor trip.
Examiner Standards Rev.8
I Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: Standbv Event No: 4 Page 1 of J Event
Description:
Pressurizer Safety Valve Sticks Open, Loss of Coolant Accident. High Pressure Safety Injection pump 'A' fails to auto start, Steam Generator #1 Economizer valve sticks 5% open.
Time Position Applicant's Actions or Behavior CRS Direct standard post trip actions and contagencies.
Ensure SIAS/CIAS initiated e
Ensure one RCP cach loop stopped.
Acknowledge containment r=Aation monitor alarms / trends.
May diagnose stuck open Pzr safety valve.
Diagnose Loss of Coolant Accident, go to 40EP-9EOO3.
Direct operator action per 40EP-9EOO3.
Ensure maxunum safety injection and charging flow.
Stop all RCPs if < 24*F subcooling.
Check no RCS leakage into nuclear cooling water.
Check no LOCA outside contaimnent.
Ensure CSAS ifinitiated.
Initiate RCS cooldown < 100*F/hr.
When Safety Injection throttle criteria met, if HPSI flow throttled, reinitiate if subcooled margin is lost.
CRS Maintain RCS pressure and temperature within P/r limits of Appendix 2.
PO Perform standard post trip actions and contingencies.
Ensure SIAS/CIAS initiated.
Ensure one RCP perloop stopped.
Start 'A' high pressure saferv injection pump.
May diagnose stuck open Pressurizer Safety valve.
Perform actions per 40EP-9EOO3, loss of Coolant Accident, Ensure maximum safety injection and charging flow.
e Stop all RCPs if <24*F subcooling.
Check no LOCA outside containment.
Ensure CSAS ifinitiated.
Examiner Standards Rev.8
L Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: Standbv Event No:
4 Page 2 ofj Event
Description:
Pressurizer Safety Valve Sticks Open, Loss of Coolant Accident. High Pressure Safety injection pump 'A' fails to auto start, Steam Generator #1 Economizer valve sticks 5% open.
Time Position Applicant's Actions or Behavior
)
PO Maintain RCS temperature and pressure within P/r limits of e
i Appendix 2.
May throttle HPSI and control charging when throttle criteria met. Reinitiate when subcooled margin is lost.
SO Perform standard post trip actions and contingencies.
detenmne contamment radiation monitor alarms / trends.
J e
f.
Perform actions per 40EP-9EOO3, Loss of Coolant Accident.
Check no RCS leakage into nuclear cooling water, j
e Check no LOCA outside containment.
e if MSIS on containment pressure ensure CIAS and MSIS. Use e
ADVs to control RCS heat removal.
1 Initiate RCS cooldown < 100'F/hr. using SBCS or ADVs.
e Reset MSIS setpoints during cooldown if applicable.
Adjust heat removal as rppropriate when HPSI throttled.
i The scenario may be terminated after a reactor coolant system cooldown j
has been initiated and high pressure safety injection throttle initiated to control pressure, or as deemed appropriate by the exam team.
1 i
I Examiner Standards Rev.8 l
e Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.:
1 Op-Test No:
)
l Examiners:
Operators:
1 Objectives:
Evaluate the crew's response to a dropped CEA.
Evaluate the crew's response to a feedwater control system failure.
Evaluate the crew's ability to diagnose an excess steam demand.
Evaluate the crew in using the EOPs during a loss of all feedwater.
Evaluate the crew in transitioning to the FRP to recover feedwater.
Initial Conditions: 100% power, equilibrium xenon, middle of cycle Tumover: The following equipment is og 4 m:
Essential Auxiliary Feei
, imp ' A', to repair the governor linkage.
Nuclear Cooling Water Pump 'B' to replace a pump casing drain valve.
Stator Cooling Pump 'A' to replace the motor.
Suspect slow Nitrogen leak on Safety Injection Tank 1 A. After turnover repressurize tank 1 A. Containment entry in two hours to investigate.
Event Malf.
Event Event Description No.
No.
Type
- 0 N
Repressurize safety injection tank 1 A 1
RD02A C/R Drop control rod 14 and recover.
2 TR01:
I
- 2 Feedwater Control System Steam Generator level transmitter SGNLTl121 LTl121 fails high.
3 MS07 M
Steam break in turbine building.
ED05A C
- Loss of NAN-S05 bus.
Fast bus transfer failure on NAN-S02 bus.
ED08B C
Essential auxiliary feedwater pump 'B' performance CP03:
C AFBP01 degrades 4
EG06A C
After feed established with non-essential auxiliary feedwater pump 'N', diesel generator 'A' trips on differential.
Transition to functional recovery procedure to recover PBA S03 from NBN-X04.
- (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
1 Event No:
0 Page 1 of_1 Event
Description:
Repressurize Safety injection Tank 1 A.
Time Position Applicant's Actions or Behavior CRS Directs use of 400P-9S103 to repressurize safety injection tank (SIT). lA to a pressure between 605 and 620 psig.
PO Obtains procedure 400P-9SIO3.
Opens GAA-UV-1, Nitrogen to SIT Isolation Valve.
Open SIB-HV-632, Nitrogen to SIT 1 A.
Commence SIT 1 A pressurization by opening valve SI A-IIV-639.
Pressurizes SIT l A until alarm 2B12B clears (605-620 psig).
When SIT 1 A repressurized close the two SIT 1 A valves and the nitrogen isolation valve.
SO Monitors plant parameters.
Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.: 1 Event No: 1 Page 1 of._2 Event
Description:
Control rod #14 drops into core, and recover.
Time Position Applicant's Actions or Behavior PO/SO/CRS Diagnose CEA #86 drops into core.
CRS Direct references to alarm response procedures for 4A04B and 4A06B.
Directs action and recovery from 41 AO-lZZ11, dropped or slipped CEA.
Directs actions to stabilize the plant Rod control to standby.
Stabilize RCS temperature by reducing turbine load.
Dilute RCS for xenon effects only.
Directs power reduction IAW Appendix A.
Begin reduction within 10 minutes.
Reduce 20% within I hour.
Refer to Tech Spec 3.1.3.1 action C.
Cue: Another reactor operator will perform COLSS Functional Verification and Shutdown Margin procedures.
Determine cause of dropped CEA.
Direct recovery of dropped CEA #86.
Maintain power by boration.
Realignment takes > 10 minutes.
Direct reset of PMS and COLSS per Appendix B.
PO/SO Identify dropped CEA as #86, monitor plant for effects.
Refer to alarm response procedures for 4A04B and 4A06B.
SO If necessary, take actions to reduce turbine load to match Tn, to Twr 2 F.
Reduce turbine load to reduce power per Appendix "A" Recover dropped CEA #86 Rod control to manual individual Withdraw CEA #86 in slow, smooth incremental manner, > 10 minutes.
Realign CEA #86 with its group.
]
Examiner Standards Rev.8
... - _.. -. _ -.. -. - - -.. -. - - - - ~
l Appendix D Operator Actions Form ES-D-2
\\
Op-Test No:
Scenario No.: 1 Event No:
1 Page_2_of 2 i
Event
Description:
Dropped CEA (cont'd)
Time Position Applicant's Actions or Behavior PO Place rod control in " standby".
Borate RCS to reduce power IAW Appendix "A".
l Recover dropped CEA by boration as required to maintain power and RCS l
temperature.
i l
l l
l 1
i l
l t
i 4
4 Examiner Standards Rev.8 J
l Appendix D Operator Actions Form ES-D-2 i
Op-Test No:
Scenario No.:
1 Event No:_2 Page 1 of._1 1
1 Event
Description:
Steam Generator Level Transmitter LT 1121 fails high to #2 Feedwater Control System.
Time Position Applicant's Actions or Behavior SO Diagnose problem with SG #2 level, FWCS #2 and LTl121.
Refer to alarm response for 6A06A "FW CONT SYS TRBL" on level channel deviation.
Take manual control of FWCS #2 and restore SG #2 level to 50%.
Determine failed instrument as LT-il21.
Select unaffected channel (LT-1122) at FWCS #2 panel.
Restore FWCS #2 to AUTO.
CRS Assist diagnosis.
Direct SO activities from alarm response procedures to recover SG #2 level.
Contact I&C to troubleshoot / repair.
PO Monitor control boards, assist diagnosis, i
l l
1 Examiner Standards Rev.8
l l
l
+
o-l l
Appendix D Operator Actions Form ES-D-2 l
Op-Test No:
Scenario No.:
1 Event No:
3 Page 1 of._1 Event
Description:
Turbine Building steam Break, loss NAN-SOS bus, Loss of Feedwater.
Time Position Applicant's Actions or Behavior CRS/PO/SO Diagnose and respond to indications of a steam break.
CRS Direct Reactor Trip. May direct SI AS, CIAS and/or MSIS.
Direct PO/SO into Standard Post Trip Actions and Contingency Actions.
Diagnose Loss of All Feed, enter LOAF procedure.
Determine no feedwater line break.
Direct use of Appendix 37 for operation of AFN-P01 after MSIS.
SO Take Standard Post Trip Actions and Contingencies.
Diagnose degraded performance of AFB-P01, inform CRS of no feed.
Ensure MSIS initiated. Ensure heat removal through ADV operation.
Diagnose no feedwater line break.
Perform Appendix 37 to operate AFN-P01 after MSIS.
- Override MSIS valves.
Start AFN-P01 and feed SG's.
PO Take Standard Post Trip Actions and Contingencies Ensures DG 'A' supplying PBA-S03.
Ensure SIAS/CI AS initiated if required.
e l
4 Examiner Standards Rev.8
..,s Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
1 Event No: 4 Page 1 of_1 Event
Description:
DG 'A' trips on differential, Loss of Feedwater, Loss of PBA S03, Functional Recovery Time Position Applicant's Actions or Behavior SO/CRS Diagnose loss of all feedwater due to loss of AFN P01 on loss of PBA-S03.
CRS Transition to Functional Recovery Procedure to recover PBA S03 due to loss of MVAC.
Detennine MVAC-1 and liR-1 asjeopardized success paths.
Direct Reset DG 'A' breaker 86 lockout.
Direct operator to cross-tie NBN-X04 to PBA-S03 by closing breaker PBA-S03K.
Direct restan of AFN-P01 and feeding of SG's.
Determine all success path criteria satisfied.
PO Diagnose loss of PBA-S03 due to loss of DG 'A' on differential trip.
Determine NBN-X03 not available, may direct AO in reset of DG 'A' 86 lockout.
Cross-tie NBN-X04 to PBA-S03 by closing breaker PBA 3K SO Prepare AFN-P01 for restart.
Restart AFN P01 and feed SG(s) LAW Heat Removal success path.
Scenario may be terminated when adequate feed is established to any or both Steam Generators, or when deemed appropriate by the exam team.
Examiner Standards Rev,8
Appendix D Scenario Outline Form ES-D-1 Facility:, PVNGS Scenario No.:
2 Op-Test No:
Examiners:
Operators:
Objectives:
Evaluate the crew's response to a loss ofletdown.
Evaluate the crew's response to a loss of condenser vacuum.
Evaluate the crew's ability to diagnose an ATWS condition.
Evaluate the crew in using the EOPs during an excess steam demand.
Initial Conditions: 100% Power, Equilibrium Xenon, Middle of Cycle.
Turnover: Control element assembly (CEA) operability checks per 41ST-ISF01 are in progress.
Continue the surveillance test after turnover at step 8.l.2. Instrument air compressor 'A' is out of service for motor bearing replacement. Charging pump 'E' is out of service for plunger repair.
Event Malf. No.
Event Event Description No.
Type' 0
N Continue 41ST-1SF01 surveillance 1
BS02:
1/C Nuclear cooling water flow switch FS613 fails low causing loss of NCNFSL613 letdown.
2 MC01A C/R Loss of condenser vacuum 3
RP06Al C
Inadvertent main steam line isolation CAE C
ATWS RV02:
M Steam generator #1 safety valve opens SGEPSV572 RP07B 1/C
'B' train sequencer failure.
CP03:
C
'A' high pressure safety injection pump performance degrades.
SIAP02 4
Safety valve rescats at 500 psig.
I i
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
)
Examiner Standards Rev.8 l
l
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
2 Event No:
O Page 1 of_1 Event
Description:
Continue 41ST-1SF01 surveillance, CEA operability checks.
Time Position Applicant's Actions or Behavior CRS Review personnel indoctrination.
Direct operator to perform / continue 41ST-ISF01 beginning at step 8.1.2 for Regulating Group 5 CEAs.
Prerequisites and Instructions for 41ST-1SF01.
Perform crew brief IAW Sensitive Issues Manual.
PO Exercise Regulating Group 5 at least 5 inches IAW 41ST-ISF01.
Exercise part length CEAs IAW 41ST-ISF01.
SO Monitor plant parameters during performance of 41ST-1SF01.
1
)
l Examiner Standards Rev.8
t:
sAppendix D Operator Actions Form ES-D-2 i
Op-Test No:
Scenario No.:
2 Event No: 1 Page 1 of 1
Event
Description:
NCW Flowswitch FS613 fails low causing loss ofletdown.
Time Position Applicant's Actions or Behavior CRS/PO Diagnose loss of Letdown flow CRS Direct PO to respond to B03 alarms IAW alarm response procedures.
Direct actions from 40AO-9ZZ05, Loss of Letdown.
Enter Tech. Spec. 3.4.3.1 action 'b' when Pzr level exceeds 56%.
Diagnose failure of FS613,' step 9.
Contact I&C tojumper FS613 contacts.
Direct Appendix 'A' actions to restore letdown.
j PO Diagnose failure of FS613 and report to CRS. (May attempt movement of C11N-TIC-223 to check controller and NC available.)
Close letdown control valves and stop all but one charging pump.
Restore letdown after FS613 jumpers installed.
SO Monitor plant parameters during loss and recovery ofletdown.
Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
2 Event No:
2 Page 1 of I
Event
Description:
Loss of Condenser Vacuum Time Position Applicant's Actions or Behavior SO/CRS Diagnose degrading vacuum in condenser shell 'A'.
CRS Direct operator actions IAW 40AO-9ZZ07, Loss of Condenser Vacuum.
Lower turbine load to stabilize vacuum at 5 inches H,A or less.
Maintain T,v,/Trer within 4 F by either boration, CEA insertion and/or SBCS operation.
Refer Tech Specs 3.1.3.6 on CEA Inserting limits.
Check locally for vacuum leaks.
Direct recovery / stabilizing actions.
Reset SBCS interlock if required.
Determine if CEAs inserted below the Transicent Insertion Limit. If so, ensure compliance with Tech Spec 3.1.1.2.
Inform ECC, plant management.
SO Lower turbine load to recover vacuum at 5 inches H A or less.
g If conditions warrant, use SBCS valves 1007,1008 to control RCS T,v, 14 F.
Check Air Removal pumps, Cire Water Pumps, Cooling Tower fans in operation.
Check Gland Seal Steam r,larm clear on B07.
When vacuum conditions stabilize:
Reset SBCS interlock if required.
PO Maintain RCS T,vg +4 F by Boration and/or CEA insertion as directed ty CRS.
When vacuum conditions stabilize:
Initiate pressurizer boron equalization if required.
f Examiner Standards Rev.8 l
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
2 Event No: 3 Page 1 of 1
Event
Description:
Steam Generator #1 Safety Open - ESD.
1 Time Position Applicant's Actions or Behavior J
PO/SO/CRS Diagnose halfleg MSIS trip, MSIVs/FWlVs going closed.
1 CRS Direct manual Reactor Trip.
Direct PO/SO in Standard Post Trip Actions and Contingencies.
Diagnose ATWS and direct opening of breakers for LO3 and L10.
3 Ensure MSIS, SIAS, CIAS as required.
May direct isolation of feed to SG #1.
Diagnose Excess Steam Demand due to SG #1 Safety open.
SO Attempt manual reactor trip.
Perform Standard Post Trip actions and contingencies.
Ensure adequate feedwater via AFA-P01 or AFB-P01.
Diagnose SG #1 safety open.
Ensure MSIS initiated completely may isolate feedwater to SG #1.
PO Trip reactor by opening breakers for LO3 and L10, reclose after reactor tripped (>5 seconds).
Perform Standard Post Trip actions and contingencies.
Start all available charging pumps, isolate letdown.
Ensure SIAS/CI AS, stop 1 RCP in each loop.
Start 'B' train loads due to sequencer r c 4 re, Diagnose 'A' HPSI performance degre d.
Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D{
Op-Test No:
Scenario No.:
2 Event No:__4 Page 1 of 1
Event
Description:
ESD SG #1, Safety Valve rescats Time Position Applicant's Actions or Behavior CRS Direct recovery actions from ESD procedure,40EP-9EOOS.
Determine SG #1 as most affected SG.
Direct isolation of SG #1.
1 Diagnose when SG #1 safety reseats.
Direct stabilization of RCS temperature by steaming the unaffected SG ADVs.
Direct throttle of HPSI when criteria met.
Direct control of charging and Pn spray to prevent Pu safety valves from lifting.
PO Throttle PEI when criteria met.
Control charging and Pu spray to maintain RCS pressure below Pu safety setpoint.
SO Perftrm actions to isolated SG #1.
Diagnose when SG #1 safety rescats.
Stabilize RCS temperatures using ADVs on SG #2 to prevent excessive RCS pressure rebound.
i l
4 The scenario may be terminated when RCS T-cold has stabilized and RCS pressure rise is under control, or as deemed appropriate by the exam team.
Examiner Standards Rev.8 i
Appendix D Scenario Outline Form ES-D-1 l
Facility: PVNGS Scenario No.:
3 Op-Test No:
Examiners:
Operators:
Objectives:
Evaluate the crew's response to a pressurizer pressure control syste n failure.
Evaluate the crew's response to a stuck open pressurizer spray valve.
Evaluate the crew's response to a steam generator tube leak.
Evaluate the crew in using the EOPs during a steam generror tube rupture.
Initial Cor.ditions: 26% power and increasing for plant startup, Middle of Cycle, j
)
Turnover: Plant startup in progress. Pressurizer is in boron equalization. High Pressure Safety Injection pump 'A' is out of service for pump inspection due to failure of its surveillance test. ARer turnover continue the plant startup in 400P-9ZZ05 at step 5.3.32. De previous crew w3s diluting at 50 gpm with a total change of 92 ppm and 13,200 gal, of RMW.
j Event Malf. No.
Event Event Description No.
Type
- 0 N/R Powerincrease 1
N102A I
Nuclear Instrument Control Channel fails low.
NIO2B 2
RCO2A C
Stuck open pressurizer spray valve, with pressurizer PT100X failed TROI:RCNPT high, close instrument air, loss of letdown, affect steam bypass 100X control.
3 "IN06B C/R Steam Generator #2 tubeleak.
4 TH06B M
Steam Generator #2 tube rupture.
ED02 C
Loss of offsite power post trip BK02:
C
'B' Diesel Generator output breaker fails to auto close.
PBBSO4B CP05:
C
'B' Spray pond pump fails to auto start.
SPBP01 EG06B C
'B' Diesel Generator trip if run without cooling water for 3 minutes or longer.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards Rev.8
Appendix D Operctor Actions Form ES-D-2 Op-Test No:
Scenario No.:
3 Event No: 0 Page 1 of_t Event
Description:
Power increase l
Time Position Applicant's Actions or Behavior CRS Direct power ascension actions per 400P-9ZZ05, Power Operations, at step 5.3.31 Brief crew on instructions.
Inform chemistry.
Direct calculation of needed dilution.
Load increase per Appendices A, C, D and J.
Generator loading per Appendix F.
PO Calculate required dilution and dilution rate. Perform dilution.
Ensure Appendix E, Equalizing Pressurizer Boron Concentration.
Maintain Tm within i 3'F of T,.r.
Maintain CEAs within Tech Spec. PDILs.
SO Maintain Main Turbine load within limits of condenser vacuum.
Adjust the dP across FWCS economizer valves as necessary using SGN-FIC-1107 and/or 1108.
Increase load on the Main Turbine and Generator.
Loading rates per Appendices A and C.
VAR loading per Appendix F.
Use load limit potentiometer or load set control.
Monitor Circulating Water temperature within limits.
J..
Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
3 Event No: 1 Page 1 of_1 i
Event
Description:
Nuclear Instrument Control Channel Fails Low Time Position Applicant's Actions or Behavior CRS Direct investigation of alarm window 4A10B using alarm response procedure.
CRS/PO/SO Diagnose NI Control Channel failed low.
i CRS Direct instrument failure response actions from 41 AO-lZZ34, RRS Malfunction.
Direct both FWCS #1 and #2 cconomizers, downcomer and MFWP speed controllers to Manual.
Direct selection of unaffected Ni channel (N12) at FWCS #1 and #2 cabinets and RRS.
Direct return of FWCS controllers to Automatic operation.
SO investigate feedwater control and flow rates to confirm diagnosis.
Place FWCS #1 and #2 economizers, downcomer and MFWP speed controllers to Manual.
Select unaffected Ni channel (N12) at FWCS #1 and #2 cabinets.
Retum FWCS controllers to Automatic operation.
PO Monitor control boards, assist in diagnosis.
1
~
l Examiner Standards Rev.8 1
)
j
?
Appendix D Operator Actions Form ES-D-2 l
Op-Test No:
Scenario No.:
3 Event No: 2 Page 1 of._1 Event
Description:
Stuck Open Pressurizer Spray Valve i
4 Time Position Applicant's Actions or Behavior i
CRS/PO/SO Respond to alarm 4A01B " Pressurizer Pressure Lo".
CRS Direct resoonse to alarm.
I Direct man' al control of pressurizer pressure controller RCN-PIK-100 to shut u
main spray valves.
Direct isolation of Instrument Air to Containment using lAN-HS-2 on B07.
Refer to 41 AO-lZZ06, less ofInstrument Air.
1 Determine Steam Bypass Control options. Direct actions.
1 i
PO Diagnose pressure channel 100X failed high. Select unaffected channel.
Diagonse main spray valves open.
The manual control of RCN-PIK-100 to shut main spray valves.
Determine spray valves remain open.
j Take action for loss ofletdown per 40AO-9ZZ05.
g Stop one charging pump.
Take long term actions.
SO Isolate instrument Air to Containment using IAN-HS-2 on B07.
Determine Steam Bypass control affected. Discuss control options. Take SBCS action as directed.
Examiner Standards Rev.8
l Appendix D Operator Actions Form ES-D-2
?
L Op-Test No:
Scenario No.:
3 Event No: 3 Page 1 of_1 W
Event
Description:
Steara Generator Tube Imk Time Position Applicant's Actions or Behavior CRS Direct response to Rad Monitor System alarm on Steam Generator #2.
Refer to 40AD-9ZZ02, Excessive RCS Leakrate.
Direct actions from 40AO-9ZZ02.
Start additional charging pumps.
e Isolate letdown if necessary.
Determine leakrate using Appendix 'A'.
Comply with T.S. 3.4.5.2, RCS leakage.
Notify RP.
Perform Appendix 'B', minimize release to emirement.
Determine SG isolation time, Determine need to shutdown.
e Direct shutdown and isolation within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 10 minutes.
t f
PO Start additional charging pumps.
Isolate letdown if necessary.
Determine RCS leakrate using Appendix 'A'.
Commence boration for shutdown.
SO Perform Appendix 'B', minimize release to the environment.
Reduce turbine load to maintain Tm - T,a t 14'F.
a
\\
l Examiner Standards Rev.8
Appendix - D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
3 Even. No: 4 Page 1 of_2 Event
Description:
Steam Generator Tube Rupture, loss of Offsite Power.
Time Position Applicant's Actions or Behavior CRS/PO/SO Diagnose increase in RCS leakrate.
CRS Detennine need to perform reactor trip.
Direct reactor trip.
Direct performance of standard post trip actions and contingencies.
Close DG 'B' output breaker, Direct or ensure SlAS actuation.
e Verify natural circulation.
Diagnose a steam generator tube rupture event and loss of offsite power.
Direct actions from 40EP-9EOO4, Steam Generator Tube Rupture.
Commence RCS cooldown to a T-hot of < 550 F using ADV's.
Reset MSIS setpoints during cooldown to avoid on MSIS.
Determine affected SG as #2.
When T-hot is < 550*F, isolate SG #2.
Maintain SG #2 < 1135 psia.
Depressurize the RCS to 50 psi of SG #2 pressure.
PO Perform standard post trip actions and contingencies.
Report status ofelectric plant.
Close DG 'B' output breaker Ensure PBB-SO4 loads start. Manually start 'B' Spray Pond pump within 3 minutes of DG 'B' breaker close.
1 l
Ensure SIAS and CIAS actuation.
Ensure maxunum safety injection flow.
Depressurize the RCS to 150 psia of SG #2, staying within Pfr limits of
)
Appendix 2.
l
'Ihrottle HPSI when criteria met to prevent excessive pressurizer level.
i Examiner Standards Rev.8 i
j
Appendix D Operator Actions Form ES-D-2 i
Op-Test No:
Scenario No.:
3 Event No:
4 Page 2 of_2 Event
Description:
Steam Generator Tube Rupture Time Position Applicant's Actions or Behavior i
SO Perform standard post trip actions and contingencies.
Perform manual reactor trip.
Ensure feed flow > 500 gpm to at least 1 SG using AFW, Operate ADVs to control RCS temperature 560-570 and SG pressure < 1200 psia.
Report steam plant activity by operating RMS.
Commence an RCS cooldown to get T-hot < 550'F using ADVs.
Reset MSIS setpoint to avoid unwanted MSIS.
Maintain SG levels 40-60% NR.
Isolate SG #2 Maintain SG #2 pressure < 1135 psia.
'Ihe scenario may be termmated when the RCS has been depressurized to within 150 psi of steam generator #2 pressure, or as deemed appropriate by the exam team.
Examiner Standards Rev.8
Appendix D Scenario Outline Form ES-D-1 1
Facility: PVNGS Scenario No.:
4 Op-Test No:
Examiners:
Operators:
Objectives:
Evaluate the crew's response to a reactor regulating system failure.
Evaluate the crew's response to a loss of a main feedwater pump without an automatic reactor power cutback.
Evaluate the crew's ability to diagnose an inter-system LOCA.
Evaluate the crew in using the EOPs during an inter-system LOCA with electrical complications.
i Initial Conditions: 100% power, Equilibrium Xenon, Middle of Cycle.
Turnover: Diesel Generator 'A' is out of senice due to field flash circuit failure during its monthly surveillance test. Diesel Generator 'B' monthly operability test in progress in 4 IST-IDG02.
One hour remaming on the run, at step 8.20.3. nen perform system restoration in section 9.0.
Turbine cooling water pump 'B' is out of semce for mspection due to high sibration.
d Event Malf.
Event Event Description No.
No.
Type' 0
N Diesel Generator 'B' test in progress.
1 TROI:
I RCS temperature instrument fails low.
RCNTTillX 2
FWISA C/R Main feed pump 'A' high vibration, manual trip pump 'A' with BS01:LONPSLl73 no auto reactor power cutback.
BS01:LONPSLl75 3
HX02:
C Reactor coolant pump 1 A high pressure seal cooler leak.
RCEE05A 4
HX02:
M Reactor coolant pump 1 A high pressure seal cooler rupture.
RCEE05A RD031UI C
Two stuck control rods on reactor tnp.
BK05:
C Loss ofload center LO9 and M15.
NGNLO9B2 i
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
4 Event No: 0 Page 1 of_L Event
Description:
Diesel Generator 'B' Monthly Operability Test.
Time Position Applicant's Actions or Behavior CRS Direct continuation of Diesel Generator 'B' test run.
PO Monitor operation of DG 'B' in accordance with 4 IST-1DG02.
SO Monitor control boards.
1 l
i i
Examiner Standards Rev.8
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
4 Event No: 1 Page l of_.t Event
Description:
RCS Temperature Instrument TE-IllX Fails lew.
Time Position Applicant's Actions or Behavior CRS Direct operator response to B04 alarm T, - T,.r HI-LO.
Determine effect of failed instrument using 41 AO-lZZ34, App. A, for Tw failed low.
Direct stabilizing and corrective actions. Call I&C for repairs.
PO Verify alarm "T, - T,,, HI-LO" by observing temperature instruments.
Determme TE-11IX has failed low and switch to the unaffected channel.
l Place pressurizer level control RCN-LIC-110 in LOCAL.
Return pressurizer level control to AUTO.
SO Remove CEA control out of Auto Sequential.
i Detemune failed instrument and switch to unaffected channel.
Retuin CEA control to Auto Sequential if desired.
l
)
i i
i Examiner Standards Rev.8
l Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
4 Event No: 2 Page 1 of_2 Event
Description:
Main Feed Pump High Vibration, Manual Trip without Reactor Power Cutback.
i Time Position Applicant's Actions or Behavior CRS Direct operator response to B06 alarm 6A03C "FWPT A HI VIB" Contact vibration group to monitor locally.
When 5 mi!s vibration confirmed, direct trip of MFP 'A' and initiate a reactor power cutback.
Direct operator actions per 40AO-9ZZO9, Reactor Power Cutback.
Verify selected CEA subgroups insert.
Verify turbine setback-runback.
Check reactor power stable or lowering.
Check feed flow stable and SG levels trading 40-60% NR.
Remove RPCBS from service.
Clear turbine setback signal.
Restore proper CEA overlap.
Refer % Tech Spec 3.1.3.6 "CEA Insertion Limits". Determine plan to restore CEA position above the Transient Insertion Limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Return to 400P-9ZZ05, Power Operations, when plant has been stabilized.
SO Take action per alarm response 6A03C, "FWPT A HI VIB".
Direct an auxiliary operator to locally investigate.
Monitor vibration on computer point or B07 recorder MTN-YR-301. Report changing vibration levels to CRS.
With CRS direction, trip the 'A' main feed pump and manually initiate a reactor power cutback when AUTO fails.
Check selected CEA subgroups insert.
Check turbine setback-runback initiation.
Check reactor power stable or lowering.
Check feedwater/SG level response proper.
Remove reactor power cutback system from sersice.
Clear the turbine setback signal.
May perform Appendix H of 400P-9ZZ05, NI Deviation Checks.
Examiner Standards Rev.8
?
Appendix D Operator Actions Form ES-D-2 Op-Test No:
Scenario No.:
4 Event No: 2 Page 2 of _2 Event
Description:
Main Feed Pump High Vibration, Manual Trip Without Reactor Power Cutback.
Time Position Applict.nt's Actions or Behavior PO Upon direction for 'A' main feed pump trip ensure proper CEA subgroups msert.
Check reactor power stable or lowering.
Restore proper CEA overlap.
Monitor control boards for plant stabilization.
Examiner Standards Rev.8
. - ~
r I
Appendix D Operator Actions Form ES-D-2 4
i Op-Test No:
Scenario No.:
4 Event No: 3 Page 1 of J l
i Event
Description:
Reactor Coolant Pump 1A High Pressure Seal Cooler Ieak.
j i
Time Position Applicant's Actions or Behavior CRS Direct operator response to B04 alarms and RMS alarms.
Diagnose RCP I A HP seal cooler leak by one of the following:
increasing trend on RU-6, Nuclear Cooling Water Rad Monitor e
increasing trend on HP cooler inlet temperature RCN-TT-157.
e alarm 4A2A, RCP 1A TRBL, at 221*F HP cooler inlet i
e temperature.
Enter and direct operator actions from 40AO-9ZZ04, RCP emergencies, j
Section 4.0.
Refer to 40AO-9ZZ02, Excessive RCS Leakrate, and direct operator actions as time allows.
4 PO Respond to B04 alarms as appropriate.
Diagnose RCP 1 A HP cooler inlet temperature indications increasing, j
Observe other important RCP 1 A seal parameters for trends.
Determine RCS leakrate as time allows.
i I
SO Respond to RMS alarms as appropriate.
l Determine alann and increasing trend on RU-6, Nuclear Cooling Water Rad Monitor.
I f
b 1
Examiner Standards Rev.8 J
i Appendix D Operat:r Actions Form ES-D-2 Op-Test No:
Scenario No.:
4 Event No: 4 Page 1 of_2 Event
Description:
Reactor Coolant Pump 1A High Pressure Seal Cooler Rupture,2 stuck rods, Loss Imd center LO9.
4 Time Position Applicant's Actions or Behavior CRS When RCP seal parameter trip setpoints are exceeded per Appendix B of 40AO-9ZZ04, direct operator actions:
Stop RCP 1 A.
e l
Direct standard post trip actions and contingencies.
Borate for 2 stuck rods.
Direct SIAS/CIAS on trend or if exceeded.
Diagnose SBLO. outside containment, go to 40EP-9EOO3, Loss of Coolant Accident.
Direct actions to isolate the leak.
1 4
stop all RCPs.
j e
close nuclear cooling water containment isolation valves.
e
. isolate seal bleedoff.
Determine RCP HP seal cooler isolation valves for RCP 1 A can't be closed due to loss ofload center LO9.
PO Diagnose increasing trends in RCP seal cooler parameters toward a worsening condition.
Upon CRS direction, stop RCP 1 A.
Perform standard post trip actions and contingencies.
j Borate for 2 stuck rods.
Ensure SIAS/CIAS is setpoint exceeded.
1 Recognize LO9 de energized.
Perform actions to isolate the leak.
stop all RCPs.
close nuclear cooling water contaimnent isolation valves.
e isolate RCP seal bleedoff.
Determine RCP 1 A HP seal cooler isolation valves can't be close due to loss ofpower.
Examiner Standards Rev. 8
1 Appendix D Operator Actions Form ES-D-2 i
Op-Test No:
Scenario No.:
4 Event No: 4 Page 2 of _2 4
Event
Description:
Reactor Coolant Pump 1 A liigh Pressure Seal Cooler Rupture,2 stuck rods, Loss Load center LO9.
1 Time Position Applicant's Actions or Behavior SO Upon CRS direction initiate reactor trip. Diagnose 2 stuck rods.
Perform standard post trip actions and contingencies.
Confirm RU-6 as only valid RMS alarm.
May perform actions to isolate RCP 1 A HP seal cooler leak at CRS direction.
close nuclear cooling water containment isolation valves.
e I
i I
4 i
The scenario may be termmated when the high pressure seal cooler rupture has been isolated to containment and crew realizes the cooler isolation valves can't be closed (ie: continue in LOCA procedure), or as deemed appropriate by the exam team.
Examiner Standards Rev.8
j EP003-J-C/R-14 j
PVNGS JOB PERFORMANCE MEASURE l
i JPM BASIS INFORMATION 1
TASK:
1250440201, Take all immediate actions prior to evacuating the Control Room due to a fire TASK STANDARD:
Reactor is tripped and MSIVs are closed within 90 seconds.
K/A:
068 AAl.23 UA RATING:
RO:
4.3 SRO: 4.4 i
K/A:
K/A RATING:
RO:
SRO:
APPLICABLE POSITION (S): RO VAllDATION TIME:
90 seconds i
REFERENCES:
41 AO-lZZ44, Control Room Fire.
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT a
i APPROVAL DEVELOPER:
W. Potter TECH REVIEW:
N Nu-- --
REVISION DATE:
08/23/96 APPROVAL:
f j
TESTING METHOD
]
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT TESTING METHOD:
SIMULATE PERFORM i
EVALUATION l
EXAMINEE NAME:
(print)
EVALUATOR NAME:
(print) 1 l
SATISFACTORY UNSATISFACTORY j
f Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG.04) 4 i
i b
OTG-02 Rev. 0 1
AAEP003CR. DOC cgc 11/07/96
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE 1.
SIMULATOR SETUP:
A.
IC# : 20 (any stable,100% power IC)
B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
N/A 2.
3.
4.
C.
SPECIAL INSTRUCTIONS:
- None D.
REQUIRED CONDITIONS:
None 2.
SPECIAL TOOLS / EQUIPMENT:
- None I
i OTG-02 Rev. 0 2
l J
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
j SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the Simulator.
The examiner will provide all responses and indications required from outside the control room.
l You may use any source ofinformation normally available.
INITIATING CUE:
There is a fire in the control room requiring evacuation.
j The CRS has directed you to perform steps 1 and 2 of 41AO-lZZ44 prior to evacuating the control room.
"TIIIS IS A TIME CRITICAL JPM" INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task e
Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed I AW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
This is a Time Critical JPM,90 seconds from the time of reactor trip to completion of MSIS.
SAFETY CONSIDERATIONS:
- None i
OTG-02 Rev. 0 3
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE
~
STEP ELEMENT STANDARD 1.
Obtains 41 AO-lZZ44, Control Room Fire.
41 AO-12Z44 obtained.
j Note: The examiner will provide the procedure.
SAT UNSAT (UNSAT requires comments) l l
STEP ELEMENT STANDARD Manually trip the Reactor.
Reactor manual trip initiated using pushbuttons 2.
on B05.
NOTE: Time critical portion starts when the reactor is tripped. Log start time here:
Time:
_ UNSAT (UNSAT requires comments) i
~
STEP ELEMENT STANDARD 3.
Perfonn the following:
Examinee ensure the following using B04/B05 instrumentation; a.
Check that Reactor power is Reactor power is decreasing.
decreasing All CEAs are inserted.
Time of tnp is recorded.
b.
Check that ALL CEAs are inserted CUE: Reactor power is decreasing and all c.
Record the time of trip.
CEAs are inserted.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
OTG-02 Rev. 0 4
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Initiate a MSIS on B05 using hand MSIS is initiated, using hand switches; SAA-4.
switches; SAA-HS-9A, SAB-HS-10A, HS-9A, SAB-HS-10A, SAC-HS-II A and SAD-SAC-HS-II A and SAD-HS-12A HS-12 A.
All valves associated with MSIS are closed.
NOTE: The time critical portion ends when MSIVs are closed (time limit is 90 sec.). Log end time here:
Time:
CUE: MSIV green lights are on.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT l
COMMENTS:
OTG-02 Rev. 0 5
)
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 14 08/28/96 6
New Format l
l l
l l
REASON REVISED Ent:r the numbers corresponding tu e reason revised in the Reason Revised column l
and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade l
4.
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) l OTG-02 Rev. 0 6
EP003-J-C/R-14 PVNGS JOB PERFORMANCE MEASURE ~
INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the Simulator.
j The examiner will provide all responses and indications required from outside the 1
=
control room.
You may use any source ofinformation normally available.
INITIATING CUE:
1, There is a fire in the control room requiring evacuation.
The CRS has directed you to perform steps 1 and 2 of 41AO-lZZ44 prior to evacuating the control room.
"TIIIS IS A TIME CRITICAL JPM" 2
SAFETY CONSIDERATIONS:
- None 1
OTG-02 Rev. 0 7
4 d
=s SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE JPM BASIS INFORMATION TASK:
1280010801, Perform surveillance test TASK STANDARD:
SGE-UV-170 Accumulator 'A' test and 10% partial stroke test, ending with valve j
full open.
K/A:
035 K6.01 K/A RATING:
RO:
3.2 SRO: 3.6 K/A:
039 K4.08 K/A RATING:
RO:
3.3 SRO: 3.4 APPLICABLE POSITION (S):
RO VALIDATION TIME:
15 min.
REFERENCES:
73ST-9SG01 SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT APPROVAL
[
f 47 '-4 DEVELOPER:
W. POTTER TECH REVIEW:
REVISION DATE:
8-20-96 APPROVAL:
TESTING METHOD ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT TESTING METHOD:
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
(print)
EVALUATOR NAME:
i (print) 1 SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTO-04)
,,.,,,....,.,,.,,,..,,.c,,
OTG-02 Rev. 0 1
A"SG018CR. DOC tbp 09'25S6
_~
i SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE 1.
SIMULATOR SETUP:
i A.
IC#: 20 (100% POWER)
B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
2.
l 3.
4.
i C.
SPECIAL INSTRUCTIONS:
i None D.
REQUIRED CONDITIONS:
None 2.
SPECIAL TOOLS / EQUIPMENT:
i None l
OTG-02 Rev. 0 2
i SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The exammer will provide all responses and indications required from outside the Control Room.
You may use any source ofinfoimation normally available.
INITIATING CUE:
The Control Room Supervisor directs you to perform the Partial Stroke Exercise (Train A) of MSIV SGE-UV-170 in accordance with 73ST-9SG01. All prerequisites have been met. An operator is stationed by the valve for any further instructions regarding this test.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be termmated when the Task Stant ard is met or adequate time has been allowed to complete the JPM. It shall be terminated whea the Exammee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
SAFETY CONSIDERATIONS:
None OTG-02 Rev. 0 3
SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Ensure both accumulators for SGE-UV-Examinee uses handswitch SGA-HJS-229 at 170 are >5000 to <5400 psig position #1 and SGA-PI-229 to verify pressure
>5000 to <5400 psig.
CUE: Both accumulators are 5100 psig.
i SAT UNSAT (UNSAT requires comments) 1 STEP ELEMENT STANDARD 2.
OPEN/ CHECK OPEN SGE-UV-170 using Examinee veriSes red OPEN light ON and SGA-HS-170A on B06.
green CLOSED light OFF on SGA-HS-170A.
]
CUE: SGE-UV-170 red light on and green light off.
i SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 3.
Ensure ' A' accumulator pressure for SGE-Examinee displays 'A' accumulator pressure by
]
UV-170 is displayed on B07 instrument or either method such that pressure can be ERFDADS.
verified when operation of the 4-way valve is veriSed.
CUE: Accumulator "A" pressure is displayed.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
4
SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 4.
Ensure operator is in position to verify Examinee communicates with the operator at pulse of air.
the valve to position himself to feel a pulse of air at the vent port behind 'N' valve.
CUE: Operator is in position and ready.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Place SGA-HS-170C to "ACC CH TEST" Examinee places switch SGA-HS-170C on B07 5.
a and release.
to the "ACC CH TEST
- position, obtains position backlighted. and releases.
Accumulator pressure decreases.
CUE: Switch SGA-HS-170C was momentarily placed in "ACC CH TEST" and released.
SAT UNSAT (UNSAT requires comments) l COMMENTS:
5
SG018-J-C/R40 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 6.
Verify acewnulator A pressure decreases Examinee verifies accumulator ' A' pressure approximately 200 psig or more and a decreases approximately 200 psig or more by pulse of air is felt at the vent port.
observing SGA-PI-229 or ERFDADS display.
NOTE: Holding the switch in the "ACC CH TEST" position more than momentarily will produce more pressure drop than desired.
INFORM CUE: The AO at the valve reports feeling a pulse of air at the vent port.
CUE: Accumulator pressure dropped 300 psig.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 1
7.
Review Section 10.0, Contingencies for Examinee reviews contingencies in Section MSIV travel beyond 10% exercise limit 10.0.
switch.
l SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 8.
Inform local operator to notify the control Examinee informs local operator prior to test room when MSIV reaches 10% closed exercise of MSIV.
exercise limit and when the valve begins to reopen.
CUE: Local operator acknowledges message.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
6
SG018-J-C/R40 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Place SGA-HS-170C to " EXERCISE",
Examinee places SGA-HS-170C on B07 to the 9.
then release.
" EXERCISE" position, then releases.
Examinee observes blue exercise limit light lit when 10% closed exercise limit is reached.
When blue exercise limit light lit, CUE: AO reports valve at its 10% closed exercise limit and now beginning to reopen.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 10.
Acceptance Criteria: SGE-UV-170 travel Examinee records acceptance criteria satisfied 1
10% closed exercise limit verified in Appendix C.
locally. Record test results in Appendix C.
SAT UNSAT (UNSAT requires comments)
)
i 4
COMMENTS:
l 7
F SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 11.
Verify SGE-UV-170 indicates OPEN at Enminee verifies red OPEN lights 'ON' and l
SGA-HS-170A and SGB-HS-170B.
green CLOSED lights 'OUT' on B06 handswitches.
NOTE: This will take several minutes.
l CUE: SCE-UV-170 is full open.
l INFORM CUE: Another operator will monitor accumulator pressures and perform i
any necessary actions in Section 9.0, Restoration.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT l
COMMENTS:
l l
l l
8 l
1.
1 SG018-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 0
08/29/96 6
New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Resised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) j 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) 1 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) i i
i OTG-02 Rev. 0
SG018-J-C/R-00 PVNGS JGB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the Control Room.
You may use any source ofinformation normally available.
INITIATING CUE:
The Control Room Supervisor directs you to perform the Partial Stroke Exercise (Train A) of MSIV SGE UV-170 in accordance with 73ST-9SG01. All prerequisites have been met. An operator is stationed by the valve for any l
further instructions regarding this test.
j SAFETY CONSIDERATIONS:
None I
1 OTG-02 Rev. 0 11
- - o EW001-J-C/R-21
- PVNGS JOB PERFORMANCE MEASURE JPM BASIS INFORMATION l
TASK:
1250030401,1250030402, Recover from cross-tie of Essential Cooling Water to Nuclear Cooling Water Loads TASK STANDARD:
Nuclear cooling water flow restored to RCPs in less than 10 minutes from time essential cooling water flow was secured.
i K/A:
008 A2.01 K/A RATING:
RO:
3.3 SRO: 3.6 K/A:
008 K3.01 K/A RATING:
RO:
3.4 SRO: 3.5 APPLICABLE POSITION (S):
RO VALIDATION TIME:
10 min.
REFERENCES:
410P-INC01, Nuclear Cooling Water 4 IOP-lEW01, Essential Cooling Water, Train "A"
-J SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT APPROVAL DEVELOPER:
W. Potter TECH REVIEW:
((e
[Mfk REVISION DATE: 08/27/96 APPROVAL:
i TESTING METHOD l
,1(
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT 4
TESTING METliOD:
SIMULATE PERFORM 4
........s..".
EVALUATION EXAMINEE NAME:
(print)
]
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTO44)
,,....... =..,,,,,.........,,......,.....,....,.
.....,..........,...."............".o.........
w.'.
..".",w,.
OTG-02 Rev. 0 1
AAEWOOICR. DOC rbp 0906,96
. - -.. - ~.... - =. _ - -
..-.~..-.
i EW001-J C/R-21
SIMULATOR SETUP:
A.
IC#: 20 (Any power IC) l B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
t
]i EVENT COMMAND DES _CRIPTION 1.
MRF CC34 80 See SpecialInstructions -
1 2.
MRF CC06 Close See Special Instructions 3.
4.
1 j
C.
SPECIAL INSTRUCTIONS:
Cross tie EW Train "A" and NC by performing Sect. 4.0 of 40AO-9ZZ03.
3 Green flag all nonnal chillers.
4 MRF CC34 80 (throttles EW-HCN-053)
Close NCN-P01 A discharge valve NCN-HCV-9 (MRF CC06 close) l FREEZE Simulator.
~
When the examinee requests the AO at NCN-P01A to open NCN-HCV-9 then MRF CC06 open. (Valve takes 3 minutes to open)
D.
REQUIRED CONDITIONS:
EW Train "A" crosstied to NC per 40AO-9ZZ03 l
2.
SPECIAL TOOLS / EQUIPMENT:
j j
e None 1
OTG-02 Rev. 0 2
EW001-J-C/R-21
TASK CONDITIONS I
INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
e De examiner will provide all responses and indications required from outside the control room.
You may use any source ofinformation normally available.
INITIATING CUE:
A loss of nuclear cooling water has occurred. Essential cooling water (EW) train "A" has been aligned to supply nuclear cooling water (NC) loads. Nuclear cooling water system problems are repaired and you have been directed to restore NC/EW Systems to normal lineup per 410P-1EW01. All prerequisites are met.
An AO is stationed at the NC pump "A". NC pump "A" discharge valve, NCN IICV-9, is closed. The AO has verified surge tank level / pressure and has completed NC pump "A" prestart check list.
TIIIS IS A TIME CRITICAL JPM.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be termmated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized compl: tion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
NOTE: This is a Time Critical JPM (10 minutes from time EW to RCPs isolated until NC restored to RCPs).
SAFETY CONSIDERATIONS:
None i
l OTG-02 Rev. 0 3
i EW001-J-C/R-21
- PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
CLOSE EWA UV-65 using EWA-HS-65.
EWA-UV-65 is closed.
NOTE: TIME CRITICAL JPM STARTS WHEN RCP LOW NCW FLOW ALARMS ANNUNCIATE. Time limit is 10 minutes.
Record Time.
TIME:
CUE: EWA-UV-65 green light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD CLOSE EWA-UV-145 using EWA-HS-EWA-UV-145 is closed.
2.
a 145.
NOTE: Operator must now transition to 4IOP-INC01, Sect. 4.
CUE: EWA-UV-145 green light is on.
}
I SAT UNSAT (UNSAT requires conunents)
STEP ELEMENT STANDARD START NCN-P01 A Nuclear Cooling Pump started.
3.
Water Pump.
CUE: NCN P01A red light is on.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
4
1 o
EW001-J-C/R-21 PVNGS JOB PERFOR fANCE MEASURE i
STEP ELEMENT STANDARD 4.
Direct AO to OPEN NC-HCV-9.
AO directed to open NCN-HCV-9.
]
NOTE: It takes approximately 3 minutes to open the valve.
1 l
INFORM CUE: That AO reports NC-IICV-9 is open.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 1
5.
Verify that pump amps are less than 135 Examinee verifies:
amps and that pump running red light is on.
Amps < 135.
Red Light is "ON".
CUE: Amps are less than 135 and red light is "ON".
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 6.
Direct AO to report pressure on NCN-PI-5.
AO directed to report discharge pressure.
INFORM CUE: Local discharge pressure reading on NCN-PI-5 is 115 psig.
3 SAT UNSAT (UNSAT requires comments) i
!s-COMMENTS:
1 5
EWOOl-J-C/R-21
- PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 7.
When the NC System Low Pressure Alarm Examinee places NC pump B handswitch to clears, place handswitch for standby NC stop. (NC Pump B) pump in AUTO.
NOTE: Operator must now transition to
{
410P-1EW01, Sect. 9.
i CUE: NC pump "B"is green flagged..
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD OPEN NCN-UV-99, NC CTMT LEADER NCN-UV-99 open within 10 minutes from time 8.
RETURN, using NCN-HS-99. Monitor EW to containment isolated.
EW and NC surge tanks.
NC to RCP Low Flow alarms should be clear, j
NOTE: TIhE CRITICAL STOPS HERE.
RECORD TIhE.
TINE:
INFORM CUE: EW and NC surge tank levels are stable and at normal level.
CUE: NCN-UV-99 red light is on.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
6
}
=
a I
EW001-J-C/R-21 *
)
PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD I
9.
Notify Chemistry to sample EW 'A'.
Chemistry notified.
INFORM CUE: EW system flowrates have been adjusted for normal operations. Steps 9.4.1 thru 9.4.6 have been completed satisfactorily.
CUE: Chemistry is notified and has completed sampling.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 10.
STOP Essential Cooling Water pump, Pump stopped.
EWA P01, using EWA-HS-1.
CUE: EWA-P01 green light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 11.
STOP Essential Spray Pond Pump, SPA-Pump stopped.
P01, using SPA-HS-1.
CUE: SPA-P01 green light is on.
IF REQUESTED CUE: Diesel Generator "A" has not been recently run.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMLNATION POINT 1
l COMMENTS:
7
i EW001-J-C/R-21
- PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 21 08/30/96 6
New Format I
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) l l
l t
OTG-02 Rev. 0 8
EW001-J-C/R-21
- PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The exanuner will provide all responses and indications required from outside the control room.
You may use any source ofinformation normally available.
INITIATING CUE:
A loss of nuclear cooling water has occurred. Essential cooling water (EW) train "A" has been aligned to supply nuclear cooling water (NC) loads. Nuclear cooling water system problems are repaired and you have been directed to restore NC/EW Systems to ncrmallineup per 410P-1EWO1. All prerequisites are met.
An AO is stationed at the NC pump "A".
NC pump "A" discharge valve, NCN.
IICV-9,is closed. The AO has verified surge tank level / pressure and has completed NC pump "A" prestart check list.
TIIIS IS A TIME CRITICAL JPM.
SAFETY CONSIDERATIONS:
None OTG-02 Rev. 0 9
w RC012-J-C/R-11 c.R ; -
PVNGS JOB PERFORMANCE MEASURE n
JPM BASIS INFORMATION TASK:
0090010401, Determine if Plant Conditions Allow Restart of RCP 1 A.
TASK STANDARD:
RCP 1 A is running.
K/A:
003 A1.05 K/A RATING:
RO:
3.4 SRO: 3.5 K/A:
K/A RATING:
RO:
SRO:
APPLICABLE POSITION (S):
RO VALIDATION TIME:
20 min.
REFERENCES:
40EP-9EOO7, Loss of Offsite Power / Loss of Forced Circulation j
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT APPROVAL C
DEVELOPER:
W. POTTER TECH REVIEW:
8%
9-&-f4 REVISION DATE:
8/29/96 APPROVAL:-
TESTING METHOD 1
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT TESTING METHOD:
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop 1
REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTO44) l OTG-02 Rev. 0 1
AfRC012CR. DOC rbp 09/25.96
..m_
RC012-J-C/R-11 PVNGS JOB PERFORMANCE MEASURE 1.
SIMULATOR SETUP:
A.
IC# : 20 (or any powerIC)
B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION l
I.
None l
l 2.
l
)
3.
l 4.
l C.
TiPECIAL INSTRUCTIONS:
r i,
Go to RUN on the Simulator.
e Manually stop all the RCP's.
e Cooldown RCS to obtain Tc < 545 degrees using SBCS Acknowledge alarms and FREEZE Simulator after running at least 5 minutes.
D.
REQUIRED CONDITIONS:
Conditions suitable to run an RCP exist in the RCS with Tc < 545 F.
)
Pressurizer level is 36% or more.
e t
5 SPECIAL TOOLS / EQUIPMENT:
. None k
i
)
i
'l 4
OTG-02 Rev. 0 2
k RC012-J-C/R-11 PVNGS JOB PERFOlGIANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from.outside the control room.
You may use any source ofinformation normally available.
INITIATING CUE:
A loss of power to the RCPs resulted in a plant trip. RCP restart is desired. Power is now available to the RCPs, and the CRS has directed you to check that plant conditions and equipment will support RCP operation and start the RCP 1 A per 40EP-9EOO7, Loss of Offsite Power / Loss of Forced Circulation.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task e
Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
Any step marked LHSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
SAFETY CONSIDERATIONS:
- None OTG-02 Rev. 0 3
RC012-J-C/R-Il PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Obtain procedure 40EP-9EOO7 Obtain procedure 40EP-9EOO7, refer to step 51.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 2.
Electrical power is available to NAN S01 Verifies power available to NAN-S01.
or NAN-S02 CUE: NAN-S01 voltage is 13.8 kv.
SAT UNSAT (UNSAT requires comments) 4 i
STEP ELEMENT STANDARD 3.
RCP 1 A seat injection and bleedoff are in Verifies RCP 1 A seal injection satisfactory, no service alamis.
Verifies RCP 1 A seal bleedoff satisfactory, no
- alarms, 4
j CUE: RCP 1 A sealinjection flow is 6.6 gpm and bleedoff flow is 2.2 gpm with no alarms.
SAT UNSAT (UNSAT requires comments) 5 STEP ELEMENT STANDARD 4.
Nuclear Cooling Water is operating to Nuclear Cooling Water low flow alarms clear.
supply bearing and motor cooling I
CUE: Nuclear cooling water is 490 gpm to RCP 1 A with no alarms.
e SAT UNSAT (UNSAT requires comments) i COMMENTS:
a e
1 OTG-02 Rev. 0 4
. ~ -.
RC012-J-C/R 11 4
i PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 5.
No high temperature alarms on the selected Verifies RCP 1 A "TRBL" alarm clear and no i
RCPs.
alarms on BO7 recorder.
I CUE: Panel 4A window 2A is off and
)
recorder IJRMTJR2 has no alarm status lights lit.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD l
6.
At least one Steam Generator has level Verifies at least one SG level 10% WR or more.
l 10% WR or more and is maintaining RCS Verifies sG maintaining RCS heat removal by l
j heat removal.
being capable of feeding and steaming.
CUE: Steam generator levels are 40% NR 4
and being fed by main feedwater. Steaming
{
is through steam bypass valve 1001.
. SAT UNSAT (UNSAT requires comments)
]
i 1
STEP ELEMENT STANDARD 7.
Determine RCS 24 F or more subcooled RCS subcooling determined to be >24 F using using CET subcooling, curves, QSPDS or other acceptable method.
CUE: RCS subcooling is 35'F by CET.
j SAT UNSAT (UNSAT requires comments) i a
COMMENTS:
OTG-02 Rev. 0 5
RC012-J-C/R-11 PVNGS JOB PERFORMANCE MEASURE
's STEP ELEMENT STANDARD 8.
G5/186R-1 and G3/186R-2,"TURB &
Verifies G5/186R-1 and G3'186R-2 are reset.
GEN AUX TRIP & LO RELAY", on MAN-C01 are reset.
Note: MAN-C01 located behind control boards.
CUE: Relays G5/186R-1 and G3/186R-2 are i
reset.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD i
9.
Ensure The RCP handswitch is green Ensures RCP 1 A handswitch green flagged.
)
j flagged.
CUE: RCP I A handswitch is green-flagged.
4 SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Ensure The RCP breaker "286 LO" Relay AO directed to reset "286 LO" relay.
10.
is reset.
Inform Cue: RCP I A "286 LO" relay reset.
J SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Ensure RCP Speed Switch Trip Relay 214 AO directed to reset RCP 1 A Speed Switch 11.
" SLOW SPEED AL" target is reset.
T'ip Relay 214.
Ir. form Cue: RCP 1 A Speed Switch Trip Relay 214 is reset.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
OTG-02 Rev. 0
RC012-J-C/R-11 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 12.
Ensure RVUH levelis 100% and Verifies RVUH levelis 100% on QSPDS or Pressurizer level is 36% or more.
ERFDADS.
Verifies Pressurizer level is 36% or more using available instmmentation, applying any necessary correction factors.
CUE: RVUli levelis 100% and pressurizer level is 36%.
i SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD 13.
Start any available Charging Pumps.
Examinee starts the remaining charging pumps.
CUE: Charging pump red lights are on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Ensure the appropriate Oil Lift Pumps have RCP 1 A Oil Lift Pump started and running.
14.
1 been running for 7 minutes or more.
CUE: Oillift pump red light is on.
Inform CUE: Oillift pump have been running for 7 minutes.
SAT UNSAT (UNSAT requires comments) i CC MMENTS:
i e
OTG-02 Rev. 0 7
i
RC012-J-C/R-11 PVNGS JOB PERFOR31ANCE SIEASURE STEP El,EMENT STANDARD 15.
Ensure that T, is less than 545 F.
Verifies T, < 545 degrees.
CUE: Tc is 543 *F.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 16.
Start RCP 1 A.
RCP 1 A running.
CUE: RCP 1 A red light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 17.
Check that RCP amps stabilize at 360 - 500
'/erifies RCP 1 A amps 360 - 500 amps.
amps CUE: RCP 1 A amps are 420.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 18.
Check NPSH, REFER TO Appendix 2 Verifies NPSH satisfied by referring to Figure Figures.
and available RCS pressure and temperature instruments.
CUE: RCS pressure is 2250 psia and T, is 543.
SAT UNSAT (UNSAT requires comments) i j
C05151ENTS:
i OTG-02 Rev. 0 8
1 i
RC012-J-C/R-11 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Operate Charging and HPSI Pumps until St Verifies HPSI throttle criteria met.
throttle criteria are met.
CUE: Pressurizer level is 40%. Subcooled margin is !6*F. Reactor vessel upper level is 100%. Steam generator levels are 40%
narrow range.
SAT UNSAT (UNSAT requires comments) i NORMAL TERMINATION POINT i
i a
i t
d 1
1 i
4 t
l OTG-02 Rev. 0 9
RC012-J-C/R-il PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 10 07/25/96 3
OTG-02 11 08/29/96 6
New Format RE ASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) 1 l
OTG-02 Rev. 0 10
RC012-J-C/R-11 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the control room.
You may use any source ofinformation normally available.
INITIATING LUt.:
A loss of power to the RCPs resulted in a plant trip. RCP restart is desired.
Power is now available to the RCPs, and the CRS has directed you to check that plant conditions and equipment will support RCP operation and start the RCP 1 A per 40EP-9EOO7, Loss of Offsite Poner/ Loss of Forced Circulation.
SAFETY CONSIDERATIONS:
None i
OTG-02 Rev. 0 11
1 3
PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE j
4 i
JPM BASIS INFORMATION s
l TASK:
0720030601, De-energize 4.16 kv Bus PBA-S03 TASK STANDARD:
Bus PBA-S03 de-energized and Diesel Generator 'A' not nmning.
i K/A:
062 A4.01 K/A RATING:
RO:
3.3 SRO: 3.1 K/A:
K/A RATING:
RO:
SRO:
i APPLICABLE POSITION (S):
RO VALIDATION TIME:
20 min.
REFERENCES:
410P-IPB01,4.16kv Class IE Powe,r l
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT 1
i APPROVAL i
~
DEVELOPER:
W. Potter TECH REVIEW:
', 8%
9-77 -74 REVISION DATE:
08/30/96 APPROVAL:
f i
i l
TESTING METHOD l
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT O
TESTING METaOD:
SIMULATE PERrORM l
EVALUATION I
EXAMINEE NAME:
(print) i i
EVALUATOR NAME:
l (print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG-04) 4 l
jlO OTG-02 Rev. 0 1
AnPD003CR.IXX' rbp 097596 J
.. -. - ~
~
PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE 1.
SIMULATOR SETUP:
l l
A.
IC#: 4 (or suitable Mode 5 IC) i B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
I EVENT COMMAND DESCRIPTION 1.
MRF CV37 E Chg pump transfer switch (see instructions) 2.
MRF CV39 E Chg pump breaker power (see instructions) 3.
MRF EGil DG "A" Control Mode Selector Switch.
4.
C.
SPECIAL INSTRUCTIONS:
Swap the E CHG Pump to "B" Train power, (mrf ev37 TRN_B_PWR, mrf ev39 B_TRN_PWR).
Place CHG Pump Mode control switch in the 2-3-1 position.
Go to RUN on the Simulator.
Establish AFW Flow from AFB-P01 and secure AFN-P01.
Green flag the "A" Normal Chiller.
Open the following LC breakers: PGA-L31B2, -L33B2, -L35B2..
Acknowledge alarms.
SIM Driver action is required at JPM Step 4 to place the DG "A" in OFF position (mrf eg 11 off).
D.
REQUIRED CONDITIONS:
Charging pump "E" on "B" Train.
AFB-P01 supplying SGs.
Normal Chiller "A" "OFF".
Load center breakers PGA-L31B2, L33B2, and L35B2 "OPEN" 2.
SPECIAL TOOLS / EQUIPMENT:
Key to bypass all eight LOP relays on Train "A" BOP /ESFAS cabinet.
OTG-02 Rev. 0 2
PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE i
TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
You may use any source ofinformation normally available.
e Operation of equipment is to be performed on the simulator.
The exammer will provide all responses anit indications required from outside the control room.
INITIATING CUE:
PBA-S03 must be de-energized for emergency repair. The CRS directs you to perform the actions necessary to de-energize PBA-S03 IAW 410P-1PB01.
Operations Management and the Shift Supervisor have given permission for PBA-S03 to be de-energized. Other ROs will perform any Surveillance's required.
An Area Operator is standing by in the "A" Train Class Switchgear room to assist as necessary. IIe has the DG "A" Control Mode Selector Key in his possession.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Exammer/ Evaluator, this JPM may be termmated when the Task e
Standard is met or adequate time has been allowed to complete the JPM. It shall be temunated when the Examinee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the exammee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
SAFETY CONSIDERATIONS:
None
=
i I
OTG-02 Rev. 0 3
l
\\
PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Review Tech. Specs. 3.8.l.1 and 3.8.3.1 Examine determines need to review Tech. Spec.
prior to isolation of 4.16 kv Bus PBA-S03.
application.
After Examine discusses need to review TechnicalSpecifications, CUE: The CRS has reviewed all Technical Specifications which are applicable.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD All eight LOP relays bypassed with the
. All eight LOP relays bypassed with the four 2.
four key switches on Train "A" key switches on the Train "A" BOP ESFAS BOP /ESFAS cabinet SAA-C02A.
cabinet SAA-C02A.
NOTE: May use 400P-9SA01 to perform bypass.
CUE: All bypass lights are on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 3.
Prior to opening breakers S03H, S03J and LCs PGA-L31,-L33,-L35 verified to be de-S03N De-energize load centers PGA-L31,-
energized.
L33,-L35 per 41OP-1PG01.
If necessary, CUE: LCs PGA-L31, L33,-
L35 B2 breakers green lights are on.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
4
1 L
PB003-J-C/R-03 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD DISABLE the DG "A" by placing the Examine directs the AO to disable DG "A" by 4.
a Control Mode Selector Switch to "OFF" placing the Control Mode Selector Switch in the "OFF" position.
After AO is given direction and action is taken, CUE: DG "A" has been place in the OFF position.
l
]
NOTE: SIM Driver must perform the following: mrf egl1 off SAT UNSAT (UNSAT requires comments)
?
STEP ELEMENT STANDARD 5.
Open the following feeder breakers on Examine verifies breakers opened.
4 PBA S03:
-S03C, Essential Spray Pond Pump SPA-Pol
-S03D, Containment Spray Pump SIA-P03 i
-S03E, H.P. Safety injection Pump SIA P02
-S03F, L. P. Safety Injection Pump SIA-P01
-S03G, Essential Chiller ECA-E01
~
-503H, Load Center PGA-L31
-S03J, Load Center PGA-L33
-S03M, Essential Cooling Pump EWA-P01
-S03N, Load Center PGA-L35
-S03P, Normal Chiller WCN-E01 A
-S03S, Aux. Feedwater Pump AFN-P01
)
CUE: Green lights are lit on all breakers on PBA-503.
1 SAT UNSAT (UNSAT requires comments) l COMMENTS:
1 4
i 5
PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 6.
Check open PBA S03K by obsening that Exarnine verifies PBA-S03K is open.
the green breaker light is on.
CUE: PBA-S03K green light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 7.
Check open DG"A" breaker PBA S03B Examine vedfies PBA-S03B is open.
by obsening that the green light is "on" CUE: PBA-503B green light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Open the PBA S03 normal supply Examine opens PBA-S03L.
8.
breaker PBA-S03L.
CUE: PBA-S03L green light is on.
SST UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT l
COMMENTS:
6
l L
PB003-J-C/R-03 l
PVNGS JOB PERFORh.ANCE MEASURE l
RECORD OF REVISIONS l
REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 03 08/30/96 6
New Format f
i t
i REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments ue to be numbered l
consecutively in each revision.
i l
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3, Procedure upgrade 4.
Internal or Extemal Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) i 1
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OTG-02 Rev,0 7
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PB003-J-C/R-03 '
PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMIhTE:
P SPECIAL CONSIDERATIONS:
You may use any source ofinformation normally available.
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the control room.
INITIATING CUE:
PBA-S03 must be de-energized for emergency repair. The CRS directs you to perform the actions necessary to de-energize PBA-503 1AW 410P-1PB01.
Operations Management and the Shift Supervisor have given permission for PBA-S03 to be de-energized. Other ROs will perform any Surveillance's required.
An Area Operator is standing by in the "A" Train Class Switchgear room to assist as necessary. He has the DG "A" Control Mode Selector Key in his possession.
SAFETY CONSIDERATIONS:
None i
l
)
l i
OTG-02 Rev. 0 8
l '
-1 r
CH003-J-C/R-22" 6.i >
PVNGS JOB FERFORMANCE MEASURE
-:.+
....m.......m.3.....
.....3..
.s...r..,.........
....s...,.
JPM BASIS INFORMATION TASK:
0150030801, Perform a Boration of the RCS TASK STANDARD:
Boration of 75 ( 25) gallons performed.
K/A:
004 A4.01 K/A RATING:
RO:
3.8 SRO: 3.9 K/A:
004 A2.23 K/A RATING:
RO:
2.6 SRO: 2.7 APPLICABLE POSITION (S):
RO VALIDATION TIME:
15 min.
REFERENCES:
410P-lCH01, CVCS Nonnal Operations,41 AL-lRK3A, Panel B03A Alarm Response SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT APPROVAL DEVELOPER:
W. Potter TECH REVIEW
[M f-2M4 REVISION DATE: 08/27/96 APPROVAL TESTING METHOD ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT I
l TESTING METHOD.
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
(print)
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY l
Time Start Time Stop l
REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG-04) l l
OTG-02 Rev. 0 1
I A:\\Cl1003CR. DOC rbp 09/26/96
l 1 CH003-J-C/R-22' PVNGS JOB PERFORMANCE MEASURE A. SIMULATOR SETUP:
- 1.. IC# 20 -
- 2. MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
IMF CV09100 30 Clog boron injection filter (see below) 2.
MMF CV09 01:00 See Special Instructions.
l 3.
l 4.
l l
1.
SPECIAL INSTRUCTIONS:
i After Examinee increases setpoint on CH-FIC-210Y to 25 gpm (JPM Step 7), enter: IMF CV09 100 30 (This clogs the Boron injection filter)
When Examinee requests AO to open filter bypass valve CHV-V164 (JPM Step 10), then {MMF CV09 01:00} (This simulates opening CHN-V164 slowly so CH-527 and CH-512 don't close on high D/P.
l 2.
REQUIRED CONDITIONS:
- . None, l
j-A. SPECIALTOOLS/ EQUIPMENT:
NONE l
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i 9
r J
OTG-02 Rev. 0 2
i I
4 CB003-J-C/R-22' PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the control
=
4 room.
You may use any source ofinformation normally available.
INITIATING CUE:
The CRS directs you to borate the RCS by using 410P-1CH01. The quantity to be added has been determined to be 75 gallons from the RWT at a rate of 25 gpm. Use CHN-FIC-210Y in automatic to the charging pump suction.
All Prerequisites are complete.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task
=
Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the exammee has been briefed 1AW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
NOTE: This is an altemate path JPM.
SAFETY CONSIDERATIONS:
NONE OTG-02 Rev. 0 3
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-..=
. =
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i CH003-J-C/R-22' PVNGS JOB PERFORMANCE MEASURE 2
STEP ELEMbT STANDARD 1
Set boric acid makeup flow controll'.r Examinee verifies controller setpoint 5 CHN-FIC-210Y to "0" gpm and place 0 and " Auto" selected.
controller to AUTOMATIC.
~
CUE: Controller CHN-FIC-210Y auto light is on, set to "0" gpm.
SAT UNSAT (UNSAT requires comments)
^
STEP ELEMENT STANDARD Set boric acid flow totalizer to desired Examinee sets the totalizer to 75 gals, 2
volume (75 gallons).
CUE: Totalizer set to 75 gallons.
i SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Select " BORATE" on makeup mode Examinee selects " Borate" 3
selector switch, CHN-HS-210.
CUE: Makeup mode selector is in
" Borate".
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 4
Verify BAMP pump stans.
Examinec verifies BAMP Pump f
mnmng.
CUE: BAMP red light is on.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
i OTG-02 Rev. 0 4
1 CH003-J-C/R-22" PVNGS JOB PERFORMANCE MEASURE STEP ELE 31ENT STANDARD 5
Vertfy CHN-FV-210X is closed.
Examinee verifies CHN-FV-210X is closed and no flow indicated.
CUE: CHN FV-210X signalis 0, flow is 0.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 6
Verify CHN-UV-527 is open.
Examinee verifies CHN-UV-527 is open.
CUE: CHN-UV-527 red light is on.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 7
Adjust CHN-FIC-210Y to the desired Exanunce adjusted the Auto setpoint to flow rate (25 gpm).
25 gpm ( 5 gpm).
NOTE: Simulator driver action required to plug BA Filter.
CUE: CHN-FIC-210Y adjusted to 25 gpm.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
l OTG-02 Rev. 0 5
i CU003-J-C/R-22" PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Venfy the proper flow rate is indicated.
Examinee identifies that the flow is not g
responding properly and informs the CRS.
CUE: Alarm 3A06A is alarming.
Alarm CRT has " Boric Acid Filter High dp". CRS directs you to respond to the alarm.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Verify alarm 3A06A; by directing Examinee directs operator to check 9
operator to read Boric Acid Filter local filter differential pressure.
differential pressure locally on CHN-PDIS-260.
INFORM CUE: Filter DP is pegged high.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
OTG-02 Rev. 0 6
a l
CH003-J-C/R-22'
]
PVNGS JOB PERFORMANCE MEASURE 4
i STEP ELEMENT STANDARD Direct operator to open Filter Bypass Examinee directs operator to open 10 Valve CHN-V164 and close CHN-CHN-V164 and close CHN-V161.
1 V161.
INFORM CUE:
CHN-V164 is open, CHN-V161 is closed.
The operator will remove the BA filter from service as directed by 1
procedure.
NOTE: Simulator driver action required to delete malfunction per j
SPECIAL INSTRUCTIONS.
4 i
4 i
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD When the desired amount of acid has Examinee ensures FIC-210Y is closed 3g been added, ensure FIC-210Y is closed.
and no excessive flow indicated after desired 75 gallons ( 25) of acid is added.
CUE: FIC-210Y output is 0, flow is 0.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Selects Auto on makeup mode select Examinee selects Auto on the Makeup 12 switch, CHN-HS-210.
Mode Select Switch.
CUE: Makeup mode select is in
" AUTO" SAT UNSAT (UNSAT requires comments)
COMMENTS:
OTG-02 Rev. 0 7
f CH003-J-C/R-22" PVNGS JOB PERFORNIANCE MEASURE
~
STEP ELE 31ENT STANDARD 13 Verify that CHN-UV-527 closes.
Examinee verifies CHN-UV-527 closed.
CUE: CHN-UV-527 green light is on.
j SAT
,UNSAT (UNSAT requires comments) i
}
STEP ELE 31ENT STANDARD y
Ensure boric acid pump stops.
Examinee ensures BAMP Pump stops.
INFORNI CUE: BASIP green light is on. Steps to flush, sample, change set points and realign system are not necessary at this time.
1' SAT UNSAT (UNSAT requires comments)
NORMAL TER311 NATION POINT i
COM51ENTS:
4 l
OTG-02 Rev. 0 8
t-
.'3 l
at CH003-J-C/R-22' PVNGS JOB PERFORMANCE MEASURE i
I j
I.ECORD OF REVISIONS l
REVISION
. REASON REVISION DATE REVISED NUMBER CONSENTS
^
22-08/28/96 6
New Format 1
i i
i i
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Resised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include nu: 10er) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) i Technical Specification Change (indicate amendment number) 6.
Other(explain in comments)
OTG-02 Rev. 0 9
-- - - ~
i 4
CH003-J-C/R-22' PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the control room.
You may use any source ofinformation normally available.
INITIATING CUE:
The CRS directs you to borate the RCS by using 410P-1CH01. The quantity to be added has been determined to be 75 gallons from the RWT at a rate of 25 gpm. Use CHN-FIC-210Y in automatic to the charging pump suction.
I All Prerequisites are complete.
i SAFETY CONSIDERATIONS:
NONE i
1 OTG-02 Rev. 0 10
8 CII008-J-PLT-14
({;;)
PVNGS JOB PERFORMANCE MEASURE JPM BASIS INFORMATION j
TASK:
0159480501, Perform Outside Control Actions for Emergency Boration using Spnt Fuel Pool through CH-HV-536.
TASK STANDARD:
Emergency Boration lined up from the Spent Fuel Pool through CHE-lW-536.
K/A:
APE 024 Al.04 K/A RATING:
RO:
3,6 SRO: 3.7 K/A:
K/A RATING:
RO:
SRO APPLICABLE POSITION (S):
RO VALIDATION TIME:
10 mins.
REFERENCES:
40AO-9ZZ01, Emergency Boration SUGGESTED TESTING ENVIRONMENT:
SIMULATOR PLANT X
APPROVAL DEVELOPER-W. Potter TECH REVIEW:
[b 9 #74 REVISION DATE:
8/30/96 APPROVAL:
TESTING METHOD ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT
(
TESTING METHOD:
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
(print)
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG44)
OTG-02 Rev. O I
ASC11008 PLT. DOC rbp 09/26.96
l s
5 CH008-J-PLT-14 PVNGS JOB PERFORMANCE MEASURE i
1.
SIMULATOR SETUP:
A.
IC#: NA B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
NA 2.
3.
4.
C.
SPECIAL INSTRUCTIONS:
1
. NA D.
REQUIRED CONDITIONS:
NA 2.
SPECIAL TOOLS / EQUIPMENT:
None i
I j
i OTG-02 Rev. 0 2
.= _
5 CII008-J-PLT-14 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS f
INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any 4
equipment.
Inform the control room staff of any discovered deficiencies.
You may use any source ofinformation normally available.
Comply with the REP, ifit is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do not enter contanunated, airborne, or high radiation areas INITIATING CUE:
The CRS directs you to perform the in-plant steps necessary to initiate emergency boration of the RCS from the spent fuel pool through CH-HV-536, per 40AO-9ZZ01, Emergency i
Boration. Only the equipment outside the control room needs to be operated.
4 Sufricient level exists in the spent fuel pool to perform this operation.
RWT cleanup using a spent fuel pool cleanup pump is not in progress.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Exammer/ Evaluator, this JPM may be termmated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be termmated when the Examinee has verbalized completion of the JPM.
4 Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
Notify unit Shift Supervimr ofin-plant JPM performance.
Examinee must comply with REP, if not failure of JPM will result.
SAFETY CONSIDERATIONS:
Hearing protection may be required.
i OTG-02 Rev. 0 3
1 l
=
5 CH008-J-PLT-14 j
PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Open ZAN-C01 DS-22-14 control circuit Examinee simulates opening DS-22-14 at 1.
a for CHE-HV-532 ZAN-C01 CUE: DS-22-14 is open.
l SAT UNSAT (UNSAT requires comments) i l
STEP ELEMENT STANDARD 2.
Ensure PCN V036, RWT M/U isol to Examinee simulates checking closed PCN-cleanup pumps suction, is closed.
V036.
CUE: PCN-V036 is closed.
j NOTE: Located on the 100' FB. Near cleanup pumps.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Open PCN-V215, SFP to CVCS isolation.
Examinee simulates checking open PCN-V215.
3.
a CUE: PCN-V215 is open.
l NOTE: Located on the 100* Fuel Bldg. North i
of cleanup pumps.
SAT UNSAT (UNSAT requires comments) l l
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COMMENTS:
4 e
e 1
4
s CH008-J-PLT-14' PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Open/ check open CH-V144, SFP to BAMP Examinee simulates opening CH-V144.
4.
a ISOL. valve.
i CUE: CH-144 is open.
NOTE: Located in the BAMP room 70' Aux.
Hearing protection may be required.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 5.
Ensure IAN-V252, Instrument Air to Examinee simulates closing IAN-V252.
CHE-HV-532 is closed.
CUE: IAN-V252 closed.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
5
s 5
CH008-J-PLT-14 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD j
6.
Unlock the handwheel for CHE-HV-532.
Examinee simulates unlocking the handwheel for CHE-HV-532.
CUE: Handwheel for CHE-HV-532 is unlocked.
j SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD Close CHE-HV-532, RWT to BAM Pump Examinee simulates closing CHE-HV 532.
l 7,
a j
by performing the following:
)
4 a.
Close CHE-HV-532 by rotating As Examinee simulates actions CUE:
handwheel clock-wise while CHE-HV-532 is closed.
]
observing downward stem movement.
1 t
5%T UNSAT (UNSAT require. comments)
"ORMAL TERMINATION POINT
- l l
COMMENTS:
I l
6
CH008-J-PLT-14' PVNGS JOB PERFORMANCE MEASURE.
RECORD OF REVISIONS I
I REVISION REASON REVISION DAH REWSED NUMBER COMMENTS 14 09/03/96 6
New Format l
l 6
1 l
l l
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicste item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments)
I 1
l OTG-02 Rev. 0 7
... ~
1 a
5 CH008-J-PLT-14 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS
\\
INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
Inform the control room staff of any discovered deficiencies.
i You may use any source ofinformation normally available.
comply with the REP, ifit is not possible to enter an area it may be permissible to discuss the equipment to be operated. do not enter contammated, airbome, or high radiation areas.
)
INITIATING CUE:
The CRS direcis you to perform the in-plant steps necessary to initiate emergency boration of the RCS from the spent fuel poci through CH-HV-536, per 40AO-9ZZ01, Emergency Boration. Only the equipment outside the control room needs to be operated.
Sufficient level exists in the spent fuel pool to perform this operation.
RWT cleanup using a spent fuel pool cleanup pump is not in progress.
l SAFETY CONSIDERATIONS:
Hearing protection may be required.
i b
e d
4 S
l OTG-02 Rev. 0 8
=. _ _ _. _. _
+
DG007-J-PLT-09 (S~
- T
.i i
JPM BASIS INFORMATION a
TASK:
1240025301, Restore DG "A" to PBA-S03 TASK STANDARD:
Diesel Generator 'B' is running.
j K/A:
EPE EA1.02 K/A RATING:
RO:
4.3 SRO: 4.4 1
K/A:
EPE EA1.06 K/A RATING:
RO:
4.1 SRO: 4.5 l
APPLICABLE POSITION (S):
RO VALIDATION TIME:
20 min.
REFERENCES:
40EP-9E010, Appendix 56, Restore DG B to PBB-SO4 i
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR PLANT X
2 APPROVAL DEVELOPER:
W. Potter TECH REVIEW:
eI P-27-f4 REV1510N DATE:
08/23/96 APPROVAL:
TESTING METHOD j
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT b
TESTING METHOD:
SIMULATE PERFORM EVALUATION J
j EXAMINEE NAME:
(print)
EVALUATOR NAME:
(print) i SATISFACTORY UNSATISFACTORY l
Time Start Time Stop I
REMEDIAL TRAINING REQUIRED?
YES NO l
(SEE OTO44) i
(
OTG-02 Rev. 0 1
A"DG007 PLT. DOC rbp 09/25S6 i
i i
.-_____m a
DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE 1.
SIMULATOR SETUP:
A.
IC# : NA B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
NA 2.
3.
4.
C.
SPECIAL INSTRUCTIONS:
NA D.
REQUIRED CONDITIONS:
NA 2.
SPECIAL TOOLS / EQUIPMENT:
None 1
i L
OTG-02 Rev. 0 2
DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any egmpment.
Inform the control room staff of any discovered deficiencies.
You may use any source ofinformation nonnally available.
INITIATING CUE:
The plant has experienced an electrical blackout condition. The emergency diesel generators are not running. The Shift Supervisor has directed you to recover and start Emergency Diese! Genernor B using 40EP-9EO10, Standard Appendices, Appendix S6.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be temunated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be temunated when the Exanunce has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
Notify unit Shift Supervisor ofin-plant JPM performance.
Do not allow any operation of equipment.
SAFETY CONSIDERATIONS:
When checking / identifying equipment on the diesel avoid placing yourself or exammee in precarious positions. Use available drawings of equipment as appropriate to discuss operation where possible (eg - intake air butterfly valve).
OTG-02 Rev. 0 3
DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Determine annunciator panel status.
Exammee obsenes annunciator panel.
CUE: Annunciator panelindicates "OVERSPEED ENGINE".
(DGB-07A)
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD EIgg "STOP" on DGB-HS-30 "DGB Examinee simulates pressing DGB-HS-30.
2.
Emergency Stop".
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STAND.GD Press the plunger on DGB-UV-238 Examinee simulates pressing plunger on DGB-3.
a "overspeed trip valve" UV-238.
NOTE: Located generator platform southeast of the diesel.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
4
=
F DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 4.
Reset the intake air butterfly valve; Examinee locates and simulates / explains Ensuring handle is latched.
resetting Intake Air Butterfly Valve by referring to Attachment 56-A. (Resetting intake air butterfly valve).
When the Examinee has identified the valve and verified per Attachment 56-A, provide the following CUE: Intake Air Butterfly i
Valve is reset and handle is latched.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 5.
Inform Control Room that the D/G may start.
s Examinee simulates informing Control Room that "B" D/G may start.
CUE: Control Room acknowledges Diesel Generator "B" may start.
SAT UNSAT (UNSAT requires comt.:ents)
STEP ELEMENT STANDARD Press " Reset" on DGB-HS-30 "DG B Examinee simulates pressing DGB-HS-30.
6.
a Emergency Stop" to start the diesel generator.
CUE: "B" diesel generator is running.
_ UNSAT (UNSAT requires comments)
COMMENTS:
5
o DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 7,
Inbrm the responsibt: operator that this CUE: Control room is informed that appendix is complete.
Appendix 56 is complete.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POLNT i
i e
COMMENTS:
~
l l
6 i
h -
y
~ -
o DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DAE REMSED NUMBER COMMENTS 09 085 0/96 6
New Format 1
l l
REASON REVISED Enter the numbers cor...ang to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comm-nts are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other(explain in comments)
OTG-02 Rev. 0 7
~.
DG007-J-PLT-09 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS i
INFORMATION PRESENTED TO EMIINEE:
{
1 SPECIAL CONSIDERATIONS:
Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
i' Inform the control room staff of any discovered deficiencies.
You may use any source ofinformation normally available.
INITIATING CUE:
The plant has experienced an electrical blackout condition. The emergency diesel l
generators are not running. The Shift Supervisor has directed you to recover and start Emergency Diesel Generator B using 40EP-9EO10, Standard Appendices, l
Appendir 56.
f SAFETY CONSIDERATIONS:
I When checking / identifying equipment on the Diesel avoid placing yourself or examinee
=
in precarious positions. Use available drawings of equipment as appropriate to discuss operation where possible (eg - intake air butterfly valve).
1 l
l 4
4 I
OTG-02 Rev. 0 8
)
a
+
__._3.-w.
.2..A
_,_A4.
4:
a4
.._..m__u-huh.-.A.,
_A..
22.
J-_
A_
A..
- _e--
Ah.
kAa-_.Am a
I I
EM007-J-PLT-14
i JPM BASIS INFORMATION TASK:
1240023901, Perform Local Operation of AFN-P01 l
TASK STANDARD:
AFN-P01 breaker is closed.
K/A:
061 A2.04 K/A RATING:
RO:
3.4 SRO: 3.8 i
K/A:
EPE EAl.1 K/A RATING:
RO:
4.0 SRO 3.9 APPLICABLE POSITION (S):
RO VALIDATION TIME:
10 mm.
l
REFERENCES:
40EP-9E010, Appendix 41, local Operation of AFN-P01 l
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR PLANT X
APPROVAL DEVELOPER:
W. Potter TECH REVIEW:
8 A2pg REVISION DATE:
08/23/96 APPROVAL:
TESTING METHOD ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT TESTING METHOD:
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
(print)
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG-04)
O OTG-02 Rev. 0 1
AfLM007 PLT. DOC rbp 09/26/96
.__-_.___-..._.-m
____-==_m__
_ _ _.l i
EM007-J-PLT-14
SIMULATOR SETUP:
I A.
IC#: NA B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
l EVENT COMMAND DESCRIPTION 1.
NA 2.
3.
4.
l l
C.
SPECIAL INSTRUCTIONS:
NA l
D.
REQUIRED CONDITIONS:
NA 2.
SPECIAL TOOLS / EQUIPMENT:
Exanunce must know where to locate the equipment needed to perform this evolution. These are found in Emergency Equipment Cabinet FPN-C02 on the 100' level of the control building in the "B" switchgear room.
l l
A suitable replacement for the actual breaker may be used, such as one from/in a breaker lab j
that has the necessary referenced components.
i i
l t-l l
l t
1 i
e 4
4 OTG-02 Rev. 0 2
s
~
EM007-J-PLT-14
- PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation ofin plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
Inform the control room staff of any discovered deficiencies.
You may use, ny source ofinformation normally available.
INITIATING CUE:
A Loss of All Feedwater event has occurred. There has also been a loss of 12SV DC control power to breaker PBA-S03S. The CRS directs you to perform a local manual start of the non-class Auxiliary Feed Pump, AFN-P01, per Standard Appendix 41, 1-A.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the examiner / evaluator, this JPM may be temunated wren the task
=
standard is met or adequate time has been allowed to complete the JPM. It shall be tenninated when the examinee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
If this is the first JPM of the set then ensure the ernninee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
Notify unit Shift Supervisor ofin-plant JPM performance.
Do not allow any operation of equipment SAFETY CONSIDERATIONS:
'Ihis breaker is located in an energized cabinet. Ensure necessary precautions to prevent contact with energized equipment.
OTG-02 Rev. 0 3
EM007-J PLT-14
- PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 1.
Check that the closing springs indicator for Examinee simulates opening breaker cubicle breaker PBA-S03S " Aux Feedwater Pump door to observe closing spring indicator.
M-AFN P01" indicates"CHGD" CUE: Closing springs do nnt indicate charged.
NOTE: Charging spring indicator located in middle left side of cubicle.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT
. STANDARD 2.
Obtain All the following equipment from Examinee simulates obtaining equipment from FPN-C02 " Emergency Equipment Cabinet" FPN-C02 " Emergency Equipment Cabinet" by Ratchet demonstrating location and how to gain access.
Extension 5/8" Socket NOTE: $/8" socket and ratchet wrench located in Emergency Equipment Locker FPN-C02 on the 100' level of the Control Bldg. in the 'B' switchgear room.
Inform CUE: Proceed to the non-class switchgear room to demonstrate breaker operations.
SAT UNSAT (UNSAT requires comments)
]
COMMENTS:
l 4
EM007-J-PLT-14
- PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD Manually charge the closing springs.
Examinee simulates manually charging closing 4.
spring by pointing out closing springs driving stud and indicating that he would rotate stud in the clockwise direction until closing springs indicator says " Charged" CUE: Closing springs indicate charged.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 5.
Close the RRA 125 V DC Control Power Examinee simulates closing Control Power Breaker.
Breaker for PBA-S03S. (RRA)
CUE: Control Power Breaker for PBA-S03S is closed.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD Press the " Manual Close" plunger for the Examinee simulates pressing the manual close 6.
breaker, PBA-S03S.
pushbutton to close PBA-S03S.
SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 7.
Check that the mechanical breaker Examinee simulates verifying PBA-S03S indication for the breaker PBA.S035 closed by observing closed flag on breaker (or indicates closed.
breaker position indicator).
1 CUE: PBA-S03S indicates closed.
SAT UNSAT (UNSAT requires comments)
COMMENTS:
5
)
EM007-J-PLT-14
STEP ELEMENT STANDARD 8.
Inform the responsible operator that the Examinee simulates informing the responsible attachment 41 A is complete.
operator that attachment 41 A is complete.
CUE: Control Room is informed of 1-A completion.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT i
1 i
i 1
l l
COMMENTS:
i 6
i
4 i
EM007-J-PLT-14
RECORD OF REVISIONS REVISION REASON
~
REVISION DATE REVISED NUMBER COMMENTS i
14 08/29/96 6
New Format i
j i
4 4
4 1
i I
REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) t i
OTG-02 Rev. 0 7
I i
a EM007-J-PLT-14
- PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS
)
INFORMATION PRESENTED TO EXAMINEE:
)
l i
SPECIAL CONSIDERATIONS:
Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT I
=
OPERATE any equipment.
Inform the control room staff of any discovered deficiencies.
You may use any source ofinformation normally available.
INITIATING CUE:
A Loss of All Feedwater event has occurred. There has also been a loss of 125V DC control power to breaker PBA-S03S. The CRS directs you to perform a Local Manual start of the non-class Aux Feed Pump, AFN-P01, per Standard Appendix 41, Attachment 41-A.
i SAFETY CONSIDERATIONS-This breaker is located in an energized cabinet. Ensure necessary precautions to prevent contact with energized equipment.
l l
\\
l l
l l
i OTG-02 Rev. 0 8
\\
l l
SF031-J-C/R-00 6-PVNGS JOB PERFORMANCE MEASURE v
t j
x
....=.:......;.-;
.......s
.o.
..,>...s..
-- 3 x
JPM BASIS INFORMATION TASK:
1290190102, Ensure compliance with Tech Specs TASK STANDARD:
Determine failure of DNBR and LHR survei! lances within time limits.
K/A:
012 K6.08 K/A RATING:
RO:
3.6*
SRO: 3.7
)
4
}
K/A:
K/A RATING:
RO:
SRO.
i APPLICABLE POSITION (S):
RO/SRO VALIDATION TIME:
15 mins.
]
REFERENCES:
72ST-9RX03 DNBR/LHR/AZTILT/ASI with COLSS Out of Service SUGGESTED TESTING ENVIRONMENT:
SIMULATOR X
PLANT j
APPROVAL DEVELOPER:
W. POTTER TECH REVIEW: b
[
9-17-f4 REVISION DATE:
8-21-96 APPROVAL:
TESTING METHOD ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT
]
TESTING METHOD:
SIMULATE PERFORM EVALUATION EXAMINEE NAME:
j (print)
EVALUATOR NAME:
(Prin0 l
SATISFACTORY UNSATISFACTORY i
]
Time Start Time Stop I
REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTG-04) 1 i
OTG-02 Rev. O I
A"SF031CR. DOC rbp 09:26/96
SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE I.
SIMULATOR SETUP:
A.
IC#: 20 B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
RJ01 COLSS orotram failure 2.
3.
4.
C.
SPECIAL INSTRUCTIONS:
None D.
REQUIRED CONDITIONS:
None 2.
SPECIAL TOOLS / EQUIPMENT:
None OTO-02 Rev. 0 2
SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The examiner will provide all responses and indications required from outside the Control Room.
You may use any source ofinformation normally available.
INITIATING CUE:
COLSS has been deternained to b'e out of service. The Control Room Stipervisor directs you to expedite performance of procedure 72ST-9RX03, DNBR/LIIR/AZTILT/ASI With COLSS Out Of Service. Notify the CRS when step 8.8 is complete.
"TIIIS IS A TIME CRITICAL JPM."
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM, It shall be terminated when the Examinee has verbalized completion of the JPM.
Any step marked UNSAT requires comments.
=
If this is the first JPM of the set then ensure the examinee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
NOTE: THIS IS A TIME CRITICAL JPM SAFETY CONSIDERATIONS:
None OTG-02 Rev. 0 3
1 SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD l
1.
Record the date and time that COLSS INFORM CUE: COLSS was declared out of became out of service in Appendix A and service at (Provide present time).
page 3 of 3 of Appendix B.
Examinee records the date and time in both i
l places.
NOTE: Examinee has 15 minutes to perform l
steps 1 through 8. Record start time here:
Time:
SAT UNSAT (UNSAT requires comments) l
~
i STEP ELEMENT STANDARD
(
2.
Obtain from each CPC the value for If requested CUE: All CPCs are operable.
a l
DNBR, point ID #406, and record in Appendix A.
Examinee obtains DNBR values and records i
these in Appendix A.
CUE: CPC "A" indicates 1.5928 CPC "B" indicates 1.9895 CPC "C" indicates 1.9891 CPC "D" indicates 1.9895 SAT UNSAT (UNSAT requires comments) s F
COMMENTS:
l l
4
Iit-SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE P
ELEMENT STANDARD Obtain from each CPC the value for LHR, Examinee obtains LHR values and records point ID #179, and record in Appendix A.
these in Appendix A.
CUE: CPC "A" indicates 13.212 CPC "B" indicates 13.219 CPC "C" indicates 13.311 CPC "D" indicates 13.314 UNSAT (UNSAT requires comments) per P
ELEMENT STANDARD ix Obtain from each CPC the value for ASI, Examinee obtains ASI values and records these point ID #187, and record in Appendix A.
in Appendix A.
CUE: CPC "A" indicates 0.32649 CPC "B" indieates 0.32191 CPC "C" indicates 0.32189 CPC "D" indicates 0.32651 UNSAT (UNSAT requires comments)
P ELEMENT STANDARD If any DNBR value is outside the region of If requested CUE: Both CEACs are acceptable operation specified in the operable.
COLR for Tech Spec 3/4.2.4.c, circle the value in Appendix A Examinee references COLR and circles all DSTRin Appendix A.
in UNSAT (UNSAT requires comments)
D1ENTS:
5
1 l
E SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE 4
i STEP ELEMENT STANDARD Determine success or failure of the DNBR Examinee determines failure of DNBR l
6.
a surveillance using the critena specified in surveillance and denotes a "NO" in the Appendix A, Note 1 and denote the result appropriate block in Appendix A.
as "YES" or "NO" in the appropriate block in Appendix A.
i SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD 7.
If the DNBR LCO is NOT met in step 8.4 Examinee commences monitoring DNBR at above, then commence monitoring DNBR intervals ofless than or equal to 15 minutes per at intervals ofless than or equal to 15 Appendix C by making an entry in Appendix
)
minutes per Appendix C to satisfy Tech C.
Spec 3.2.4 ACTION statement a.2.
l SAT UNSAT (UNSAT requires comments)
STEP ELEMENT STANDARD
)
8.
If any LHR value exceeds the maximum Examinec notes all LHR values acceptable m value specified in Tech. Spec. 3/4.2.1, Appendix A.
circle the value in Appendix A.
1 SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD 9.
Determine success or failure of the LHR Examince circles "YES" in the appropriate surveillance using the criteria specified in block of Appendix A after using the criteria in Appendix A, Note 2, and denote the results Appendix A, Note 2.
l as "YES" or "NO" in the appropriate block j
in Appendix A.
SAT UNSAT (UNSAT requires comments) l s
i COMMENTS:
4 i
4 6
SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE STEP ELEMENT STANDARD 10.
If the LHR LCO is not met in step 8.7 Examinee notes increased monitoring of LHR ab(,ve, then commence monitoring LHR at is not required.
intervals ofless than or equal to 15 minutes per Appendix D to satisfy Tech.
NOTE: Record completion time here.
Spec. 3.2.1 ACTION Statement a.2.
Time:
CUE: The CRS will assign another Reactor Operator to complete 72ST 9RX03.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT COMMENTS:
t 7
i 1
SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS 0
08/26/96 6
New JPM REASON REVISED
. Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4.
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 6.
Other (explain in comments) -
OTG-02 Rev. 0 8
w.
SF031-J-C/R-00 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS j
i INFORMATION PRESENTED TO EXAMINEE:
i SPECIAL CONSIDERATIONS:
Operation of equipment is to be performed on the simulator.
The e.xaminer will provide all responses and indications required from outside the Control Room.
You may use any source ofinformation normally available.
=
INITIATING CUE:
COLSS has been determined to be out of service. The Control Room Supervisor directs you to expedite performance of procedure 72ST-9RX03, DNBR/LHR/AZTILT/ASI With COLSS Out Of Service. Notify the CRS when step 8.8 is complete.
"THIS IS A TIME CRITICAL JPM."
SAFETY CONSIDERATIONS:
None OTG-02 Rev. 0 9
t EP018-J-PLT-01
.)
PVNGS JOB PERFORMANCE MEASURE 4
JPM BASIS INFORMATION TASK:
1240102002 Classify Events Requiring Emergency Plan Implementation TASK STANDARD:
Event classified as a General Emergency and Protective Action Requirements specified.
K/A:
2.4.41 K/A RATING:
RO:
2.3 SRO: 4.1 K/A:
2.4.44 K/A RATING:
RO:
2.1 SRO: 4.0
{
APPLICABLE POSITION (S):
SRO VALIDATION TIME:
10 min.
REFERENCES:
16DP-0EP13, Emergency Classification
)
SUGGESTED TESTING ENVIRONMENT:
SIMULATOR PLANT X
APPROVAL DEVELOPER:
W. POTTER TECH REVIEW:
[
f fd i
REVISION DATE:
8/27/96 APPROVAL:
j i
v l
TESTING METHOD i
ACTUAL TESTING ENVIRONMENT:
SIMULATOR PLANT
~
(
TESTING METHOD:
SIMULATE PERFORM 4
EVALUATION EXAMINEE NAME:
j (print)
EVALUATOR NAME:
(print)
SATISFACTORY UNSATISFACTORY Time Start Time Stop i
i REMEDIAL TRAINING REQUIRED?
YES NO (SEE OTO 04) i OTG-02 Rev. O I
A:\\EP018 PLT. DOC tbp 09/27/96 1
EP018-J-PLT-01 PVNGS JOB PERFORMANCE MEASURE l
1.
SIMULATOR SETUP:
A.
IC# : N/A B.
MALFUNCTIONS, OVERRIDES & REMOTE FUNCTIONS:
EVENT COMMAND DESCRIPTION 1.
N/A 2.
3.
i 4.
C.
SPECIAL INSTRUCTIONS:
None i
D.
REQUIRED CONDITIONS:
None 2.
SPECIAL TOOLS / EQUIPMENT:
None j
i i
OTG-02 Rev. 0 2
a-EP018-J-PLT-01 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS-Operation ofin-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
Inform the control room staff of any discovered de6ciencies.
1 You may use any source ofinformation normally available.
INITIATING CUE:
An event occurred t.t Palo Verde 25 minutes ago. The crew responded to auxiliary building sump and radiation alarms to find a leak upstream of CVB-UV-523. Pressurizer level was not able to be maintained with two available charging pumps, resulting in a manual reactor trip, SIAS and CIAS. RCS pressure is currently 1650 psig with only one HPSI pump injecting due to a failure of the other pump. Attempts to isolate the leak were unsuccessful. Seventeen minutes ago RU-143 and RU-144 were reading " STATUS -
INACTIVE" and 1.2E+01uCi/cc (CH-1) respectively. Wind is blowing from 88*. You j
are directed to classify this event and determine any Protective Action Recommendations (PARS) required.
INFORMATION FOR EVALUATOR'S USE:
- Denotes Critical Step At the discretion of the Examiner / Evaluator, this JPM may be terminated when the Task e
Standard is met or adequate time has been allowed to complete the JPM. It shall be term' mated when the Examinee has verbalized completion of the JPM.
Any step marked UNS AT requires comments.
=
if this is the first JPM of the set then ensure the exammee has been briefed IAW OTG-01.
Step sequence is not critical unless noted or will prevent achieving the task standard.
SAFETY CONSIDERATIONS:
None
=
OTG-02 Rev. 0 3
EP018-J-PLT-01 PVNGS JOB PERFORMANCE MEASURE j
STEP ELEMENT STANDARD 1.
Obtain 16DP-0EP13, Emergency 16DP-0EP13 obtained Classification i
SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD Classify the event.
Classify the event as a General Emergency 2.
based on the following:
RCS leak > 44 gpm.
Failure of both CTMT isolation valves in any one line to close and paLSway to environment exists.
RU-144 CH-1 reading >2.20E+00 uCi/cc for 15 minute or longer.
SAT UNSAT (UNSAT requires comments) i STEP ELEMENT STANDARD Detennine protective action requirements.
Determine the following PARS:
i 3.
Evacuation for 5-mile radius.
Evacuation for 10-mile radius in sections L M, N, P, Q.
SAT UNSAT (UNSAT requires comments)
NORMAL TERMINATION POINT COMMENTS:
4
~..
. _ _ ~. -. -
EP018-J-PLT-01
)
PVNGS JOB PERFORMANCE MEASURE E
RECORD OF REVISIONS REVISION REASON REVISION DATE REVISED NUMBER COMMENTS l
0 8/27/96 6
New JPM e
l l
a 4
1 REASON REVISED Enter the nurn' vers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.
i 1.
Vendor reference document upgrade 2.
Plant modification (include number) 3.
Procedure upgrade 4
Internal or External Agency Commitment (indicate item number) 5.
Technical Specification Change (indicate amendment number) 4 6.
Other (explain in comments) i W
OTG-02 Rev. 0 5
EP018-J-PLT-01 PVNGS JOB PERFORMANCE MEASURE INITIAL CONDITIONS INFORMATION PRESENTED TO EXAMINEE:
SPECIAL CONSIDERATIONS:
Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.
Inform the control room staff of any discovered deficiencies.
=
You may use any source ofinformation normally available.
INITIATING CUE:
An event occurred at Palo Verde 25 minutes ago. The crew responded to auxiliary building sump and radiation alarms to find a leak upstream of CVB-UV-523. Pressurizer level was not able to be maintained with two available charging pumps, resulting in a manual reactor trip, SIAS and CIAS. RCS pressure is currently 1650 psig with only one HPSI pump injecting due to a failure of the other pump. Attempts to isolate the leak were unsuccessful. Seventeen minutes ago RU-143 and RU-144 were reading " STATUS - INACTIVE" and 1.2E+01uCi/cc (CH-1) respectively. Wind is blowing from 88'. You are directed to classify this event and determine any Protective Action Recommendations (PARS) required.
SAFETY CONSIDERATIONS:
None i
\\
1 OTG-02 Rev. 0 6
l INDIVIDUAL WALK THROUGH 1
l RELATED JPM:
EM007 l
QUESTION:
1.
l A station blackout has occurred and a single gas turbine generator was lined-up to supply PBA-S03 using Appendix 80. The Technical Support Center wants the control room crew to run non-essential auxiliary feedwater pump AFN-P01 and secure AFA-P01.
Explain why AFN-P01 should not be operated in this condition.
j l
l l
RELATED ANSWER:
l L
i Basis:
A single GTG cannot supply PBA-S03 vital loads and AFN-P01 due to load limitations.
)
i EXAMINEE'S ANSWER:
l l
l I
l
REFERENCE:
EOP Operations Expectations.
40DP-9AP13, Blackout Technical Guideline.
NOTE: Reference may not be used for this question
INDIVIDUAL WALK THROUGH 2
RELATED JPM:
EM007 QUESTION:
2.
An overcurrent condition has caused a loss of PKA-M41 with damage to the bus. From what power source can control power be supplied to PBA-S03S, the AFN-P01 breaker?
RELATED ANSWER:
Alternate source from battery charger "A".
EXAMINEE'S ANSWER:
J
REFERENCE:
DWG. 01-E-AFB-002.
INDIVIDUAL WALK THROUGH 3
RELATED JPM: DG007 QUESTION:
3.
A loss of offsite power occurs and the plant trips. The "A" Diesel Generator is tagged out i
for repairs. The "B" Diesel Generator does not connect to the bus. During SPTA's your observation from B01 is that voltage and frequency are below normal. No other problems are evident. What actions can be taken from the control room during SPTA's to get the "B" Diesel Generator output breaker closed?
RELATED ANSWER:
Minimum Answer: Override the system to gain control of voltage and frequency.
(Use handswitches for diesel generator voltage and frequency on B01 to raise voltage and frequency (to 60 IIz and 3750 volts) until the DG output breaker closes automatically.)
EXAMINEE'S ANSWER:
REFERENCE:
EOP Operations Expectations.
410P-1DG01, Diesel Generator.
NOTE: References may not be used for this question.
INDIVIDUAL WALK THROUGH 4
RELATED JPM: DG007 QUESTION:
4.
Determine the maximum permissible long-term MW and MVAR load, while at > 0.80 lagging power factor.
RELATED ANSWER:
5.5 Mwe and 4.0 MVAR.
i EXAMINEE'S ANSWER:
4 1
1 J
REFERENCE:
40EP-9EOO7, Blackout.
410P-1DG02, Emergency Diesel Generator B.
l INDIVIDUAL WALK THROUGH 5
RELATED JPM: CH008 QUESTION:
5.
i You are currently emergency borating the RCS from the spent fuel pool through CH-HV-536. Assume the pipe from the spent fuel pool ruptures at CH-HV-536. What design feature of the spent fuel pool system will prevent loss of the required water level over the spent fuel?
RELATED ANSWER:
Minimum Answer: A siphon breaker in the line (prohibits fuel pool level from dropping below a minimum level.)
EXAMINEE'S ANSWER:
REFERENCE:
Drawing 01-M-PCP-001, Spent Fuel Pool STM.
1
INDIVIDUAL WALK THROUGH 6
RELATED JPM:
C11003 QUESTION:
6.
During normal full power operation, volume control tank level transmitter LT-227 fails low. The required actions have been completed in the CVCS system to mitigate the effects of this failure. Describe the fmal status of the components manipulated while taking these actions.
RELATED ANSWER:
- 1. CIIN-UV-501 is open and de-energized.
- 2. CLIN-UV-514 is closed and de-energized.
)
- 3. CIIE-11V-536 is closed and de-energized.
EXAMINEE'S ANSWER:
i l
REFERENCE:
41 AL-1RK3A,3 A088.
INDIVIDUAL WALK THROUGH 7
RELATED JPM: CH003 QUESTION:
7.
When emergency borating from the refueling water tank through CHB-UV-536, with i
CHA-UV-501 open, why might flow come from the volume control tank instead of the refueling water tank?
RELATED ANSWER:
Volume control tank is pressurized and may overcome the head from the refueling water tank.
EXAMINEE'S ANSWER:
REFERENCE:
40AO-9ZZ01, Emergency Boration..
NOTE: References may not be used for this question.
INDIVIDUAL WALK THROUGH 8
RELATED JPM: PB003 QUESTION:
8.
During an event where SIAS is actuated, one HPSI pump motor breaker opens on an 86 j
lockout. Describe the two (2) methods available in the control room to alert an operator
~
that this motor has an 86 lockout.
RELATED ANSWER:
i 1.
Green breaker "OPEN" indication brighter than normal.
2.
White SEIS light for the affected motor on the SESS panel (for that train).
1 EXAMINEE'S ANSWER:
4 G
REFERENCE:
DWG. 01-E-SIB-001.
41 AL-1ES2A, SES Alarm Response.
INDIVIDUAL WALK THROUGH 9
RELATED JPM: PB003 QUESTION:
9.
The PBA-S03 bus normal supply breaker has an 786 lockout on it. It is preventing closure of the Diesel Generator "A" Output Breaker. What are four (4) of the five (5) j procedural requirements that must be met to close the breaker?
RELATED ANSWER:
i Any four of the following:
1.
Cause of the signal has been investigated and/or corrected.
2.
Relay target report complete.
1 3.
CRS/SS has authorized resetting.
4.
Ensure all associated relay targets are reset.
5.
Reset the 786 lockout (from the control room or locally at the switchgear).
EXAMINEE'S ANSWER:
I 4
REFERENCE:
40DP-00P02, Relay Resetting.
41 AO-lZZ52, Diesel Generator Operations After ESFAS Actuation's.
.=
INDIVIDUAL WALK THROUGH 10 i
RELATED JPM: EP003 QUESTION:
10.
Explain the basis for why the Main Steam Isolation Valves are closed before Control Room evacuation (i.e., quickly, after reactor trip).
RELATED ANSWER:
To prevent a steam generator overfill (FWPT continue feeding at full flow).
EXAMINEE'S ANSWER:
4 1
1 4
1
REFERENCE:
41 AO-lZZ44, Appendix K, Shift Supervisor Actions.
INDIVIDUAL WALK THROUGH 11 RELATED JPM: RC012 QUESTION:
11.
While operating in Mode 3, why are both reactor coolant loops required to be operable but only one of those loops is required to be in oneration?
i RELATED ANSWER:
In Mode 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be operable.
EXAMINEE'S ANSWER:
l
REFERENCE:
Tech. Spec. 3/4.4.1 Bases.
)
l
1 INDIVIDUAL WALK THROUGH 12 RELATED JPM: RC012 l
QUESTION:
12.
1 Locally, RCP breaker position status is indicated by a red and green light for closed and open, respectively. Additionally, there is also a white light and a clear light. What do the white and clear lights indicate when lit.
RELATED ANSWER:
1.
The WHITE light monitors the lockout relay coil circuit continuity and indicates that the relay is ready to operate (also indicates control power available).
2.
The CLEAR light indicates that the breaker closing spring is charged.
EXAMINEE'S ANSWER:
4 l
REFERENCE:
410P-lNA01, App. B.
40DP-00P02, Relay Resetting.
i
INDIVIDUAL WALK THROUGH 13 RELATED JPM: EW001 l
QUESTION:
13.
1 Why is an essential cooling water train that is paralleled to nuclear cooling water considered inoperable?
1 RELATED ANSWER:
l The train is unable to perform its required function of providing cooling water to essential plant loads because a non-class system is being cross-connected with a class system.
EXAMINEE'S ANSWER:
J
REFERENCE:
40AO-9ZZ03, Loss of Cooling Water, Section 4.0 Technical Specification 3.7.3,3.7.6.
INDIVIDUAL WALK THROUGH 14 l
RELATED JPM: EW001 QUESTION:
14.
What are four (4) nuclear cooling water " priority loads" that can be supplied by essential cooling water?
RELATED ANSWER:
(Any Four) i 1.
RCP Seal Coolers.
2.
RCP Motor Coolers.
3.
CEDM ACU's.
4.
Normal Chillers.
5.
RCS Sample Coolers.
6.
Spent Fuel Pool Heat Exchangers.
j
)
EXAMINEE'S ANSWER:
?
4
REFERENCE:
P & ID,13-M-NCP-001 thru 003.
40AO-9ZZO3, Loss of Cooling Water, Section 4.0.
r
INDIVIDUAL WALK THROUGH 15 RELATED JPM: EP003 QUESTION:
15.
During a natural circulation cooldown from outside the control room, why is the operator required to maintain PZR pressure as high as possible within acceptable pressure / temperature limits of Tech. Spec. 3/4.4.8.1, until conditions allow shutdown cooling to be placed in-service?
RELATED ANSWER:
To minimize the possibility of drawing a bubble in the reactor vessel head.
EXAMINEE'S ANSWER
REFERENCE:
41 AO-1ZZ44, Control Room Fire.
INDIVIDUAL WALK THROUGH 16 l
RELATED JPM: SG018 4
QUESTION:
16.
l During the performance of the partial stroke exercise (Train A) of MSIV SGE-UV-170 the "B" operating solenoid fails. What affect does this failure have on the ability of the MSIV to close if an MSIS signal was received 7 Briefly explain.
RELATED ANSWER:
Does not affect ability of valve to close on MSIS due to the availability of the "B" train accumulator.
EXAMINEE'S ANSWER:
l i
REFERENCE:
73ST-9SG01, MSIVs In-sen' ice Test.
Tech. Spec. 3.7.1.5, Main Steam Line Isolation Valves.
l
INDIVIDUAL WALK THROUGli 17 1
RELATED JPM: SG018 QUESTION:
17.
Main Steam Isolation Valves must close in no more than 4.6 seconds. Describe one reason for this requirement related to possible detremental effects on the plant.
RELATED ANSWER:
- a. Minimize positive reactivity additions from RCS cooldown.
- b. Limit containment pressure.
(note for evaluator: either 'a' or 'b' is required) 1 EXAMINEE'S ANSWER:
REFERENCE:
NKA01-RC-807-01 Transient and Accident Analysis, increase in heat removal.
INDIVIDUAL WALK THROUGH 18 RELATED JPM: SF031 QUESTION:
18.
During normal 100% power operations a rod bottom contact closes on one of the CEAs.
What action must be taken for the Core Operating Limits Supervisory System (COLSS).
RELATED ANSWER:
Must perform a COLSS Functional Verification.
EXAMINEE'S ANSWER:
l
REFERENCE:
41 AO-lZZ11, Dropped / Slipped CEA.
INDIVIDUAL WALK THROUGH 19 RELATED JPM: SF031 QUESTION:
19.
Assume steady state 100% power operation and all COLSS inputs are operable and accurate.
What affect will the failure ofone T-cold transmitter going from 555*F to 560 F have on COLSS DNBR power operating limit?
RELATED ANSWER:
Margin to DNBR lowers (worse).
EXAMINEE'S ANSWER:
REFERENCE:
INDIVIDUAL WALK THROUGH 20 RELATED JPM:
CH008 QUESTION:
20 i
I Why is the RWT level maintained above 34% during an emergency boration?
j 1
RELATED ANSWER:
To prevent a charging pump low suction trip.
EXAMINEE'S ANSWER:
l 4
i
REFERENCE:
41 AO-lZZ01, Emergency Boration.
NOTE: References may not be used for this question.
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.1 Reactor Startun KSA#: 2.L2 LP #: NKA01-00-RS-203-000 QUESTION 1.
A reactor startup is in progress. The ACP data sheets and table are attached. Explain, using this data, any actions that need to be taken. ECRP data is as follows:
ECRP - 500 pcm position = 3 at 90 inches.
ECRP
= 4 at 70 inches.
ECRP + 500 pcm position = 5 at 130 inches.
t REFERENCE ANSWER:
Insen all Reg Group CEAs to the lower group stop.
EXAMINEE'S ANSWER.
1 1
REFERENCE:
400P-9ZZ03, Reactor Startup N
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.1 Reactor Startup KSA#: 2.1.23 LP #: NKA01-00-RS-203-000 QUESTION 2.
Preparation for a reactor startup is in progress. T is 565 F. Core burnup is 300 EFPD and RCS c
boron concentration is 682 ppm. All CEAs are fully inserted. Identify one (1) condition, with regard to shutdown margin, which must be met to exercise regulating group CEA #86.
Be specific.
REFERENCE ANSWER:
Either of the following:
Boron concentration must be increased to >922 i
OR the shutdown groups must be disabled.
EXAMINEE'S ANSWER:
i
REFERENCE:
72ST-9RX15, Shutdown Margin - Modes 3,4 and 5 with Trip Breakers closed.
400P-9ZZ11, Mode Change Checklist.
i
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.3 Radiation Control KSA#: 211 LP #: GET/ Rad Worker QUESTION 3.
l 1
You must enter the immediate area around LPSI pump 'A', which has been designated a Hot Particle Control Area (HPCA). The work is expected to take 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and requires personal protective clothing. If you enter the HPCA at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> to commence work, when, during the work, would you be expected to leave the HPCA to perform a whole body frisk using a PCM-17 REFERENCE ANSWER:
The requirement is to frisk using a PCM-1 or equivalent at approximately 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals.
Therefore, a worker would be expected to exit for this purpose at 1600 and 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />.
EXAMINEE'S ANSWER:
REFERENCE:
75RP-9RP06, Hot Particle Control
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.3 Radiation Control KSA#: 214 LP #: GET/ Rad Worker QUESTION 4.
I Due to lowering level in SIT 1 A a containment entry was planned to investigate for leakage at 100% power. The original planned entry was to be yesterday at 0800. All paperwork was completed for that entry. The entry was postponed until today at 1600. Is the entry paperwork valid? Why or why not?
REFERENCE ANSWER:
No.
It has exceeded its' 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit.
EXAMINEE'S ANSWER:
REFERENCE:
02AC-9ZZ01, Containment Entry in Modes 1 through 4.
GET/ Rad Worker Training.
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.1 Fuel Handling KSA#: 033 A4.06 LP #: NKA01-00-RC-353-000 QUESTION 5.
Describe two(2) concerns associated with using the condensate storage tank to makeup to the spent fuel pool.
REFERENCE ANSWER:
i Dilution of spent fuel pool and chemical content of CST.
EXAMINEE'S ANSWER:
1
REFERENCE:
41 AO-lZZ03, Loss of Refueling Pool and/or Spent Fuel Pool Level NOTE:
References may not be used for this question.
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION:
A.1 Fuel Handling KSA#: 033 A2.03 LP #: NKA01-00-RC-353-000
\\
QUESTION 6.
You are the SRO assigned to fuel movement during core off-load. You have an irradiated fuel assembly grappled with the hoist up. You notice level of the pool is dropping and hear water j
spilling through the cask pit seals. Area radiation monitors are not alarming. Describe three (3) actions you need to take assuming you are currently over the fuel storage racks.
REFERENCE ANSWER:
Notify Control Room of Spent Fuel Pool level drop.
e Lower assembly into fuel racks or deep part of pooljust above the floor.
. Evacuate area.
EXAMINEE'S ANSWER:
i i
l l
REFERENCE:
41 AO-lZZ53, Loss of Refueling Pool and/or Spent Fuel Poal Level.
NOTE:
References may not be used for this question.
GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCRIPTION: A.2 Tagging and Clearance KSA#: 2.2.13 LP #: NKA01-00-RC-708-000 QUESTION 7.
ADV 178 requires valve disc and seat repairs. The clearance has been accepted by Valve Services, Electrical Maintenance, and Mechanical Maintenance. During the work, the electricians suspect a degraded condition on the >ower supply cable to solenoid SGD-HY-178S. The electricians request a red tag be removec to allow a megger test of the cable. Describe the action required to permit the red tag removal?
REFERENCE ANSWER:
Either one of the following:
Obtain concurrence from all acceptors (Valve Services and Mechanical Maintenancc) e OR Have the other acceptors release the clearance e
EXAMINEE'S ANSWER:
l
REFERENCE:
40DP-90P30, Clearance Processing.
I GROUP #:
ADMINISTRATIVE TOPIC / SUBJECT DESCli PTION: A.2 Tagging and Clearance KSA#: 2.2.13 LP #: NKA01-00-RC-708-000 l
QUESTION 8.
Valve disc and seat repair work on ADV 178 has been completed and the clearance has been removed. List the requirements necessary to demonstrate the operability of ADV 178. The plant is in Mode 5.
REFERENCE ANSWER:
ADV 178 (as an ASME Section XI Valve) requires stroking to verify operability.
EXAMINEE'S ANSWER:
I i
REFERENCE:
30DP-9WP04, Post Maintenance Retest Development.
73DP-9ZZO9, Tech Spec Surveillance Requirements Cross Reference.