ML070820520
| ML070820520 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/23/2007 |
| From: | Shortell T Constellation Energy Group |
| To: | Caruso J Operations Branch I |
| Sykes, Marvin D. | |
| Shared Package | |
| ML060800077 | List: |
| References | |
| Download: ML070820520 (72) | |
Text
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Perform N1 -ST-DO DAILY CHECKS (Partial)
Task Number:
Approvals:
Operations Training (Designee)
Revision: NRC 2006 NA EXAM SECURITY I
General Supervisor Date Operations (Designee)
NA EXAM SECURITY I
Configuration Control Date Performer:
(ROISRO)
Trai ne r1Eva I ua tor:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time: 20 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop lime:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
valuator Signature:
Date:
NRC RO ADMlN JPM 1 October 2006
Recommended Start Location: (Completion time based on the start location)
If actual readings are to be taken, Simulator must be setup and used, otherwise perform in other designated area.
Simulator Set-up:
IC-238 contains setup conditions for Admin JPMs 1. TURN OFF PI MONITOR. JPM readings are taken with simulator in FREEZE.
Establish 70% reactor power, 40 mlb/hr total recirc flow, align Feedwater Level Column to 12, and override reactor water level and hotwell level instruments as necessary to read those indicated in the Attachment. Override both hotwell indication to 55 inches and activate crywolf for alarms H2-2-7 and 3-7 for low level.
Directions to the InstructorlEvaIuator:
Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM /
CSO permission.
Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a 0.
- 2. During Evaluated JPM:
- 3. During Training JPM:
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
NRC RO ADMlN JPM 1 October 2006
References:
1, GAP-OPS-01; 3.1 0.
- 2. N1-ST-DO; 6.0, 7.0 and 8.0.
- 3. 2.1.I8 (2.9) Ability to make accurate / clear and concise logs / records / status boards / and reports.
Tools and Equipment:
- 1. None Task Standard:
Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
The plant is operating at 75% power.
Surveillance test N1 -ST-DO, DAILY CHECKS, is in progress ALL computer point readings are consistent with control room panel instrument readings.
Ask the operator for any questions.
Initiating cue:
(Operators name), obtain the instrument readings needed from control room panels to complete N l -ST-DO, DAILY CHECKS Attachment 1 sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.
- 1. Provide repeat back of initiating cue. Evaluafor Acknowledge repeat back providing correction if necessary RECORD START TIME
- 1. *Obtain a copy of the reference procedure and review/utilize the correct section.
- 2. *Records section 6.0 Reactor Recirc Pump Inlet Temperature readings
- 3. Compares reading and determines readings within 15°F Proper communications used for repeat back (GAP-OPS-01)
N-ST-DO obtained.
- Section 6.0, 7.0 and 8.0 referenced.
NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM.
Records Reactor Recirc Pump Inlet Temperature readings.
Compares reading and determines readings within 15°F of each other.
Checks YES block in Section 6.0, indicating the maximum difference in loop temperatures is < 15°F.
Sat/Unsat Sat/Unsat SatlUnsat PasslFail PasslFail NRC RO ADMIN JPM 1 October 2006
- 4.
- 5.
- 6.
- Records section 7.0 readings
.Compares YARWAY C h l l -
Ch12 (RPS Level Column) instrument readings to guide values.
.Performs GEMAC C h l l - Ch12 variance check per Section 7.1.
- 7..Records section 8.0 Condensate readings
- 8. Provides completed sections to SRO. Informs of out of spec readings.
Recorded Section 7.0 LOW-Low Level alarm and Feedwater Level Column selected to checks agree with without error.
Recorded Section 7.0 instrument readings agree with Attachment 1 within k 1 inch.
Record Total Recirc Flow per step 7.1.2 for GEMAC variance check.
Determines YARWAY (RPS Level Column) instrument readings differ by 5 which is above the guide value of 4.
Determines YARWAY (RPS Level Column) instruments OPERABLE.
Indicates an ACR is required to have the calibration checked.
Determines GEMAC variance is 6 Compares GEMAC variance to total recirc flow and determines on line between ALERT RANGE and INOP Determines that GEMAC 11 or GEMAC 12 must be declared inoperable.
Reports out of specification readings to SRO.
Records Condensate readings Determines Hotwell level is below 57 inches (Tech Spec Minimum)
Informs SRO Hotwell level is below 57 inches (Tech Spec Minimum).
<Ref 2> is TS 3.1.8, HPCl is inoperable.
SRO informed of out of spec readings.
PasslFail PasslFail Sat/Unsat Sa t/U n sa t PasslFail Sat/Unsat SatIUnsat SatIUnsat PasslFail PasslFail SatIUnsat PasslFail PasslFail PasslFai I SatIUnsat End of JPM TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
RECORD STOP TIME NRC RO ADMlN JPM 1 October 2006
Initial Conditions:
I. The plant is operating at 75% power.
- 2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress
- 3. ALL computer point readings are consistent with control room panel
- 4. Ask the operator for any questions.
instrument readings.
Initiating cue:
(Operators name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO, DAILY CHECKS Attachment I sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO.
NRC RO ADMIN JPM 1 October 2006
Setup Attachment Override Value Settings Panel Meter Meter Reading Obtained E-Panel Vessel Level Indicator (E Panel 10590)
GEMAC Level Column (F f an el: 36-76A, K-Panel Vessel Level Indicator (K Panel: 3 6 ~ 9 ~
I Ch 11 77.5 K-Panel Flange Level Indicator (K Panel: to ~
~
~
~
t o
f Reactor Vessel Level Recorder (F ~
a
~
~
1
~
3 6 ~ ~ ~
Wide Range Level Indicator
(!=Panel: 3 6 - 9 ~ ~
2Y-L inches None 1 :elow
-3 7.2 1-z Ch12 I 1 1 12 79-80; 73 76; 72 NRC RO ADMIN JPM 1 October 2006
ATTACHMENT 1 (Cont)
ANSWER KEY. DO NOT PROVIDE TO APPLICANT Reactor Recirc Pump Inlet Temperature RRP 11 Inlet Temp RRP 12 Inlet Temp RRP 13 Inlet Temp RRP 14 Inlet Temp RRP 15 Inlet Temp Maximum difference in loop temperatures 15°F 7.0 Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks Feedwater Level Column selected to (E ~
a
~
~
~
)
520 OF 525 OF 520 OF 530 OF 520 O F YES No OYES I N 0 n 1 1 12 E-Panel Vessel Level Indicator (E Panel)
I 73 I inches I
K-Panel Vessel Level Indicator (K ~~~e~~ 36-9 I
76 I inches I
I
<-3 I feet I
K-Panel Flange Level Indicator 3
Reactor Vessel Level Recorder (F Pane!: 3 I
74 I inches I
Wide Range Level Indicator (F Pa I
6 I feet I
I 77 I 72 I
in***
I Column <Ref 1 > fF ~
a
~
~
~
3 If reading difference is greater than the guide valve, review previous readings for the instrument(s). If a single reading is the cause for the recorded value being greater than the guide value, verify that reading. If reading difference is still greater than guide value, consider the indicator OPERABLE and generate an ACR to have the calibration checked. If reading difference is grossly greater than guide value, consider the indicator INOPERABLE, enter applicable Tech Spec action and generate an ACR.
See Section 7.1 If the difference between Yarway indicators Ll-36-09 and LI-36-10 is 6" or greater, THEN declare the following instruments inoperable and initiate the required Technical Specification actions (ESA for DER 1-2001 -3027):
LT-36-03C, LT-36-03D LT-36-04C, LT-36-04D LT-36-216, LT-36-21 D NRC RO ADMIN JPM 1 October 2006
ATTACHMENT 1 (Cont)
ANSWER KEY. DO NOT PROVIDE TO APPLICANT 7.1 GEMAC Variance Check 7.1.I Calculate Variance Between Ch 12 and Ch 11 GEMAC Level Recorders.
6 73 79 Ch 12 Ch 11 Variance (in.)
/
Ind. Verif 7.1.2 Record Total Recirc Flow 40 Mllb/Hr (E ~~~~~
init 1 date 7.1.3 Verify GEMAC 11/12 Variance as a function of Total Recirc Flow is in the Acceptable Range as determined in the Graph below. (Note, ignore negative sign, if any.)
Yes (Sat)
No (Unsat), DER Required inif 1 date If results are in ALERT range, generate DER for Engineering Evaluation.
If results are in INOP range, declare GEMAC 11 and/or 12 INOP.
GEMAC LEVEL COLUMN 11 / 12 VARIANCE 10 9
8 2
1 0
0 5
10 15 20 25 30 35 40 45 50 55 60 65 70 Total Recirc Flow CBJllb/Hr)
NRC RO ADMlN JPM 1 October 2006
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Determine Plant Impact of Mispositioned Liquid Poison Components Revision: NRC 2006 Task Number:
Approvals:
NA EXAM SECURITY I
General Supervisor Date az-.
12bk?
Date Generaf Supervisor Operations Training (Designee)
Operations (Designee)
NA EXAM SECURITY I
Configuration Control Date Performer:
(RO)
TrainerlEvaluator:
Evaluation Method:
X Perform Simulate Eva I ua tio n Location :
Plant X
Simulator or other location Expected Completion Time: 15 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
NRC RO ADMIN JPM 2 October 2006
e start location)
Simulator or other designated location with prints and procedures available Simulator Set-up (if required):
NA Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec.
Operability, operational status, or the effects are unknown, obtain specific SM I CSO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a 0.
- 2. During Evaluated JPM:
- 3. During Training JPM:
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. P&ID C-18019-C
- 2. N1-OP-12, Attchment2
- 3. Tech Spec 3.1.2 Tools and Equipment:
NRC RO ADMlN JPM 2 October 2006
- 1. None Task Standard: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.
Initial Conditions:
0000 The plant is in operating at 100% power.
0000 Liquid Poison System 11 is in normal standby lineup 0030 Clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump as indicated on Attachment 1.
01 00 As-found component lineup is reported with component lineup indicated on Attachment 2.
lnitiating cue:
(Operators name), determine the correctness of the resulting component lineup and the plant impact and consequences of the as-found configuration. Document any findings on JPM scorecard.
Performance Steps Standard Grade
- 1.
Provide repeat back of initiating cue.
Proper communications used for repeat SatlUnsat Evaluator Acknowledge repeat back providing correction if necessary.
back (GAP-OPS-01/ CNG-HU-1.Ol-1001)
RECORD START TIME
- 2. Reviews JPM Attachment 1 to determine Reviews Attachment 1 and P&ID C-Sat/Unsat intended equipment lineup.
1801 9-C o Determines LP Pump 12 power Sat/Unsat supply, suction and discharge paths are to be isolated.
- 3. Reviews JPM Attachment 2 to determine 0 Reviews Attachment 2 and identifies the as found configuration of Liquid Poison Pump 11 and 12 system corn ponen ts.
the following incorrectly positioned components and consequences.
o 41-1 1 LP-2 BV-LP PUMP 12 PasslFail SUCTION FROM LP TANK is open and should be tagged closed.
NRC RO ADMIN JPM 2 October 2006
Grade u
With LP Pump 12 drain 42-12 LP-704 open, the boron tank is draining due to improper lineup.
o 41-07 LP-3 BV-LP PUMP 11 SUCTION FROM LP TANK is closed but should be open.
Determines that with 41-07 closed LP Pump 11 is inoperable because of loss of suction path.
o 41-06 LP-19 BV-LP PUMP 11 SUCTION FROM TEST TANK is open but should be locked closed.
Determines that with 41-06 open LP Pump 11 is incorrectly lined up to the test tank.
Determines cumulative effect of as-found component lineup.
u Determines both systems of Liquid Poison are not operable.
Identifies tag applied to incorrect component. Informs Control Room per GAP-OPS-01.
of red clearance tag.
Notifies CRS of improperly positioned com ponen ts and incorrect a p p I ication PasslFail Pass/Fail Pass/Fail PasslFail Sat/Unsat PasslFail Sat/Unsat
- 6. Determines Tech Spec LCO conditions Determines that these conditions Pass/Fail for liquid Poison are exceeded.
result in Tech Spec entry for the Liquid Poison system.
NRC RO ADMIN JPM 2 October 2006
J Pe rfo r ma n ce S te ps Standard Grade
Sat/Unsat NOTE:
applies because the redundant If a single pump was inoperable 7 days would be allowed to restore the inoperable pump.
component is also inoperable.
Since both are inoperable, specification e applies and an orderly shutdown must be initiated within one hour.
- 8. Determines that one subsystem must be o
restored to operable.
lentifies the requirement to res,xe one of the redundant components to OPERABLE within one hour or an orderly shutdown is required PasslFail End of JPM Terminating Cue:
restored within one hour or an orderly shutdown is required.
Determines both Liquid Poison subsystems are inoperable and one must be RECORD STOP TIME NRC RO ADMIN JPM 2 October 2006
JPM 2 Scorecard For Applicant Use. KEY DO NOT PROVIDE TO CANDIDATE Determine the correctness of the resulting component lineup and the plant impact and consequences of the as-found configuration.
Findings 41-1 1 LP-2 BV-LP PUMP 12 SUCTION FROM LP TANK is open and should be tagged closed.
41-07 LP-3 BV-LP PUMP I1 SUCTION FROM LP TANK is closed but should be open.
41-06 LP-19 BV-LP PUMP 11 SUCTION FROM TEST TANK is open but should be locked closed.
Determines both systems of Liquid Poison are not operable and Tech Spec entry is required (TS 3.1.2).
Impact on plant 3perat ionlconsequen ces Nith LP Pump 12 drain 42-12 LP-704 open, ihe boron tank is draining due to improper ineup.
Determines that with 41-07 closed LP Pump 11 is inoperable because of loss of suction path Determines that with 41-06 open LP Pump 11 is incorrectly lined up to the test tank.
Identifies the requirement to restore one of the redundant components to OPERABLE within one hour or an orderly shutdown is required NRC RO ADMlN JPM 2 October 2006
Initial Conditions:
0000 The plant is operating at 100% power.
0000 Liquid Poison System 11 is in normal standby lineup 0030 Clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump as indicated on JPM Attachment 1.
01 00 As-found component lineup is reported with component lineup indicated on JPM Attachment 2.
Initiating cue:
(Operators name), determine the correctness of the resulting component lineup and the plant impact and consequences of the as-found configuration. Document any findings on JPM scorecard.
NRC RO ADMIN JPM 2 October 2006
7 JPM 2 Scorecard For Applicant Use Determine the correctness of the resulting component lineup and the plant impact and consequences of the as-found configuration.
Findings NRC RO ADMIN JPM 2 Impact on plant ope rat io n/co nseq ue n ces October 2006 Clearance Section Tags To Be Applied Location PB17B e
Tag Type PI Seq Place Verif Tagged Position Restoration Danger 1
INSTALLED IN INSTALLED IN Position OFF POS ON POS Tagged Component 42-38 CLOSE FUSES PB17B 42-38 MTR BKR CONN Danger 2
DISC 42-38 TRIP FUSES PBI 7B RB 298 S 41-1 1 LP-2 Danger 3
INSTALLED IN INSTALLED IN OFF POS ON POS Danger 4
CLOSED OPEN 41-18 LP-18 RB 298 S 42-02 LP-20 Danger 4
CLOSED CLOSED 42-04 LP-4 RB 298 S 42-12 LP-704 Danger 4
CLOSED OPEN AND LOCKED Description RB 298 S LIQUID POISON PUMP 12 Danger 5
OPEN CLOSED LIQUID POISON PUMP 12 LIQUID POISON PUMP 12 BV-LP PUMP 12 SUCTION FROM LP TANK BV-LP PUMP 12 SUCTION FROM TEST TANK BV-LP PUMP 12 DISCHARGE TEST BV-LP PUMP 12 DISCHARGE DRAIN LP PUMP 12 TO 55 GAL DRUM I
I I
I I
I I
I I
I I
I I
NRC RO ADMIN JPM 2 October 2006
42-39 MTR BKR 42-39 TRIP FUSES LIQUID PB16B POISON PUMP 11 LIQUID PB16B POISON PUMP 11 42-03 LP-5 BV-LP PUMP RB 298 11 DISCHARGE S As Found Component Positions Description Component 42-38 CLOSE FUSES Location PBI 7B As Found Position INSTALLED IN OFF POS As Found Position INSTALLED IN ON POS LIQUID POISON PUMP 12 PB16B POISON PUMP 42-38 MTR BKR LIQUID POISON PUMP 12 PB17B DISC CONN 42-38 TRIP FUSES LIQUID POISON PUMP 12 PBI 7B INSTALLED IN OFF POS IN STALLED IN ON POS I
CLOSED 41-11 LP-2 BV-LP PUMP 12 SUCTION FROM LP TANK RB 298 S
OPEN 41-07 LP-3 BV-LP PUMP RB 298 11 SUCTION FROM LP TANK 41-18 LP-18 BV-LP PUMP 12 SUCTION FROM TEST TANK RB 298 S
CLOSED 41 -06 LP-19 BV-LP PUMP 11 SUCTION FROM TEST TANK RB 298 S
OPEN 42-02 LP-20 BV-LP PUMP 12 DISCHARGE TEST RB 298 S
CLOSED 42-01 LP-21 BV-LP PUMP 11 DISCHARGE TEST RB 298 S
CLOSED 42-04 LP-4 BV-LP PUMP 12 DISCHARGE CLOSED RB 298 S
OPEN 42-12 LP-704 DRAIN LP PUMP 12 TO 55 GAL DRUM RB 298 S
OPEN CLOSED 42-11 LP-703 GAL DRUM NRC RO ADMIN JPM 2 October 2006
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
N1 -EOP-3.1 RPS Jumper Operation Electrical Print Reading Revision: NRC 2006 Task Number: N/A Approvals:
NA EXAMINATION SECURITY Gdneral Super isor Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(RO)
TrainerlEvaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time: 20 min Time Critical Task:
NO Alternate Path Task:
NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
\\
Evaluator Signature:
Date:
NRC RO ADMIN JPM 3 October 2006
Recommended Start Location: (Completion time based on the start location)
For NRC Exam 2006, This Admin JPM is performed in Simulator.
Simulator Set-up:
None Directions to the Instructor/Evaluator:
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional / concurrent verifier.
Notes to Instructor / Evaluator:
- 1.
- 2.
During Evaluated JPM:
- 3.
During Training JPM:
Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a 0.
Self-verification shall be demonstrated.
Self-verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. Drawing C-I 9859-C Sheet 4 and 7
- 2. N1-EOP-3.1, Alternate Control Rod Insertion
- 3. K/A 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.
Tools and Equipment:
- 1. None.
Task Standard: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.
NRC RO ADMIN JPM 3 October 2006
Initial Conditions:
- 1. The plant is experiencing a failure to scram.
- 2. N1-EOP-3 has been entered.
- 4. Repeated manual scrams will be attempted.
- 5. Ask the operator for any questions.
Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component (relays, contacts and switches) operation necessary to reset the RPS Channel 12 scram logic.
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME
- 1. Obtain a copy of the necessary procedures and drawings
- 2. Using C-19859-C Sheet 7, locates trip circuits and jumpers.
- 3. Using C-19859-C Sheet 7, identifies the signals defeated when jumpers are installed.
Proper communications used for repeat back (GAP-OPS-01)
SaUUnsat Obtains the following documents, as needed:
N1-EOP-3.1 Sat/Unsat/NA Drawing Index, if needed Sat/Unsat/NA Drawing C-I 9859-C Sheet 7 PasslFail Locates SCRAM BYPASS jumper PasslFail (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP # I circuit.
Locates SCRAM BYPASS jumper (EOP jumper 13) at drawing coordinate B-I to B-5, in REACTOR TRIP #2 circuit.
PasslFail Identifies that ALL AUTOMATIC PasslFail scram signal relay trip contacts are bypassed when jumper is installed.
NOTE: The manual scram circuit is not bypassed by the jumpers.
NRC RO ADMIN JPM 3 October 2006
- 4. Using C-19859-C Sheet 7, 0
Indicates when jumper is installed in PasslFail describes electrical component operation necessary to reset the scram.
REACTOR TRIP # I circuit, relay 12K51A (coordinate B-5) energizes and closes the following contacts:
12K51A L1-TI for GROUP 1 (coordinate D-2) 12K51A L2-T2 for GROUP 2 (coordinate E-2) 12K51A L3-T3 for GROUP 3 (coordinate F-2) 12K51A L4-T4 for GROUP 4 (coordinate G-2) 12K51A 7-8 for Backup Scram circuitry (coordinate H-2) 0 Indicates when jumper is installed in PasslFai I REACTOR TRIP #2 circuit, relay 12K52A (coordinate C-5) energizes and closes the following contacts:
12K52A L1-TI for GROUP I (coordinate D-2) 12K52A L2-T2 for GROUP 2 (coordinate E-2) 12K52A L3-T3 for GROUP 3 (coordinate F-2) 12K52A L4-T4 for GROUP 4 (coordinate G-2) 12K52A 7-8 for Backup Scram circuitry (coordinate H-2) u Indicates that depressing switch 1S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C-4), closes its IS3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).
NRC RO ADMIN JPM 3 October 2006 Sat/Unsat
I Performance Steps I Standard
- 10. Reports JPM complete Grade Indicates that Relay 12K53 Sat/Unsat energizing closes its 7-8 contact (coordinate D-4) and energizes relay 12K55 and 12K56 (coordinate D-5) in REACTOR MANUAL SCRAM circuit Indicates that Relay 12K55 energizing and closes the following contacts:
0 12K55 L1-TI for GROUP 1 (coordinate D-2) 12K55 L2-T2 for GROUP 2 (coordinate E-2) 12K55 L3-T3 for GROUP 3 (coordinate F-2) 12K55 L4-T4 for GROUP 4 (coordinate G-2) 12K55 7-8 for Backup Scram circuitry (coordinate H-2) 0 0
0 PasslFail Indicates that Relay 12K56 provides a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released.
SatIUnsat Indicates that when all three contacts in the four GROUP 1 through 4 circuits for 12K51 A, 12K52A and 12K55 are closed the scram is reset (for channel 12). Four white lights on F and M panels are ON and the scram pilot solenoids are energized for RPS Channel 12.
PasslFail Reports JPM complete NRC RO ADMIN JPM 3 SatIUnsat October 2006
identified on station electrical drawings and operation is explained.
RECORD STOP TIME NRC RO ADMIN JPM 3 October 2006
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
- 5.
The plant is experiencing a failure to scram.
N 1 -EOP-3 has been entered.
EOP Director directs execution of EOP-3.1.
Repeated manual scrams will be attempted.
Ask the operator for any questions.
Initiating cue: (Operators name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component operation necessary to reset the RPS Channel 12 scram logic.
NRC RO ADMlN JPM 3 October 2006
- 4.
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Radiological Requirements Related to Entry Into High Radiation Areas Revision: NRC 2006 Task Number: N/A NA EXAMINATION SECURITY G e ndr a I Sup e rv 6 or Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(RO)
Trainer/Evaluator:
Evaluation Method:
X Perform Simulate Eva I ua t ion Location :
Plant X
Simulator or other location Expected Completion Time: 10 minutes Time Critical Task: NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
NRC RO ADMIN JPM 4 October 2006
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
NIA Directions to the Instructor/Evaluator:
RWPs and survey maps are to be provided.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional /
concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a e.
- 2. During Evaluated JPM:
- 3. During Training JPM:
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. GAP-RPP-01; 3.5.
- 2. GAP-RPP-02; 3.3.
- 3. GAP-RPP-08; 3.2.
- 4. GAP-RPP-07; 3.2.5
- 5. K/A 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
Tools and Equipment:
1. None.
Task Standard: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.
NRC RO ADMIN JPM 4 October 2006
Initial Conditions:
1, Unit 1 is operating at 100% power.
- 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.
- 3. Current exposure is 1800 mrem TEDE.
- 4. RWP and survey map are provided.
- 5. Ask the operator for any questions.
Initiating cue:
(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard.
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 2.
- 3.
- 4.
- 5.
- 6.
Classify the area.
Determine highest on contact and general area dose rates and location, based on survey map Determines highest contamination levels in the room.
Determine RWP and Task Number required for entry.
Determines insufficient delta exposure to enter without additional approval.
Proper communications used for repeat back (GAP-OPS-01)
NOTE: A score card is attached to this JPM identifying the items for the performer to identify.
Determines the area is a HIGH RADIATION AREA.
Determines highest on contact dose rate to be 500 mremlhr at 12 SDC pump.
Determines highest general area dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger.
Determines highest contamination level to be 8000 dpmllOO cm2 at 12 SDC Pump, smear location #7.
Determines RWP 106001 Task 2 is correct for the job.
Determine within delta exposure of 300 mrem and additional approvals required prior to performing the inspection. (GAP-RPP-08 3.2.2, minimum delta exposure of 300 mRem needed to enter HRA). Admin limit of 2000 mr, from GAP-RPP-07.
2000 - 1800 = 200 mrem delta 300 mrem delta is required.
SatlUnsat PasslFail PasslFail PasslFail PasslFail PasslFail PasslFail NRC RO ADMIN JPM 4 October 2006
End of JPM TERMINATING CUE: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.
RECORD STOP TIME NRC RO ADMIN JPM 4 October 2006
Initial Conditions:
- 1. Unit 1 is operating at 100% power.
- 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance
- 3. Current exposure is 1800 mrem TEDE.
- 4. RWP and survey map are provided.
- 5. Ask the operator for any questions.
on BV 38-03 SDC Pump 11 suction handwheel.
Initiating cue:
(Operators name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel. RWP and survey maps are provided.
Address the radiological aspects of performing this job and record findings on scorecard.
NRC RO ADMlN JPM 4 October 2006
Answer the following when performing this task:
- 4.
Designate the RWP and task number required to be used:
- 5.
NRC RO ADMIN JPM 4 October 2006
NOTE: THIS IS THE EXAMINER SCORlZCARD.
DO NOT PROVIDE TO THE CANDIDATE.
Answer the following when performing this task:
- 1. PasslFail Classify the area (check one):
0 Radiation Area J High Radiation Area 0 Locked High Radiation Area 0
Very High Radiation Area
- 2. PasslFail Designate the highest on contact dose rate in the area and the location AND the highest general area dose rate and location:
500 mrem/hr on contact at 12 SDC Pump 100 mrem/hr near BV 38-03 and 11 SDC Pump, 72 SDC Pump and I 1 SDC Heat Exchanger (east side of HX).
- 3. PasslFail Designate the highest contamination levels in the room and location:
8,000 dpm/IOOcm2 at 12 SDC Pump at smear location #7 RWP # 106001 Task 2 (because task is in Contaminated High Radiation Area)
- 5. PasslFail Evaluate delta exposure for entry into the area: (check one):
NRC RO ADMIN JPM 4 October 2006
RB 261' Shut-Down Cooling Room Udt One 13SDCPurnp I Map No.
100 %
Rx Power scfm H, Inj. Rate 6
- 250 75
@ 38-05 PIPE TAPS (SHIELDED) 1
/
50 @ DO NOT LINGER SIGN, WHICH IS ALSO AT BOTTOM OF LADDER TO SCAFFOLD INSULATED PIPES WITHIN REACH OF THE LADDER TRAVEL PATH I ^ ^ I I
I I
10/24/2006 8: 19:28AM Page 1 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.
Inspections, Maintenance and Surveillances in High Radiation Areas.
TASK: 1 High Radiation Area (HRA) 7391 Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Protective Clothing Requirements:
No Protective Clothing Required.
TLD, Electronic Dosimeter If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.
instructions:
I)
RPS approval and survey required for system breech.
- 2) Pre-job briefing by RP required. Work crew will provide work area locations
- 3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
- 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry
- 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
ALARA Review Number:
Survey Data:
Radiation Levels:
Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRem/hr 2 - 250mRem/hr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels:
e400 - 10,000 dprn/lOOcm2 Airborne Levels:
~ 0. 3 DAC Specific areas as per RP briefing and / or survey maps.
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back
10/24/2006 7:46:25AM Page 2 of 2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.
Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas.
TASK: 2 High Radiation Area (HRA) 7389 Dose Alarm 50 mRem Dose Rate Alarm 500 mRem/Hr Backoff Dose 40 mRem Protective Clothing Requirements:
Single Full Set Of Protective Clothing Hood, Cotton Liners, Rubber Gloves (I),
Cotton Boots (I),
Rubbers (1)
Coveralls (I),
TLD, Electronic Dosimeter Radiation Protection Tech. may change protective clothing, respirator, or other requirements as work locations and conditions change.
Leather gloves may be worn instead of rubber gloves for safety reasons. When Leather gloves are worn, SURGEON gloves or RUBBER MUST be worn underneath them.
Instructions:
- 1) RPS approval and survey required for system breech.
- 2) Pre-job briefing by RP required. Work crew will provide work area locations
- 3) HEPA Vacuums & Ventilation Units are radiological engineering instruments: To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.
- 4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry.
- 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.
A U R A Review Number:
Survey Data:
Radiation Levels:
Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRemlhr 2 - 25OmRemlhr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels:
e400 - 10,000 dpm/lOOcm2 Airborne Levels:
~ 0. 3 DAC Specific areas as per RP briefing and / or survey maps.
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Assess Reportability Requirements Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Perform e r :
(SRO)
Trainer/Evaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time: 25 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
October 2006
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
None Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1.
- 2. During Evaluated JPM:
- 3. During Training JPM:
Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a ".".
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. NIP-IRG-01
- 2. 10CFR50.72
- 3. NUREG 1022 Rev 2, Section 3.2.6
- 4. EAL Matrix
- 5. CR NM-2006-4134 Plant Event Unit 2 Log Entry 9/5/06 1130 Tools and Equipment:
- 1. None Task Standard:
Determine notification requirements.
October 2006
Initial Conditions:
The plant is operating at 100% power.
Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.
While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.
0 After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.
Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and NI-OP-43C, Plant Shutdown is being implemented.
Reactor power is now at 50%.
Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.
All rods fully insert After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.
Plant conditions are stabilized and a normal cool down occurs.
Psig Initiating cue:
(Operators name), identify the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category.
I. Provide repeat back of initiating Proper communications used for repeat SatlUnsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2
- Obtain a copy of the any of the 0
Reference materials obtained.
reference documents related to regulatory notifications. These are likely to include the following:
NIP-IRG-01 10CFR50.72 and 73 NUREG1022 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7.
October 2006
50.72 (b)(3)(iv)(B)(2).
logic is not reportable under 50.72 (b)(3)(iv)(B)(2) because the actuation is not due to a valid signal.
LER is not a verbal reporting 0 LER is required under 50.73 SatIUnsatlNA requirement.
(b)(2)(iv). Identification of this requirement is not required.
- 4. Locate and identify applicability of 0 Identifies leak rate above 10 gpm PasslFail 50.72(a)(I )(i). Declaration of an Emergency Class.
requires EAL 2.1.I UNUSUAL EVENT must be declared.
0 Identify reportability per 50.72(a)(l)(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of declaration.
- 5. Locate and identify applicability of 0 Refer to Tech Spec 3.2.5.a.1 and SatIUnsat 50.72(b)(2)(i). Non-emergency four hour report. Initiation of a plant shutdown required by Tech Specs. (If not already reported with the 50,72(a)(l)(i).
determines that with specification not being met, the required action to comply with Tech Spec is to be cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The plant shutdown being performed is required by Tech Specs.
0 Identify reportability per 50.72(b)(
PasslFail 2)(i) within four hours, if not already reported.
- 6. Locate and identify applicability of Identify reportability per PasslFail 50.72(b)(2)( iv)( B) Non-emergency four hour report.
Actuation of RPS when the reactor is critical.
50,72(b)(2)(iv)(B) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not already reported.
- 7. Locate and identify applicability of 0 Identify reportability per PasslFail 50.72(b)(3)(iv)(B)(S) Non-emergency eight hour report.
Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.
50.72(b)(3)(iv)(B)(S) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if not already reported.
End of JPM TERMINATING CUE: Determine notification requirements.
RECORD STOP TIME NRC SRO ADMIN JPM 1 4
October 2006
Applicant Cue Sheet Initial Conditions:
The plant is operating at 100% power.
Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short.
While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs. No other systems are affected.
After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.
Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and NI-OP-43C, Plant Shutdown is being implemented.
Reactor power is now at 50%.
Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited.
After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 psig Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches.
Plant conditions are stabilized and a normal cool down occurs.
Initiating cue:
(Operators name), identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.
October 2006 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Re port a bi I i ty Rea u i re men t 50.72 (b)(3)(iv)( B)(2).
General contain men t isolation signals.
50.72(a)(I )(i) and (a)(3).
Declaration of an Emergency Class 50.72(b)(Z)(i). Initiation of a plant shutdown required by Tech Specs 50.72( b)(2)( iv)( B).
Actuation of RPS when the reactor is critical.
50.72( b)(3)(iv)(B)(5). Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.
Time Limit NOT REPORTABLE Within 15 minutes of declaration,
immediately after notifying state and local agencies and not later than one hour after the time of declaration Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not previously reported.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not previously reported.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if not previously reported.
Reason (Event) Category Applies Containment Purge Isolation during maintenance activity. Also, only affects one system.
Declaration of UE 2.1.I initiation of a plant shutdown required by Tech Specs 3.2.5.a.1. Unidentified leakage is above 5 gpm.
Automatic reactor trip when the reactor is critical.
Manual initiation of Emergency Condensers to control pressure.
Intentional manual actions are valid initiations. Also, the HPCl mode (feedwater coolant injection) is actuated.
October 2006 JPM Scorecard For Applicant Use I
Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category I
Reporta bil ity I Time Limit Req u i rem en t Reason (Event) Category Amlies NRC SRO ADMIN JPM 1 7
October 2006
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Review Reactivity Maneuver Request and Classify Reactivity Events Revision: NRC 2006 Task Number: NA Ap p rova Is :
NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(SRO)
Train e r/Eva I u a tor:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time: 20 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if an\\/ critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
October 2006
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
N /A Directions to the InstructorlEvaluator:
Applicant is to be provided with 3D Monicore printout data and RMR for review and approval. A 5 Loop Power to Flow Map is also required.
Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
- 2. During Evaluated JPM:
- 3. During Training JPM:
0 Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
I. GAP-OPS-05 Tools and Equipment:
- 1. None Task Standard:
Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map.
Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.
October 2006
PART 1 0
0 The plant is operating at rated power.
An intended plant maneuver to raise rod line is being planned.
A Reactivity Maneuver request is provided for review.
Initiating cue:
PART 1 (Operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.
PART 2 (After actions are complete for RMR)
The following events occur:
Loud abnormal noises are reported from the Main Turbine.
Power is rapidly reduced to 75% with Recirc Flow.
After power is reduced to 75% the Main Turbine automatically trips.
EOPs are entered and implemented.
ERVs actuate.
Turbine Bypass Valves were observed to remain closed throughout the transient.
Control Rod 18-19 is at position 04.
All other control rods are at position 02.
PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided.
- 1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
- 02. Obtain a copy of the any of the 0 Reference materials obtained.
reference documents.
PART I
- 03. Reviews RMR and supporting 3D 0 Determines predicted results cause PasslFail Monicore predictor case.
operation outside ELLLA Operating Limit (PFR Line) of Power Flow Map. (PFR is > 1.O)
Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. (PFR is > 1.O)
October 2006 PasslFail
Grade PART 2
- 04. Refer to GAP-OPS-05 section Identifies the emergency power PasslFail 3.13 to classify reactivity event severity levels.
reduction OR unplanned scram as Severity Level 4 (4-1 Rapid Downpower 2 0.5% RTP or shutdown due to emergent issues)
OR 4-9 Unplanned Reactor Scram While Critical.
Sat/Unsat 0 May also identify other SL-4 events, such as 4-1 1, with rods at 02 and 04, following the scram.
0 Identifies the Main Turbine Trip with PasslFail Bypass Valve failure to operate as Severity Level 2 (2-1 Main Turbine Trip With Bypass System failure).
NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram.
All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.
SatlUnsat Identifies CR (DER) is required for severity level 1,2,3 and 4 events.
- 13. Report completion.
Reports completion.
Sat/Unsat TERMINATING CUE: Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR. Identifies and initiates actions for Reactivity Events.
RECORD STOP TIME NRC SRO ADMIN JPM 2 4
October 2006
Applicant Cue Sheet Initial Conditions:
PART 1 The plant is operating at rated power.
An intended plant maneuver to raise rod line is being planned.
A Reactivity Maneuver request is provided for review.
Initiating cue:
PART 1 (operators name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.
PART 2 (After actions are complete for RMR)
The following events occur:
e 0
Loud abnormal noises are reported from the Main Turbine.
Power is rapidly reduced to 75% with Recirc Flow.
After power is reduced to 75% the Main Turbine automatically trips.
EOPs are entered and implemented.
ERVs actuate.
Turbine Bypass Valves were observed to remain closed throughout the transient.
Control Rod 18-19 is at position 04.
All other control rods are at position 02.
PART 2 (Operators name), based on the plant events that occur identify any internal classification and administrative actions related to the events.
Document findings and conclusions on scorecard provided.
October 2006 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events.
ACTIONS Determines predicted results cause operation outside ELLLA Operating Limit (PFR Line > 1.O) of Power Flow Map.
Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map.
Identifies the emergency power reduction or unplanned scram as Severity Level 4.
Identifies the Main Turbine Trip with Bypass Valve failure to operate as Severity Level 2 NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram. All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram.
Identifies CR (DER) is required for severity level 1,2,3 and 4 events.
Explanation 100% power and 83.9% core flow
( I 12.3% rod line) results in operation above ELLLA. (PFR > I.O)
GAP-OPS-05 Attachment 1 Item 2 evaluates the RMR for maintaining operation within allowable regions of the power to flow map. Since this maneuver does not accomplish this, the RMR should not be approved.
GAP-OPS-05 section 3.13 SL 4.
Example 4-1 Rapid Downpower 1 0.5% RTP or shutdown due to emergent issues OR 4-9 Unplanned Reactor Scram While Critical.
GAP-OPS-05 section 3.13 Example 2-1 Main Turbine Trip With Bypass System failure.
GAP-OP-05 section 3.13.2 NRC SRO ADMIN JPM 2 6
October 2006
JPM Scorecard For Applicant Use Document any findings and conclusions for PART 1 and PART 2 events.
Actions Exdanation NRC SRO ADMIN JPM 2 7
October 2006
CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE
Title:
Emergency Classification With PARS Task Number: N/A Revision: NRC 2006 NA EXAMINATION SECURITY General Supervisor Date Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
PRO)
TrainerlEvaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time:
20 min Time Critical Task:
YES Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature:
Date:
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with proper references.
Simulator Set-up (if required):
None Directions to the InstructoriEvaluator:
Candidate is to be provided with blank SM/ED Emergency Plan packet (obtained from control room or simulator) that would be used by SMlED during actual emergency plan implementation.
Directions to Operators:
Read Before Everv JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional / concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a
- 2. During Evaluated JPM:
- 3. During Training JPM:
0 Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
1.
- 2. EPIP-EPP-20, Emergency Notifications
- 3. EAL Matrix EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations SRO ADMIN JPM 5 October 2006
Tools and Equipment:
- 1. EAL Matrix
- 2. SM/ED Emergency Plan Packet Task Standard:
Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.)
Initial Conditions:
1.
- 2.
- 3.
- 4.
The plant is under accident conditions.
A Site Area Emergency has been declared based on plant conditions.
An Exclusion Area Evacuation has been directed and is in progress.
The Chemistry Technician has reported the following release data:
Dose assessment for ground level release rate is 58 Curies per second (Cilsecond)
Dose assessment for elevated level release rate is 502 Cilsecond Wind speed is 8 mph Wind direction is from the East South East (150)
Pascal Stability Class is E Initiating Cues:
(Operators name), Take the required actions as the Emergency Director.
Performance Steps Standard Grade Evaluator Note: Inform the Candidate that this is a Time-Critical task 1,
Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary.
RECORD TASK 1 CRITICAL START TIME
- 2.
Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.
- 3.
Using given plant data and EPIP-EPP-08 Table 1.I and Table 1.2, determine that a General Emergency exists based upon calculated total release (ground release + elevated release).
Proper communications used for repeat back (GAP-OPS-01 /Operations Manual)
The candidate may reference anylall of the following:
EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A General Emergency is declared, within 15 minutes of recorded start time for Task 1.
From EPP-08 Attachment 1 58/83 + 502/1250 = 1.1003 (General Emergency Exists if above 1.O)
SatlUnsat Sa t/U n sa t PasslFail SRO ADMlN JPM 5 October 2006
RECORD TASK 1 CRITICAL STOP/ TASK 2 CRITICAL START TIME
- 4.
Review meteorological data and EPIP-PARs made and indicated on Part 1 PasslFail EPP-08 and/or EPIP-EPP-20 to determine PARs.
Notification Fact Sheet to evacuate and implement KI plan for ERPAs 1, 2, 3, 26, and 27 and shelter all remaining ERPAs, within 15 minutes of recorded start time for Task 2.
RECORD TASK 2 CRITICAL STOP TIME Terminating Cue:
RECORD STOP TIME The event is classified as a General Emergency and PARs are made.
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
The plant is under accident conditions.
A Site Area Emergency has been declared based on plant conditions.
An Exclusion Area Evacuation has been directed and is in progress.
The Chemistry Technician has reported the following release data:
0 Dose assessment for ground level release rate is 58 Curies per second (Ci/second)
Dose assessment for elevated level release rate is 502 Ci/second.
Wind speed is 8 mph Wind direction is from the East South East (150°)
Pascal Stability Class is E Initiating Cues:
(Operators name), Take the required actions as the Emergency Director.
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Determine Thermal Limits with Inoperable Pressure Regulator Revision: NRC 2006 Task Number: NA 7
NA EXAMINATION SECURITY Gederal Su&rvisor date General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
(SRO)
Trainer/Evaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time: 25 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
October 2006
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
Applicant is to be provided with N1-RESP-1 for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and N1-OP-31 Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a "*".
- 2. During Evaluated JPM:
- 3. During Training JPM:
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1.
- 2.
- 4. N1-OP-31. H.5.0 and H.3.0 Core Operating Limits Report (COLR)
N1 -RESP-1 Daily Thermal Limit Surveillance Tools and Equipment:
- 1. None Task Standard:
October 2006
essure regulator. Identify COLR MCPR limit is exceeded and TechSpec 3.1.7 actions required.lnitial Condkons:
e e
e e
The plant is operating at power Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue:
(Operators name), using the 3D Monicore printout provided complete N1 -RESP-I, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13.
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary Proper communications used for repeat RECORD START TiME
-2. Obtain a copy of the any of the 0
reference documents.
e3. Candidate may reference N1-OP-0 31, H.3.0.
- 4. Record data in N1-RESP-1 by 0
obtaining information from 3D Monicore printout.
0 0
Reference materials obtained.
Refers to N1-OP-31, H.3.0 for direction for operation with one pressure regulator inoperable.
Refer to Core Operating Limits Report for applicable MFLPD and MFLCPR thermal limit restrictions.
IF unable to meet COLR thermal limit restrictions, THEN perform the following:
Enter applicable Tech Spec (3.1.7)
Notify Reactor Engineering to obtain direction to achieve compliance with applicable thermal limit restrictions.
Records Core Thermal Power in step 9.2.2 as 1591 MWth and 86.O O/O.
Records Total Core Flow in step 9.2.3 as 48.023 Mlbm/hr and 71.I Yo Records step 9.2.4 as NA, since all RRPs are operating.
Sa t/U n sa t Sat/Unsat/NA SaVUnsat PasslFail PasslFail Sa t/U n sa t Sat/Unsat Sat/Unsat NRC SRO ADMIN JPM 3 3
October 2006
Grade
- 5. Determine Adjusted MCPR limit value for step 9.2.6.1, with pressure regulator out of service and thermal power between 45%
and 90% from the COLR.
- 6. Determine Actual MCPR Value from 3D Monicore printout.
- 8. Enter Tech Spec 3.1.7.c
- 9. Record data in N1-RESP-I by obtaining information from 3D Monicore printout.
Records MAPRAT and location in step 9.2.5 as 0.775 and 41-38 Records step 9.2.6 as NA, since all RRPs are operating.
Determines adjusted value to be I
.809, from COLR Section 2.1 and Figure 2b, as follows:
For 70% 2 P (Rated OLMCPR)/FRTP 90% MCPR Limit =
Rated OLMCPR= MCPRlim*Kf
= 1.53*1.017 = 1.556
= 1.5561.860 = 1.809 Enters 1.809 as Adjusted MCPR limit value for step 9.2.6.1 Determines actual MCPR value to be 1.753, from printout.
Enters 1.753 as Actual MCPR Value for step 9.2.6.1 Evaluates actual MCPR value to be less than adjusted limit and that the MCPR thermal limit is NOT met.
Recognize entry into Tech Spec 3.1.7 specification c.
Identifies action shall be initiated within 15 minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit.
Notifies Reactor Engineering to obtain direction to achieve compliance with applicable limits.
(OP-31 H.3.2.2)
Records MFLCPR and location in step 9.2.7 as 1.032 and 29-14.
Records step 9.2.8 as NA, since all RRPs are operating.
Records Power to Flow Ratio (PFR) step 9.2.9 as 0.933.
SatlUnsat PasslFail SatlUnsat PasslFail SatIUnsat PasslFail PasslFail SatlUnsat SatlUnsat SatlUnsat Sa t1U n sa t NRC SRO ADMlN JPM 3 4
October 2006
Grade
- 10. Determine Adjusted LHGR limit Determines adjusted value to be PasslFail value for step 92.10, with pressure regulator out of service and thermal power between 45%
and 90% from the COLR.
0.860, from COLR Section 3.1 and Figure 3, as follows:
For 70% I P < 90% MFLPD Limit =
FRTP
= 1591 /I 850 = 0.8600 Enters 0.860 as Adjusted LHGR Sat/Unsat limit value for step 9.2.10.
- 11. Determine Actual MFLPD Value Determines actual MFLPD value to PasslFail from 3D Monicore printout.
be 0.735, from printout.
Enters 0.735 as Actual MFLPD Sat/Unsat Value for step 9.2.10
- 12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met.
less than adjusted limit and that the MFLPD thermal limit is met.
Records MFLPD and location in step Sat/Unsat 9.2.1 1 as 0.735 and 41-38.
Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.
0 Records step 9.2.1 3 as NA, since FPAPDR is < 1.O.
Sa t/U n sa t
- 13. Report completion.
0 Reports completion.
Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.
RECORD STOP TIME NRC SRO ADMIN JPM 3 5
October 2006
Applicant Cue Sheet Initial Conditions:
The plant is operating at power 0 Current core thermal power and flow are indicated on 3D Monicore printout 0 The Mechanical Pressure Regulator is out of service for repairs 0 MPR linkage is disconnected at the Front Standard Initiating cue:
(Operators name), using the 3D Monicore printout provided complete N1 -RESP-1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.1 3.
October 2006
PAGE 1
.I CORE PARAMETERS 3 DM/ P11 POWER MWT FLOW MLB /HR FPAPDR SUBC BTU/LB PR PSIa CORE MWD/sT CYCLE MWD/sT MCPR T STEP HOURS 1591.0 48.023 0.855 28.31 1012.63 26190.6 9709.3 1.753 0.7 CALC RESULTS K e f f 1.0034 XE WORTH %
-2.33 XE/RATED 1.01 AVE VF 0.371 PFR 0.933 CORRECTION FACTORS: MFLCPR= 1.017 MFLPD= 1.000 OPTION: PRE-ARTS 5 LOOPS ON MANUAL FLOW 20-OCT-2006 13:39 CALCULATED 20-OCT-2006 13:40 PRINTED CASE ID FTFF1061020133947 RESTART FMLD1061020084721 FIT - FULL CORE LOAD LINE
SUMMARY
CORE POWER 86.0%
CORE FLOW 71.1%
LOAD LINE 107.5%
MAPRAT= 1.000 MCPRLIM= 1.530 MOST LIMITING LOCATIONS (NON-SYMMETRIC)
MFLCPR LOC MFLPD LOC PCRAT LOC MAPRAT LOC 0.887 0.880 0.879 0.878 0.868 0.868 0.863 0.863 0.862 0.861 51 47 43 39 35 31 27 23 19 15 11 07 03 L
L L
L L
L 29-14 31-12 33-14 31-16 27-18 39-24 41-22 39-20 37-22 35-26 0 0 0 0 0.735 41 4 0.775 0.732 37 4 0.772 0.726 39 4 0.772 0.723 35 4 0.764 0.723 37 4 0.760 0.722 41 9 0.756 0.721 27 9 0.755 0.720 33 4 0.751 0.716 43 9 0.751 0.715 33 4 0.750 41 4 0.862 37 7 37 5 0.859 23 5 37 4 0.859 29 7 39 4 0.859 43 9 33 5 0.859 43-24-11 33 5 0.857 37 5 35 4 0.857 33 5 43 5 0.856 41 7 27 8 0.856 29 5 43 5 0.855 33 7 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL 08 0 0 06 36 P
C 36 06 36 08 L
L L
L L
L 02 06 10 14 18 22 26 30 34 38 42 46 5 0 NOTCH REL PW 00 02 04 06 08 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 0.154 0.276 0.574 0.737 0.840 0.928 0.976 0.982 1.107 1.160 1.178 1.217 1.253 1.262 1.255 1.285 1.293 1.271 1.292 1.304 1.272 1.171 0.928 0.285 LOC 24 23 22 21 20 19 18 17 16 15 14 13 12 11 10 09 08 07 06 05 04 03 02 01
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Determine Actions for Service Water Radiation Monitor Low Flow Revision: NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date General Supervisor Date 0 pe ra t i o n s 'T ra i in g ( Des i g nee )
Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer:
P O )
TrainerlEvaluator:
Evaluation Method:
X Perform Simulate Evaluation Location:
Plant X
Simulator or other location Expected Completion Time:
20 min Time Critical Task:
NO Alternate Path Task: NO Start Time:
Stop Time:
Completion Time:
JPM Overall Rating:
Pass Fail NOTE:
A JPM overall rating of fail shall be given if an^ critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.
Comments:
Evaluator Signature:
Date:
October 2006
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area Simulator Set-up:
N /A Directions to the Instructor/Evaluator:
None Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Traininq JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a o.
- 2. During Evaluated JPM:
- 3. During Training JPM:
Self checking shall be demonstrated.
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. ARP HI; HI-4-5.
- 2. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. IB.
- 5. K/A 2.3.1 1 (3.2) Ability to control radiation releases.
- 6. 2.4.45 (3.6) Ability to prioritize and interpret the significance of each annunciator or alarm.
Tools and Equipment:
- 1. None Task Standard: Determine actions per ARP HI-4-5 and ODCM in response to service water radiation monitor low flow condition.
October 2006
Initial Conditions:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
The plant is operating at 100% power.
High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (1 2) hours.
H I 5, LQ PROCESS RAD MON, has alarmed.
Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel.
Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).
Sample flow cannot be adjusted.
Ask the operator for any questions.
Initiating cue:
(Operators name), determine the appropriate actions in response to these conditions.
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME
- 1..Obtain a copy of the reference procedure and reviewhtilize the correct section.
- 2. *Per ARP HI-4-5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:
- a..Notify Radiation Protection Instrument Support for repair b..lnitiate LCO sampling (Chemistry).
- 3..Reference ODCM and takes appropriate actions.
Proper communications used for repeat back (GAP-OPS-01)
ARP HI-4-5 obtained.
Operator Actions referenced.
ODCM obtained.
DLCO 3.6.14 referenced.
TBL D3.6.14-1 referenced.
Notifies Radiation Protection Instrument Support to initiate repairs.
Directs Chemistry to perform DLCO sampling per TBL D 3.6.14-1 Instrument1 B action (d); twelve (1 2) hour grab samples to be collected/analyzed for SW effluent.
Determines SW Radiation Monitor is inoperable.
References ODCM DLCO 3.6.14.a and TABLE D 3.6.14-1 Instrument 1 B and note (d) applies.
Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action Sat/Unsat SatIUnsat Sat/Unsat PasslFail PasslFail SatlUnsat PasslFail NRC SRO ADMIN JPM 4 3
October 2006
shown in TBL D 3.6.14-1.
Determines action (d) applies.
PasslFail Effluent releases via this pathway can continue provided that at least once per twelve (1 2) hours grab samples are collected and analyzed SW effluent.
Initiates CR for unplanned LCO entry.
SatlUnsat End of JPM TERMINATING CUE: SW Radiation Monitor flow adjusted and restored to operable status.
RECORD STOP TIME NRC SRO ADMIN JPM 4 4
October 2006
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. High wind conditions (20-25 mph with higher gusts) are present and are
- 3. HI-4-5, LQ PROCESS RAD MON, has alarmed.
- 4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.
- 5. Operator reports an EQUIP FAIL Light is shown for the Service Water
- 6. Chemistry reports alarm is caused by low sample flow. Flows are reading
- 7. Sample flow cannot be adjusted.
- 8. Ask the operator for any questions.
expected to continue for the next twelve (12) hours.
Discharge Monitor at the J Panel.
0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB).
Initiating cue:
(Operators name), determine the appropriate actions in response to these conditions.
October 2006 JPM Scorecard KEY Determine the appropriate actions in response to these conditions.
Action Direct Chemistry to initiate required LCO sampling Determines SW Radiation Monitor is inoperable.
Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in TBL D 3.6.14-1.
Determines action identified in note (d) applies. Effluent releases via this pathway
- an continue provided that st least once per twelve (1 2) hours grab samples are Zollected and analyzed SW 3ffl uent.
Required By (Document)
ARP H I 5 ODCM DLCO 3.6.14 TABLE D 3.6.14-1.
ODCM DLCO 3.6.14 TABLE NOTE (d)
October 2006 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.
Action Required Bv (Document)
October 2006