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) Revision: NRC 2006 Task Number:
Approvals:
NA EXAM SECURITY I General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAM SECURITY I Configuration Control Date Performer: (ROISRO)
Trainer1EvaIuator:
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 l i m e : 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
NRC RO ADMlN JPM 1 October 2006
References:
1, GAP-OPS-01; 3.10.
- 2. N1-ST-DO; 6.0, 7.0 and 8.0.
- 3. 2.1. I 8 (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. 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 instrument readings.
- 4. 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 Proper communications used for repeat Sat/Unsat cue. Evaluafor Acknowledge repeat back (GAP-OPS-01) back providing correction if necessary RECORD START TIME
- 1. *Obtain a copy of the reference N-ST-DO obtained. Sat/Unsat procedure and review/utilize the - Section 6.0, 7.0 and 8.0 referenced.
correct section.
NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM.
- 2. *Records section 6.0 Reactor Records Reactor Recirc Pump Inlet SatlUnsat Recirc Pump Inlet Temperature Temperature readings.
readings
- 3. Compares reading and Compares reading and determines PasslFail determines readings within 15°F readings within 15°F of each other.
Checks YES block in Section 6.0, PasslFail indicating the maximum difference in loop temperatures is < 15°F.
NRC RO ADMIN JPM 1 October 2006
- 4. *Records section 7.0 readings Recorded Section 7.0 LOW-LowLevel PasslFail alarm and Feedwater Level Column selected to checks agree with Attachment 1 without error.
Recorded Section 7.0 instrument PasslFail readings agree with Attachment 1 within k 1 inch.
Sat/Unsat Record Total Recirc Flow per step 7.1.2 for GEMAC variance check.
5 . .Compares YARWAY C h l l - Determines YARWAY (RPS Level Sat/Unsat Ch12 (RPS Level Column) Column) instrument readings differ by 5 instrument readings to guide which is above the guide value of 4.
values.
Determines YARWAY (RPS Level PasslFail Column) instruments OPERABLE.
Indicates an ACR is required to have the Sat/Unsat calibration checked.
- 6. .Performs GEMAC C h l l - Ch12 Determines GEMAC variance is 6 SatIUnsat variance check per Section 7.1.
Compares GEMAC variance to total SatIUnsat recirc flow and determines on line between ALERT RANGE and INOP Determines that GEMAC 11 or GEMAC PasslFail 12 must be declared inoperable.
Reports out of specification readings to PasslFail SRO.
- 7. .Records section 8.0 Records Condensate readings SatIUnsat Condensate readings Determines Hotwell level is below 57 PasslFail inches (Tech Spec Minimum)
Informs SRO Hotwell level is below 57 PasslFail inches (Tech Spec Minimum).
<Ref 2> is TS 3.1.8, HPCl is inoperable. PasslFai I
- 8. Provides completed sections to SRO informed of out of spec readings. SatIUnsat SRO. Informs of out of spec readings.
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 instrument readings.
- 4. Ask the operator for any questions.
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 Panel Meter Override Meter Value Reading Settings Obtained E-Panel Vessel Level Indicator (E Panel 10590)
K-Panel Vessel Level Indicator (K Panel: 3 6 ~ I9 ~
K-Panel Flange Level Indicator (K Panel: to ~ ~ ~ ~ t None 2Y-Lo f 1 inches
- elow -3 Reactor Vessel Level Recorder (F ~ a 3 6~ ~ ~ ~ ~ 1 ~
Wide Range Level Indicator (!=Panel: 3 6 - 9 ~ ~ 7.2 1-z Ch 11 Ch12 I11 12 GEMAC Level Column (F f an el: 36-76A, 77.5 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 520 OF RRP 12 Inlet Temp 525 OF RRP 13 Inlet Temp 520 OF RRP 14 Inlet Temp 530 OF RRP 15 Inlet Temp 520 OF Maximum difference in loop temperatures 15°F YES No 7.0 Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks OYES I N 0 Feedwater Level Column selected to (E ~ a ~ ~ ~ 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 K-Panel Flange Level Indicator 3 I <-3 I feet I Reactor Vessel Level Recorder (F Pane!: 3 I 74 I inches I Wide Range Level Indicator (F Pa I 6 I feet I I Column <Ref 1> fF ~ a3 ~
I ~
77 I ~
72 I in***
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-36-21D 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.
73 79 - 6 /
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:
az-.
Approvals:
Generaf Supervisor Operations Training (Designee) 1 Date2 b k ? NA EXAM SECURITY General Supervisor Operations (Designee)
I Date NA EXAM SECURITY I Configuration Control Date Performer: (RO)
TrainerlEvaluator:
Evaluation Method: X Perform Simulate EvaIuatio 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
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.
0100 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 back (GAP-OPS-01/ CNG-HU-1 .Ol-1001) providing correction if necessary.
RECORD START TIME
- 2. Reviews JPM Attachment 1to determine Reviews Attachment 1 and P&ID C- Sat/Unsat intended equipment lineup. 18019-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 the following incorrectly positioned Poison Pump 11 and 12 system components and consequences.
cornponents .
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- PasslFail 704 open, the boron tank is draining due to improper lineup.
o 41-07 LP-3 BV-LP PUMP 11 Pass/Fail SUCTION FROM LP TANK is closed but should be open.
Determines that with 41-07 closed Pass/Fail LP Pump 11 is inoperable because of loss of suction path.
o 41-06 LP-19 BV-LP PUMP 11 PasslFail SUCTION FROM TEST TANK is open but should be locked closed.
Determines that with 41-06 open Sat/Unsat LP Pump 11 is incorrectly lined up to the test tank.
Determines cumulative effect of as- u Determines both systems of Liquid PasslFail found component lineup. Poison are not operable.
Identifies tag applied to incorrect Notifies CRS of improperly positioned Sat/Unsat component. Informs Control Room per components and incorrect appIication GAP-OPS-01. of red clearance tag.
- 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 Perfo rmance Ste ps Standard Grade
- 7. Refers to LCO 3.1.2 Identifies LCO 3.1.2 Specification b. Sat/Unsat NOTE: applies because the redundant If a single pump was inoperable 7 days component is also inoperable.
would be allowed to restore the inoperable pump.
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 lentifies the requirement to res,xe PasslFail restored to operable. one of the redundant components to OPERABLE within one hour or an orderly shutdown is required End of JPM Terminating Cue: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required.
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 Impact on plant 3perationlconsequences 41-1 1 LP-2 BV-LP PUMP 12 SUCTION Nith LP Pump 12 drain 42-12 LP-704 open, FROM LP TANK is open and should be ihe boron tank is draining due to improper tagged closed. ineup.
Determines that with 41-07 closed LP Pump 41-07 LP-3 BV-LP PUMP I1 SUCTION 11 is inoperable because of loss of suction FROM LP TANK is closed but should be path open.
41-06 LP-19 BV-LP PUMP 11 SUCTION Determines that with 41-06 open LP Pump 11 FROM TEST TANK is open but should is incorrectly lined up to the test tank.
be locked closed.
Determines both systems of Liquid Identifies the requirement to restore one of the Poison are not operable and Tech Spec redundant components to OPERABLE within entry is required (TS 3.1.2). 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.
0100 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 Impact on plant ope ration/consequences NRC RO ADMIN JPM 2 October 2006
e Clearance Section Tags To Be Applied Tagged Component Description Location Tag Type PI Seq Place Verif Tagged Position Restoration Position 42-38 CLOSE FUSES LIQUID POISON PB17B Danger 1 INSTALLED IN INSTALLED IN PUMP 12 OFF POS ON POS 42-38 MTR BKR LIQUID POISON PB17B Danger 2 DISC CONN PUMP 12 42-38 TRIP FUSES LIQUID POISON PBI 7B Danger 3 INSTALLED IN INSTALLED IN PUMP 12 OFF POS ON POS 41-1 1 LP-2 BV-LP PUMP 12 RB 298 S Danger 4 CLOSED OPEN SUCTION FROM LP TANK 41-18 LP-18 BV-LP PUMP 12 SUCTION FROM TEST TANK 42-02 LP-20 BV-LP PUMP 12 RB 298 S Danger 4 CLOSED CLOSED DISCHARGE TEST I I I I I I I I 42-04 LP-4 BV-LP PUMP 12 RB 298 S Danger 4 CLOSED OPEN AND DISCHARGE LOCKED I I I I I 42-12 LP-704 DRAIN LP PUMP 12 RB 298 S Danger 5 OPEN CLOSED TO 55 GAL DRUM NRC RO ADMIN JPM 2 October 2006 As Found Component Positions Component Description Location As Found As Found Position Position 42-38 CLOSE FUSES LIQUID POISON PBI 7B INSTALLED PB16B INSTALLED PUMP 12 IN OFF POS POISON PUMP IN O N POS 42-38 MTR BKR LIQUID POISON PB17B DISC 42-39 MTR BKR LIQUID PB16B CONN PUMP 12 POISON PUMP 11 42-38 TRIP FUSES LIQUID POISON PBI 7B INSTALLED 42-39 TRIP FUSES LIQUID PB16B INSTALLED PUMP 12 IN OFF POS POISON PUMP IN ON POS 11 I
41-11 LP-2 BV-LP PUMP 12 RB 298 OPEN 41-07 LP-3 BV-LP PUMP RB 298 CLOSED SUCTION FROM S 11 SUCTION LP TANK FROM LP TANK 41-18 LP-18 BV-LP PUMP 12 RB 298 CLOSED 41-06 LP-19 BV-LP PUMP RB 298 OPEN SUCTION FROM S 11 SUCTION S TEST TANK FROM TEST TANK 42-02 LP-20 BV-LP PUMP 12 RB 298 CLOSED 42-01 LP-21 BV-LP PUMP RB 298 CLOSED DISCHARGE S 11 DISCHARGE S TEST TEST 42-04 LP-4 BV-LP PUMP 12 RB 298 CLOSED 42-03 LP-5 BV-LP PUMP RB 298 OPEN DISCHARGE S 11 DISCHARGE S 42-12 LP-704 DRAIN LP PUMP RB 298 OPEN 42-11 LP-703 CLOSED 12 TO 55 GAL S DRUM 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. Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a 0.
- 2. During Evaluated JPM:
Self-verification shall be demonstrated.
- 3. During Training JPM:
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 Proper communications used for repeat SaUUnsat initiating cue. Evaluator back (GAP-OPS-01)
Acknowledge repeat back providing correction if necessary RECORD START TIME
- 1. Obtain a copy of the necessary Obtains the following documents, as procedures and drawings needed:
N1-EOP-3.1 Sat/Unsat/NA Drawing Index, if needed Sat/Unsat/NA Drawing C-I 9859-C Sheet 7 PasslFail
- 2. Using C-19859-C Sheet 7, Locates SCRAM BYPASS jumper PasslFail locates trip circuits and jumpers. (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP # I circuit.
Locates SCRAM BYPASS jumper PasslFail (EOP jumper 13) at drawing coordinate B - I to B-5, in REACTOR TRIP #2 circuit.
- 3. Using C-19859-C Sheet 7, Identifies that ALL AUTOMATIC PasslFail identifies the signals defeated scram signal relay trip contacts are when jumpers are installed. 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 REACTOR TRIP # I circuit, relay operation necessary to reset the 12K51A (coordinate B-5) energizes scram. 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 Sat/Unsat 1S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C-4), closes its I S 3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).
NRC RO ADMIN JPM 3 October 2006
I Performance Steps I Standard 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 PasslFail energizing and closes the following contacts:
0 12K55 L1-TI for GROUP 1 (coordinate D-2) 0 12K55 L2-T2 for GROUP 2 (coordinate E-2) 12K55 L3-T3 for GROUP 3 (coordinate F-2) 0 12K55 L4-T4 for GROUP 4 (coordinate G-2) 0 12K55 7-8 for Backup Scram circuitry (coordinate H-2)
Indicates that Relay 12K56 provides SatIUnsat a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released.
Indicates that when all three contacts PasslFail in the four GROUP 1 through 4 circuits for 12K51A, 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.
identified on station electrical drawings and operation is explained.
RECORD STOP TIME NRC RO ADMIN JPM 3 October 2006
Initial Conditions:
- 1. The plant is experiencing a failure to scram.
- 2. N 1-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 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 Revision: NRC 2006 High Radiation Areas Task Number: N/A NA EXAMINATION SECURITY Ge ndraI Superv6 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 EvaI uat 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
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 Proper communications used for repeat SatlUnsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME NOTE: A score card is attached to this JPM identifying the items for the performer to identify.
2 . Classify the area. Determines the area is a HIGH PasslFail RADIATION AREA.
3 . Determine highest on contact Determines highest on contact dose PasslFail and general area dose rates and rate to be 500 mremlhr at 12 SDC location, based on survey map pump.
Determines highest general area PasslFail dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger.
- 4. Determines highest Determines highest contamination PasslFail contamination levels in the room. level to be 8000 dpmllOO cm2at 12 SDC Pump, smear location #7.
- 5. Determine RWP and Task Determines RWP 106001 Task 2 is PasslFail Number required for entry. correct for the job.
6 . Determines insufficient delta Determine within delta exposure of PasslFail exposure to enter without 300 mrem and additional approvals additional approval. 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.
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 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.
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
Map No.
U d t One RB 261' Shut-Down Cooling Room Rx Power 100 %
H, Inj. Rate 6 scfm 13SDCPurnp I
/
-*250 -
50 @ DO NOT LINGER SIGN, 75 WHICH IS ALSO AT BOTTOM 1 @ 38-05 PIPE TAPS (SHIELDED)
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 o f 2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk.
7391 Inspections, Maintenance and Surveillances in High Radiation Areas.
TASK: 1 High Radiation Area (HRA)
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 -
2 200mRem/hr Reactor Building HRAs 2 - 250mRem/hr Rad Waste Buiding HRAs 2 - GOOmRem/hr Off Gas Building HRAs -
2 120mRem/hr Contamination Levels: e400 - 10,000 dprn/lOOcm2 Airborne Levels: ~ 0 . 3DAC 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.
7389 Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas.
TASK: 2 High Radiation Area (HRA)
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 2 - 200mRemlhr Reactor Building HRAs 2 - 25OmRemlhr Rad Waste Buiding HRAs 2 - GOOmRem/hr Off Gas Building HRAs 2 - 120mRem/hr Contamination Levels: e400 - 10,000 dpm/lOOcm2 Airborne Levels: ~ 0 . 3DAC 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 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:
NRC SRO ADMIN JPM 1 1 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:
by a ".".
- 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted
- 2. During Evaluated JPM:
Self checking shall be demonstrated.
- 3. During Training JPM:
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.
NRC SRO ADMIN JPM 1 2 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.
After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm.
0 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 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.
NRC SRO ADMlN JPM 1 3 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 requires EAL 2.1 .IUNUSUAL Emergency Class. 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 determines that with specification not four hour report. Initiation of a being met, the required action to plant shutdown required by Tech comply with Tech Spec is to be cold Specs. (If not already reported shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The plant with the 50,72(a)(l)(i). 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- 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 emergency four hour report. not already reported.
Actuation of RPS when the reactor is critical.
- 7. Locate and identify applicability of 0 Identify reportability per PasslFail 50.72(b)(3)(iv)(B)(S) Non- 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 emergency eight hour report. not already reported.
Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.
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.
NRC SRO ADMIN JPM 1 5 October 2006
Attachment 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reporta biIity Time Limit Reason (Event) Category Reauirement Applies 50.72 (b)(3)(iv)(B)(2). NOT Containment Purge Isolation General contain ment REPORTABLE during maintenance activity. Also, isolation signals. only affects one system.
50.72(a)(I )(i) and (a)(3). Within 15 minutes Declaration of UE 2.1 .I Declaration of an of declaration ,
Emergency Class immediately after notifying state and local agencies and not later than one hour after the time of declaration 50.72(b)(Z)(i). Initiation of a Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if initiation of a plant shutdown plant shutdown required by not previously required by Tech Specs Tech Specs reported. 3.2.5.a.1. Unidentified leakage is above 5 gpm.
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 Automatic reactor trip when the Actuation of RPS when the not previously reactor is critical.
reactor is critical. reported.
50.72( b)(3)(iv)(B)(5). Event Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if Manual initiation of Emergency or condition results in valid not previously Condensers to control pressure.
actuation of BWR isolation reported. Intentional manual actions are condenser system and valid initiations. Also, the HPCl feedwater coolant injection. mode (feedwater coolant injection) is actuated.
NRC SRO ADMIN JPM 1 6 October 2006
Attachment 2 JPM Scorecard For Applicant Use Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability I Time Limit Reason (Event) Category Requirement Amlies I
I 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 provaIs:
NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)
Trainer/Eva Iuator:
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:
NRC SRO ADMIN JPM 2 1 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
0 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.
NRC SRO ADMIN JPM 2 2 October 2006
PART 1 0 The plant is operating at rated power.
0 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 0 3 . 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)
PasslFail 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)
NRC SRO ADMlN JPM 2 3 October 2006
Grade PART 2
- 04. Refer to GAP-OPS-05 section Identifies the emergency power PasslFail 3.13 to classify reactivity event reduction OR unplanned scram as severity levels. 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.
0 May also identify other SL-4 Sat/Unsat 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.
Identifies CR (DER) is required for SatlUnsat 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:
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.
e Control Rod 18-19 is at position 04.
0 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.
NRC SRO ADMIN JPM 2 5 October 2006
Attachment 1 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events.
ACTIONS Explanation Determines predicted results 100% power and 83.9% core flow cause operation outside ( I 12.3% rod line) results in ELLLA Operating Limit (PFR operation above ELLLA. (PFR > I .O)
Line > 1.O) of Power Flow Map.
GAP-OPS-05 Attachment 1 Item 2 Does NOT approve the RMR evaluates the RMR for maintaining based on failure to maintain operation within allowable regions of plant operation within the power to flow map. Since this allowable regions of the power maneuver does not accomplish this, to flow map. the RMR should not be approved.
GAP-OPS-05 section 3.13 SL 4.
Identifies the emergency Example 4-1 Rapid Downpower 1 power reduction or unplanned 0.5% RTP or shutdown due to scram as Severity Level 4. emergent issues OR 4-9 Unplanned Reactor Scram While Critical.
GAP-OPS-05 section 3.13 Example Identifies the Main Turbine 2-1 Main Turbine Trip With Bypass Trip with Bypass Valve failure System 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 GAP-OP-05 section 3.13.2 for severity level 1,2,3 and 4 events.
NRC SRO ADMIN JPM 2 6 October 2006
Attachment 2 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 Revision: NRC 2006 Task Number: N/A 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
Self checking shall be demonstrated.
0 Peer checking shall be demonstrated.
References:
- 1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations
- 2. EPIP-EPP-20, Emergency Notifications
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. The plant is under accident conditions.
- 2. A Site Area Emergency has been declared based on plant conditions.
- 3. An Exclusion Area Evacuation has been directed and is in progress.
- 4. 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. Proper communications used for repeat SatlUnsat Evaluator Acknowledge repeat back back (GAP-OPS-01/Operations Manual) providing correction if necessary.
RECORD TASK 1 CRITICAL START TIME
- 2. Obtain a copy of the reference procedure The candidate may reference anylall of Sat/Unsat and reviewhtilize the correct section of the the following:
procedure. EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A
- 3. Using given plant data and EPIP-EPP-08 General Emergency is declared, within 15 PasslFail Attachment 1 Table 1 .Iand Table 1.2, minutes of recorded start time for Task 1 .
determine that a General Emergency exists based upon calculated total release From EPP-08 Attachment 1 (ground release + elevated release).
58/83 + 502/1250 = 1.1003 (General Emergency Exists if above 1.O)
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 Notification Fact Sheet to evacuate and PARs. 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: The event is classified as a General Emergency and PARs are made.
RECORD STOP TIME SRO ADMIN JPM 5 October 2006
Initial Conditions:
- 1. The plant is under accident conditions.
- 2. A Site Area Emergency has been declared based on plant conditions.
- 3. An Exclusion Area Evacuation has been directed and is in progress.
- 4. The Chemistry Technician has reported the following release data:
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°)
0 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:
NRC SRO ADMlN JPM 3 1 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. Core Operating Limits Report (COLR)
- 2. N1-RESP-1 Daily Thermal Limit Surveillance
- 4. N1-OP-31. H.5.0 and H.3.0 Tools and Equipment:
- 1. None Task Standard:
NRC SRO ADMIN JPM 3 2 October 2006
essure regulator. Identify COLR MCPR limit is exceeded and TechSpec 3.1.7 actions required.lnitial Condkons:
e The plant is operating at power e Current core thermal power and flow are indicated on 3D Monicore printout e The Mechanical Pressure Regulator is out of service for repairs e 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 Proper communications used for repeat Sat/U nsat 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.
e3. Candidate may reference N1-OP- 0 Refers to N1-OP-31, H.3.0 for Sat/Unsat/NA 31, H.3.0. direction for operation with one pressure regulator inoperable.
Refer to Core Operating Limits SaVUnsat 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 PasslFail (3.1.7)
Notify Reactor Engineering to PasslFail obtain direction to achieve compliance with applicable thermal limit restrictions.
- 4. Record data in N1-RESP-1 by 0 Records Core Thermal Power in Sat/U nsat obtaining information from 3D step 9.2.2 as 1591 MWth and Monicore printout. 86 .O O/O.
0 Records Total Core Flow in step Sat/Unsat 9.2.3 as 48.023 Mlbm/hr and 71 .IYo 0 Records step 9.2.4 as NA, since all Sat/Unsat RRPs are operating.
NRC SRO ADMIN JPM 3 3 October 2006
Grade Records MAPRAT and location in SatlUnsat step 9.2.5 as 0.775 and 41-38 Records step 9.2.6 as NA, since all RRPs are operating.
- 5. Determine Adjusted MCPR limit Determines adjusted value to be PasslFail value for step 9.2.6.1, with I.809, from COLR Section 2.1 and pressure regulator out of service Figure 2b, as follows:
and thermal power between 45%
and 90% from the COLR. For 70% 2 P 90% MCPR Limit =
(Rated OLMCPR)/FRTP Rated OLMCPR= MCPRlim*Kf
= 1.53*1.017 = 1.556
= 1.5561.860= 1.809 SatlUnsat Enters 1.809 as Adjusted MCPR limit value for step 9.2.6.1
- 6. Determine Actual MCPR Value Determines actual MCPR value to be PasslFail from 3D Monicore printout. 1.753, from printout.
Enters 1.753 as Actual MCPR SatIUnsat Value for step 9.2.6.1
- 7. Determines COLR thermal limit Evaluates actual MCPR value to be PasslFail restriction for MCPR is not met. less than adjusted limit and that the MCPR thermal limit is NOT met.
- 8. Enter Tech Spec 3.1.7.c Recognize entry into Tech Spec PasslFail 3.1.7 specification c.
Identifies action shall be initiated SatlUnsat 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 SatlUnsat obtain direction to achieve compliance with applicable limits.
(OP-31 H.3.2.2)
- 9. Record data in N1-RESP-I by Records MFLCPR and location in SatlUnsat obtaining information from 3D step 9.2.7 as 1.032 and 29-14.
Monicore printout.
Records step 9.2.8 as NA, since all RRPs are operating.
Records Power to Flow Ratio (PFR) Sat1Unsat step 9.2.9 as 0.933.
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 0.860, from COLR Section 3.1 and pressure regulator out of service Figure 3, as follows:
and thermal power between 45%
and 90% from the COLR. 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.
1 1 . 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 9.2.11 as 0.735 and 41-38.
Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.
0 Records step 9.2.13 as NA, since Sat/U nsat FPAPDR is < 1.O.
- 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 9.2.13.
NRC SRO ADMIN JPM 3 6 October 2006
.I PAGE 1 CORE PARAMETERS 3DM/P11 20-OCT-2006 13:39 CALCULATED 20-OCT-2006 13:40 PRINTED POWER MWT 1591.0 CASE ID FTFF1061020133947 FLOW MLB /HR 48.023 CALC RESULTS RESTART FMLD1061020084721 FPAPDR 0.855 FIT - FULL CORE SUBC BTU/LB 28.31 Keff 1.0034 PR PSIa 1012.63 XE WORTH % -2.33 LOAD LINE
SUMMARY
CORE MWD/sT 26190.6 XE/RATED 1.01 CORE POWER 86.0%
CYCLE MWD/sT 9709.3 AVE VF 0.371 CORE FLOW 71.1%
MCPR 1.753 PFR 0.933 LOAD LINE 107.5%
T STEP HOURS 0.7 CORRECTION FACTORS: MFLCPR= 1.017 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE-ARTS 5 LOOPS ON MANUAL FLOW MCPRLIM= 1.530 MOST LIMITING LOCATIONS (NON-SYMMETRIC)
MFLCPR LOC MFLPD LOC MAPRAT LOC PCRAT LOC 0.887 29-14 0.735 41 4 0.775 41 4 0.862 37 7 0.880 31-12 0.732 37 4 0.772 37 5 0.859 23 5 0.879 33-14 0.726 39 4 0.772 37 4 0.859 29 7 0.878 31-16 0.723 35 4 0.764 39 4 0.859 43 9 0.868 27-18 0.723 37 4 0.760 33 5 0.859 43-24-11 0.868 39-24 0.722 41 9 0.756 33 5 0.857 37 5 0.863 41-22 0.721 27 9 0.755 35 4 0.857 33 5 0.863 39-20 0.720 33 4 0.751 43 5 0.856 41 7 0.862 37-22 0.716 43 9 0.751 27 8 0.856 29 5 0.861 35-26 0.715 33 4 0.750 43 5 0.855 33 7 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT *=MULTIPLE CORE AVE AXIAL 51 NOTCH REL PW LOC L 00 0.154 24 47 02 0.276 23 04 0.574 22 43 36 06 0.737 21 L P 08 0.840 20 39 10 0.928 19
- 12 0.976 18 35 08 06 14 0.982 17 L 16 1.107 16 31 18 1.160 15 20 1.178 14 27 00 00 00 36 22 1.217 13 L 24 1.253 12 23 26 1.262 11 28 1.255 10 19 06 08 30 1.285 09 L 32 1.293 08 15 34 1.271 07 C 36 1.292 06 11 36 38 1.304 05 L 40 1.272 04 07 42 1.171 03 44 0.928 02 03 46 0.285 01 L L L L L L 02 06 10 14 18 22 26 30 34 38 42 46 50
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 0perat io ns 'Tra i ing ( 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:
NRC SRO ADMIN JPM 4 1 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:
Self checking shall be demonstrated.
- 3. During Training JPM:
Self checking shall be demonstrated.
Peer checking shall be demonstrated.
References:
- 1. ARP H I ; 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.
NRC SRO ADMIN JPM 4 2 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 expected to continue for the next twelve (12) hours.
- 3. H I 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 Discharge Monitor at the J Panel.
- 6. 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).
7 . Sample flow cannot be adjusted.
- 8. 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 Proper communications used for Sat/Unsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
- 1. .Obtain a copy of the reference ARP HI-4-5 obtained. SatIUnsat procedure and reviewhtilize the Operator Actions referenced.
correct section.
ODCM obtained.
DLCO 3.6.14 referenced.
TBL D3.6.14-1 referenced.
- 2. *Per ARP HI-4-5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then:
- a. .Notify Radiation Protection Notifies Radiation Protection Sat/Unsat Instrument Support for repair Instrument Support to initiate repairs.
b..lnitiate LCO sampling Directs Chemistry to perform DLCO PasslFail (Chemistry). sampling per TBL D 3.6.14-1 Instrument1B action (d); twelve (12) hour grab samples to be collected/analyzed for SW effluent.
- 3. .Reference ODCM and takes Determines SW Radiation Monitor is PasslFail appropriate actions. inoperable.
References ODCM DLCO 3.6.14.a SatlUnsat and TABLE D 3.6.14-1 Instrument 1B and note (d) applies.
Determines less than the minimum number of radioactive liquid effluent PasslFail monitoring channels for service water effluent and takes action 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 (12) hours grab samples are collected and analyzed SW effluent.
Initiates CR for unplanned LCO SatlUnsat entry.
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 expected to continue for the next twelve (12) hours.
- 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 Discharge Monitor at the J Panel.
- 6. 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).
- 7. Sample flow cannot be adjusted.
- 8. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the appropriate actions in response to these conditions.
NRC SRO ADMIN JPM 4 5 October 2006
Attachment 1 JPM Scorecard KEY Determine the appropriate actions in response to these conditions.
Action Required By (Document)
Direct Chemistry to initiate ARP H I 5 required LCO sampling Determines SW Radiation Monitor is inoperable.
Determines less than the ODCM DLCO 3.6.14 TABLE D minimum number of 3.6.14-1.
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 ODCM DLCO 3.6.14 TABLE releases via this pathway NOTE (d)
- an continue provided that st least once per twelve (12) hours grab samples are Zollected and analyzed SW 3ffl uent.
NRC SRO ADMIN JPM 4 6 October 2006
Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.
Action Required Bv (Document)