ML051570317
| ML051570317 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/06/2005 |
| From: | Godley R Constellation Energy Group |
| To: | Todd Fish Operations Branch I |
| Conte R | |
| References | |
| Download: ML051570317 (79) | |
Text
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Evaluate Shift Log Reading Data Per N2-OSP-LOG-DO01 Revision: NRC 2005 Task Number: 3410320303 Approvals:
NA EXAMINATION SECURITY Datd ' General Supervisor Date Operations Training (Designee) Operations -(Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)
TrainedEvaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 25 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:
2005 NRC RO ADMIN JPM 1 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
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 Pass/Fail. All steps are sequenced critical unless denoted by a a.
- 2. During Evaluated JPM:
0 Self-verification shall be demonstrated.
- 3. During Training JPM:
0 Self-verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OSP-LOG-DO01
- 2. K/A 2.1.18 Ability to make accurate / clear and concise logs / records / status boards / and reports (2.9).
Tools and Equipment:
- 1. Calculator.
Task Standard: Identify Jet pump number 13 differential pressure is outside of limits and informs CRS / SM 2005 NRC RO ADMIN JPM 1 2 4/20/2005
(
Initial Conaitions:
- 1. The plant is operating at 100 O/O power
- 2. N2-OSP-LOG-DO01 is in progress
- 3. Ask the operator for any questions.
Initiating cue:
(Operators name), given the data provided on JPM Attachment 1 and applicable section of N2-OSP-LOG-DO01 enter the instrument readings and take appropriate actions based on those checks.
- 1. Provide repeat back of Proper communications used for initiating cue. Evaluator repeat back (GAP-OPS-01 )
Acknowledge repeat back providing correction if necessary EVALUATOR to provide JPM Attachment IData Sheet and copy of NZ-OSP-LOG-DO01 Attachment 10 to candidate.
RECORD START TIME
- 2. .Obtain a copy of the o N2-OSP-LOG-DO01 Attachment Sat/Unsat reference procedure and I O , Two loop jet pump operability reviewhtilize the correct verification section.
- 3. .Use Data from Att.1 (Item 1 o Determines that Recirc loop B Sat/Unsat
& 2) transfer Recirculation FCV is < 85% and Recirc loop A pump FCV position data to FCV is < 95%
Att.10 Step 2.1.1 o Records FCV positions in Table Sat/Unsat 10-1. F C V A = 6 8 %
- 2. FCV B = 76%
2005 NRC RO ADMIN JPM 1 3 4/20/2005
1 Performallce Steps I Standard Grade Comments
- 4. Use Data from Att.1 (Item 3 o Transfers data to Table 10-1 Sat/Unsat
& 4) transfer B22-R611A and B22-R611A = 52%
B22-611B Sum Jet Pmp Flo to u Transfers data to Table 10-2. Sat/U nsat Att 10 step 2.2.1 B22-R611B = 52%
position for loop A recorded in table 10-1 obtain the Jet pump u Uses figure 10-1 Records High loop flow high and low limits and Low limits in table 10-1 Sat/Unsat for loop A from figure 10-1 and -
u HIGH Limit 56.5 (56-57) record them in table 10-1 step Low Limit - 46 2.3.2.a
position for loop B recorded in table 10-1 obtain the Jet pump o Uses figure 10-2 Records High loop flow high and low limits and Low limits in table 10-1 SaUUnsat for loop B from figure 10-2 and P High limit = - 56 record them in table 10-lstep o Low limit = 46-2.3.2.b
- 7. .Compare the actual Loop A o Reviews the data in table 10-1 SaUUnsat and Loop B Jet pump flows to and recognized the values are the respective Loop High and within the limits Low limits indicate in step 2.4 whether the actual values fall within the limits Step 2.4
- 8. Obtain Recirc Loop Drive o Transfers data to Table 10-2 Sat/Unsat Flows from Att 1 and records u B35-R614 LOOP A = 42,000 them in table 10-2 ( Item 5 &6) u B35-R614 LOOP B = 41,000 Step 3.2.1
- 9. Using the Recirc Loop A drive Uses figure 10-3 to obtain High and SaUUnsat Flow recorded in Table 10-2 Low limits and records values in obtain the jet pump loop flow Table 10-2 High and Low limits for Loop A -
High limit = 55.5 (55-56) from Figure 10-3 Step 3.3.1 Low limit = - 45.5 (45-46) 2005 NRC RO ADMlN JPM 1 4 4/20/2005
I Comments 10.Using the Recirc Loop B drive Uses figure 10-4to obtain High and Sat/U nsat Flow recorded in Table 10-2 Low limits and records values in obtain the jet pump loop flow Table 10-2 High and Low limits for Loop B High limit = -54.5(54-55) from Figure 10-4Step 3.3.2 Low limit = -44.5(44-45) 1 1 . Compare the actual Loop A Reviews data in Table 10-2and PasslFail and Loop B Jet pump flows to recognizes that the actual values fall the respective Loop High and within the limits Low limits as recorded in Table 10-2and indicate whether the actual values fall within limits Step 3.4 12.Use Data from Att. 1 transfer Transfers data to Table 10-3 SaWnsat value for each Jet pump AP in Loop A (Item 7) step 4.1 13.Calculate Loop A Average Jet Calculates Loop A average AP and Sat/Unsat pump AP and record in table record in Table 10-3 10-3Step 4.2 Average = 41.5 14.Divide each Loop A jet pump Divides each jet pump AP by the SaUUnsat AP by Loop A Average Jet average and record in table 10-3 pump AP and record resulting Jet pump 1 = 1.036 individual to average AP ratios Jet pump 2 = 0.867 in table 10-3Step 4.3 Jet pump 3 = 0.964 Jet pump 4 = 0.964 Jet pump 5 = 1 .I 08 Jet pump 6 = 1.I 57 Jet pump 7 = 0.964 Jet pump 8 = 0.964 Jet pump 9 = 0.964 Jet pump 10 = 1.012 2005 NRC RO ADMIN JPM 1 5 4/20/2005
I Performance Steps I Standard I Grade Comments 15.For all Jet pumps in Loop A Compare results and recognizes Pass/Fai compare each Jet pumps that the actual limits are within the individual to average AP ratio limits of Table 10-3 to the Limits gives in Table 10-3 and indicate whether the actual values are within the limits Step 4.4
- 16. Use Data from Att.1 transfer Transfers data to Table 10-3 Sat/Unsat value for each Jet pump AP in Loop B (Item 7 ) Step 4.1
- 17. Calculate Loop B Average Jet Calculates Loop B average AP and SaUUnsat pump AP and record in table record in Table 10-3 10-3 Step 4.2 Average = 39.1
- 18. Divide each Loop B jet pump Divides each jet pump AP by the SaUUnsat AP by Loop B Average Jet average and record in table 10-3 pump AP and record resulting Jet pump 11 = 1.023 individual to average AP ratios Jet pump 12 = 0.972 in table 10-3 Step 4.3 Jet pump 13 = 0.767 Jet pump 14 = 0.972 Jet pump 15 = 1.125 Jet pump 16 = 1.176 Jet pump 17 = 1.023 Jet pump 18 = 0.946 Jet pump 19 = 1.023 Jet pump 20 = 0.972
- 19. For all Jet pumps in Loop B Compare results and recognizes PasslFail compare each Jet pumps that the actual limit for Jet Pump 13 individual to average AP ratio is not within the limits of Table 10-3 to the Limits gives in Table 10-3 and indicate whether the actual values are within the limits Step 4.4 2005 NRC RO ADMlN JPM 1 6 4/20/2005
Comments Cue: As CRS / SM inform cand idate that appropriate actions will be taken for Jet pump 13 End of JPM TERMINATING CUE: Identify Jet pump number 13 differential pressure is outside of limits and informs CRS / SM.
RECORD STOP TIME 2005 NRC RO ADMIN JPM 1 7 4/20/2005
Initial Conditions:
Initial Conditions:
- 1. The plant is operating at 100 YO power
- 2. N2-OSP-LOG-DO01 is in progress
- 3. Ask the operator for any questions.
Initiating cue:
(Operators name), given the data provided on JPM Attachment 1 and applicable section of N2-OSP-LOG-DO01 enter the instrument readings and take appropriate actions based on those checks.
2005 NRC RO ADMIN JPM 1 a 4/20/2005
JPM Attachment 1 N2-OSP-LOG-DO01 Data Sheet Item # Description Value 1 I 2RCS-HCI603A, RECIRC 68%
LOOP A FLOW CONTROL 2 2RCS-HC1603B, RECIRC 76%
LOOP B FLOW CONTROL 3 B22-R611A, RECIRC LOOP 52 1A SUM JET PMP FLO 4 B22-R611B, RECIRC LOOP 52 1B SUM JET PMP FLO 5 B35-R614 RECIRC FLOW 42,000 LOOP A 6 B35-R614 RECIRC FLOW 4 1,000 2005 NRC RO ADMIN JPM 1 9 4/2012005
Attachment 2: Evaluation and Recommendation(s) (If performed in classroom)
OK TO PROVIDE TO CANDIDATE RECORD YOUR RESULTS BELOW Name:
Summary of Evaluation of data:
Summary Act ions:
2005 NRC RO ADMIN JPM 1 10 4/20/2005
Attachment 3: Evaluation and Recommendation(s) (If performed in classroom)
DO NOT PROVIDE TO CANDIDATE RECORD YOUR RESULTS BELOW Name:
Summary of Evaluation of data:
Actual Loop A and Loop B jet pump flows are within limits of Table 10-2 Loop A Jet Pumps are within limits of Table 10-3 Loop B Jet Pump 13 is NOT within specified limits of Table 10-3. All other jet pumps are within Table 10-3 limits.
Sum ma ry Actions :
Reported to CRS/SM 2005 NRC RO ADMlN JPM 1 11 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Perform Control Room System Verification Lineup Revision: NRC 2005 Task Number:
Approvals:
NA EXAMINATION SECURITY Date General SuDervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)
Trainer/Evaluator:
Evaluation Method: PERFORM Evaluation Location : SIMULATOR Expected Completion Time: 20 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:
Eva1uator Signature: Date:
2005 2005 NRC RO ADMIN JPM 2 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up:
On P871, place both Div. 2 Service Water Pump Bay Unit Cooler Control Switches in Pull-to-Lock.
On P871, place HVC*FN2B in Pull-to-Lock and hang RED CLEARANCE TAG on control switch.
Directions to the InstructorlEvaluator:
Provide candidate with partially completed Attachment 3 of S-PM-D001. The 0630-1830 column of Attachment 3 should be completed up to Section 2.1 5, which is completed for items except Service Water Ventilation, Control Building Ventilation, Reactor Building Ventilation UC409s and Standby Gas Train. These are the items to be evaluated by the candidate.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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 Training 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 I concurrent verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a o,
- 2. During Evaluated JPM:
0 Self-verification shall be demonstrated.
- 3. During Training JPM:
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. Operations Manual Section OM.2.2.
- 2. S-PM-D001.
- 3. N2-ARP-01 871308
- 4. N2-OP-58, Attachment 1
- 5. NUREG 1123, Rev. 2 K/A G 2.1.3 (3.0), Knowledge of Shift Turnover Practices Tools and Equipment:
- 1. None Task Standard: Identify abnormal configuration of Service Water Pump Bay Unit Coolers and informs CRS/SM.
Determines SWP system is inoperable. Completes Attachment 3 section 2.1 5 2005 2005 NRC RO ADMIN JPM 2 2 4/20/2005
\
Initial Condirions:
- 1. The plant is operating at 100% power.
- 2. You are the oncoming day shift CSO.
- 3. S-PM-DO01, Control Room System Lineup Verification, Attachment 3 is in progress and Section 2.15 is partially completed.
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), complete Section 2.15 of S-PM-D001, Attachment 3.
I Performance Steps I Standard I Grade I Comments
- 1. Provide repeat back of initiating 0 Proper communications used for SaWnsaI cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
- 1. Obtain a copy of the reference u S-PM-DO01 obtained, and SaVUnsaI procedure and reviewhtilize the Attachment 3 reviewed correct section.
- 2. .Recognize annunciator 871308 Recognize and report annunciator SaVUnsaI DIVISION II SW PUMP BAY 871308 DIVISION II SW PUMP BAY VENT SYSTEM INOPERABLE is VENT SYSTEM INOPERABLE is alarming alarming
- 3. .Record Attachment 3 lineup u Records lineup verifications. Checks PasslFail verifications, starting with section NO for Screenwell Bldg Vent Sys 2.1 5 Screenwell Bldg Vent Sys (Service Water Pump Bay 6)
(Service Water Pump Bay B ) ,
and evaluates.
- 4. .Recognizes A Control Switch Recognizes control switch for A PasslFail for Screenwell Building Vent Service Water Pump Bay Unit System (Service Water Pump Cooler is out of position (Switch is in Bay A) is out of position. PuII-to-loc k).
- 5. .For abnormal switch and/or o immediately reports out of position SaVUnsat indications detected which are switch to CRS.
2005 2005 NRC RO ADMIN JPM 2 3 4/20/2005
I Performar1L.e Steps I Standard I Grade Comments not expected, the Control Room Supervisor shall be immediately informed. No attempt shall be made to correct the condition u Does not attempt to correct the PasslFail prior to obtaining permission from condition prior to obtaining the Control Room Supervisor, permission from the Control Room and the expected response of Supervisor.
such actions is completely understood.
Note: If candidate only reports the abnormal condition to the CRS/SM, then ask the candidate to identify the impact of the observed condition.
6 . .Assesses impact of control References N2-OP-58 or ARP SaVUnsat switch being out of position. 871308 to determine impact on system Determines that, with both Unit PasslFail Coolers in Pull-to-Lock, Div II Service Water is inoperable
- 7. .Record Attachment 3 lineup Identifies HVC*FN2B is in PTL and PasslFail verifications, for section 2.15 not in standby.
Control Building HVAC in Service and evaluates. Records lineup verifications. Checks PasslFail NO for Control Building HVAC in Service Notes condition in REMARKS section SaVUnsat because a RED CLEARANCE is attached.
- 8. .Record Attachment 3 lineup Identifies one of two HVR*UC409s in PasslFail verifications, for section 2.1 5 Rx AUTO and the other in Pull-to-Lock.
Bldg. Vent System in Service with the standby 2HVR*UC409 in Records lineup verifications. Checks PasslFail PTL and evaluates. YES for Rx Bldg. Vent System in Service) 2005 2005 NRC RO ADMIN JPM 2 4 4/20/2005
I PedormanLe Steps I Standard I Grade I Comments
- 9. *Record Attachment 3 lineup May refer to N2-OP-61B, Standby verifications, for section 2.1 5 Gas Treatment System section F.1.3 Standby Gas Treatment System to determine required system and evaluates. configuration.
IF 2GTS*FLTl B is in standby, verify the following:
[7 At 2CEC*PNL871 verify: Sat/Unsat/NA GTS*MOVIB, INLET FROM FX !
BLDG VENTILATION closed.
GTS*AOV2B, TRAIN B INLET VALVE closed.
GTS*AOV3B, FAN 1B DISCH ISOL VLV closed.
GTS*AOV28B, DECAY HEAT X-TIE VLV open.
GTS*FNlB, SBGTS FAN stopped.
GTS*MOV4A, DECAY HEAT FILTER 1A closed.
TRAIN B INITIATION control switch in AUTO AFTER STOP.
2GTS*PDIK5B, REACTOR BLDG INLET/OUTLET DlFF PRESS controller, AUTO light lit.
2GTS*PDIKSB set at -0.6 in WG.
2005 2005 NRC RO ADMIN JPM 2 5 4/20/2005
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Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. You are the oncoming day shift CSO.
- 3. S-PM-D001, Control Room System Lineup Verification, Attachment 3 is in progress and Section 2.15 is partially completed.
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), complete Section 2.15 of S-PM-D001, Attachment 3.
2005 2005 NRC RO ADMIN JPM 2 7 4/20/2005
Attachment 2: Evaluation and Recommendation(s) (If performed in classroom)
RECORD YOUR RESULTS BELOW Name:
Evaluation:
System Impact:
2005 2005 NRC RO ADMIN JPM 2 8 4/20/2005
DO NOT PROVIDE TO THE CANDIDATE Attachment 3, EXAMINER GRADING SHEET (If performed in classroom)
RECORD YOUR RESULTS BELOW Name:
Evaluation:
Control Switch for Div. II SWP Pump Bay Unit Cooler 2HW*UC2B i s out of position Control Switches for both Division II Service Water Pump Bay Unit Coolers are in Pull-to-Lock HVC*FN2B is out of normal lineup, and RED CLEARANCE is applied. (OK, but noted in REMARKS)
HVR*UC409s are in the correct lineup.
Standby Gas Train B is in the correct lineup.
System Impact:
Both Control Switches in Pull-to-Lock renders both Unit coolers inoperable.
Division II Service water is inoperable based upon both unit coolers in an area being inoperable (N2-OP-58, Attachment 1) 2005 2005 NRC RO ADMIN JPM 2 9 4/20/2005
DO NOT PROVIDE TO THE CANDIDATE JUSTIFICATION FOR EVALUATION AND IMPACT ASSESSMENT of N2-OP-58, shown below, describes the impact of Service Water Pump Bay Unit Coolers on overall system operability.
With both unit coolers in Pull-to-Lock, the Unit Coolers are now unable to perform their design function. As such, they are declared inoperable. As seen below, in Action 1.c, with both unit coolers in an area inoperable, that division of Service Water must be declares inoperable Also N2-ARP-01 annunciator 871308 provides the following:
CAUTION Service Water Pump Bay Unit Coolers are 100% redundant. Loss of either unit cooler does not affect Service Water Pump operability. Loss of both unit coolers would result in the inoperability of Service Water Pumps in that division.
2005 2005 NRC RO ADMIN JPM 2 10 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Defeat RClClMain Turbine Trip Per EOP-6, Electrical Print Reading Revision: NRC 2005 Task Number: NA Approvals:
6 W NA Exam Security Gbd6ral SuEervisor Ddte General Supervisor Date Operations Training (Designee) Operations (Designee)
NA Exam Security Configuration Control Date Performer: (RO)
TrainedEvaluator:
Evaluation Method: Simulate Evaluation Location: Simulator or other designated location Expected Completion Time: 20 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:
2005 NRC RO ADMIN JPM 3 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated area.
Simulator Set-up:
NONE Directions to the Instructor/Evaluator:
This print reading evaluation may be performed in a sequence other than that outlined in the JPM. It is possible for a candidate to go in the reverse direction from the sequence outlined. The steps are not sequence critical.
Highlighter may be used to identify relays and contacts on drawings Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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.
0 No other verification shall be demonstrated.
References:
- 1. N2-EOP-C5 and
- 2. N2-EOP-6 Attachment 2.
- 3. GE DWG 807E173TY Sheet 2 and 9
- 4. ESK-8SPU02
- 5. ESK-11ICSO5.
- 6. 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.
Tools and Equipment:
- 1. None Task Standard:
TERMINATING CUE: Relays and contacts used to defeat RCIC/Main Turbine Trip identified on station electrical drawings and operation is explained.
2005 NRC RO ADMIN JPM 3 2 4/20/2005
(
Initial Conditions:
- 1. The plant is experiencing a Failure To Scram
- 2. N2-EOP-C5 has been entered.
- 3. Defeating the Main Turbine trip from RClC initiation is directed
- 4. A s k the operator for any questions.
Initiating cue:
"(Operator's name), Using station procedures and drawings, identify station electrical components that are used to defeat the Main Turbine trip from RClC initiation AND explain how defeating this function is accomplished."
1 Performance Steps 1 Standard I Grade I Comments I
- 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
Determines EOP-6 Attachment 2 is Sat/Unsat used to defeat RCIC/Main Turbine trip
- 2. .Refer to N2-EOP-6 Attachment Refer to EOP-6 Attachment 2 SaVUnsat 2.
Determines relay E51A-Kl02 in 2CEC*PNL613 is to be removed and PasslFail delivered to SSS.
- 3. .Using station electrical drawings Obtains drawing index and Sat/Unsat locate correct sheet containing determines GE drawings E51A-Kl02. 807E173TY use is necessary Refer to 807E173TY Sheet 2 (coordinates 8-2) Relay Table and Sat/Unsat determines relay E51A-Kl02 is on Sheet 9.
2005 NRC RO ADMIN JPM 3 3 4/20/2005
- 4. .Using station electrical [ i Refer to 807E173TY Sheet 9 and PasslFail drawings, identify relay E51A- locates relay E51A-Kl02 at K102 coordinates K-12 SatlUnsat L! Determines K102 contact M I - T I will be used on ESK-8SPU02
- 5. Using station electrical ri Refer to ESK 8SPUO2 and locates PasslFail drawings, identify relay E51A- E51A-K102 contact M I -TI at K102 contact MI-T1 in Turbine coordinates 6-2.
Trip circuit n Identifies contact M1-TI cannot close to actuate Turbine Trip circuitry when PasslFail relay E51A-KI02 is removed, preventing actuation of the turbine trip in P843 EHC Cabinet.
Evaluator Note:
It is not required for the candidate to refer to EHC drawings identified as EHC Cabinet (0007.330-002-0 17).
Explanation of operation:
When relay is pulled its contact M1-TI, which would normally close on RCIC initiation and injection MOV open after 4 minute time delay cannot close. EHC cabinet relays ESK 8SPUO2 cannot actuate to cause the Main Turbine to trip.
End of JPM TERMINATING CUE: Relays and contacts used to defeat RCICIMain Turbine Trip identified on station electrical drawings and operation is explained.
RECORD STOP TIME 2005 NRC RO ADMIN JPM 3 4 412012005
Initial Conditions:
- 1. The plant is experiencing a Failure To Scram
- 2. N2-EOP-C5 has been entered.
- 3. Defeating the Main Turbine trip from RClC initiation is directed
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), Using station procedures and drawings, identify station electrical components that are used to defeat the Main Turbine trip from RClC initiation AND explain how defeating this function is accomplished .
2005 NRC RO ADMIN JPM 3 5 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Radiological Requirements Related to Operator Inspection Revision: NRC 2005 Of High Radiation Areas Task Number: N/A Approvals:
NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)
TrainedEvaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED LOCATION Expected Completion Time: 20 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:
2005 NRC RO ADMIN JPM 4 1 04/20/05
Recommended Start Location: (Completion time based on the start location)
- Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
RWP and survey map to be provided with this JPM.
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 PassIFail. All steps are sequenced critical unless denoted by a 0 .
- 2. During Evaluated JPM:
Self-verification shall be demonstrated.
- 3. During Training J PM:
0 Self-verification shall be demonstrated.
0 No other verification 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. KIA 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 performance of high radiation area inspection are met prior to and during the performance of the inspection.
2005 NRC RO ADMIN JPM 4 2 04/20/05
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. N2-PM-M008, Monthly Checklist is scheduled for this shift.
- 3. You will be conducting an inspection of the Outer Tip Room, Reactor Bldg 250.
- 4. An RWP and survey map are provided.
- 5. Your exposure is 800 mrem TEDE at the beginning of the shift. You have inspected 3 areas already and your ED indicated 10 mrern, 15 rnrem, and 5 rnrern, respectively for the 3 areas already inspected.
- 6. Ask the operator for any questions.
Initiating cue:
(Operators name), you will be performing N2-PM-M008, Monthly Checklist, for the Outer Tip, Reactor Building 250. An RWP and a survey map are provided. Address the radiological aspects of performing this inspection. Document your findings on the SCORECARD provided I Performance Steps I Standard I Grade 1 Comments
- 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 NOTE: A score card is attached to this JPM identifying the items for the performer to identify.
- 2. *Obtain a copy of the reference N2-PM-MOO8 obtained and referenced. Sat/Unsat procedure and review/utilize the correct section.
GAP-RPP-01; 3.5 referenced as required.
GAP-RPP-02; 3.3 referenced as required GAP-RPP-08; 3.2 referenced as required GAP-RPP-07; 3.2.5 referenced as required 2005 NRC RO ADMIN JPM 4 3 04120/05
- 3. .Applicable radiological Reviews RWP/ Survey Map.
precautions shall be observed.
Rad Protection shall be - Determine radiological controls:
contacted for guidance as required SCORECARD # I :HIGH RADIATION PasslFail AREA SCORECARD #2: Area dose rates PasslFail up to 150 mrem/hour.
- Determine protective clothing:
SCORECARD #3: Although no PC PasslFail requirements are outlined on the RWP, determines PROTECTIVE CLOTHING IS REQUIRED because the area is a contaminated area and determines that RP must be consulted for guidance.
- Determine entry requirements dosimetry: SatlUnsat SCORECARD #4: Determine TLD and ED required to enter the area.
- Per GAP-RPP-08, Step 3.2.2, determine delta exposure: PasslFail SCORECARD #5: Determine required delta exposure of 300 mrem. Additional approvals ARE NOT required prior to performing the inspection.
800+10+15+5+300 = 1130 mrem (Administrative limit is 2000 mrem).
2005 NRC RO ADMIN JPM 4 4 04/20/05
I
- 4. C h e c k the Radiation/ SCORECARD #6: Notes area with PasslFail Contamination survey Map Entry highest contamination levels.
Record Sheet for the area which require inspection.
- c. .Obtain associated key(s) from SCORECARD #7: Determine H2D-13 SatlUnsat RP would not issue an X-R key if requested so not radiation protection. key is needed (indicated on survey critical.
map) and it is obtained from radiation protection.
End of JPM TERMINATING CUE: Radiological requirements related to the performance of high radiation area inspection are met prior to and during the performance of the inspection.
RECORD STOP TIME 2005 NRC RO ADMIN JPM 4 5 04/20/05
Initial Conditions:
- 1. The plant is operating at 100% power.
- 2. N2-PM-M008, Monthly Checklist is scheduled for this shift.
- 3. You will be conducting an inspection of the Outer Tip Room, Reactor Bldg 250.
- 4. A RWP and survey map are provided.
- 5. Your exposure is 800 mrem TEDE at the beginning of the shift. You have inspected 3 areas already and your ED indicated 10 mrem, 15 mrem, and 5 mrem, respectively for the 3 areas already inspected.
- 6. Ask the operator for any questions.
InitiatinQcue:
(Operators name), you will be performing N2-PM-M008, Monthly Checklist, for the Outer Tip, Reactor Building 250. An RWP and a survey map are provided. Address the radiological aspects of performing this inspection. Document your findings on the SCORECARD provided 2005 NRC RO ADMIN JPM 4 6 04/20/05
Reactor Building 250' Map No.
NMP -
Outer TIP Room For Training Only 29A Survey No. 2RB-25430 Quarterly Radiation/Contamination Survey
'. - = RopeIArea Boundary 2. @ =smear~ocation 3. A = Generalha Unkss~oted 4.
- Y P Y P30m contact
- 4 =Area Rad Monitor 1-1
- 9. = VAMP Number y = Readings in mRemlhr. = Readings in mRad/hr.
.-..,iber of Smears 9 RO-2 5769 06/02/05 t
f i BC4 438 06110105 Remarks: No beta detected BC4 230 07/03/05 SAC4 1033 04/05/05 RM-14 3009 08/01/05
3/15/2005 10:00:25AM Page 1 of 1 Radiation Work Permit: 205022 A Shift OPS HRA Standing RWP L
Survey Data:
Radiation Turbine Building HRAs c l to 45OmRemlhr / Reactor Building HRAs 4 to 400mRemlhr
~ ~ ~~
Levels: Rad Waste Buiding HRAs 4 to 400mRemlhr I Off Gas Building HRAs < toI120mRemlhr Contamination Levels: 4 0 0 - 45,000dpmll OOcm / Airborne Levels: ~0.3DAC Specific areas as per RP briefing and / or survey maps.
- Low Risk Activity **********
Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Elapsed Time Alarm 780 minutes 1433 Task: 1 High Radiation Area BAR CODE Clearances
~ ~~ ~~
Task: 2 High Radiation Area BAR CODE Cond.Demin Activities L
Task: 3 High Radiation Area BAR CODE Other Ops Activities Task: 4 High Radiation Area BAR CODE Training Activities Task: 5 High Radiation Area BAR CODE Turbine Building Rounds Task: 6 High Radiation Area BAR CODE Reactor Building Rounds Task: 7 High Radiation Area BAR CODE SurveiIIa nce's/PMs Protective Clothing Requirements (common to all tasks): Standing RWP PCs L
TLD, Electronic Dosimeter Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP.
Page 1 of 1 Radiation Work Permit: 205022 A Shift OPS HRA Standing RWP Survey Data:
Radiation Turbine Building HRAs c1 to 450mRemhr / Reactor Building HRAs 4 to 400mRemlhr Levels: Rad Waste Buiding HRAs 4 to 400mRemhr / Off Gas Building HRAs <1 to 120mRemlhr Contamination Levels: e400 - 45,000dpdl OOcm / Airborne Levels: c0.3 DAC Specific areas as per RP briefing and / or survey maps.
- Low Risk Activity -****
Dose Alarm 50 mRem Dose Rate Alarm 500 mRedHr Backoff Dose 40 mRem Elapsed Time Alarm 780 minutes 1433 PC Requirements based on areas entered If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.
\-
Instructions (common to all tasks):
- 1) Notify RP prior to venting/draining evolutions or other system breach.
- 2) No entry above arms reach unless specifically approved by RP.
ALARA Review Number:
Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP.
OK TO PROVIDE TO CANDIDATE Answer the following when performing this task:
SCORECARD #7:
0 High Radiation Area Cl Locked High Radiation Area 0Very High Radiation Area SCORECARD #2:
Designate the highest dose rate in the area and the location.
SCORECARD #:
Designate whether or not protective clothing is required (check one). 0 Yes 0 No SCORECARD #4:
Designate required dosimetry to enter the area 0Additional approval(s) required SCORECARD #6:
Designate the highest contamination levels in the room and the location SCORECARD #7:
Designate the key to be obtained AND who controls the key:
2005 NRC RO ADMIN JPM 4 7 04/20/05
NOTE: THIS IS THE EXAMINER SCORECARD.
DO NOT PROVIDE TO THE CANDIDATE.
Answer the following when performing this task:
J High Radiation Area 0 Locked High Radiation Area 0Very High Radiation Area 150 mrem/hr, Between Tip Machine D & C 0 Additional approval(s) required SCORECARD #7: SATlUNSAT Designate the key to be obtained AND who controls the key:
HZD-13 controlled by RP 2005 NRC RO ADMIN JPM 4 8 04/20/05
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Determine Required Actions for RClC Room Unit Coolers Revision: NRC 2005 Out of Service During Plant Startup Task Number: 3410320303 Approvals:
NA EXAMINATION SECURITY GMeral Supervisor Date' ' General Supervisor Date Operations Training (Designee) Operations .(Designee)
NA EXAMINATION SECURITY Configuration Control Date Performe r : (SRO)
Trainer/Evaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA 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 SRO ADMIN JPM 1 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
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 I..
- 2. During Evaluated JPM:
Self-verification shall be demonstrated.
- 3. During Training JPM:
0 Self-verification shall be demonstrated.
No other verification shall be demonstrated.
References:
- 1. N2-OP-35, Reactor Core Isolation Cooling.
- 2. N2-OP-52, Reactor Building Ventilation.
- 3. N2-OP-78, Remote Shutdown System.
- 4. Tech Spec 3.0.4 and bases
- 5. Tech Spec 3.5.3 and bases
- 6. Tech Spec 3.6.4.3 and bases
- 7. K/A 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation (4.0).
Tools and Equipment:
- 1. None.
Task Standard: Stops plant heatup prior to exceeding 150 psig Reactor Steam Dome
-- pressure per Tech Spec 3.0.4.
NRC SRO ADMIN JPM 1 2 4/20/2005
f I Initial Conditions:
- 1. Startup and Heatup is in progress following Refueling Outage.
- 2. The reactor is critical with RPV pressure at 130 psig.
- 3. Investigation into a rising RClC Room temperature determined that isolation valves SWP*V162A and B in the Service Water lines to the RClC Pump Room Unit Coolers were installed improperly restricting flow.
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the impact on Reactor Startup and Heatup. Document on the form provided.
I Performance Steps I Standard I Grade I Comments 1
- 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME Proper communications used for repeat back (GAP-OPS-01)
Sat/Unsat w
- 2. .Obtain a copy of the reference o N2-OP-52 obtainec Attachmen. 6, Sat/Unsat procedure and reviewhtilize the Table (Modes 1, 2, 3) on pages 68 correct section. & 69 referenced
- 3. .Attachment 6, Secondary o Determines that both Sat/Unsat Containment Unit Coolers for HVR*UC412A and HVR*UC412B HVR*UC412A/B. are inoperable Determines Note 3 and are Sat/Unsat applicable.
- 4. .Attachment 6, Note 3.a. and o Declares RClC inoperable. Pass/Fail 3.b. for both RClC Pump Room Unit Coolers inoperable. Declares one GTS train Pass/Fail inoperable.
- 5. .N2-OP-78 Attachment 11 for NOTE: Actual ESL entry is not HVR*UC412A. required to be perfromed for this JPM NRC SRO ADMIN JPM 1
I Standard I Grade Comments I Determines an ESL entry is Sat/Unsat required for HVR*UC412A.
- 6. .Tech Spec 3.6.4.3. Determines that Tech Spec Sat/Unsat 3.6.4.3 ACTION A. is applicable Determines that the inoperable GTS must be restored to Sat/Unsat OPERABLE status with 7 days Determines startup may continue Sat/Unsat with a Risk Assessment performed per Tech Spec 3.0.4
- 7. .Tech Spec 3.5.3. Reviews the APPLICABILITY and Sat/Unsat determines that RClC is not required until Reactor Steam Dome pressure exceeds 150 psig Cue: High Pressure Core Spray is Determines High Pressure Core Sat/Unsat OPERABLE. Spray is OPERABLE.
Determines that LCO 3.0.4.b is Sat/Unsat not applicable.
- 8. Applies Tech Spec LCO 3.0.4. Determines that heatup must be PasslFail Exceeding 150 psig constitutes entry into an stopped. LCO 3.0.4 does not "other specified condition" permit exceeding 150 psig Reactor Steam Dome pressure with RClC inoperable.
End of JPM TERMINATING CUE: Stops plant heatup prior to exceeding 150 psig Reactor Steam Dome pressure per Tech Spec 3.0.4.
RECORD STOP TIME NRC SRO ADMIN JPM 1 4 4/20/2005
KEY DO NOT PROVIDE TO CANDIDATE RECORD YOUR RESULTS BELOW Name:
Reference used to identify impact on plant operation:
Impact on Plant Operation:
.JPM SteD 4 Per N2-OP-52 Attachment 6 Note 3 a and 3 b for both RClC Pcimp Room Unit Coolers inoperable Ueclares KClC is inoperable because both RClC pump room unit coolers are inoperable (PasslFail)
JPrd Stw 4 Per N2-OP-52Attachment 6 Note 3 a and 3 b for both RCIC Pcimp Room Unit Coolers inomrable Declares :>Ytrain of GTS inoperable (PasslFail)
JPM Step 8 Applies Tech Spec LCO 3.0.4. Determines that heatup must be stopped LCO 3.0.4 does not permit exceeding 150 psig Reactor Steam Dome pressure with RClC inoperable (PasdFail)
NRC SRO ADMIN JPM 1 5 4/20/2005
OK to provide to candidate Initial Conditions:
- 1. Startup and Heatup is in progress following Refueling Outage.
- 2. The reactor is critical with RPV pressure at 130 psig.
- 3. Investigation into a rising RClC Room temperature determined that isolation valves SWP*V162A and B in the Service Water lines to the RClC Pump Room Unit Coolers were installed improperly restricting flow.
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the impact on Reactor Startup and Heatup. Document on the form provided.
NRC SRO ADMIN JPM 1 6 4/20/2005
OK to provide to candidate RECORD YOUR RESULTS BELOW Name:
Reference used to identify impact on plant operation:
Impact on Plant Operation:
NRC SRO ADMIN JPM 1 7 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Determination of Reactivity Event Severity Level and Supporting Actions Revision: NRC 2005 Task Number: 3449340503 Approvals:
NA EX, MlNATlC J SEC JRlTY Daie General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: FRO)
Trainer/Evaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 20 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 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 2 1 04/20/05
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:
To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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.
by a ".".
Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted During Evaluated JPM:
Self-verification shall be demonstrated.
- 3. During Training JPM:
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. GAP-OPS-05; 3.13
- 2. Facility License; 2.C(1) and 2.F
- 3. K/A 2.1.7 (4.4), Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
Tools and Equipment:
- 1. None Task Standard: Determine Severity Level 2 Reactivity Event occurred, because License thermal power limit was exceeded. A power reduction is required, and the event is reportable per 10CFR50.72 (24 hour) and 10CFR50.73 (30 day).
NRC SRO ADMIN JPM 2 2 04/20/05
Initial Conuitions:
- 1. The plant was returned to 100% reactor power at 06:OO this morning.
- 2. Power restoration occurred following the return of the RWCU system to service following on-line maintenance.
- 3. At 18:30, you obtain a Core Thermal Power Calculation and determine the RWCU input to the heat balance is zero (0).
- 4. At 19:00, the Reactor Engineer determines the reactor has been at 3474 MWth since returning reactor power to 1OOoh as indicated on the APRMs.
- 5. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the required administrative actions. Record the results on the grading sheet provided.
Performance Steps I Standard I Grade Comments
- 1. Provide repeat back of initiating Proper communications used for repeat back Sat/Unsat cue. Evaluator Acknowledge (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
- 2. .Obtain a copy of the reference o GAP-OPS-05 obtained. Section 3.13 Sat/Unsat procedure and reviewlutilize the referenced for event severity correct section. classification.
0 Facility LicenseiTech Specs obtained and SaUUnsat referenced for license thermal power level.
U NIP-IRG-01 obtained and referenced. Sat/Unsat
- 3. .Determine the Reactivity Event u Classifies event severity as LEVEL 2: PasslFail Severity per GAP-OP-05. Improper heat balance that results in operation outside the analysis basis.
- 4. .Notifies SM, General Supervisor u Following personnel notified: Sat/Unsat of Operations, Operations - Shift Manager Manager, and Reactor Engineer, - General Supervisor of Operations per Operations Manual, OM -Operations Manager 2.5.4.
NRC SRO ADMIN JPM 2 3 04/20/05
i I Performance Steps I Standard I Grade I Comments
- 5. .Determines DER is required. 0 Determines DER is required.
SatUnsat
- 6. .Evaluate Facility License/Tech u Determines license thermal power limit PasslFail Spec com pliance. was exceeded. This is a license condition, not in the actual TS appendix.
Note: N2-OP-101D Step F.2.0 0 Direct a reactor power reduction to less Pass/Fail requires power to be restored below than or equal to 3467 Mwth. May direct a 3467 MWth. lower power to provide margin below 3467 Mwth until heat balance is verified accurate.
- 7. .Evaluate notification per License Initial report to NRC Operations Center PasslFail Note: 30 day LER is not critical because Condition 2.F & NIP-IRG-01 via the ENS within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. this is a licensing Department function.
SRO should recognize LER is required but 0 Written followup report within 30 days per Sat/Unsat should not be required to (in this case) 10CFR50.73(b), (c) and (e). determine 30 dav LER.
- 8. .Notifies SM, General Supervisor o Following personnel notified:
of Operations, Operations - General Supervisor of Operations Manager, and Plant Manager per - Operations Manager Operations Manual Section - Plant General Manager OM.2.5.4.
End of JPM TERMINATING CUE: Determine Severity Level 2 Reactivity Event occurred, because License thermal power limit was exceeded. A power reduction is required, and the event is reportable per 10CFR50.72 (24 hour) and 10CFR50.73 (30 day).
RECORD STOP TIME NRC SRO ADMIN JPM 2 4 04/20/05
Initial Conditions:
- 1. The plant was returned to 100% reactor power at 06:OO this morning.
- 2. Power restoration occurred following the return of the RWCU system to service following on-line maintenance.
- 3. At 18:30, you obtain a Core Thermal Power Calculation and determine the RWCU input to the heat balance is zero (0).
- 4. At 19:00, the Reactor Engineer determines the reactor has been at 3474 MWth since returning reactor power to 100% as indicated on the APRMs.
- 5. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the required administrative actions. Record the results on the grading sheet provided.
NRC SRO ADMlN JPM 2 5 04/20/05
I RECORD YOUR RESULTS BELOW Name:
I Administrative Actions:
Impact on Plant Operation:
Reporting Requirements :
NRC SRO ADMIN JPM 2 6 04/20/05
DO NOT PROVIDE TO THE CANDIDATE JUSTIFICATION FOR CORRECT ANSWER REGARDING REPORTING REQUIREMENTS; Per License Conditions section 2.C(1)
(1) Maximum Power ,Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor me power levels not in excess of 3467 megawattsthermat (1 00 percent raled power) in accordance with the conditions specified herein.
Per License Conditions section 2.F F. Except as otherwise provided in h e Technical Specifications or Environmental Protection Plan, Nine Mile Point Nuclear Station, LLC shalt report any violations of the requirements contained in %tian 2.C of thrs license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System, with written followup within 30 days in accordance with the procedures described in 10 CFR 50.73@), (c), and (e).
I RECORD YOUR RESULTS BELOW 1 I Name: I Administrative Actions:
Step 3: (PasslFail) Reactivity event severity at LEVEL 2. (Improper heat balance results in operation outside the analysis basis).
Step 4: (Sat/Unsat) Notify Shift Manager, General Supervisor of Operations & Operations Manager Step 5: (Sat/Unsat) Determine DER is required.
Step 8: (Sat/Unsat) Notify Operations and Plant Management of Initial report to the NRC.
This may also be listed as a reporting requirement below Facility License/Tech Spec actions:
Step 6: (PasslFail) License thermal power limit exceeded.
Step 6: (PasslFail) Direct a reactor power reduction to less than or equal to 3467 MWth.
Reporting Requirements:
Step 7: (PasslFail) Initial report to the NRC Operations Center via the ENS within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Step 7: (Sat/Unsat) Written followup report within 30 days per 10CFR50.73(b), (c) and (e).
Step 8: See Administrative Actions above.
NRC SRO ADMIN JPM 2 7 04/20/05
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Review Operations Surveillance Procedure (OSP) Following Performance, Revision: NRC 2005 Identify and Determine Response To Abnormal Parameters Task Number:
Approvals:
-i Genxral Supervisor h date' NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)
TrainedEvaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 25 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 SRO ADMIN JPM 3 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator:
To be performed as an administrative JPM.
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:
0 Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. KIA 2.2.1 2 Knowledge of Surveillance Procedures (3.4).
- 2. K/A 2.2.24 Ability to analyze the affect of maintenance activities on LCO status (3.8).
- 3. KIA 2.2.22 Knowledge of limiting conditions for operations and safety limits (4.1)
- 4. N2-OSP-ICS-Q@002, RClC Pump and Valve Operability Test and System Integrity Test and ASME XI Functional Test.
Tools and Equipment:
- 1. Marked up copy of N2-OSP-ICS-Q@002 to be provided to the candidate for evaluation.
See Attachment 1 for faults introduced into the marked up OSP that are to be identified and evaluated by the candidate during performance of the JPM.
- 2. Copy of ASME SECTION XI should be available as usable reference for candidate.
Task Standard: Identify N2-OSP-ICS-Q@002 steps that have out of specification parameters and determine appropriate action(s) in response to the out of specification parameters.
NRC SRO ADMIN JPM 3 2 4/20/2005
Initial Conditions:
- 1. The plant is at 100% power.
- 2. N2-OSP-ICS-Q@002, RClC Pump and Valve Operability Test and System Integrity Test and ASME XI Functional Test was just completed. The System Integrity Test and ASME XI Functional Test were not required.
- 3. Ask the operator for any questions.
I Performance Steps I Standard Grade Comments
- 1. Provide repeat back of Proper communications used for Sat/Unsat
- 2. .Step I O . 1.1: Evaluate step Determines data is accurate 8.3.32 performance data. Sat/Unsat LI Check ( J ) SATISFACTORY. PasslFail I
- 3. *Step I O . 1.2.a: Evaluate step -1 Determines a calculation error is Sat/Unsat Note: Identification of calculation error is not 8.3.32 and step 8.3.33 present in the step 8.3.33 Pass/Fail since the error does not cause the performance data. calculation. evaluation to be INOP. Its a competency Sat/Unsat measurement to determine ifcalculation is checked J Determines data is within for accuracy or assumed to be correct tolerance PasslFail LI Check (J)Accept for step 10.1.2.a.
NRC SRO ADMIN JPM 3 3 4/20/2005
- 4. .Step 10.1.2.b: Evaluate -1 On Attach 2, check the following: PasslFail Attachment 2 ASME - PT I H , l V , I A , 2H - A C performance data . - PT 2V - AL
- I Check (J)Alert for step I O . 1.2.b. PasslFail J Notifies IST to initiate corrective PasslFail actions.
3 Determines RCIC pump still PasslFail operable. (Inferred from NOTES 1
& 2 of step 10.1.2.b) PasslFail LI Determines test frequency is to be doubled until evaluation is performed.
Cue: As IST acknowledge the report of the AL vibration for the PUMP ASME test.
fl
- 5. .Step 10.1.3: Evaluate o On Attach 2, check the following: PasslFail Attachment 2 MVMP (non- - PT 3H, 4H, 4V, 4A - AC ASME) performance data. - PT 3V - CO LI Check (i) Concern for step PasslFail 10.1.3.
PasslFail J Notifies IST to initiate corrective actions.
PasslFail il Determines RCIC pump still operable. PasslFail o Determines increased monitoring required.
Cue: As IST acknowledge the NRC SRO ADMIN JPM 3 4 4/20/2005
- 6. .Step 10.1.4: Evaluate valve II) Check ( J )NOT REQUIRED. Sat/Unsat test results.
- 7. .Step 10.1.5: Evaluate valve -I Evaluate section 8.2 steps. Sat/Unsat test results.
-1 Evaluate steps 8.3.7, 8.3.9, Sat/Unsat 8.3.11, 8.3.16.b. 8.3.18, 8.3.22, 8.3.32, 8.3.35. 8.3.55, 8.3.57for properly recorded data.
LI Check (i) SATISFACTORY SaVUnsat
- 8. .Step 10.1.6: Evaluate valve o Check ( J )NOT REQUIRED. Sat/Unsat test results.
- 9. .Step 10.1.7: Record results u Check (i) SATISFACTORY, PasslFail of evaluation . corrective action required.
u Document deficiencies in remarks PasslFail section:
o Note ASME vibration point PT 2V SaVUnsat in ALERT requiring doubling test frequency until an evaluation is performed.
1 Note MVMP vibration PT 3V in Sat/Unsat CONCERN requiring increased monitoring.
LI Sign and date Sat/Unsat End of JPM NRC SRO ADMIN JPM 3 5 4/20/2005
LD 0
0 cv 0
cv W
.. w u I 3 F L) n e
u, n
p!
0 0
w p!
Initial Conditions:
- 1. The plant is at 100% power.
- 2. N2-OSP-ICS-Q@002, RClC Pump and Valve Operability Test and System Integrity Test and ASME XI Functional Test was just completed. The System integrity Test and ASME XI Functional Test were not required.
- 3. Ask the operator for any questions.
Initiating cue:
(Operators name), evaluate performance data per Section 10.1, Acceptance Criteria of the provided procedure, N2-OSP-ICS-Q@002, RClC Pump and Valve Operability Test, NRC SRO ADMIN JPM 3 7 4/2 0/2005
Attachment 1 DO NOT PROVIDE TO THE CANDIDATE
-~ Following are the faults introduced into the marked up N2-OSP-ICS-Q@002, RClC Pump and Valve Operability Test, that are to be identified and evaluated by the candidate during performance of the JPM.
For step 8.3.33:
Provide an error in the calculation that maintains the PSlD within the Acceptance Range of 1175 to 1312.7 psid.
For Attachment 2:
Enter a value that places ASME PT 2V in the ALERT range (.3230)
Enter a value that places MVMP (non-ASME) PT 3V in CONCERN range (.2133)
For the remainder of the surveillance, enter actual values obtained from an archived copy of the surveillance.
NRC SRO ADMIN JPM 3 8 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Offsite Dose Calculation Manual (ODCM) Assessment Revision: NRC 2005 And Reportability for Radiological Effluent Monitoring Task Number:
Approvals:
NA EXAMINATION SECURITY Date General SuDervisor Date Operations Training (Designee) Operations '(Designee)
NA EXAMINATION SECURITY Configuration Control Date Perform er : (SRO)
Trainer/Eval uator :
Evaluation Method: PERFORM Evaluation Location: SIMULATOR OR OTHER DESIGNATED AREA Expected Completion Time: 15 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 SRO ADMIN JPM 4 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location Simulator Set-up:
N/A Directions to the Instructor/Evaluator To be performed as an administrative JPM with two parts (Part A and Part B)
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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:
0 Self-verification shall be demonstrated.
- 3. During Training JPM:
Self-verification shall be demonstrated.
0 No other verification shall be demonstrated.
References:
- 1. N2-OP-42, Offgas System.
- 2. ODCM D.3.3.2, Radioactive Gaseous Effluent Monitoring Instrumentation.
- 3. K/A 2.3.1 1, Ability to control radiation releases (3.2).
Tools and Equipment:
- 1. None Task Standard: Determines that periodic OFG effluent grab samples and analyses are required per the ODCM and the time limits for the first and second grab samples.
NRC SRO ADMIN JPM 4 2 4/20/2005
Initial Conditions:
- 1. Reactor power is 45% with power ascension in progress.
- 2. Both OFG*RE13A and OFG*RE13B were previously OPERABLE and in-service
- 3. Both OFG*13A and OFG*13B indications have just failed downscale.
- 4. Troubleshooting has not yet commenced.
- 5. Ask the operator for any questions.
Initiating cue:
(Operators name), Determine required actions.
1 Performance Steps I Standard I Grade I Comments I
- 1. Provide repeat back of initiating cue. Evaluator A ckn oWedge repeat back providing correction if necessary RECORD START TIME Proper communications used for repeat back (GAP-OPS-01)
Sat/Unsat 1
- 1. .Obtain a copy of the reference o ODCM obtained. Section D.3.3.2 and procedure and reviewhtilize the Bases B 3.3.2 are referenced.
correct section.
- 2. .Reference CONDITION B 0 Determines that the inoperable OFG Sat/Unsat Radiation Monitors must be restored to OPERABLE status within 30 days.
U Refers to Table 3.3.2-1 Sat/Unsat 0 Determines that CONDITION C is Sat/Unsat applicable NRC SRO ADMIN JPM 4 3 4/20/2005
I Performance Steps I Standard I Grade Comments
- 3. *Reference CONDITION C u Determines that tripping both Sat/Unsat channels of OFG*REI 3A and B NOTE: Candidate is NOT expected would isolate OFG requiring a scram.
to implement REQUIRED ACTION C. 1, however if implemented, must determine that OFG will isolate and a manual scram is required.
u Determines that OFG grab samples PasslFail must be taken within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
o Determines that the samples must PasslFail be analyzed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sample completion.
Cue: Acknowledge the sample requirements for OFG.
Part B NOTE: If candidate implements REQUIRED ACTION C.l instead of C.2, the JPM PART B is not applicable.
EVALUATOR: When the candidate Cue: Asked the candidate to determines the ODCM sample determine when the first and second requirements, provide the samples are due based upon a 06:OO candidate with the attached PART time for the OFG*RE13A/B B Initial Conditions and Initiating inoperabilities.
Cues Information Sheet.
NRC SRO ADMIN JPM 4 4 4/20/2005
i i
[ Performance Steps I Standard I Grade I Comments
- 1. .Obtain a copy of the applicable o Reviews ODCM Section 3.0, Sat/Unsat reference documents and review/ Applicability.
utilize the correct sections. 0 Reviews Tech Spec Section 1.3, SaVUnsat Completion Times.
- 2. .Determines that Example 1.3-1 u First sample is due by 18:OO today PasslFail applies to the first 12 Hours
- 3. .Determines that Example 1.3-6 o Second sample is due by 06:OO PasslFail 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> + a 25% extension of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> = 15 I applies to the next AND once tomorrow, with an allowable hours per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. extension of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (as late as 09:OO)
End of JPM TERMINATING CUE:
Determines that periodic OFG effluent grab samples and analyses are required per the ODCM and the time limits for the first and second grab samples.
RECORD STOP TIME NRC SRO ADMIN JPM 4 5 4/20/2005
PART A Initial Conditions:
- 1. Reactor power is 45% with power ascension in progress.
- 2. Both OFG*RE13A and OFG*RE13B indications have failed downscale.
- 3. Troubleshooting has not yet commenced.
- 4. Ask the operator for any questions.
Initiating cue:
(Operators name), Determine required actions.
NRC SRO ADMIN JPM 4 7 4/2 0/2005
PART B Initial Conditions and Initiating Cue Information Sheet Initial Conditions:
- 1. OFG*RE13A/B were declared inoperable at 06:OO today
- 2. Ask the operator for any questions.
Initiating cue:
(Operators name), determine the latest time that the first sample is due. Then based upon this time, determine the latest time the next sample can be taken.
NRC SRO ADMIN JPM 4 9 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Emergency Classification for Scenario 1 Revision: NRC 2005 Task Number: 3440190303 Approvals:
9 12,(0: NA EXAMINATION SECURITY Date General Supervisor Date 0perat ions ' f i ai ning ( Designee ) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)
TrainedEvaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR FOLLOWING SCENARIO AS SRO Expected Completion Time: 15 minutes 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:
Evaluator Signature: Date:
NRC SRO ADMlN JPM 5-1 1 4/20/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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 cuesasnecessary.
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 I concurrent verifier.
..- Notes to Instructor / Evaluator:
- 1. Critical steps are identified as PasslFail. All steps are sequenced critical unless denoted by a "*"
- 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. EPIP-EPP-02, Classification of Emergency Conditions at Unit 2.
- 2. EPMP-EPP-0102, Unit 2 Emergency Classification Bases.
- 3. EPIP-EPP-18, Activation and Direction of the Emergency Plan.
- 4. NUREG K/A 2.4.40 Knowledge of the SROs responsibilities in emergency plan implementation (4.0).
Tools and Equipment:
- 1. None.
Task Standard: Scenario properly diagnosed and classified as a Site Area Emergency NRC SRO ADMIN JPM 5-1 2 4/20/2005
Initial Conditions:
- 1. High Turbine vibration led to a reactor SCRAM and turbine trip
- 2. Control rods inserted, but all rods did not fully insert
- 4. Ask the operator for any questions Initiating Cue:
(Operators name), assume the role of the SM/ED and determine the emergency classification of this event.
1 Performance steps I Standard 1 Grade Comments
- 1. Provide repeat back of initiating cue. Proper communications used for SatlUnsat Start time is logged to determine total RECORD START TIME classification time.
- 2. .Obtain a copy of the reference o EPIP-EPP-02 obtained. Sat/Unsat procedure and reviewlutilize the Attachment 1, Section 2.2.2 is correct section. referenced.
- 3. RPS setpoint has been exceeded o Site Area Emergency is declared PasdFail The time elapsed between START TIME AND Automatic & Manual scrams per EAL 2.2.2. and determination MUST BE 4%
Suppression Pool temperature was
>11OF.
End of JPM TERMINATING CUE: Scenario properly diagnosed and classified as a Site Area Emergency.
RECORD STOP TIME NRC SRO ADMlN JPM 5-1 3 4/20/2005
Initial Conditions:
- 1. High Turbine vibration led to a reactor SCRAM and turbine trip
- 2. Control rods inserted, but all rods did not fully insert
- 4. Ask the operator for any questions Initiating Cue:
(Operators name), assume the role of the SM/ED and determine the emergency classification of this event.
NRC SRO ADMIN JPM 5-1 4 4/20/2005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE 1.-
Title:
Emergency Classification for Scenario 2 Revision: NRC 2005 Task Number: 3440190303 Approvals:
NA EXAMINATION SECURITY General Su&rvisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)
Trainer/Evaluator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR FOLLOWING SCENARIO AS SRO Expected Completion Time: 15 minutes 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:
Evaluator Signature: Date:
NRC SRO ADMIN JPM 5-2 1 412 1/2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
N/A Directions to the Instructor/Evaluator To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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 Pass/Fail. All steps are sequenced critical unless denoted by a l..
- 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. EPIP-EPP-02, Classification of Emergency Conditions at Unit 2.
- 2. EPMP-EPP-0102, Unit 2 Emergency Classification Bases.
- 3. EPIP-EPP-18, Activation and Direction of the Emergency Plan.
- 4. NUREG K/A 2.4.40 Knowledge of the SROs responsibilities in emergency plan implementation (4.0).
Tools and Equipment:
- 1. None.
Task Standard: Scenario properly diagnosed and classified as an Alert NRC SRO ADMIN JPM 5-2 2 4/2112005
Initial Conditions:
- 2. N2-EOP-C2 was performed to allow low pressure injection to recover RPV water level.
- 3. The lowest actual RPV water level during this event was -50 inches
- 4. Ask the operator for any questions Initiating Cue:
(Operators name), assume the role of the SM/ED and determine the emergency classification of this event.
- 1. Provide repeat back of initiating cue. Proper communications used for Sat/Unsat valuator Acknowledge repeat back repeat back (GAP-OPS-01 )
providing correction if necessary Start time is logged to determine total RECORD START TIME classification time.
- 2. *Obtain a copy of the reference o EPIP-EPP-02 obtained. Sat/Unsat procedure and review/utilize the Attachment 1, Section 3.1 .Iis correct section. referenced.
- 3. Primary Containment pressure has o Alert is declared per EAL 3.1.1. PasslFail The time elapsed between START TIME exceeded 1.68 psig. and determination MUST BE <15minutes to Dass the JPM.
End of JPM TERMINATING CUE: Scenario properly diagnosed and classified as a Alert.
RECORD STOP TIME NRC SRO ADMIN JPM 5-2 3 4/2112005
Initial Conditions:
- 2. N2-EOP-C2 was performed to allow low pressure injection to recover RPV water level.
- 3. The lowest actual RPV water level during this event was -50 inches
- 4. Ask the operator for any questions Initiating Cue:
(Operators name), assume the role of the SMlED and determine the emergency classification of this event.
NRC SRO ADMIN JPM 5-2 4 412 112005
Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE
Title:
Emergency Classification for Scenario 3 Revision: NRC 2005 Task Number: 3440190303 Approvals:
NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee) Operations (Designee)
NA EXAMINATION SECURITY Configuration Control Date Performer : (RO)
Tra iner/EvaIuator:
Evaluation Method: PERFORM Evaluation Location: SIMULATOR FOLLOWING SCENARIO AS SRO Expected Completion Time: 15 minutes 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:
Evaluator Signature: Date:
NRC SRO ADMIN JPM 5-3 1 4i20 '2005
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated location.
Simulator Set-up:
_. N/A Directions to the Instructor/Evaluator To be performed as an administrative JPM.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SSS, 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 PasdFail. All steps are sequenced critical unless denoted by a a.
- 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. EPIP-EPP-02, Classification of Emergency Conditions at Unit 2.
- 2. EPMP-EPP-0102, Unit 2 Emergency Classification Bases.
- 3. EPIP-EPP-18, Activation and Direction of the Emergency Plan.
- 4. NUREG K/A 2.4.40 Knowledge of the SROs responsibilities in emergency plan implementation (4.0).
Tools and Equipment:
- 1. None.
Task Standard: Scenario properly diagnosed and classified as a Site Area Emergency NRC SRO ADMIN JPM 5-3 2 4:20.:2005
Initial Conditions:
- 1. Reactor building temperatures rise to an isolation setpoint.
- 2. RClC has failed to isolate.
- 3. Reactor building temperatures and radiation levels continue to rise.
- 4. N2-EOP-SC does not yet require RPV Blowdown.
- 5. Ask the operator for any questions.
NRC SRO ADMIN JPM 5-3 3 4!20,2005
- 1. Provide repeat back of initiating cue. Proper communications used for Sat/Unsat valuator Acknowledge repeat back repeat back (GAP-OPS-01) providing correction if necessary Start time is logged to determine total RECORD START TIME classification time.
- 2. .Obtain a copy of the reference u EPIP-EPP-02 obtained. Sat/Unsat procedure and reviewhtilize the Attachment 1, Section 3.4.1 is correct section. referenced.
- 3. RCIC Steam Line isolation failure Site Area Emergency is declared AND a release pathway outside per EAL 3.4.1. and determination MUST BE <I 5minutes normal system flowpaths from an to pass the JPM.
unisolable system, exists outside primary containment.
End of JPM TERMINATING CUE: Scenario properly diagnosed and classified as a Site Area Emergency RECORD STOP TIME NRC SRO ADMIN JPM 5-3 4 412012005
Initial Conditions:
- 1. Reactor building temperatures rise to an isolation setpoint.
- 2. RClC has failed to isolate.
- 3. Reactor building temperatures and radiation levels continue to rise.
- 4. N2-EOP-SC does not yet require RPV Blowdown.
- 5. Ask the operator for any questions.
Initiating Cue:
(Operators name), assume the role of the SM/ED and determine the emergency classification of this event.