ML022380336
| ML022380336 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/29/2002 |
| From: | Pisano L Constellation Nuclear |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| 05000410/02-301 05000410/02-301 | |
| Download: ML022380336 (60) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point # 2 Date of Examination:
July 29 2002 Examination Level (circle one): RO Operating Test Number:
1 Administrative Topic/Subject Describe method of evaluation:
Description
- 2. TWO Administrative Questions A. I JPM - Line up the Containment Monitoring system to determine Containment Plant Parameter water level above the 224 foot elevation.
Verification (EOP-6, Attachment 23)
K/A's 2.1.7 (3.7) 2.1.20 (4.3) 2.1.31 (4.2)
Task J223-959-04-01-2 Question 1 - Given N2-OSP-LOG-S004/5 Mode 5 Shift Checks and plant Refueling specific out of specification data, determine the required actions K/A's 2.1.23 (3.9)
Question 2 - Given plant conditions related to Offsite Power and Emergency Diesel Generator availability, determine if Shutdown Safety Criteria is met for the Power Availability Safety Function.
K/A 2.1.23 (3.9) Reference, NIP-OUT-0 1, Attachment 4 A.2 JPM - Given a completed "Clearance Request Form", blank "Clearance Sheet" Tagging and and "Tag List" and access to the appropriate reference material, develop a Clearances clearance boundary.
K/A 2.2.13 (3.6)
Task J299-902-03-50-3 A.3 Question - Given a specified survey map, identify radiological hazards.
Radiation Work Permit K/A 2.3.10 (2.9)
Question - While walking through the Plant next to a high radiation area you see a leak that can be isolated by reaching over the barrier rope and closing the valve.
What are the requirements for doing this?
K/A's 2.3.4 (2.5) 2.3.10 (2.9)
A.4 JPM - Perform the actions required when notified of an injured and Emergency contaminated person in the Plant.
Protective Action (EPIP-EPP-04)
Recommendations K/A's 2.4.12 (3.4) 2.4.39 (3.3)
Task J200-921-05-01-2 NUREG-1021, Revision 8
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE Task Nbitle:
Task Number:
Determine Containment Water Level above the 224 foot elevation.
Revision: 0 223-959-04-01 Lineup the Containment Monitoring system to determine Containment level above 224 feet.
Approvals:
Operations Training (Designee)
Configuration Control Date Ope A
to (Di-e G6"fietaT S~pervisor Operations (Designee)
Performer:
(RO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
X Plant Simulator Expected Completion Time:
10 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 EXAM Administrative RO/JPM # A. 1. 1 Date I
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
Main Control Room or other designated site.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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. N2-EOP-6, Attachment 23
- 2. NUREG K/A General Knowledges and Abilities 2.1.7 (3.7), 2.1.20 (4.3), 2.1.31...(4.2)
Tools and Equipment:
- 1. None Task Standard:
Determine Containment Water Level using N2-EOP-6, attachment 23.
NRC EXAM Administrative RO/JPM # A. 1. 1 2
APRIL 2002
Initial Conditions:
- 1. The Plant is scrammed.
- 2. Containment flooding is in progress.
- 3. Current conditions dictate that Containment Level can NOT be determined due to level being greater than the upper range of the level instrument.
- 4. N2-EOP-6, Attachment 23 has been completed up to Step 3.7.
Initiating Cues:
"(Operator's name), the SSS has directed you to complete Step 3.7 of N2-EOP-6, Attachment 23 and report current Containment Water Level."
Performance SteDs Standard r
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O I/Operations Manual)
Sat/Unsat RECORD START TIME
- 2. Obtain a copy of the reference procedure and N2-EOP-6, Attachment 23 is obtained.
review/utilize the correct section of the procedure.
Sat/Unsat CUE:
Acting as the SSS, provide the Candidate with the copy of 3 completed up to Step 3.7.
- 3. Review of Attachment 23.
- 4. Performs Containment Level determination.
Reviews ATTACHMENT 23, to ensure that the Steps up to Step 3.7 are complete.
Uses the appropriate Figure 23.1 a or b to determine Containment Water Level as follows; CUE: When asked, indicated injection temperatures are approximately 72°F.
Determines with the current injection temperatures that Figure 23.b is the appropriate figure for use.
NRC EXAM Administrative RO/JPM # A. 1. 1 Sat/Unsat Sat/Unsat Pass/Fail Rtzndnrd 3
APRIL 2002
Performance Stp.tadr CUE:
When asked, indicate that 2CMS*PI7A on Panel 601 is reading 48psig. And that 2CPS-PI127 on Panel 873 is reading 33 psig.
Determines appropriate AP by; "o Determining the S-D pressure.
"o "S" pressure is SUPPRESSION CHAMBER PRESSURE as indicated on 2CMS*PI7A on Panel 601.
"o "D" pressure is PRIMARY CONTAINMENT INLET NITROGEN PRESSURE as indicated on 2CPS-PI127 on Panel 873.
Using a AP of 15 psi and the "D" pressure from above, determines and reports that CONTAINMENT WATER LEVEL is approximately 264 feet.
CUE: As the SSS, acknowledge the Candidates report of Containment Water Level.
Terminating Cue:
A Containment Water level has been determined.
RECORD STOP TIME NRC EXAM Administrative RO/JPM # A. 1.1 Sat/Unsat Pass/Fail Performance Steps Standard 4
APRIL 2002
Initial Conditions:
- 1. The Plant is scrammed.
"v2. Containment flooding is in progress.
- 3. Current conditions dictate that Containment Level can NOT be determined due to level being greater than the upper range of the level instrument.
- 4. N2-EOP-6, Attachment 23 has been completed up to Step 3.7.
Initiating Cues:
"(Operator's name), the SSS has directed you to complete Step 3.7 of N2 EOP-6, Attachment 23 and report current Containment Water Level."
NRC EXAM Administrative RO/JPM # A. 1.1 APRIL 2002 5
Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A. 1 Subject
Description:
Fuel Handling/Shift Checks Question Number:
1 Question:
The plant is in Mode 5, with the following:
Recently Irradiated fuel is being moved in the Spent Fuel Pool You are the Reactor Operator performing Mode 5 Shift Checks.
Review the ECCS Equipment Room temperature data provided and determine the required actions, if any?
SAT UNSAT Answer:
Notify the SSS of the out of spec reading. Action must be initiated to restore Low Pressure Core Spray and RHS "A" Pump Room temperatures to at least 70OF as soon as practicable. (N2-OP-52, Precaution & Limitation D.26.0)
Explanation: N2-OSP-LOG-S004/5, Item 93, Note [ba] requires action if any EGGS Equipment Room temperature is < 70 0F.
Technical Refere nce(s):
SN2'OSP-LOG-S004/5, Item 93, Note...I
( ba], Precaution and Limitation 6.2
[N2-OP-52. Precaution & Limitation
/D.26.0 K/A#:
Importance:
2.1.23
3.9 FComments
0 0
Evaiuator is to provide candidate with marked up copy of appropriate pages of N2-OSP-LOG-S004/5.
Candidate Copy Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A. 1 Subject
Description:
Question Number:
1 Question:
The plant is in Mode 5, with the following:
Recently Irradiated fuel is being moved in the Spent Fuel Pool You are the Reactor Operator performing Mode 5 Shift Checks.
Review the ECCS Equipment Room temperature data provided and determine the required actions, if any?
0 S
Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A. 1 Subject
Description:
Fuel Handling/Shutdown Safety Question Number:
2 Question:
The plant is in Mode 5, with the following:
Line 5 is operable.
Line 6 is operable.
Division I Emergency Diesel Generator is operable.
Division II Emergency Diesel Generator is inoperable and removed from service under a Red Clearance.
THEN, A plant worker inadvertently removes the "Close" circuit control power fuses for Division I Emergency Diesel Generator Output Breaker and breaks the fuse holder.
Is the minimum Shutdown Safety Criteria being met? Justify your answer.
SAT UNSAT Answer:
wAimmum onutaown Safety Jriteria tor Power Availability is NOT being met.
Explanation: From NIP-OUT-01 Attachment 4: Power Availability, the Shutdown Safety Criteria during Mode 5 is met when available power sources = N+1 =3.
With both offsite lines available (2 sources) and no EDGs available, then the plant is below the required value of 3. Additionally, none of the available sources is an EDG.
Technical Reference(s):
NIP-OUT-01, Attachment 4 K/A #:
I.mportance:
2.1.23 3.9 Nine Mile Point 2 Category "A" - Examination Outline Cross ReferenrcA
Candidate Copy Nine Mile Point 2 Catgory "A"-Examination Outline Cross Reference=......
Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A. 1 Subject
Description:
Question Number:
2
[Question:
The plant is in Mode 5, with the following:
"* Line 5 is operable.
"* Line 6 is operable.
"* Division I Emergency Diesel Generator is operable.
"* Division II Emergency Diesel Generator is inoperable and removed from service under a Red Clearance.
"* THEN, A plant worker inadvertently removes the "Close" circuit control power fuses for Division I Emergency Diesel Generator Output Breaker and breaks the fuse holder.
Is the minimum Shutdown Safety Criteria being met? Justify your answer.
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
Title:
Task Number:
Develop a Clearance Boundary for Spent Fuel Pool Cooling Pump 2SFC*P1A Revision: 0 299-902-03-50 Developing Clearance Boundaries Approvals:
/
General Supervisor Date Operations Training (Designee)
/
Configuration Control Date
/
General Supervisor Date Operations (Designee)
Performer:
(RO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
X Plant Simulator 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 EXAM Administrative RO/JPM # A.2.1 July 2002 I
Recommended Start Location: (Completion time based on the start location)
Main Control Room or other designated site.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a"o".
- 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. GAP-OPS-02
- 2. PID-38B-10
- 3. EE-lQ
- 4. N2-OP-38
- 5. NUREG K/A General Knowledges and Abilities 2.2.13 (3.6)
Tools and Equipment:
- 1. None Task Standard:
Develop a Clearance boundary.
NRC EXAM Administrative RO/JPM # A.2.1 2
July 2002
Initial Conditions:
- 1. The Plant is operating at 100%.
- 2. Maintenance has requested a Clearance be placed on 2SFC*P1A.
- 3. The SSS has just handed you the Clearance Request Form for this job.
- 14.
2SFC*P1A is shut down and 2SFC*P1B is operating.
Initiating Cues:
- 1. Provide candidate with Attachment 5, Clearance Request Form and Blank Tag List, Attachment 7
- 2.
"(Operator's name), Develop a Clearance boundary for the requested Clearance. Indicate the appropriate boundaries, vents/drains, power supplies, and required positions for a safe clearance on a Tag List. Return the completed Tag List to the SSS for review."
Performance Steps Standard Standard rnA
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Indicate power supplies needed for Clearance boundary.
- 4. Indicate valves needed for Clearance boundary.
- 5. Return the Tag List Attachment 7 to the SSS.
GAP-OPS-02 is obtained.
PID-38 is referenced N2-OP-38, Attachment 4 or EE-lQ is referenced.
Includes 2SFC*P1A control switch in pull-to-lock.
Includes 2ENS*SWG101-5 breaker open and racked-out.
"* Includes 2SFC*V2 IA (pump discharge isol valve) closed.
Includes 2SFC*V13A (pump suction isol valve) closed.
Includes 2SFC*V16A (vent) AND/OR 2SFC*V1 I IA (drain) open.
Returns Attachment 7 to the SSS.
NRC EXAM Administrative RO/JPM # A.2.1 July 2002 Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Pass/Fail Pass/Fail Pass/Fail Sat/Unsat 3
PromneSesStaindard
%t CUE:
As the SSS acknowledge the receipt of the Tag List.
Terminating Cue:
Completed GAP-OPS-02 Tag List, Attachment 7 is returned to the SSS.
RECORD STOP TIME NRC EXAM Administrative RO/JPM # A-2.1-July 2002 Performance Stems
,*t*nd*rd 4
Initial Conditions:
- 1.
The Plant is operating at 100%.
- 2.
Maintenance has requested a Clearance be placed on 2SFC*P1A.
- 3.
The SSS has just handed you the Clearance Request Form for this job.
- 4.
2SFC*P1A is shut down and 2SFC*P1B is operating.
Initiating Cues:
- 1.
Provide candidate with Attachment 5, Clearance Request Form and Blank Tag List, Attachment 7
- 2.
"(Operator's name), Develop a Clearance boundary for the requested Clearance. Indicate the appropriate boundaries, vents/drains, power supplies, and required positions for a safe clearance on a Tag List. Return the completed Tag List to the SSS for review."
NRC EXAM Administrative RO/JPM # A-2_ 1 July 2002 5
ATTACHMENT 5: CLEARANCE REQUEST FORM CLEARANCE REQUEST FORM Unit2 Date of Request TOjDAY Type of Clearance I Danger El Operating Permit El Caution Equipment and System to be Cleared: SFC *P1A - Spent Fuel Pool Coolinq System Work Controlling Document No./Description of Work:
Clearance is required to repair the pump. This is scheduled corrective maintenance. Breach of pump pressure boundary is required. Pump must be de-coupled from the motor.
Suggested Clearance Tagging Points (Not Required):
Hazards Associated with the Work to be Performed:
Potential Adverse Effects:
Other Systems Affected:
Grounds Required:
YES El NO I Starting Time 08:00 Date TOMORROW Duration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Reference Drawings(s)
Clearance to be held by:
Jay Lawrence 1234 Name(s)
Phone(s)
Requester/Planner:
Jay Lawrence 1234 Name Phone Recommended Clearance Boundary:
Operations Review:
Name Date Clearance No.
Assigned by Initial Date NRC EXAM Administrative RO/JPM # A.2.1 July 2002 i
6
ATTACHMENT 7: TAG LIST NRC EXAM Administrative RO/JPM # A.2.1 July 2002 7
(
ATTACHMENT 7: TAG LIST NRC EXAM Administrative RO/JPM # A.2.1 8
July 2002 C
C
Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A.3 Subject
Description:
Radiation Work Permits Question Number:
1 Question:
Using the attached Survey 68 for Turbine Building 277' Condensate Demin Valve Aisle, identify the radiological posting(s) required at the entrance to the area, if any.
SAT UNSAT Answer:
- a. Contaminated Area Contaminated areas identified by dashed lines on the east side of the room with contamination levels of 24K dpm/100cm2, 3100 dpm/1OOcm2, and 420 dpm/1 OOcm2.
- b. High Radiation Area High radiation levels in the central west side of the Valve aisle near the 4" Resin Transfer Pipe with radiation levels of 11 Omr/hr and 900 mr/hr @ 30 cm.
Technical Reference(s):
S-RAP-RPP-0103, Sect. 4.0
,Importance.
2.3.10
2.9 Comments
Candidate Copy Nine Mile Point2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" Test: 1 Examination Level RO Administrative Topic A.3 Subject
Description:
Question Number:
1 Question:
Using the attached Survey 68 for Turbine Building 277' Condensate Detain Valve Aisle, identify the radiological posting(s) required at the entrance to the area, if any.
I Turbine Building 277' Survey #: 2TB-17439 Date :
7/10/2002 68 Condensate Demin Valve Aisle Page 7 1of01 mRem/hr general area (3
-contamination in dpm/100crrn No 0 detected unless otherwise noted.
"mRad/hr general area 3
-contamination on component in dpm/1 00c1 ld 30cm-dose rate @ 30cm from component location of LAW10
% of all smears >100dpm/100cm2
/cont - dose rate @ contact with component were counted for a with results <10dpm boundary 100cm 2 unless otherwise noted LRx power level:
100 Surveyed by:0 R.Manant Exposure:
.mRemI Surveyed by: R.Mapnant Exposure:
mRem Down 4" Resin 900 @ 30 cm 4
6 20 30 110 35 100 90 1.5 0.6 H2T-7 4" Resin Transfer Pipe Instrument Inst. #
Cal Due date RO-2 BC-4 BC-4 SAC-4 I
- IJI.Ua'.J, I L
=ýri L,+÷r k
Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" NRC Exam Examination Level RO Administrative Topic A.3 Subject
Description:
Radiation Work Per Question Number:
2 Question:
While performing rounds in the Reactor Building, you notice a small leak has developed on a line inside of a High Radiation area. You know you can stop the leak immediately by reaching over the radiation rope boundary and tightening the isolation valve.
What, if any, are the requirements for performing this type of activity?
SAT UNSAT Technical Reference(s):
GAP-RPP-08, Section 3.2, Rev. 8 K/A #:
Importance:
2.3.4 2.5 2.3.10
2.9 Comments
Answer:
- To isolate the leak, obtain permission from Radiation Protection and sign in on the appropriate RWP is required.
The Candidate may include in the answer, to contact the Control Room to obtain SSS permission for this activity. This is a correct answer for this question however, it is NOT required for complete credit.
NOTE.
CANDIDATE'S COPY Question:
While performing rounds in the Reactor Building, you notice a small leak has developed on a line inside of a High Radiation area. You know you can stop the leak immediately by reaching over the radiation rope boundary and tightening the isolation valve.
What, if any, are the requirements for performing this type of activity?
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE fitle:
Task Number:
Perform required CSO actions for an injured AND contaminated person.
Revision: 0 200-921-05-01 Perform the actions required when notified of an injured and contaminated person in the plant.
Approvals:
/
General Supervisor Date Operations Training (Designee)
/
Configuration Control Date General Supervisor Operations (Designee)
Performer:
(RO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
X Plant Simulator 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 EXAM Administrative RO/JPM # A.4.1
/
Date I
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
Main Control Room or other designated site.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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:
I. EPIP-EPP-04 and Attachment 1
- 2. NUREG K/A General Knowledges and Abilities 2.4.12 (3.4), 2.4.39 (3.3)
Tools and Equipment:
- 1. None Task Standard:
Under the direction of the SSS, complete Attachment 1 of EPIP-EPP-04 when notified of an injured and contaminated person in the Plant.
NRC EXAM Administrative RO/JPM # A.4.1 2
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 100%.
- 2.
You have just received a report that a Plant Mechanic has passed out in between the "B" & "C" Condensate Pumps.
- 3. The Mechanic is bleeding from the left arm and respiration is shallow.
Initiating Cues:
"(Operator's name), Perform the required actions, as the CSO."
Performance Steps Standard
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Place the GAItronics in the "Merge" Mode.
NOTE: If the Candidate chooses to use the GAItronics it should be placed in the "MERGE mode. Its OK if the Candidate chooses to NOT use the GAItronics, just mark this step NA.
Obtains a copy of EPIP-EPP-04.
References Section 3.1 and Attachment 1.
Places the GAItronics in the "MERGE" mode, IF USED, by placing the switch on the Communications Console in the Control Room to the "MERGE" position.
Sat/Unsat Sat/Unsat/NA
- 4. Notify the Fire Brigade.
NOTE: Any of the listed notification methods is acceptable.
CUE:
As the Fire Brigade Leader reply that, "the Brigade is on the way to the Condensate Pump Bay and I will report on the situation as soon as I arrive on the scene."
Notifies the FIRE BRIGADE AND requests response via the,
"* GAItronics
"* Phone
"* Radio Dispatch the Fire Brigade to the scene to evaluate the situation.
NRC EXAM Administrative RO/JPM # A.4-1 Sat/Unsat Pass/Fail Pass/Fail Standard rn A-3 APRIL 2002
PromneSesStandard n]
Notifies the SSS of the reported situation.
CUE: As the SSS, acknowledge the Candidates report.
CUE:
As the Fire Brigade Leader, request Radiation Protection and Medical Department assistance. Also requests an ambulance as the Mechanic is still unconscious.
- 6.
Contact Radiation Protection.
NOTE: Any of the listed notification methods is acceptable.
CUE:
As the Radiation Protection Tech state that, "Radiation Protection assistance is on the way to the Condensate Pump Bay and they will report on any radiation concerns as soon as they evaluate the scene."
- 7.
Contact the Medical Department.
CUE:
As the Medical Department Representative acknowledge the report of the situation.
Contacts Radiation Protection AND request that they report to the scene of the medical emergency via,
"* GAltronics
"* Phone
"* Radio Contacts the Medical Department AND request that they report to the scene of the medical emergency via,
"* GAltronics
"* Phone
"* Radio Pass/Fail Pass/Fail Pass/Fail CUE:
As the Fire Brigade Leader at the scene report to the Candidate that, "Radiation Protection Technicians have determined that the injured Mechanic IS CONTAMINATED."
Also request that an ambulance is required at this time.
NRC EXAM Administrative RO/JPM # A.4-1
- 5. Notify the SSS.
Performance Steps Standard 4
APRIL 2002
Perforance teps Sandar
- 8.
Contact Oswego County 911 Center.
Contact OSWEGO COUNTY 911 CENTER and request an ambulance be sent to the NINE MILE POINT UNIT 2 SECURITY ACCESS.
"* Via land telephone line at 343-1313.
"* Inform the 911 Center that the person for transport IS CONTAMINATED.
CUE:
As the 911 Center Operator acknowledge the request and that the person for transport is contaminated.
State that an ambulance will be on the way shortly.
- 9. Contact Site Security Supervisor.
CUE:
As the Site Security Supervisor acknowledge the request.
- 10. Contact the Oswego Hospital.
CUE:
As the Oswego Hospital Representative acknowledge the report of the situation and state that the REA will be setup.
- 11. Request that Radiation Protection supervision and a Radiation Protection Tech report to the Oswego Hospital.
CUE:
As the SSS, acknowledge that you will contact on-call Radiation Protection Supervisor.
Contacts the SITE SECURITY SUPERVISOR and request a security force member be sent to the Condensate Pump Bay AND informs them of the impending ambulance arrival.
Contacts the OSWEGO HOSPITAL.
"* Via land telephone line at 349-5522.
"* Informs them that ONE contaminated injured person will be transported to them.
"* Request that setup the RADIATION EMERGENCY AREA (REA).
Request the SSS to contact on-call Radiation Protection.
State that Radiation Protection supervision and a Tech need to report to Oswego Hospital.
State that a Radiation Protection Tech will accompany the contaminated injured person in the ambulance.
NRC EXAM Administrative RO/JPM # A.4.1 Sat/Unsat Pass/Fail SatiUnsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Performance Steps Standard
- r.rl*
5 APRIL 2002
PromneSesStandard
'rd
- 12. Contact Site Security Supervisor.
CUE:
As the Site Security Supervisor acknowledge the request.
CUE:
As the Fire Brigade Leader, inform the Candidate that the contaminated injured person has left the site and is proceeding to Oswego Hospital in the ambulance.
- 13. Inform the SSS of the termination of the emergency.
Direct the SITE SECURITY SUPERVISOR to contact the MANAGER, NUCLEAR COMMUNICATIONS AND PUBLIC AFFAIRS AND provide details of the incident.
Informs the SSS that the contaminated injured person has left the site in an ambulance and is being transported to Oswego Hospital.
Indicates to the SSS that the emergency can be terminated.
CUE: As the SSS, acknowledge the Candidates report.
Terminating Cue:
The SSS has received and acknowledged the report that indicates the contaminated injured person has left the Site in an ambulance and that the Emergency can be terminated.
RECORD STOP TIME NRC EXAM Administrative RO/JPM # A.4.1 Sat/Unsat Sat/Unsat Sat/Unsat Performance Steos Standard 6
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 100%.
- 2. You have just received a report that a Plant Mechanic has passed out in between the "B" & "C" Condensate Pumps.
- 3. The Mechanic is bleeding from the left arm and respiration is shallow.
Initiating Cues:
"(Operator's name), Perform the required actions, as the CSO."
NRC EXAM Administrative RO/JPM # A.4.1 APRIL 2002 7
111 1. SLuM vauvI DCL pl ULUume Form ES-301-1 Facility: Nine Mile Point # 2 Date of Examination:
July 29,2002 Examination Level (circle one): SRO Operating Test Number:
1 Administrative Topic/Subject Describe method of evaluation:
Description
- 2. TWO Administrative Questions A. 1 Reactor Plant JPM - Given GAP-CHE-01 BWR Water Chemistry Limits and "Action Level Startup 1" values exceeded for CDI conductivity, determine and make the appropriate Requirements notifications.
K/A 2.1.34 (2.9)
Task J341-022-03-03-2 Plant Parameter JPM - Determination of Technical Specification Actions When in Single Loop Verification Operation and APLHGR is Exceeded.
K/A 2.1.7 (4.4)
Task J341-032-03-03-2 A.2 Surveillance JPM - Given a completed surveillance test and appropriate results ensure test Testing and results comply with specifications and requirements.
K/A's 2.2.12 (3.4) 2.2.24 (3.8)
Task J341-012-01-03-2 A.3 Control of JPM - Direct Reactor Building Evacuation due to a Radiation Emergency Radiation Release K/A's 2.3.11 (3.2) 2.3.6 (3.1)
Task J344-906-05-03-2 A.4 Emergency JPM - Emergency Plan Classification And Protective Action Recommendation Classification Approval.
K/A's 2.4.29 (4.0) 2.4.41 (4.1)
NUREG-1021, Revision 8 I*I-'121 I
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
Title:
Notifications due to exceeding CDI Conductivity - Action Level I Revision: 0 Task Number:
341-022-03-03-2 Monitor Plant Chemistry Parameters to ensure conformance to requires Units.
Approvals:
General Supervisor Date
ýe 4ralutpervisor Date Operations Training (Designee)
Operations (Designee)
/,'A Elt A $-2ch/7y Configuration Control Date Performer:
(SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator iExpected Completion Time:
10 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 EXAM Administrative JPM # A. 1.1 APRIL 2002 I
Recommended Start Location: (Completion time based on the start location)
Simulator or other designated site.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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. GAP-CHE-0 1, Enclosure #2
- 2. NUREG K/A General Knowledges and Abilities 2.1.34 (2.9)
Tools and Equipment:
- 1. GAP-CHE-01, Enclosure #2 Task Standard:
Determine Action Level status and make appropriate notification(s) for a given value of CDI Conductivity.
NRC EXAM Administrative JPM # A. 1. 1 APRIL 2002 2
Initial Conditions:
- 1. The Reactor is operating at 20% power.
- 2.
You have just been handed a Chemistry Report that indicates Condensate (CDI) Conductivity (ftS/cm) @ 25°C is reading 0.246.
Initiating Cues:
"(Operator's name), determine if a Chemistry Action Level has been exceeded and if necessary, identify Station personnel that are required to be notified."
Performance Steps Standard
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 3. Determines Action Level 1 is exceeded
- 4. Performs appropriate Notifications.
CUE: Role playing as the SSS and all the called Managers, acknowledge the Candidate's report of the CDI Conductivity exceeding Action Level 1.
GAP-CHE-01 obtained. is referenced.
Using the supplied Chemistry Analysis information and Enclosure 2;
"* Determines that Action Level 1 HAS been exceeded under Section III.b.
"* Determines that Action Level 2 HAS NOT been exceeded using the same section.
Enters Section 3.2.1 of GAP-CHE-01.
Notifies the following personnel of the parameter that has exceeded ACTION LEVEL 1;
"* SSS
"* Chemistry Manager
"* Operations Manager
"* Plant Manager, AND
"* Engineering Services Branch Manager.
NRC EXAM Administrative JPM # A. 1.1 Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat APRIL 2002 Standard A
3
PromneSesStandard1 CriA~
CUE: As the SSS, tell the Candidate that troubleshooting will begin to determine the cause.
Terminating Cue:
An Action Level has been chosen and the appropriate notification for that level have been made.
RECORD STOP TIME NRC EXAM Administrative JPM # A. 1.1 APRIL 2002 Performance Steps Stnndarcl 4
Initial Conditions:
- 1. The Reactor is operating at 20% power.
-2. You have just been handed a Chemistry Report that indicates Condensate (CDI)
Conductivity (pS/cm) @ 25°C is reading 0.246.
Initiating Cues:
"(Operator's name), determine if a Chemistry Action Level has been exceeded and if necessary, identify Station personnel that are required to be notified."
NRC EXAM Administrative JPM # A. 1.1 5
APRIL 2002
FNCI O£1IRF 2-WATER CHEMISTRY GUIDELINES - UNIT 2 Operating Condition/Parameter Action Level Prior to Startup 1
2 1
Cold Shutdown (Mode 4,5)
- a. Reactor Water and Fuel Storage Pool Conductivity (gS/cm) @ 250C
>2.0"
>5.0"
>10.0(1)0
<1.0 Chloride (ppb)
>100"
>200*
>500(1)0
<100 Sulfate (ppb)
>100
<100 pH at 250C (Low)
<5.3"(1)
<4.9*
<4.6*
(High)
>8.6"(1)
>9X3
>9.6*
I.
Startup/Hot Standby (Mode 2,3)
- a.
Reactor Water Conductivity (gS/cm) @ 2500.5
>1.0
>5.0
<1.0
>2.0(1)
Chloride (ppb)
>100(1)
>200
<20 Sulfate (ppb)
>100
>200
<20 Dissolved Oxygen (ppb) above 284°F (1400C)
>300 pH @ 250C (Low)
<5.6'-')
<4.90
<4.6*
(High)
>8.6'(-)
>9.3*
>9.6*
- b.
Feedwater/Condensate Feedwater and CDE Conductivity (pS/crm) @ 250C
>0.15"*
Feedwater Suspended Corrosion Products (ppb)
>100 Condensate (CDI) Conductivity (g.S/cm) @ 250C
>0.10***(4)
>0.5"*
>1.0"*.(2)
Feedwater Dissolved Oxygen (ppb)
>200**
<200**
Ill.
Power Operation (Mode 1) (>10% Power)
Normal Water Chemistry (NWC)
HWC/NMCA
- a.
Reactor Water (>25% Power For Fuel Warranty Parameters)
Action Levels Action Levels 1
2 3
1 2
3 Conductivity (pS/cm) @ 25oC
>0.30
>1.0(1)
>5.0 0.30(6) 1.0 5.0 Chloride (ppb)
>5
>20
>100
>5
>50
>200 Sulfate (ppb)
>5
>20
>100
>5
>50
>200 pH at 250C (Low
<5.6"(1)
<4.9*
<4.6*
(High
>8.6*(')
>9.3*
>9.6*
>0.065*
>0.1"
>0.2*
Individual Condensate Demineralizer Outlet conductivity ([.S/cm) @ 25°C
>0.2--
>0.5....
Condensate (CDI) Conductivity/(gS/cm) @ 250C
>0.10
>0.5***
>1.0"*.(2)
Feedwater Total Metals (ppb) Fe,Cu,NiZn Sol and Insol
>15'
>30*
>60*
Tota
>5 (3)
>20*
>40*
(Insol)
>10' (Sol)
>1.0"
>2.0*
>4.0' Feedwater Total Copper (ppb)
>0.2((3)7)*
>2.0*
>4.0*
Feedwater and ODE Dissolved Oxygen (ppb)
(low'
<20*
<100
<5' (High'
>50*
>200*
>550*
- c.
Control Rod Drive Water Conductivity e(pS/cm)
@ 25-C
>0.15 Dissolved Oxygen(ppb)
>200 (1)
Technical Requirements Manual Actions are controlling.
Fuel Warranty Umits (2)
Limit of 10i.Slcm applies with no chemical addition 0*
After establishing condenser vacuum with steam air ejector to circulating water system.
EPRI Guidelines weekly integrated value.
RG 1.56 (4)
Limit applies during Chemical Additions (5)
During NMCA the Conductivity will intentionally exceed AL2 for over 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. No further actions are required.
(6)
Conductivity excludes contribution from Iron during and post noble metals chemical addition.
S (7)
Feedwater total copper Fuel Warranty action level 1 limit equals 0.5 ppb.
Page 10 GAP-CHE-01 Rev 06
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
.tle:
Determination of Technical Specification Actions when in Single Loop Operation and APLHGR is exceeded.
Revision: 0 Task Number:
341-032-03-03 Evaluate Plant System's performance and coordinate appropriate actions per Technical Specifications, as required..
Approvals:
/
General Supervisor Date Operations Training (Designee)
/
Configuration Control Date Performer:
(
General Supervisor Operations (Designee)
SRO)
Trainer/Evaluator:
Evaluation Method: X Perform aluation Location:
X Plant Simulate Simulator Expected Completion Time:
10 min.
Time Critical Task:
No Alternate Path Task:
No Start Time:
JPM Overall Rating:
Stop Time:
Pass Fail Completion Time:
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 EXAM Administrative SRO/JPM # A.1.2 I
Date Performer:
i I
APRIL 2002
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up (if required):
None
"-rrrections to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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. Plant Technical Specifications
- 2. NUREG K/A General Knowledges and Abilities 2.1.12(4.0)
Tools and Equipment:
- 1. 3D Monicore Periodic Log indicating MAPRAT is above 1.0 Task Standard:
Given current plant status and Thermal Limit information, determine the actions required by Technical Specifications.
NRC EXAM Administrative SRO/JPM # A. 1.2 2
APRIL 2002
Initial Conditions:
- 1. The Reactor was operating at 100% power when ONE RCS pump tripped due to an unknown cause.
- 2. N2-SOP-29 has been completed through step 4.3.3.g.
SMaintenance is investigating the cause of the RCS Pump trip.
'--initiating Cues:
"(Operator's name), determine the actions required by Technical Specification."
Performance Steps Standard Grade
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
U Enters T.S. - 3.4.1, Recirculation Loops Operating.
NOTE: The Steps listed as c. and d. were accomplished by I&C in step 4.3.3.d of N2-SOP-29.
CUE: As the Reactor Engineer, provide the candidate with a copy of 3D Monicore Periodic Log.
Obtains a copy of Technical Specifications.
Refers to Reactor Coolant System (RCS)
Section.
Enters T.S. - 3.4.1 and determines "Single Loops" operation is allowable as long as the specified LCO's are met.
- a. LCO 3.2.1, Average Planar Linear Heat Generation Rate.
- b. LCO 3.2.2, Minimum Critical Power Ratio.
- c.
LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation.
o Reset APRM Biased Thermal Power-Upscale for Single Loop.
- d.
LCO 3.3.2.1, Control Rod Block Instrumentation.
o Reset RBM - Upscale for Single Loop.
Review 3D Monicore Periodic Log and determine MAPRAT is above 1.0 Determines APLHGR limit is being exceeded NRC EXAM Administrative SRO/JPM # A. 1.2 Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Pass/Fail 3
APRIL 2002
Perfrmace SepsStanardGrade
- 4. Determines Technical Specification LCO requirements.
Refers to T.S. 3.4.1, Condition "C" and determines; The APLHGR must be returned to within its LCO limit within four (4) hours, and Refers to T.S. 3.2.1, Condition "A" and determines;
"* The APLHGR(s) must be restored to within limits within two (2) hours
"* IF Required Action A. 1 is not met, power must be below 25% RTP in four (4) hours per Required Action B. 1 CUE:
If asked as the Reactor Engineer, tell the Candidate that you are investigating Rod patterns that will lower the affected APLHGR.
Terminating Cue:
Appropriate Technical Specifications have been entered and LCO's referenced.
RECORD STOP TIME NRC EXAM Administrative SRO/JPM # A. 1.2 Pass/Fail Pass/Fail Performance Steps Standard Grade 4
APRIL 2002
Initial Conditions:
- 1. The Reactor was operating at 100% power when ONE RCS pump tripped due to an unknown cause.
- 2. N2-SOP-29 has been completed through step 4.3.3.g.
- 3. Maintenance is investigating the cause of the RCS Pump trip.
Initiating Cues:
"(Operator's name), determine the actions required by Technical Specification."
NRC EXAM Administrative SRO/JPM # A. 1.2 5
APRIL 2002
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- FATLPT, SENSORS:
(
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(
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(
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NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE
"--Title:
Review and Approval of Completed Surveillance Test N2-OSP-DER-QOO, Revision: 0 Drywell Equipment Drains Valve Operability Test.
Task Number:
341-012-01-03-2 Review surveillance test results to ensure compliance with specifications.
Approvals:
General Supervisor Operations Training (Designee)
Date
ý*eunerarSupervisor Operations (Designee)
Configuiaation Control Dat6 Performer:
Trainer/Evaluator:
Evaluation Method: X Perform Evaluation Location:
Plant Simulate X
Simulator Expected Completion Time:
Start Time:
10 m e.
Time Critical Task:
Stop Time:______
No Alternate Path Task:
No 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 EXAM Administrative SRO/JPM # A.2.1 APRIL 2002 Date (SRO)
I
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by aC")
- 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. N2-OSP-DER-Q001, Drywell Equipment Drains Valve Operability Test
- 2. NUREG K/A General Knowledges and Abilities 2.2.12 (3.4), 2.2.24 (3.8)
Tools and Equipment:
I. Copy ofN2-OSP-DER-Q00o, Drywell Equipment Drains Valve Operability Test, completed through Step 9.4.
Task Standard:
Given a copy of N2-OSP-DER-QOO1, Drywell Equipment Drains Valve Operability Test, completed through Section 9.4. Complete Section 10.0, Acceptance Criteria and determine if the valves meet the proper specifications.
NRC EXAM Administrative SRO/JPM # A.2.1 2
APRIL 2002
Initial Conditions:
- 1. The Plant is operating at 100% power.
- 2. N2-OSP-DER-Q0O1, Drywell Equipment Drains Valve Operability Test, has just been completed through Section 9.4.
Initiating Cues:
"(Operator's name), this is a copy ofN2-OSP-DER-Q001, Drywell Equipment Drains Valve Operability Test, just completed through Section 9.4, as the Station Shift Supervisor, review the test results and complete Sections 10.1 and 10.2."
Performance Steps Standard I
0 a.
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
RECORD START TIME
- 2.
Review/utilize the correct section of the procedure.
Evaluator is to provide the marked up copy of N2-OSP-DER-Q001, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST, to the candidate.
- 3. Determines Status of the completed Surveillance.
CUE: As the Assistant Station Shift Supervisor, tell the Candidate that you are entering the Tech. Specs. and will advise him on the LCO requirements.
- 4. Notify appropriate Plant Management.
CUE: As the Manager of Operations acknowledge the status presented.
Sferminating Cue:
Reviews General Test Methods, References/Commitments and the Precaution and Limitation Sections.
Review of the completed sections of N2-OSP DER-Q001, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.
Determines that 2DER*MOV13 1, EQUIPMENT DRAIN TANK VENT OUTBOARD ISOLATION VALVE, is NOT OPERABLE, due to;
"* Step 8.7, stroke time, greater than Tech.
Spec. limit [*18 sec.].
"* Surveillance is UNSATISFACTORY.
Completes Sections 10.1 and 10.2 of N2-OSP DER-QOO1, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.
Notifies MANAGER OF OPERATIONS or designee.
Determination of the status of this surveillance has been made and the proper notifications have been performed.
NRC EXAM Administrative SRO/JPM # A.2.1 APRIL 2002 Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Standard 3
RECORD STOP TIME NRC EXAM Administrative SRO/JPM # A.2-1 APRIL 2002 4
Initial Conditions:
- -1. The Plant is operating at 100% power.
- 2. N2-OSP-DER-QOO 1, Drywell Equipment Drains Valve Operability Test, has just been completed through Section 9.4.
Initiating Cues:
"(Operator's name), this is a copy of N2-OSP-DER-QOO1, Drywell Equipment Drains Valve Operability Test, just completed through Section 9.4, as the Station Shift Supervisor, review the test results and complete Sections 10.1 and 10.2."
NRC EXAM Administrative SRO/JPM # A.2.1 5
APRIL 2002
NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE SFitle:
Direct Reactor Building Evacuation due to a Radiation Emergency.
Task Number:
344-906-05-03 Direct Actions required for a Radiation Emergency.
Approvals:
/
General Supervisor Date Operations Training (Designee)
/
Configuration Control Date Revision: 0
/
General Supervisor Date Operations (Designee)
Performer:
(SRO)
Trainer/Evaluator:
Evaluation Method: X Perform Simulate Evaluation Location:
Plant X
Simulator
-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 EXAM Administrative SRO JPM # A.3. I MAY 2002 I
Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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-5A and Attachment 1
- 2. NUREG K/A General Knowledges and Abilities 2.3.10(3.3),
2.4.29(4.0) 2.4.38(4.0)
Tools and Equipment:
- 1. None Task Standard:
Given a set of Plant conditions, direct actions to evacuate a local area without an Emergency Classification being declared.
NRC EXAM Administrative SRO JPM # A.3.1 MAY 2002 2
Initial Conditions:
The Reactor is operating at 100% power.
It is Day Shift on a Tuesday morning and normal work is being carried out in the Reactor Building.
I&C is working in the TIP Room.
A problem with one of the TIP probes has caused a high radiation condition in that area Several area Rad Monitors on Reactor Building 240 and 261 are alarming.
Current radiation readings in the TIP Room area are 600 mr/hr.
NO emergency has been declared.
Initiating Cues:
"(Operator's name), Take necessary action to ensure safety of plant personnel."
Performance Steps StandardA
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O l/Operations Manual)
RECORD START TIME
- 1. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
Evaluator is to provide a blank copy of EPIP-EPP-05A, Attachment 1 to the candidate.
- 2.
Inserts information into Attachment I of EPIP-EPP-5A.
EPIP-EPP-5A is obtained and Attachment 1 is referenced.
Inserts the following information into ATTACHMENT 1; (Block 3a): "This is NOT a Drill.
(Block 3b): Nine Mile Point, Unit 2 is evacuating the Reactor Building (minimum acceptable area is RB 240 and 261 elevations)
(Block 3c): Due to high radiation conditions (Block 3d): ALL personnel should leave the Unit 2 Reactor Building (minimum acceptable area is RB 240 and 261 elevations).
NRC EXAM Administrative SRO JPM # A.3.1 MAY 2002 Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Pass/Fail Pass/Fail Standard 3
Performance Steps Standard Grade
"* Personnel should NOT leave the Sat/Unsat area via any North or West accesses.
"* Staying clear of the TIP Room.
Pass/Fail
"* Personnel should report to their normal work locations.
CUE:
(Block 3e) When asked by the Candidate, state that "ACCOUNTABILITY" is NOT being performed.
(Block 3e): Should be left blank, based on the Cue (Block 3f): Checks either block 1 or 2 NOTE:
(Block 31) The Candidate may check either of these boxes as this is up to his/her opinion.
(Block 3g): Circles "is not a drill".
Sat/Unsat Sat/Unsat
- 6. Provide completed Attachment I to the CSO.
Cue:
When the Candidate completes ATTACHMENT 1, inform candidate that the CSO will make the announcment.
Terminating Cue:
Provides the CSO with the completed ATTACHMENT 1.
SatlUnsat When the Candidate has completed Attachment 1 and given it to the CSO for announcement.
RECORD STOP TIME NRC EXAM Administrative SRO JPM # A.3. I MAY 2002 4
Initial Conditions:
- The Reactor is operating at 100% power.
- It is Day Shift on a Tuesday morning and normal work is being carried out in the Reactor Building.
- A problem with one of the TIP probes has caused a high radiation condition in that area
- Several area Rad Monitors on Reactor Building 240 and 261 are alarming.
- Current radiation readings in the TIP Room area are 600 mr/hr.
- NO emergency has been declared.
Initiating Cues:
"(Operator's name), Take necessary action to ensure safety of plant personnel."
NRC EXAM Administrative SRO JPM # A.3.1 5
MAY 2002
NINE MILE POINT NUCLEAR STATION r-ritle:
Task Number:
OPERATOR JOB PERFORMANCE MEASURE Emergency Classification and Protective Action Recommendations (PAR'S)
Revision: 0 344-019-03-03 Classify Emergency Events requiring Emergency Plan Implementation.
344-902-05-03 Make Protective Action Recommendations as necessary per EPP's.
Approvals:
General Supervisor Operations Training (Designee)
D ate Jral' Supervisor Operations (Designee)
Configuration Control ate Performer:
Trainer/Evaluator:
Evaluation Method: X Perform Evaluation Location:
X Plant Simulate Simulator Expected Completion Time:
15 min.
Time Critical Task:
No Alternate Path Task:
No Start Time:
JPM Overall Rating:
Stop Time:
Pass Completion Time:
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 EXAM Administrative SRO JPM # A.4 Date (SRO)
I MAY 2002
Recommended Start Location: (Completion time based on the start location)
Main Control Room or any other appropriate location with the proper references.
Simulator Set-up (if required):
None.
Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SSS / 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 SSS / CSO permission.
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.
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 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 independent/peer verifier.
Notes to Instructor / Evaluator:
- 1. Critical steps are identified in grading areas as Pass/Fail. 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. EPIP-EPP-18, Activation and Direction of Emergency Plans
- 3. EPIP-EPP-08, Off-Site Dose Assessment and Protective Action Recommendation
- 4. Unit 2 EOP Flow Charts, N2-EOP-C2, N2-EOP-C5, and N2-EOP-PC
- 5. NUREG 1123, 2.4.16(4.0),
2.4.29(4.0),
2.4.40(4.0),
2.4.41(4.1),
2.4.44(4.0)
Tools and Equipment:
- 1. N2-EOP Flowcharts, EAL Matrix and marked up copy of Part I Notification Fact Sheet Task Standard:
Given a set of Plant conditions, classify the Emergency and make Protective Action Recommendations (PAR's)
"as required.
NRC EXAM Administrative SRO JPM # A.4 MAY 2002 2
Initial Conditions:
0 A LOCA is in progress, Drywell pressure is 10 psig rising slowly and N2-EOP-PC has been entered.
- Not all Control Rods were fully inserted on the Scram, N2-EOP-C5, Failure to Scram, has been entered.
All attempts to insert the Control Rods have failed to this point.
Indicated Reactor Vessel Water level was -85 inches and remaining fairly constant.
Reactor Power is 12% as indicated on SPDS.
N2-EOP-C2, RPV Blowdown, has been entered.
All 7 ADS Valves are open Reactor Pressure is 100 psig and lowering slowly.
Indicated Reactor Vessel Water level is -90 inches and slowly lowering, following the blowdown.
- ALL available "Preferred ATWS Injection Systems" and "Alternate ATWS Injections Systems" are injecting into the Reactor Vessel.
Initiating Cues:
"(Operator's name), using the Emergency Operating Procedures (EOP's) and Emergency Action Level Matrix, determine the required Emergency Classification for this event."
Performance SteDs Starndzrd Standard1 I a
- 1. Provide repeat back of initiating cue.
Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O 1/Operations Manual)
- '--RECORD START TIME Part A
- 1. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
- 2.
Determines and declares a "General Emergency".
N2-EOP-C5 is referenced and reviewed against current conditions.
EPIP-EPP-02 Attachment 1 (EAL Matrix) referenced.
Determines that with the provided conditions, N2-EOP-C5 must be exited and all SAP's entered from Step L-18 (or Step L-8).
GENERAL EMERGENCY is declared based on Primary Containment Flooding IS REQUIRED (EAL GE 2.1.3 OR 2.2.3)
NRC EXAM Administrative SRO JPM # A.4 Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail 3
MAY 2002
Performance Steps Standard Grade Part B NOTE: If the candidate declares an event below Sthe General Emergency level, the critical step is unsatisfactory. The JPM shall be stopped.
EVALUATOR: When the candidate declares a General Emergency, provide the candidate with attached Part B Initial Conditions and Initiating Cue Information Sheet.
Cue: As the Control Room Communicator, provide the candidate with the attached Part I-Notification Fact Sheet for SSS/ED review.
- 3. Review Part I-Notification Fact Sheet.
NOTE: If necessary, inform the candidate that verification of data other than Block #7 on the notification sheet is not required. Only the verification of PARs is required.
- 4. Determines ERPAs to be evacuated and sheltered.
- 5. Confirms ERPAs identified on Part I are correctly identified.
- 6. Indicates approval of the Part I-Notification Fact Sheet PARs by signing the "Approved By (SSS/ED or ED/RM)" line on the bottom of the form OR for this JPM, verbally indicates to the Evaluator that the PARs are correct.
Terminating Cue:
Refers to EPIP-EPP-08, Step 3.1.2 to review and approve Part I-Notification Fact Sheet Refers to EPIP-EPP-08, Attachment 1 Uses TABLE 1.2 to determine affected ERPA's, based on wind direction of 280',
identified in Block #12 of the Part I.
Confirms the following ERPAs are identified in Block #7 Block #7 B: EVACUATES two (2) miles around and five (5) miles downwind of the following ERPA's:
o 1, 2,3, 4,5, 7,9, 26, 27.
AND o
SHELTERS all remaining ERPA's.
Signs"Approved By (SSS/ED or ED/RM)"
line on the bottom of the form OR verbally indicates to the Evaluator that the PARs indicated on the sheet are correct.
Sat/Unsat Sat/Unsat Pass/Fail Pass/Fail Determination of an Event Classification and Protective Action Recommendations (PAR's) for the given situation.
RECORD STOP TIME NRC EXAM Administrative SRO JPM # A.4 4
MAY 2002
Part A Initial Conditions:
"* A LOCA is in progress, Drywell pressure is 10 psig rising slowly and N2-EOP PC has been entered.
"* Not all Control Rods were fully inserted on the Scram, N2-EOP-C5, Failure to Scram, has been entered.
"* All attempts to insert the Control Rods have failed to this point.
"* Indicated Reactor Vessel Water level was -85 inches and remaining fairly constant.
"* Reactor Power is 12% as indicated on SPDS.
"* N2-EOP-C2, RPV Blowdown, has been entered.
"* All 7 ADS Valves are open
"* Reactor Pressure is 100 psig and lowering slowly.
"* Indicated Reactor Vessel Water level is -90 inches and slowly lowering, following the blowdown.
"* ALL available "Preferred ATWS Injection Systems" and "Alternate ATWS Injections Systems" are injecting into the Reactor Vessel.
Initiating Cues:
"(Operator's name), using the Emergency Operating Procedures (EOP's) and Emergency Action Level Matrix, determine the required Emergency Classification for this event."
NRC EXAM Administrative SRO JPM # A.4 5
MAY 2002
Part B Initial Conditions and Initiating Cue Information Sheet "Initial Conditions:
- 1.
A General Emergency has been declared, based on the previous plant conditions
- 2.
You have assumed the role as SSS/ED in the Control Room.
Initiating Cue:
"(Operator's Name), Prior to transmitting the Part I-Notification Fact Sheet to offsite agencies, review and approve the Protective Action Recommendations that are identified on the Part I-Notification Fact Sheet, that has been provided to you by the Control Room Communicator".
NRC EXAM Administrative SRO JPM # A.4 6
MAY 2002