Text

Final - Section a Operating
	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)
	v • d • e

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 1. ONE Administrative JPM, OR

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: Determine Containment Water Level above the 224 foot elevation. Revision: 0 Task Number: 223-959-04-01 Lineup the Containment Monitoring system to determine Containment level above 224 feet.

Approvals:

Ope toA (Di-e G6"fietaT S~pervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date 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 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 Rtzndnrd Standard r

1. Provide repeat back of initiating cue. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeat back (GAP-OPS-O I/Operations Manual) providing correctionif necessary RECORD START TIME

2. Obtain a copy of the reference procedure and N2-EOP-6, Attachment 23 is obtained. Sat/Unsat review/utilize the correct section of the procedure.

CUE: Acting as the SSS, provide the Candidate with the copy of Attachment 23 completed up to Step 3.7.

3. Review of Attachment 23. Reviews ATTACHMENT 23, to ensure that Sat/Unsat the Steps up to Step 3.7 are complete.

4. Performs Containment Level determination. Uses the appropriate Figure 23.1 a or b to Sat/Unsat determine Containment Water Level as follows; CUE: When asked, indicated injection temperatures are approximately 72°F.

Determines with the current injection Pass/Fail temperatures that Figure 23.b is the appropriate figure for use.

NRC EXAM Administrative RO/JPM # A. 1. 1 3 APRIL 2002

Performance Steps Standard Performance Stp.tadr

" Determines appropriate AP by; Sat/Unsat "o Determining the S-D pressure.

CUE: When asked, indicate that "o "S" pressure is SUPPRESSION 2CMS*PI7A on Panel 601 is reading CHAMBER PRESSURE as 48psig. And that 2CPS-PI127 on indicated on 2CMS*PI7A on Panel Panel 873 is reading 33 psig. 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 Pass/Fail 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 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 5 APRIL 2002

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:

0 Recently Irradiated fuel is being moved in the Spent Fuel Pool 0 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 0 F.

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:

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:

0 Recently Irradiated fuel is being moved in the Spent Fuel Pool S 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?

Nine Mile Point 2 Category "A" - Examination Outline Cross ReferenrcA 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

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:

Develop a Clearance Boundary for Spent Fuel Pool Cooling Pump 2SFC*P1A Revision: 0 Task Number: 299-902-03-50 Developing Clearance Boundaries Approvals:

/ /

General Supervisor Date General Supervisor Operations Training (Designee) Date Operations (Designee)

Configuration Control /Date 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 I July 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"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. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeat back (GAP-OPS-O 1/Operations Manual) providing correctionif necessary RECORD START TIME

2. Obtain a copy of the reference procedure and GAP-OPS-02 is obtained. Sat/Unsat review/utilize the correct section of the procedure. PID-38 is referenced Sat/Unsat N2-OP-38, Attachment 4 or EE-lQ is Sat/Unsat referenced.

3. Indicate power supplies needed for " Includes 2SFC*P1A control switch in Pass/Fail Clearance boundary. pull-to-lock.

" Includes 2ENS*SWG101-5 breaker open Pass/Fail and racked-out.

4. Indicate valves needed for Clearance "* Includes 2SFC*V2 IA (pump discharge Pass/Fail boundary. isol valve) closed.

" Includes 2SFC*V13A (pump suction isol Pass/Fail valve) closed.

" Includes 2SFC*V16A (vent) AND/OR Pass/Fail 2SFC*V1 I IA (drain) open.

5. Return the Tag List Attachment 7 to the Returns Attachment 7 to the SSS. Sat/Unsat SSS.

NRC EXAM Administrative RO/JPM # A.2.1 3 July 2002

Performance Stems ,*t*nd*rd 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- 4 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.

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 5 July 2002

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 i

NRC EXAM Administrative RO/JPM # A.2.1 6 July 2002

ATTACHMENT 7: TAG LIST NRC EXAM Administrative RO/JPM # A.2.1 7 July 2002

C ( C ATTACHMENT 7: TAG LIST NRC EXAM Administrative RO/JPM # A.2.1 8 July 2002

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 68 Condensate .... Demin Valve Aisle Date Page : 7/10/2002 7 1of01

- mRem/hr general area (3 -contamination in dpm/100crrn No 0 detected unless otherwise noted.

"mRad/hrgeneral 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:

Surveyed by:0 R.Manant 100 %

Exposure: .mRemI Surveyed by: R.Mapnant Exposure: mRem H2T-7 Down 4

6 20 30 4" Resin 110 35 4" Resin Transfer Pipe 900 @ 30 cm 100 90 1.5 0.6 Instrument Inst. # Cal Due date RO-2 BC-4 BC-4 SAC-4

=ýri L,+÷r k I *IJI.Ua'.J, I - L

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?

Answer:

To isolate the leak, obtain permission from Radiation Protection and sign in on the appropriate RWP is required.

NOTE. The Candidatemay 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 requiredfor complete credit.

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:

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: Perform required CSO actions for an injured AND contaminated person. Revision: 0 Task Number: 200-921-05-01 Perform the actions required when notified of an injured and contaminated person in the plant.

Approvals:

/ /

General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

/

Configuration Control Date 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 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 Standard rn A-

1. Provide repeat back of initiating cue. Proper communications used for repeat back EvaluatorAcknowledge repeat back (GAP-OPS-O 1/Operations Manual) Sat/Unsat providing correctionif necessary RECORD START TIME

2. Obtain a copy of the reference procedure and Obtains a copy of EPIP-EPP-04.

review/utilize the correct section of the References Section 3.1 and Attachment 1. Sat/Unsat procedure.

3. Place the GAItronics in the "Merge" Mode. Places the GAItronics in the "MERGE" mode, IF USED, by placing the switch on NOTE: If the Candidate chooses to use the the Communications Console in the Control GAItronics it should be placed in Room to the "MERGE" position. Sat/Unsat/NA the "MERGE mode. Its OK if the Candidate chooses to NOT use the GAItronics, just mark this step NA.

4. Notify the Fire Brigade. Notifies the FIRE BRIGADE AND requests response via the, Pass/Fail NOTE: Any of the listed notification "* GAItronics methods is acceptable. "* Phone

"* Radio Dispatch the Fire Brigade to the scene to evaluate the situation. Pass/Fail 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."

NRC EXAM Administrative RO/JPM # A.4-1 3 APRIL 2002

Performance Steps Standard PromneSesStandard n]

5. Notify the SSS. Notifies the SSS of the reported situation. Pass/Fail 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. Contacts Radiation Protection AND request that they report to the scene of the medical emergency via, Pass/Fail NOTE: Any of the listed notification "* GAltronics methods is acceptable. "* Phone

"* Radio 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. Contacts the Medical Department AND request that they report to the scene of the medical emergency via, Pass/Fail

"* GAltronics

"* Phone CUE: As the Medical Department "* Radio Representative acknowledge the report of the situation.

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 4 APRIL 2002

Performance Steps Standard *r.rl*

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. Sat/Unsat

"* Inform the 911 Center that the person for transport IS CONTAMINATED. Pass/Fail 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. 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. SatiUnsat CUE: As the Site Security Supervisor acknowledge the request.

10. Contact the Oswego Hospital. Contacts the OSWEGO HOSPITAL.

"* Via land telephone line at 349-5522. Sat/Unsat

"* Informs them that ONE contaminated Sat/Unsat injured person will be transported to them.

"* Request that setup the RADIATION EMERGENCY AREA (REA). Pass/Fail 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 Request the SSS to contact on-call Radiation supervision and a Radiation Protection Tech Protection. Sat/Unsat report to the Oswego Hospital.

State that Radiation Protection supervision and a Tech need to report to Oswego Hospital. Sat/Unsat State that a Radiation Protection Tech will accompany the contaminated injured person in the ambulance. Sat/Unsat CUE: As the SSS, acknowledge that you will contact on-call Radiation Protection Supervisor.

NRC EXAM Administrative RO/JPM # A.4.1 5 APRIL 2002

Performance Steos Standard PromneSesStandard 'rd

12. Contact Site Security Supervisor. Direct the SITE SECURITY SUPERVISOR to contact the MANAGER, NUCLEAR COMMUNICATIONS AND PUBLIC AFFAIRS AND provide details of the incident. Sat/Unsat 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 Informs the SSS that the contaminated injured emergency. person has left the site in an ambulance and is being transported to Oswego Hospital. Sat/Unsat Indicates to the SSS that the emergency can be terminated. Sat/Unsat 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 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 7 APRIL 2002

I*I-'121 I AA 111 1. SLuM vauvI pl DCL 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 1. ONE Administrative JPM, OR

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

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 I APRIL 2002

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 2 APRIL 2002

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 Standard A

1. Provide repeat back of initiating cue. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeatback (GAP-OPS-O 1/Operations Manual) providingcorrection if necessary RECORD START TIME

2. Obtain a copy of the reference procedure and GAP-CHE-01 obtained. Sat/Unsat review/utilize the correct section of the Enclosure 2 is referenced.

procedure.

3. Determines Action Level 1 is exceeded Using the supplied Chemistry Analysis information and Enclosure 2;

"* Determines that Action Level 1 HAS been Pass/Fail exceeded under Section III.b.

"* Determines that Action Level 2 HAS Pass/Fail NOT been exceeded using the same section.

Enters Section 3.2.1 of GAP-CHE-01. Sat/Unsat

4. Performs appropriate Notifications. 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. Sat/Unsat CUE: Role playing as the SSS and all the called Managers, acknowledge the Candidate's report of the CDI Conductivity exceeding Action Level 1.

NRC EXAM Administrative JPM # A. 1.1 3 APRIL 2002

Performance Steps Stnndarcl 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 4 APRIL 2002

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*

b. Feedwater/Condensate Feedwater and CDE Conductivity (1iS/cm) @ 25°C >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*

Feedwater Total Iron (ppb) 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 @25-C e(pS/cm) >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. ** SER 89-069 and SER 90-142 (3) 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . 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 Revision: 0 and APLHGR is exceeded.

Task Number: 341-032-03-03 Evaluate Plant System's performance and coordinate appropriate actions per Technical Specifications, as required..

Approvals:

/

General Supervisor I Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control /

Date Performer: i SRO)

Performer: (

Trainer/Evaluator:

Evaluation Method: X Perform Simulate aluation 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 SRO/JPM # A.1.2 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. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeat back (GAP-OPS-O 1/Operations Manual) providingcorrection if necessary RECORD START TIME

2. Obtain a copy of the reference procedure and Obtains a copy of Technical Specifications. Sat/Unsat review/utilize the correct section of the Refers to Reactor Coolant System (RCS) procedure. Section.

U Enters T.S. - 3.4.1, Recirculation Loops Enters T.S. - 3.4.1 and determines "Single Pass/Fail Operating. 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.

NOTE: The Steps listed as c. and d. were c. LCO 3.3.1.1, Reactor Protection System accomplished by I&C in step 4.3.3.d (RPS) Instrumentation.

of N2-SOP-29. 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 CUE: As the Reactor Engineer, provide the Pass/Fail candidate with a copy of 3D Monicore determine MAPRAT is above 1.0 Periodic Log.

Determines APLHGR limit is being exceeded Pass/Fail NRC EXAM Administrative SRO/JPM # A. 1.2 3 APRIL 2002

Performance Steps Standard Grade Perfrmace SepsStanardGrade

4. Determines Technical Specification LCO Refers to T.S. 3.4.1, Condition "C" and requirements. determines;

The APLHGR must be returned to within Pass/Fail 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 Pass/Fail 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 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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NTNE MTLE PT2 -V0R TNSPRMENP REAOTUG(,S/!TATUI PAGE SPQUPENCP NO 11 2 CALTRPAT'ED LTPRM READTNGS 10-JIIL-2002 11!40 10-JIUL-2002 11:40 CATL(CIULATED PRTNTED i .3 0I.3 1.1 (G I1.I CASE 1-2 1.22I TD PMLD102071011404P R 1.1 17.0- LPRM SNAPE - FILL,,CORE 17.3 0-15.1 13.0 16.5 A 26.2 33 .2 r) 49 (-7 .34. 6 30.3 29.9 37. R 39.-4 34.5 40-4 51 .0 53.3 R 46.6 14.4 19.9 20.3 20.5 IR.0 FATLPT, SENSORS:

20.-1 2R.9 39.9 A 41.1 .W.5 LPRM ( 0 STCTNAT, FATTED) 36.2 .32.9 45.4 LPRM ( 0 PANACEA REJECTED) 41Di 40.-0 46.7 .39.5 OTHER RENSOpRS (

41.2 44.5 61.4 0 TOTAL,)

C 63 -I 52.0 55 .6 52.5 19.6 20.6 21 .R 21 -2 20. 1 21 .R SUFR RO-DS i5.1 39.3 -37. 4 42.6 43.9 17.R A 36_5 44.7 NONE 30.3 40.5 33', 4R .5 -39.5 34.5 60.4 5.3. 2 67.4 56.3 52.0 46.6 20.0 21 .2 R 21 ..£ 21 .6 21 .4 20.5 i7_3 40.1 A 317. R 42.6 37.5 43.0 41-1 34.7 45.6 4R.5 42.5 42.9 4.9 46-.7 .39. 4 61-6

63. 1 65..5 55.9 66.1 56.4 53.3 19.9 21 .0 21 .7 21 .6 21 .q 20. 3 39.9 16.5 .tR. 1 43.6 43.9 36.9 -33.2 T TTP RUN RECOMMENDED 45.4 41 -2 49.7 .17.5 42.5 = MPTLPR LOCATTON 49.-9 40-.0 .37. R (G N = MAPRA' TOCA'rTT)N C 67.5 61 .4 54.2 67.1 55.9 52.6 51 .0 17.3 20.2 0 = MFTPD ,(-CATr-ON R 20.6 21 .0 21.-2 19.9 1 3. 1 34.7 p = PCRAT TO(-CArTON A 37.4 39.9 40.-6 42.6 = M[JL'TTPLE LO,(ATTON 39.4 46.2 3R.l 4R.5 09o 40.5 45. 4 2q. 9 5.3..3 62.4 C 54.2 65.5 53-3 61 -4 40.4 17.3 19.9 A 20.0 14.4 34.7 39.9 40.1 39.6 2P - C OR K6 24 32 40 4R 56 CORE

SUMMARY

CORE POWER CATC RlIR PS,0FLW L:O(A DE 45. 4* DP MEAR T.O-A 0 FLOW 44.7 OPER SIUR FLOW PST 45.60 LTNE .53.-3* -0.9* DP CALC PST FLOW RASTS MEAS 3 2 . 9.3 PEEDWTrR FLOW MT.R!HR 61-39 APRM CALTRRATTON RPEAOiTNG 1 2 3 4 61.6 60.4 44.5 APRA 6R.3 54.904 4-956 50.527 4-R14 APRM - tC-'Pp 105.9 q .7 70.q 70.9 "TIP RUNS RECOMMENDED STRTNGS:

NONE

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 Date ý*eunerarSupervisor Date Operations Training (Designee) Operations (Designee)

Configuiaation Control Dat6 Performer: (SRO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator Expected Completion Time: 10 m e. 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.2.1 I APRIL 2002

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 covers. If opening the equipment cabinet or inspection and inspection cover will affect Tech. Spec. Operability, operational the effects are unknown, obtain specific SSS / status, or 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 direction to perform this task, I will provide you to providing with the initial conditions and answer any questions.

performance, I will identify the steps to be simulated, During task or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning devices will be simulated by discussion and acknowledged of 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 determined that a verifier is not available and Room Supervisor has 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

2. NUREG K/A General Knowledges and Abilities Valve Operability Test 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 Section 9.4. Complete Section 10.0, Acceptance through 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 Standard 0I a.

1. Provide repeat back of initiating cue. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeatback (GAP-OPS-O 1/Operations Manual) providing correction if necessary RECORD START TIME

2. Review/utilize the correct section of the Reviews General Test Methods, Sat/Unsat procedure. References/Commitments and the Precaution and Limitation Sections.

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 Review of the completed sections of N2-OSP Sat/Unsat Surveillance. DER-Q001, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.

Determines that 2DER*MOV13 1, Pass/Fail EQUIPMENT DRAIN TANK VENT OUTBOARD ISOLATION VALVE, is NOT OPERABLE, due to; CUE: As the Assistant Station Shift "* Step 8.7, stroke time, greater than Tech.

Supervisor, tell the Candidate that Spec. limit [*18 sec.].

you are entering the Tech. Specs. and "* Surveillance is UNSATISFACTORY.

will advise him on the LCO requirements.

4. Notify appropriate Plant Management. Completes Sections 10.1 and 10.2 of N2-OSP Sat/Unsat DER-QOO1, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.

Notifies MANAGER OF OPERATIONS or Sat/Unsat designee.

CUE: As the Manager of Operations acknowledge the status presented.

Sferminating Cue: 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 3 APRIL 2002

RECORD STOP TIME NRC EXAM Administrative SRO/JPM # A.2-1 4 APRIL 2002

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.

Revision: 0 Task Number: 344-906-05-03 Direct Actions required for a Radiation Emergency.

Approvals:

/

General Supervisor /

Date General Supervisor Operations Training (Designee) Date Operations (Designee)

Configuration Control /Date 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 I MAY 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 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 2 MAY 2002

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 Standard StandardA

1. Provide repeat back of initiating cue. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeat back (GAP-OPS-O l/Operations Manual) providingcorrection if necessary RECORD START TIME

1. Obtain a copy of the reference procedure and EPIP-EPP-5A is obtained and Attachment 1 Sat/Unsat review/utilize the correct section of the is referenced.

procedure.

Evaluator is to provide a blank copy of EPIP-EPP-05A, Attachment 1 to the candidate.

2. Inserts information into Attachment I of Inserts the following information into EPIP-EPP-5A. ATTACHMENT 1;

(Block 3a): "This is NOT a Drill. Pass/Fail

(Block 3b): Nine Mile Point, Unit 2 is Pass/Fail evacuating the Reactor Building (minimum acceptable area is RB 240 and 261 elevations)

(Block 3c): Due to high radiation Pass/Fail conditions (Block 3d): ALL personnel should leave Pass/Fail the Unit 2 Reactor Building (minimum acceptable area is RB 240 and 261 elevations).

NRC EXAM Administrative SRO JPM # A.3.1 3 MAY 2002

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.

(Block 3e): Should be left blank, based on CUE: (Block 3e) When asked by the the Cue Candidate, state that "ACCOUNTABILITY" is NOT being performed.

(Block 3f): Checks either block 1 or 2 NOTE: (Block 31) The Candidate may check Sat/Unsat either of these boxes as this is up to his/her opinion.

(Block 3g): Circles "is not a drill".

Sat/Unsat

6. Provide completed Attachment I to the Provides the CSO with the completed CSO. SatlUnsat ATTACHMENT 1.

Cue: When the Candidate completes ATTACHMENT 1, inform candidate that the CSO will make the announcment.

Terminating Cue: 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 4 MAY 2002

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."

NRC EXAM Administrative SRO JPM # A.3.1 5 MAY 2002

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE ritle:

r- Emergency Classification and Protective Action Recommendations (PAR'S) Revision: 0 Task Number: 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 Date Jral' Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control ate Performer: (SRO)

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 SRO JPM # A.4 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 2 MAY 2002

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. Proper communications used for repeat back Sat/Unsat EvaluatorAcknowledge repeat back (GAP-OPS-O 1/Operations Manual) providingcorrection if necessary

'--RECORD START TIME Part A

1. Obtain a copy of the reference procedure and N2-EOP-C5 is referenced and reviewed Sat/Unsat review/utilize the correct section of the against current conditions.

procedure. EPIP-EPP-02 Attachment 1 (EAL Matrix) referenced.

2. Determines and declares a "General Determines that with the provided conditions, Sat/Unsat Emergency". N2-EOP-C5 must be exited and all SAP's entered from Step L- 18 (or Step L-8).

GENERAL EMERGENCY is declared Pass/Fail based on Primary Containment Flooding IS REQUIRED (EAL GE 2.1.3 OR 2.2.3)

NRC EXAM Administrative SRO JPM # A.4 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.

Refers to EPIP-EPP-08, Step 3.1.2 to review Sat/Unsat

3. Review Part I- Notification Fact Sheet. and approve Part I- Notification Fact Sheet NOTE: If necessary, inform the candidate that Refers to EPIP-EPP-08, Attachment 1 verification of data other than Block #7 on the Uses TABLE 1.2 to determine affected Sat/Unsat notification sheet is not required. Only the ERPA's, based on wind direction of 280',

verification of PARs is required.

identified in Block #12 of the Part I.

Confirms the following ERPAs are identified Pass/Fail

4. Determines ERPAs to be evacuated and in Block #7 sheltered.

Block #7 B: EVACUATES two (2) miles around and five (5) miles downwind of

5. Confirms ERPAs identified on Part I are the following ERPA's:

correctly identified. o 1, 2,3, 4,5, 7,9, 26, 27.

AND o SHELTERS all remaining ERPA's.

6. Indicates approval of the Part I- Notification Signs"Approved By (SSS/ED or ED/RM)" Pass/Fail Fact Sheet PARs by signing the "Approved By line on the bottom of the form OR verbally (SSS/ED or ED/RM)" line on the bottom of the indicates to the Evaluator that the PARs indicated form OR for this JPM, verbally indicates to the on the sheet are correct.

Evaluator that the PARs are correct.

Terminating Cue: 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

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