ML022400078

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Draft - Section a Operating
ML022400078
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 07/29/2002
From: Pisano L
Constellation Nuclear
To: Caruso J, Miller H
NRC/RGN-I/DRS/OSB
Conte R
References
50-410/02301, NMP-97924 50-410/02301
Download: ML022400078 (60)


Text

RO. Box 63 Lycoming, New York 13093 Constellation NMP-97924 Nuclear Nine Mile Point Nuclear Station A Member of the Constellation Energy Group Mr. Hubert J. Miller Regional Administrator USNRC Region I 475 Allendale Road King of Prussia, PA 19406 ATTENTION: Mr. John Caruso

SUBJECT:

NINE MILE POINT UNIT 2 INITIAL OPERATOR EXAMINATION SUBMITTAL Mr. Miller:

In response to the NRC Corporate Notification Letter dated April 1, 2002, arrangements were made for the administration of licensing examinations at Nine Mile Point, Unit 2 during the week of July 29, 2002.

The examinations are being prepared based on the guidelines in Revision 8, Supplement 1, of NUREG 1021, "Operator Licensing Examination Standards for Power Reactors." To meet the examination schedule, Nine Mile Point Nuclear Station is required to furnish the examinations by June 7, 2002.

Enclosed are the examination materials for the Reactor Operator and Senior Reactor Operator operating tests and associated quality checklists. The written examination materials will be provided in a separate mailing to be received no later than June 11, 2002.

Please withhold these examination materials from public disclosure until after the examinations have been completed.

If you have any questions regarding the submittal, please contact me at (315) 349-2073 or Mr. Jerry Bobka at (315) 349-2569.

Sincerely, fr-Louis E. Pisano M

Manager Nuclear Training LEP/crr

Jim-, -J,.4 /

-UAm " 17* /

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.1 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 JPM - Perform A thfuel loor Evacuation During A Refel Floor Event.

Fuel Handling (SOP-39, EPIP-21,

-5A, EPIP-18)

K/A's 2A.4

.0) 2.1.7 (3.7)

Task 120 -016-05-01-2 A.2 JPM - Given a completed "Clearance Reqluest 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)

Szeem ly~

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 ritle:

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:

(2z c i~

General Suprvisor Da ek Operations Training (Designee)

Configuration Control Date O

aptis(ervisor Operations (Designee)

Date Performer:

(RO)

Trainer/Evaluator:-

Evaluation Method: X Perform Simulate E~valuation 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. I 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"e".
2. During Evaluated JPM:

a 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. I 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 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)

SatlUnsat 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; Sat/Unsat Sat/Unsat CUE: When asked, indicated injection temperatures are approximately 720F.

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

Pass/Fail NRC EXAM Administrative RO/JPM # A. 1. I 3

APRIL 2002

Pprfnrm nnne '.ti-nq Standard Grade Prfcrnnre

St.n'

Standard Grade 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-P1127 on Panel 873.

Sat/Unsat Using a AP of 15 psi and the "D" pressure from above, determines and reports that CONTAINMENT WATER LEVEL is approximately 264 feet.

Pass/Fail 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.
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."

NRC EXAM Administrative RO/JPM # A. 1.. I 5

APRIL 2002

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE ritle:

Perform A Refuel Floor Evacuation During A Refuel Floor Event Revision: 0 Task Number:

200-016-05-01-2 -Perform the actions required for an Inadvertent Criticality during Fuel loading.

Approvals:

/

1,,

0g/$

General Supervisor Date ee al pervisor Da e Operations Training (Designee)

Operations (Designee)

A//

A 6gAas tio/Cotro Configuration Control Date' Performer:

(RO)

Trainer/Evaluator:_

Evaluation Method: X Perform Simulate Evaluation Location:

X Plant Simulator xpected 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.1.2 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. EPIP-EPP-05A and Attachment I
2. NUREG K/A General Knowledges and Abilities 2.4.4 (4.0), 2.1.7 (3.7)

Tools and Equipment:

1. None Task Standard:

Perform the administrative actions of the CSO for an inadvertent criticality during refueling operations.

NRC EXAM Administrative RO/JPM # A. 1.2 2

APRIL 2002

initial Conditions:

1. The Plant is shutdown, refueling in progress.
2.

The following indication of an inadvertent criticality have just been received; I I..-

a.

Rising SRM count rate with a positive stable period.

b. Annunciator 603209, SRM SHORT PERIOD.
3. Actions of N2-SOP-39, Section 4.4 have been completed.
4. The SSS has directed an evacuation of the Refueling Floor, but has not declared an Emergency Classification.

Initiating Cues:

"(Operator's name), using EPIP-EPP-05A and Attachment I of the same procedure, perform the steps required for an evacuation of the Refueling Floor as the CSO."

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)

Sat/Unsat RECORD START TIME

2. Obtain a copy of the reference procedure and EPIP-EPP-05A is obtained and reviewed.

review/utilize the correct section of the procedure.

Sat/Unsat CUE:

Acting as the SSS, provide the Candidate with the completed copy of Attachment 1.

3.

Review of Attachment 1.

4. Performs Evacuation announcement.

Reviews ATTACHMENT 1, to ensure appropriate boxes have been checked so that a coherent evacuation announcement can be made.

Places GAItronics in MERGE.

Sat/Unsat Pass/Fail Sounds the EVACUATION alarm for about TEN (10) SECONDS.

Sat/Unsat NRC EXAM Administrative RO/JPM # A. 1.2 3

APRIL 2002

Performance Steps Standard Grade Performance Steps Standard Grade Announces the following; Pass/Fail "This is NOT a drill" "NMP Unit 2 is ordering an evacuation of the Unit 2 Refueling Floor."

"Due to an inadvertent criticality."

"All personnel are to leave the Unit 2 Refueling Floor using the closest exit and report to their work centers."

"Personnel in protective clothing should leave the area immediately and obtain RP assistance at the Control Point."

"Repeat, this is NOT a drill."

Repeat the alarm and announcement.

Sat/Unsat Consult with the opposite Unit SSS and determine if the GAItronics should be left in Sat/Unsat MERGE.

CUE: As the Unit 1 SSS, tell the Candidate that the GAItronics should NOT be left in MERGE at this time.

Terminating Cue:

Evacuation announcement has been made and the GAItronics is no longer in MERGE.

RECORD STOP TIME NRC EXAM Administrative RO/JPM # A. 1.2 4

APRIL 2002

Initial Conditions:

1. The Plant is shutdown, refueling in progress.
2. The following indication of an inadvertent criticality have just been received;
a. Rising SRM count rate with a positive stable period.
b. Annunciator 603209, SRM SHORT PERIOD.
3. Actions of N2-SOP-39, Section 4.4 have been completed.
4. The SSS has directed an evacuation of the Refueling Floor, but has not declared an Emergency Classification.

Initiating Cues:

"(Operator's name), using EPIP-EPP-05A and Attachment 1 of the same procedure, perform the steps required for an evacuation of the Refueling Floor as the CSO."

NRC EXAM Administrative RO/JPM # A. 1.2 5s APRIL 2002

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE 7-fitle:

Task Number:

Develop a Clearance boundary for the Hot Water Heating Pump, 2HVH-P1A. Revision: 0 299-902-03-50 Developing Clearance Boundaries Approvals:

/

4/

General Supervisor Date Operations Training (Designee) n i

Cnr D5'i; 6

a te

(

Configuration Control Date' Op4~ervisor Operations (Designee)

Date Performer:

(RO)

Trainer/Evaluator:_

Evaluation Method: X Perform Simulate Evaluation Location:

X Plant Simulator e..xpected 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:

,t Evaluators Signature:

A NRC EXAM Administrative RO/JPM # A.2.1 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. GAP-OPS-02
2.

PID-49A-13

3.

EE-1 CZ

4. NUREG K/A General Knowledges and Abilities 2.2.13 (3.6)

Tools and Equipment:

1. None Task Standard:

Using the supplied prints develop a Clearance boundary.

NRC EXAM Administrative RO/JPM # A.2. 1 2

APRIL 2002

Initial Conditions:

1. The Plant is operating at 100% Power.
2. Maintenance has requested a Clearance be placed on the Hot Water Heating Pump, 2HVH-PIA.
3. The SSS has just handed you the Clearance Request Form for this job.

Initiating Cues:

"(Operator's name), using GAP-OPS-02 and the supplied prints, develop a Clearance boundary for the requested Clearance. Indicate the appropriate boundaries, vents/drains, and power supplies required for a safe clearance by circling or highlighting on the supplied prints. Return the marked up prints to the SSS for review."

Performance Stens 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 I /Operations Manual)

Sat/Unsat RECORD START TIME

2.

Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.

GAP-OPS-02 is obtained.

PID-49A-13 is referenced.

Sat/Unsat Sat/Unsat EE-ICZ or N2-OP-49, Attachment 4 is referenced.

Sat/Unsat

3.

Indicate valves needed for Clearance boundary.

NOTE: Per GAP-OPS-02 only one of these valves is required for a Clearance Boundary. However, the Candidate may choose a combination or all three of these valves for a vent and/or drain path.

Indicates ALL valves required to establish a clearance boundary, by circling or highlighting on PID-49A-13, the following valves; 2-HVH-V51, Pump IA discharge isolation valve.

2-HVH-V50, Pump IA suction isolation valve.

2-HVH-V42, Pump IA discharge line vent valve, OR, 2-HVH-V185, Pump IA casing drain valve, OR, 2-HVH-V35, Strainer IA drain valve.

Pass/Fail Pass/Fail Pass/Fail NRC EXAM Administrative RO/JPM # A.2.1 3

APRIL 2002

Performance Steps Standard C'IrnAe Performance Steps Standard (rarlp

4. Indicate Power Supplies needed for Clearance boundary.

NOTE:

Although GAP-OPS-02 also requires the Pump control switch to be tagged for a Clearance Boundary in which a control switch is available, it is NOT required for this JPM.

5. Return marked up prints to the SSS.

Indicates ALL Power Supplies required to establish a clearance boundary, by circling or highlighting on EE-1CZ, the following breaker; 2NJS-US10-5D, Power to HVH-P1A.

Returns the marked up prints to the SSS.

Pass/Fail Sat/Unsat CUE:

As the SSS acknowledge the receipt of the marked up prints.

Terminating Cue:

Supplied prints are marked up and returned to the SSS.

RECORD STOP TIME NRC EXAM Administrative RO/JPM # A.2. 1 4

APRIL 2002

Initial Conditions:

1. The Plant is operating at 100% Power.

'2. Maintenance has requested a Clearance be placed on the Hot Water Heating Pump, 2HVH-P1A.

3. The SSS has just handed you the Clearance Request Form for this job.

Initiating Cues:

"(Operator's name), using GAP-OPS-02 and the supplied prints, develop a Clearance boundary for the requested Clearance. Indicate the appropriate boundaries, vents/drains, and power supplies required for a safe clearance by circling or highlighting on the supplied prints. Return the marked up prints to the SSS for review."

NRC EXAM Administrative RO/JPM # A.2. 1 5s APRIL 2002

Al tACMlLNT:. OL4ANCLL LOQLSTi FIRN CLEARANCE REQUEST FORM Unit _

Date cf Request _

o l'A1 Tyfe of Clearanice P( Canger F. Operatinq Permit

f. Caut~cr Equipmnent and 3ysteT. :o be C.eared :

'Weck Con-roliqg Dccumrent No.D escrnpto of 'zrk L

QO S&Jgestet Cleaxance Tagging Points (Not Required):

H azarcs Asscciated,with the Wcfk. to be -erfornieg: _

Octertial Adverse Effects:_

CtIer Svs-emr Afferced:

GIounds Required YES 1 40 N

Staril l ire

__IPDate Diatiaon Reference Dra'wings's)s Ciearanme tc, be held ty: ij1q Nan-ae's; Phonefs)

Req jes-;erPar ner N,. 'LLEF{

r~anae Phone Recomne'ded CTeao: ne Budary:

£R

£ r 3E OperaticIs Revieiv- _

Rarne Date Clearanze Nc.

Assigined by S

155 Initial Date acic J36 GAThCSIi lRe 1d NRC EXAM Administrative RO/JPM # A.2. 1 6

APRIL 2002

Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" NRC Exam 2002 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 Demineralizer Valve Aisle, determine if this area must be designated as a "Locked High Radiation Area".

Answer:

NO.

  • There is no indication that an individual entering this area could receive a dose equivalent to 1000 mrem in one hour at 30 cm.

SAT UNSAT Technical Reference(s):

S-RAP-RPP-0103, Sect. 4.0 KIA#:

I Importance:

2.3.10 12.9 l

Comments:

CANDIDATE'S COPY Question:

Using the attached Survey 68 for Turbine Building 277' Condensate Demineralizer Valve Aisle, determine if this area must be designated as a "Locked High Radiation Area".

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Nine Mile Point 2 Category "A" - Examination Outline Cross Reference Operating Test Number Cat "A" NRC Exam 2002 Examination Level RO Administrative Topic A.3 Subject

Description:

Radiation Work Permit.

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 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.

SAT UNSAT SAT UNSAT I

TechnicalfReference(s):

GAP-RPP-08, Section 3.2, Rev. 8 KIA #:

Importance:

2.3.4 2.5 2.3.10 2.9 I Comments:

CANDIDATE'S COPY Question:

I 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 T 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:

6/

(O I GAG 7S; General Supervisor Date Operations Training (Designee)

OAlk Control DateA Configuration Control Date/

pal'upervisor Operations (Designee)

Date 1

A n

/I90 Performer:

(RO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate 2

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:

1. 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 I 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), as the CSO enter EPIP-EPP-04 and perform the required actions of Attachment I for this situation."

Performance Steps Standard lr'... 1 I

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)

Sat/Unsat RECORD START TIME

2.

Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.

Obtains a copy of EPIP-EPP-04.

References Section 3.1 and Attachment 1.

Sat/Unsat

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.

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/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.

Pass/Fail Sat/Unsat NRC EXAM Administrative RO/JPM # A.4. 1 APRIL 2002

Performance Steps Standard Grade Performance Steps Standard Grade

5. Notify the SSS.

Notifies the SSS of the reported situation.

Sat/Unsat 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.

Contacts Radiation Protection AND request that they report to the scene of the medical emergency via, GAltronics Phone Radio Sat/Unsat 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 the Medical Department AND request that they report to the scene of the medical emergency via, GAltronics Phone Radio Sat/Unsat CUE:

As the Fire Brigade Leader at the scene report to the Candidate that, "Radiation Protection Technicians have determined that the injured Mechanic, a male age 40, IS CONTAMINATED. The HP Technician at the scene will be accompanying the contaminated/

injured person to the hospital." Also request that an ambulance be called at this time.

NRC EXAM Administrative RO/JPM # A.4.

4 4

APRIL 2002

Performance Steps Standard f-~rnrle-Performance Steps Standard

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.

Sat/Unsat 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.

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.

Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat NRC EXAM Administrative RO/JPM # A.4. 1 5

APRIL 2002

Performance Steps Standard f-r-4P Perfrmane Stps tandrd

(~.. au

12. Request the SSS contact the RP On-Call Supervisor.

CUE:

As the SSS, acknowledge the Candidates request.

Request the SSS contact the RP On-Call Supervisor and requests that a RP technician and a RP Supervisor report to the Oswego Hospital.

As the SSS, report to the Candidate that an RP Technician and Supervisor are on their way to the Oswego Hospital.

13. Contact Site Security Supervisor.

CUE:

As the Site Security Supervisor acknowledge the request.

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 Fire Brigade Leader, inform the Candidate that the contaminated injured person has left the site and is proceeding to Oswego Hospital in the ambulance.

14. Inform the SSS of the termination of the emergency.

Informs the SSS that the contaminated injured 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), as the CSO enter EPIP-EPP-04 and perform the required actions of Attachment 1 for this situation."

NRC EXAM Administrative RO/JPM # A.4.

A 7

APRIL 2002

ATTACHMENT 1: CSO MEDICAL EMERGENCY CHECKLIST I

FNAME:

I DATE I I INIMT 17 i

m-,

I _ _ I DE Ii II.

I I

TIME OF NOTIFICATION LOCATION OF MEDICAL EMERGENCY Comple NOTE:

If making emergency announcements via GAltronics, always place in Merge mode.

1.

Notify the Fire Brigade by phone, radio, or GAltronics, and request response....................................... l

2.

Notify the SSS.[

2.

No ify t e SSS......................................................................................................................................... E

3.

Take ANY of the following actions, IF requested by the Fire Brigade Leader:

A.

IF Radiation Protection assistance is required, THEN contact RP and request that they report to the scene of the medical emergency.,,....,,,,,,,,,,,,,,,,...,.[1 B.

IF an ambulance is required, THEN:

1.

Contact Oswego County 911 Center at 343-1313 and request an ambulance(s) be sent to the Nine Mile Point Unit 2 Security Access,................... El NOTE: IF patient is contaminated OR potentially contaminated, THEN inform 911 Center of this.

2.

Contact Site Security Supervisor and request a security force member to be sent to the scene of the medical emergency AND inform them of the impending ambulance arrival........................................................................ °l

3.

WHEN the Fire Brigade Leader has requested setup of the Hospital Radiation Emergency Area (REA),

OR WHEN the patient is contaminated or potentially contaminated, THEN:

a.

Contact Oswego Hospital at 349-5522.......................................,1

b.

Inform them of the number of patients..,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

[1

c.

Request setup of the REA..........

,1 NOTE: If hospital requests patient status OR extent of injuries AND this information is known, it may be given to the hospital.

C.

IF Medical Department assistance is required, THEN contact via GAltronics, telephone, or radio.

D.

IF transportation by NMPC vehicle is requested, THEN request that the SSS notify the injured persons supervisor to obtain the necessary vehicle and driver.El E.

IF it is necessary for the RP Technician to accompany the ambulance, THEN request that the SSS contact the RP on-call supervisor and request that RP supervision and an RP Technician report to the hospital.,.............El..............

1 F.

IF the incident involves a contaminated injuryfillness AND requires transportation, THEN: Direct Site Security Supervisor to contact Manager, Nuclear Communications and Public Affairs and provide details of the incident.E.l..

..............,[

G.

WHEN the patient has left the site OR when the Fire Brigade Leader indicates the emergency is terminated, THEN inform the SSS that the emergency is terminated.El............

D ted N/A El El El El El El El El El Page 8 EPIP-EPP-04 Rev 07

ES-301 Administrative Topics Outline Form ES-3 01 -1 Facility: Nine Mile Point # 2 Date of Examination:

Jllly 29,2002 Examination Level (circle one): SRO Operating Test Number:

I 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 I" 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 ritle:

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 Date Operations Training (Designee)

Operations (Designee)

NIA EkeN Saecsq A/,'

&(?24~$~Cu

/7 Configuration Control Date Performer:

(SRO)

Trainer/Evaluator:_

Evaluation Method: X Perform Simulate Evaluation Location: _Plant X

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 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-01, Enclosure #2
2. NUREG K/A General Knowledges and Abilities 2.1.34 (2.9)

Tools and Equipment:

1. GAP-CHE-0 1, 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. 1.1A 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 (pS/cm) @ 250C 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 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 I /Operations Manual)

Sat/Unsat RECORD START TIME

2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
3. Determines Action Level I is exceeded GAP-CHE-0 1 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.

SatlUnsat Pass/Fail Pass/Fail Enters Section 3.2.1 of GAP-CHE-01.

Sat/Unsat

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.

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 NRC EXAM Administrative JPM # A. 1.1 3

APRIL 2002

Performance Steps Standard Grade Performance Steps Standard Grade 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.. I 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 (S/cm)

@ 250C 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.

A 5s APRIL 2002

1I7j11.LUOUI-Ir ;,

VVA I CM1 Ufl"ICV11 I 1-1 UU11FL1fL 0~, - UN~I 1 Operating ConditionjParameter I

Action Level Prior to Startup 1

1 0

I.

Cold Shutdown (Mode 4,5)

a. Reactor Water and Fuel Storage Pool Conductivity (gS/cm) @ 25'C

>2.0'

>5.0'

>10.00))

<1.0 Chloride (ppb)

>100.

>200*

>500")'

S 1O0 Sulfate (ppb)

>100

<100 pH at25C (Low)

<5.3-(1)

<4.9'

<4.6-(High)

>8.6'(1)

>9.3-

>9.6'

1.

Startup/Hlot Standby (Mode 2,3)

a.

Reactor Water Conductivity (g+/-S/cm) @ 25'C.5

>11.0

>5.0

<1.0

>2.0()

Chloride (ppb).

>1000)

>200

<20 Sulfate (ppb)

>100

>200

<20 Dissolved Oxygen (ppb) above 284'F (140'C)

>300 pH @ 25oC (Low)

<5.6"'0

<4.9'

<4.6' (High)

>8.6(0)

>9.3

>9.6'

b.

Feedwater/Condensate Feedwater and CDE Conductivity (j+/-Slcm) @ 25oC

>0.15-Feedwater Suspended Corrosion Products (ppb)

>100 Condensate (CDI) Conductivity (gS/cm) § 25'C

>0.10 (4)

>0.5'

>1.0--(2)

Feedwater Dissolved Oxygen (ppb)

>200

<200-IIl.

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 (PSIcrn) @ 25-C

>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 25'C (Low

<5.6'0)

<4.9'

<4.6' (High

>8.6')'

>9.3^

>9.6'

=

b. Feedwater/Condensate Feedwater and CDE Conductivity (LS/cm) @ 25'C

>0.065'

>0.1-

>0.2 -

Individual Condensate Demineralizer Outiet conductivity (uS/cm) @ 25'C

>0.2..

>0.5..

Condensate (CDI) Conductivity/(gS/cm) @ 25'C

>0.10

>0.5"'

>1.0-"')-

Feedwater Total Metals (ppb) Fe,CuNiZn 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))()'

>2.0'

>4.0' Feedwater and CDE Dissolved Oxygen (ppb)

(low

<20

<10'

<5' (Hig 50

>200

>550'

c. Control Rod Drive Water Conductivity (pSlcm) @ 25'C l

>0.15 l

l l

Dissolved Oxygen(ppb)

>200 (1)

Technical Requirements Manual Actions are controlling.

Fuel Warranty Limits (2)

Limit of 10[tS/cm applies with no chemical addition After establishing condenser vacuum wit 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 <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.

(7)

Feedwater total copper Fuel Warranty action level 1 limit equals 0.5 ppb.

,h steam air ejector GAP-CHE-01 Rev 06 Page 10

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE

Title:

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 Operations Training (Designee)

/ Date o

Date eat Operations (Designee) 1 Dat Date at EXA 56tr 1;lt Configuration Control Date Performer:

Trainer/Evaluator:

(SRO)

Evaluation Method: X Perform wvaluation Location:

X Plant Simulate 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 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 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:

I. 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. None 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.
3. Maintenance 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)

Sat/Unsat RECORD START TIME

2. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.
3. 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.

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.

Sat/Unsat SatlUnsat CUE: As the Reactor Engineer, inform the Candidate that MAPLHGR is ABOVE the Single Loop Limit and that is the only thermal limit out of specifications at this time.

NRC EXAM Administrative SRO/JPM # A. 1.2 3

APRIL 2002

Performance Steps Standard Grade Performance Steps Standard Grade

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, or Pass/Fail Refers to T.S. 3.2.1, Condition "A" and determines; The APLHGR(s) must be restored to within limits within two (2) hours, or Pass/Fail 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 5s APRIL 2002

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE

Title:

Task Number:

Review and Approval of Completed Surveillance Test N2-OSP-DER-Q00l, Revision: 0 Drywell Equipment Drains Valve Operability Test.

341-012-01-03-2 Review surveillance test results to ensure compliance with specifications.

Approvals:

Ha/

(./

v a2 General Supervisor Da e Operations Training (Designee)

C Aonfg 6o o tro Date Configuration Control Date' pers(ervisor Operations (Designee)

Date Performer:

(SRO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location:

Plant X

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.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 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-OSP-DER-QoO1, 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:

1. Copy ofN2-OSP-DER-QOOI, Drywell Equipment Drains Valve Operability Test, completed through Step 9.4.

Task Standard:

Given a copy of N2-OSP-DER-QOO 1, 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-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."

Performance SteDs Sntandaird I.

- A n

%ji auc

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-O1/Operations Manual)

Sat/Unsat RECORD START TIME

2. Review/utilize the correct section of the procedure.

Evaluator is to provide the marked up copy of N2-OSP-DER-Q00 1, 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.

Reviews General Test Methods, References/Commitments and the Precaution and Limitation Sections.

Review of the completed sections of N2-OSP-DER-Q00 1, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.

Determines that 2DER*MOV 131, 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-QOO 1, DRYWELL EQUIPMENT DRAINS VALVE OPERABILITY TEST.

Notifies MANAGER OF OPERATIONS or designee.

Sat/Unsat Sat/Unsat Pass/Fail Sat/Unsat Sat/Unsat terminating 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

Title:

Direct Reactor Building Evacuation due to a Radiation Emergency.

Task Number:

344-906-05-03 Direct Actions required for a Radiation Emergency.

Approvals:

L iC/a o

General Supervisor Date Operations Training (Designee)

Operations (Designee)

Revision: 0 Date A( on Cono Dry Confgur ionConrolDWte 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.3.1 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.

The decision has been made to do a Local Area Evacuation even though NO emergency has been declared.

Initiating Cues:

"(Operator's name), Complete the Emergency Announcement attachment of the Emergency Plan Implementing Procedures, to initiate a Local Area Evacuation, such that the CSO can make the appropriate announcement."

Performance Steps Standard If--

-4

~-I -due

1. Provide repeat back of initiating cue.

Evaluator Acknowledge repeat back providing correction if necessary Proper communications used for repeat back (GAP-OPS-01/Operations Manual)

Sat/Unsat RECORD START TIME

1. Obtain a copy of the reference procedure and review/utilize the correct section of the procedure.

EPIP-EPP-5A is obtained and Attachment 1 is referenced.

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

2. Inserts information into Attachment lof EPIP-EPP-5A.

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).

Sat/Unsat Sat/Unsat Sat/Unsat Pass/Fail NRC EXAM Administrative SRO JPM # A.3.1 3

MAY 2002

Performance Steps Standard Grade Performance Steps Standard Grade Personnel should NOT leave the area via any North or West accesses.

Staying clear of the TIP Room.

Personnel should report to their normal work locations.

SatlUnsat Pass/Fail (Block 3e): Should be left blank, based on the Cue CUE:

(Block 3e) When asked by the Candidate, state that "ACCOUNTABILITY" is NOT being performed.

(Block 3f): Checks either block 1 or 2 NOTE:

(Block 3f) The Candidate may check either of these boxes as this is up to his/her opinion.

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

6. Provide completed Attachment I to the CSo.

Provides the CSO with the completed ATTACHMENT 1.

SatlUnsat NOTE: When the Candidate supplies you as the CSO with a completed ATTACHMENT 1, the JPM is concluded.

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.3.1 44 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.
  • The decision has been made to do a Local Area Evacuation even though NO emergency has been declared.

Initiating Cues:

"(Operator's name), Complete the Emergency Announcement attachment of the Emergency Plan Implementing Procedures, to initiate a Local Area Evacuation, such that the CSO can make the appropriate announcement."

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

ATTACHMENT 1:

EMERGENCY ANNOUNCEMENT LOCAL AREA/BUILDING EVACUATION (No emergency has been declared)

Instructions: (check boxes to select appropriate announcement)

1.

Place GAItronics in Merge,

2.

Sound the EVACUATION alarm for 10 seconds

3.

Announce (if checked, include in announcement),

LI

a. Attention, Attention a7l personnel, this (is / is not) a drill.

II

b. Nine Mile Point (Unit 1 or 2) is ordering an evacuation of
(Provide specific location or building to be evacuated)_

C]I

c. Due to:

(provide conditions necessiting the evacuation) l

d. A77 personnel are to hve the_________________

(area/bui7ding)

LI 1.

StahK I~~

1-tREa/1t~

, anid'

.*~~~~~~~~~~~~~~~~~~~

~~~~~.*.

.*..~*.....*.*.

.*.....*...*....~......

...~.*

~.

..***...~*

E LI

e. Accountability is being performed, all personnel shall report to an assembly area, card in and remain in the area until further notice.

LI

f. Personne7 in protective clothing should (select appropriate):

13

1. Leave the area removing PC's as indicated at the step off pad.

OR 0i

2. Leave the area hffaTyand obtain Radiation Protection assistance

~

cnrlpin~

g. I repeat this is/is not a drill.
4.

Repeat the alarm and announcement.

Page 8 EPI P-EPP-05A Rev 01

NINE MILE POINT NUCLEAR STATION OPERATOR JOB PERFORMANCE MEASURE ritle:

Task Number:

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 Date Operations Training (Designee)

Configuration Control ate I Supervisor Operations (Designee) aeOZ Date 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 l 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-1 8, 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:

A LOCA is in progress, Drywell pressure is 10 psig rising slowly and N2-EOP-PC 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 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-O1/Operations Manual)

SatlUnsat 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).

SatlUnsat Sat/Unsat GENERAL EMERGENCY is declared based on Primary Containment Flooding IS REQUIRED (EAL GE 2.1.3 OR 2.2.3)

Pass/Fail NRC EXAM Administrative SRO JPM # A.4 MAY 2002

Performance Steps Standard Grade Performance Steps Standard Grade Part B NOTE: If the candidate declares an event below the 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 SSSJED 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.

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 2800, identified in Block #12 of the Part I.

Confirms the following ERPAs are identified in Block #7 Sat/Unsat Sat/Unsat Pass/Fail 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.

Pass/Fail 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.
  • All attempts to insert the Control Rods have failed to this point.
  • 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.
  • 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 5s 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