BVY 04-137, Draft - Section a Operating (Folder 2)

Draft - Section a Operating (Folder 2)

ML050810080
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/23/2004
From:	Gosekamp M Entergy Nuclear Northeast
To:	Caruso J NRC/RGN-I/DRS/OSB
Conte R
References
BVY 04-137, TDL 04-014
Download: ML050810080 (36)

Text

Entergy Nuclear Northeast Ei!?rg)r Nuclear CperaTior-s, 1. i ~

','errront Yankee PO @oi05GO 185 0 d Fe:ry Road Eraii!?boro. VT 05302-0530

?el 802 257 5271 December 23,2004

'04

~JEC 27 r2 117 TDL 04-014 BVY 04-137 Regional Administrator, Region 1 ATTN: Mr. John Caruso United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-14 15

References:

(a)

License No. DPR-28 (Docket No. 50-271)

Subject :

Senior Reactor Operator Licensing Examination, Vermont Yankee, February 2005 Enclosed for your review are the examination materials to support the Vermont Yankee NRC Examination scheduled for the week of February 1,2005.

Per ES-20 1, Attachment 1, regarding examination security, I would request that the enclosed materials be withheld from public disclosure until after the examinations have been completed.

This examination has been developed in accordance with NUREG-102 1 Revision 9. The written examination sample plan has changed. The JPM selections and scenarios have been modified based on discussions between yourself and Mr. Kevin Murphy during the preparation week.

For any additional assistance, please call Frank Fagan at (802) 258-4256 or myself at (802) 258-4161.

Sincerely, Entergy Nuclear Northeast - Vermont Yankee Michael E. Gosekamp Operations Training Superintendent c:

USNRC Resident Inspector - VYNPS (Attachments Withheld from Public Disclosure)

USNRC Project Manager - VYNPS (Attachments Withheld from Public Disclosure)

Document Control Desk - (Attachments Withheld from Public Disclosure)

VT Department of Public Service (Attachments Withheld from Public Disclosure)

ES-301 Rev 1, 11/26/04 Administrative Topics Outline Form ES-301-1 11 Facility:

Vermont Yankee Date of Examination: Jan 31,2005 I Examination Level (circle one):

SRO Administrative Topic (see Note)

Conduct of Operations Radiation Control I Emergency Plan I

Type Code D

Operating Test Number:

1 Describe activity to be performed A.l Respond to a Code Red Event (Note 1) 2.1.1 3 SRO 2.9 A.2 (29902) Evaluate CRO logs for readings out of specification and determine required action 2.1.18 SRO 3.0 A.3 (2341 1) Respond to lowering spent fuel pool level during refueling 2.2.28 SRO 3.3 A.4 (29903) Locate and determine radiological conditions for valve inspection 2.3.4 SRO 3.1 A.5 (20036) Offsite Protective Action Recommendation Using ODPS (Note 1) 2.4.44 SRO 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (I 1; randomly selected)

(S)imulator Note 1: Changed from initial outline.

ES-301 Rev 1, 11/26/04 Administrative Topics Outline Form ES-301-1 Narrative Summary A.1 The Security Shift Supervisor declares a Code Red event. The applicant enters the Security Event procedure and implements the Code Red section. The actions include sending a licensed operator out of the control room, notifying plant personnel not to move, classifying the event and initiating the paging system with a Code Red event code.

A.2 The on shift Control Room Supervisor will review the CRO log of a CRO trainee on shift. The applicant will determine if all readings are in spec and take any required action for out of spec readings.

A.3 The applicant is the Refueling SRO and is in the process of moving fuel. Fuel pool level starts to decrease and the applicant is to direct fuel movement stop, the bundle lowered and all personnel evacuate the refuel floor. The SRO will then be directed to fill the fuel pool with the local fill valve.

A.4 The applicant will utilize a radiological survey to determine the area of highest dose, lowest contamination and allowable stay time.

AS Fuel damage has occurred and a release is underway. A previous initial PAR, based upon plant conditions, had been made the recommended shelter for certain towns. A PAR based upon radiological conditions is to be made using ODPS (a computer system). The computer system will show that EPA guidelines have been exceeded and that evacuation of towns 5 miles downwind are required.

JPM-299 10 Rev O., 11/04 Page 1 of 4 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Evaluate CRO Logs for Readings Out of Specification and Determine Rewired Actions OP 0150, Conduct of Operations and Operator Rounds Fai 1 ure Mode:

N/A

Reference:

Task Number:

2990090301 Task Performance: AO/RO/SRO -

RO/SRO Only X SE Only -

Sequence Critical:

Yes -

No Time Critical:

Yes -

No 3 Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation -

Performance Discuss Setting: Classroom X Simulator __ Plant Performance Expected Completion Time: 20 minutes Evaluation Results:

Performance: PASS -

FAIL -

Time Required:

~

Prepared by:

//I30 / 04 Operations Traininghstructor Date A T J d ~ l k

/3d /o v Date Reviewed by:

ed Reviewer 7<14wi Approved by:

/AA/*v bfkr%ions fraining Superintendent Date

JPM-299 10 Rev O., 11/04 Page 2 of 4 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have. This JPM will be performed in the Classroom and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

The plant is at 100% power. The following equipment was taken out of service on the last shift:

"A" Rx Bldg Supply Fan for lubrication "B" RHRSW pump for impeller replacement There is one active 30 day LCO for the RHRSW pump per Tech Specs 3.5.c.2. The plant is in summer time operations with circ water in closed cycle operation.

Initiating Cues:

The Shift Manager has requested you to review a CRO trainee's practice set of log entries, pages 24-

27. You are to ensure the entries are appropriately entered, per OP 0150, and to ensure all readings are in spec.

Task Standards:

It is determined that the current cooling tower basin temperature requires all 4 RHRSW pumps operable and, with one pump inoperable, Alternate Cooling is inoperable and a 7 day LCO is entered.

Required Materials:

OP 01 50, "Conduct of Operations and Operator Rounds" (latest revision), including sheets 24-27 and completed with appropriate data OP 2 18 1 "Service WaterIAlternate Cooling Operating Procedure Tech Specs Simulator Setup: N/A

Evaluation SATAJNSAT JPM-299 10 Rev O., 11/04 Page 3 of 4 Performance Steps TIME START:

Step 1:

Obtain Procedure OP 0150, Operator Rounds, and review procedure.

Standard:

OP 0150 obtained and reviewed.

Interim Cue: Provide log sheets (VYOPF 0150.03 Sheets 24-27) with appropriate data filled in.

Note: If the candidate questions the accuracy of a log entry, inform him the readings are accurate.

SATPUNSAT Step 2:

Review log readings.

Standard:

Compare log entry to logs Required Condition SATAJNSAT SATPUNSAT SATAJNSAT

. SATAJNSAT Step 3:

Determines inappropriate lineout of reading Standard:

Indicates that the Torus Water Volume reading should have initials next to the lineout.

Step 4:

Reviews OP 2181 Standard:

Reviews OP 2181 admin for required RHRSW pumps

• Step 5:

Determine basin temperature and RHRSW requirements.

Standard:

Step 6:

Notify Shift Manager.

Determines 4 RHRSW pumps required.

Standard:

Candidate informs Shift Manager that the plant has less than the required 4 RHRSW pumps.

Interim Cue: Shift Manager requests that you determine what actions are required.

Note: The candidate may determine Tech Spec required actions before informing the Shift Manager.

Evaluation SAT/UNSAT SAT/UNSAT SATPUNSAT JPM-299 10 Rev O., 11/04 Page 4 of 4 Performance Steps

• Step 7:

Determine LCO Standard:

Candidate determines that the Alternate Cooling System is inoperable and the plant is in a 7 day LCO Step 8:

Notify Shift Manager.

Standard:

Candidate informs Shift Manager that the Alternate Cooling System is inoperable and the plant is in a 7 day LCO.

Step 9:

Complete review of logs Standard:

Candidate continues to review logs.

Interim Cue: The Shift Manager will complete the review of the logs.

• Critical Step TIME FINISH:

Terminating Cue:

It is determined that the current cooling tower basin temperature requires all 4 RHRSW pumps operable and, with one pump inoperable, Alternate Cooling is inoperable and a 7 day LCO is entered.

Evaluator Comments:

System:

WA's:

System Generic WA's:

2.1.18 SRO 3.0

JPM-299 10 Rev O., 11/04 Page 1 of 1 EXAMINEE HANDOUT Initial Conditions:

The plant is at 100% power. The following equipment was taken out of service on the last shift:

A Rx Bldg Supply Fan for lubrication B RHRSW pump for impeller replacement There is one active 30 day LCO for the RHRSW pump per Tech Specs 3.5.c.2. The plant is in summer time operations with circ water in closed cycle operation.

Initiating Cues:

JPM-299 10 Rev O., 11/04 Page I of 1 EXAMINEE HANDOUT Initial Conditions:

The plant is at 100% power. The following equipment was taken out of service on the last shift:

A Rx Bldg Supply Fan for lubrication B RHRSW pump for impeller replacement There is one active 30 day LCO for the RHRSW pump per Tech Specs 3.5.c.2. The plant is in summer time operations with circ water in closed cycle operation.

Initiating Cues:

The Shift Manager has requested you to review a CRO trainees practice set of log entries, pages 24-

27. You are to ensure the entries are appropriately entered, per OP 0150, and to ensure all readings are in spec.

CRO ROUND SHEET (Contini H2AN-OG 2921 (A/B)

(SR 91-75)

Ed)

Date REQUIRED CONDITION 00-06 06-12 12-18 18-24 TS [TRM]

(ODCM) 0.o 0.0 3.8.3.1 (4.3.4)

1. 400% of Full Scale

2. Agrees w/in 10% Full Scale of 4.8.J. 1

( 100%=4 %H2)

HzAN-OG 2922 (A5)

1. 400% of Full Scale

2. Agrees w/in 10% Full Scale of (100%=4%H2) 1(T 1.2)

H2AN-OG 2922 (A/B)

S&T-B XT-5 0.0 0.0 Rad Monitor 312713128 (SR 90-20) (SR 91-75)

(4.3.4)

(T.4.1.2)

Rad Monitor 3 127/3 128 Instrument Check I 70H bad 503 2Bl I H&N-OG 2921 (A5)

Ism-& l=T-!3l (4.3.4)

(T.4.1.2)

I 70H bad 503 2Bl

]Agree w/in 1 decade I

WAC Fans (AC, AH, & EXH)

CRP 9-23 rain A or B Running (Note a Jmbination of A and B fans running

~ an indication that a standby unit lay have auto-started)

I -'

I - t I

I Bearing Metal Temps (TR-110-5/R-1)

(ER950525-02)

Plate Metal) 5225OF.

Hotwell Conductivity A/B (CR 109-2 1/23)

Outside Gai-Tronics I

Highest Channels ~ 0. 2

@o/cm Normally off 1800-0600 weekdays VYOPF 0150.03 OP 0150 Rev. 41 Page 24 of 27

CRO ROUND SHEET (Continued)

Date REQUEED CONDlTION 00-06.

TS PRMI (ODCM) 06-12 12-18 18-24 OTHER VYOPF 0150.03 OP 0150 Rev. 41 Page 25 of 27

CRO ROUND SHEET (Continued)

Date I

4.6.C et Pump Surveillance 4.6.F. 1 VYOPF 41 10.04 4.6.F.2 VYOPF 0150.03 OP 0150 Rev. 41 Page 26 of 27

CRO ROUND SHEET (Continued)

Date REQUIRED CONDITION 00-06 06-12 12-18 TS [TRM]

(ODCM) 18-24 Core Parameters 4.11.A VYOPF 4401.01 SaT 4.11.B 4.1 l.C Control Room Recorders Timed/Trend Dated I

Input Data into "Runtanks" for CST and DST Perform Daily Operations Department Control Room Panel Walkdown Checklist VYOPF 0150.1 GENERAL NOTES:

When recorders that monitor Tech. Spec./[TRM] items are out of service, perform the following:

a,

b.

Compare the operable APRM GAFs from ERFIS REO screen from one shift to another at steady state conditions (no power changes greater than 5% in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or no rod pattern adjustment within the last 2A hours).

a.

If all the operable APFW GAFs change by greater than 0.010 (equivalent to 15.93 MWth) and this change cannot be attributed to APRM GAF adjustment by I&C or some other known reason.

2)

If all the operable MRM GAFs change by more than 0.010

1)

If the parameter is required to be continuously recorded, log the parameter hourly in the Comments section.

If the parameter is not required to be continuously recorded, log the parameter once a shift in the Comments section.

Then request Reactor Engineering validate heat balance inputs.

Then maintain actual RTP less than or equal 100% APRM power indication.

b.

Notify SM if increase M.03 ft. (4 gpm in-leakage) from previous 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reading. The Shift Supv. shall have previous week's readings trended to determine normal volume increase. If Torus volume increases 4 gpm higher than nonnal, action shall be taken to determine the cause.

(If the 87.3T limit is exceeded refer to OP 21 15 Appendix G for additional margin based upon instrument and computer point availability)

VYOPF 0150.03 OP 0150 Rev. 41 Page 27 of 27

CRO ROUND SHEET TURNOVER SHEET Date I

REQUIRED CONDITION 00-06 06-12 12-18 18-24 TS [TRM]

(ODCM)

DAYS NIGHTS Time/

Time/

Equipment/Component/Annunciator Reason Inoperable or Degraded W W O Number Initial Initial VYOPF 0150.03A OP 0150 Rev. 41 Page I of 4

JPM-234 1 1 Rev 2, 11/05 Page 1 of 4 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification :

Reference:

OP 1101 Task Number:

2337140401,34102903,34404203 Respond to LowerinE Spent Fuel Pool Level DurinP Refueling Task Performance: AO/RO/SRO __ RO/SRO - SRO Only 3 Sequence Critical:

Yes No Time Critical:

Yes __

No 2

Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation X Performance -

Discuss Setting: Classroom - Simulator - Plant Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS - FAIL -

Time Required:

\\

Date Prepared by:

q d 4iov Reviewed by:

4.

I 4

> P /l-> &c/h Opemations Training Instdtor 4

i

(-L SRO LicensedKertified Reviewer Date

/

f

L i

Approved by:

/,?

i Operatiods Training Superin tendent Date

JPM-234 1 1 Rev 2, 11/05 Page 2 of 4 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Plant and you are to simulate all actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Initial Conditions:

Refueling is in progress and you are the SRO on the refueling bridge. An A 0 and spotter are on the bridge with you moving fuel. A new fuel bundle has been grappled and is being raised from location R-41 in the Spent Fuel Pool. It has not yet cleared the rack.

Initiating Cues:

You notice an unexpected drop in fuel pool level, lowering at about 1 inch per minute. There are no radiation alarms. You are to take any required actions.

Task Standards:

Respond in accordance with OP 1101, precaution 4, evacuate the refuel floor and initiate makeup to the fuel pool.

Required Materials:

OP 1101 General

References:

None

Evaluation SAT/UNSAT JPM-234 1 1 Rev 2, 11/05 Page 3 of 4 Performance Steps TIME START:

• Step 1:

Direct Refuel Platform Operator to Stop Raising the New Fuel Bundle Standard:

Direction given to platform operator to stop.

Interim Cue: Grapple raise motion is stopped.

SAT/UNSAT

• Step 2:

Direct Refuel Platform Operator to Lower the New Fuel Bundle to Full Down Standard:

Direction given to lower the bundle full down in SFP R-41 or any empty fuel pool location.

Interim Cue: The bundle has been lowered to the full down position.

Note: The candidate may direct that the main grapple be opened; however this is not required.

SAT/UNSAT

• Step 3:

Standard:

Direct All Refuel Floor Personnel to Evacuate the Refuel Floor Direction given to all refuel floor personnel to evacuate.

Interim Cue:

Refuel floor personnel have commenced evacuation. The Shift Manager directs you to initiate makeup to the spent fuel poo1,prior to you evacuating, by opening DW-111, and report back on level.

Evaluation SATPUNSAT JPM-23411 Rev 2, 11/05 Page 4 of 4 Performance Steps

• Step 4:

Open DW-111 Standard:

Candidate rotates DW-1 1 1 handwheel counter clock-wise until resistance is felt.

Interim Cue: DW-I 11 handwheel rotates smoothly CCW until resistance is felt. Fuel pool level is now rising.

SATIUNSAT Step 5:

Standard:

Report to Control Room that DW-111 is OPEN Make report to control room that DW-111 is open and level is rising.

Interim Cue: NO FURTHER ACTIONS ARE REQUIRED FOR THIS JPM.

TIME FINISH:

Terminating Cue:

New fuel bundle returned to full down, refuel floor being evacuated, DW-1 I 1 open providing SIT makeup.

Evaluators Comments:

WA's:

2.2.28 SRO 3.3

JPM-234 1 1 Rev 1, 1 1/04 Page 1 of 1 EXAMINEE HANDOUT Initial Conditions:

Refueling is in progress and you are the SRO on the refueling bridge. An A 0 and spotter are on the bridge with you moving fuel. A new fuel bundle has been grappled and is being raised from location R-41 in the Spent Fuel Pool. It has not yet cleared the rack.

Initiating Cues:

You notice an unexpected drop in fuel pool level, lowering at about 1 inch per minute. There are no radiation alarms. You are to take any required actions.

JPM-299 1 1 Rev O., 11/04 Page 1 of 5 VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Task Identification:

Title:

Failure Mode:

N/A

Reference:

AP 0506, Personnel Monitoring Task Number:

2990100301 Locate and Determine Radiological Conditions for Valve Inspection Task Performance: AO/RO/SRO __ RO/SRO Only X SE Only -

Sequence Critical:

Yes -

No 2 Time Critical:

Yes -

No 3 Individual Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation -

Performance X Discuss -

Setting: Classroom X Simulator -

Plant Performance Expected Completion Time: 15 minutes Evaluation Results:

Performance: PASS -

FAIL __

Time Required:

Prepared by:

. Operations Training Instructor Date e/ 7 &ALJl.tt-i~ /3& Y Date Reviewed by:

SRO LicensedldertifiedReviewer f@-

7ie letd/

Approved by:

\\

/opkrat%ns TdnKSuperi n tenden t Date

JPM-299 1 1 Rev O., 11/04 Page 2 of 5 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the individual has failed the Job Performance Measure.

After providing the initiating cue, ask the individual "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Classroom and you are to perform all actions.

You are requested to "talk-through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

You have requested that an A 0 verify the RCU Pump "A" suction, CU-l9A, is open and to observe the pump run. The A 0 currently has an accumulated dose (TEDE) of 1800 mr for the year and is the only one available for the job. He is a new A 0 and has no accumulated dose for previous years. As part of preparation for a pre-job brief you are to review the survey map to determine the radiological conditions.

Initiating Cues:

Determine the following information for the brief Maximum stay time if:

Area with the lowest dose Area with the lowest contamination levels o A 0 stands next to ladder to observe valve and pump and he does not exceed VY "Routine Annual Administrative Guidelines" for dose In the event a dose extension is necessary, determine who's approval is necessary to extend the dose to VY's "Maximum Annual Administrative Guidelines" for dose Task Standards:

Areas with the lowest dose and contamination levels are determined. The correct stay time is calculated. The proper authorities for a dose extension are named.

JPM-299 1 1 Rev O., 11/04 Page 3 of 5 Required Materials:

AP 0506, Personnel Monitoring Radiological Survey Map for 280E RWCU A Pump Room Simulator Setup:

N/A

JPM-299 1 1 Rev O., 11/04 Page 4 of 5 Evaluation SATrCRVSAT Performance Steps TIME START:

Step 1:

Obtain and review survey map.

Standard:

Survey map obtained and information reviewed.

Interim Cue: Provide survey map.

SATNNSAT

• Step 2:

Determine area with lowest dose.

Standard:

Area in front of step off pad identified.

SAT/UNSAT

• Step 3:

Determine area with lowest contamination levels.

Standard:

Area in front of step off pad identified.

SATPUNSAT

• Step 4:

Calculate maximum stay time.

Standard:

Calculates a maximum stay time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Note: Calculation based on 200 mr remaining on a routine admin limit of 2000 mr. The general area dose near ladder is 100 mr/hr.

SATPUNSAT

• Step 5:

Identifv authorities required for dose extension to Maximum Admin Limits.

Standard:

The RP Superintendent and General Manager identified as approval authorities for extension.

• Critical Step

JPM-399 1 1 Rev O., 11/04 Page 5 of 5 TIME FINISH:

Terminating Cue:

Low contaminatioddose areas identified, stay time calculated and extension authorities identified.

Evaluator Comments:

System:

WA's:

System Generic WA's:

2.3.4 SRO 3.1

JPM-299 1 1 Rev O., 11/04 Page 1 of 1 EXAMINEE HANDOUT Initial Conditions:

You have requested that an A 0 verify the RCU Pump A suction, CU-l9A, is open and to observe the pump run. The A 0 currently has an accumulated dose (TEDE) of 1800 mr for the year and is the only one available for the job. He is a new A 0 and has no accumulated dose for previous years. As part of preparation for a pre-job brief you are to review the survey map to determine the radiological conditions.

Initiating Cues:

Determine the following information for the brief:

Maximum stay time i f Area with the lowest dose Area with the lowest contamination levels o A 0 stands next to ladder to observe valve and pump and he does not exceed VY Routine Annual Administrative Guidelines for dose In the event a dose extension is necessary, determine whos approval is necessary to extend the dose to VYs Maximum Annual Administrative Guidelines for dose

JPM-20036 Rev. 11, 11/05 Page 1 of 7 Task Identification:

Title:

Failure Mode:

Reference:

Task Number:

Task Performance:

Sequence Critical:

Time Critical:

VERMONT YANKEE JOB PERFORMANCE MEASURE WORKSHEET Off-Site Protective Action Recommendations Using ODPS OP-35 1 1, Off-Site Protective Action Recommendations OP-3513. Evaluation of Offsite Radiological Conditions 2007 150501 N/A AO/RO/SRO __ RO/SRO X SRO Only -

Yes _. No 3 Yes - No Operator Performing Task:

Examiner:

Date of Evaluation:

Activity Code:

Method of Testing: Simulation -

Performance X Discuss -

Setting: Classroom -

Simulator & Plant Performance Expected Completion Time: 30 minutes Evaluation Results:

Performance: PASS - FAIL -

Time Required:

Date Prepared by:

q d G5-y rations Training Instrdtor v

Reviewed by:

SRO LicensedCertified Reviewer

/

/

i I

Approvedby:

Operatans Training Manager Date

JPM-20036 Rev. 11, 11/05 Page 2 of 7 Directions:

Discuss the information given on this page with the operator being evaluated. Allow time for him to ask questions before beginning performance of the task. As each performance step is performed, evaluate the performance of that step by circling either "Sat" or "Unsat". Comments are required for any "Unsat" classification. If a step is preceded by an asterisk (*), it is a critical step. If a critical step is skipped or performed unsatisfactorily, then the operator has failed the Job Performance Measure.

After providing the initiating cue, ask the operator "Do you understand the task?"

Read to the person being evaluated:

Before starting, I will explain the initial conditions, provide the initiating cues and answer any questions you have.

This JPM will be performed in the Simulator and you are to perform the actions.

You are requested to "talk through" the procedure, stating the parameters you are verifying or checking and the steps you are performing.

Inform me upon completion of this task.

Initial Conditions:

The following plant conditions exist:

- A reactor transient has occurred that caused fuel damage

- Reactor is shutdown

- Elevated release is in progress

- NO ground release has occurred

- Release began two hours ago

- General Emergency EAL has just been declared

- Chemistry technician is talung a silver zeolite air sample from the stack

- Site Boundary Team dispatched

- PAR based on plant conditions has been completed per OP 351 1, section I.

Initiating Cues:

The PED has requested that you determine off-site protective action recommendations based on Radiological Dose information using ODPS per OP 35 1 1, section D[.

Task Standards:

Operator makes appropriate off-site PAR determination per OP 35 1 1.

JPM-20036 Rev. 11, 11/05 Page 3 of 7 Required Materials:

OP 35 11, Off-Site Protective Action Recommendations (latest revision)

VYOPF 35 11.01, Protective Action Recommendation Worksheet completed for initial PAR on plant conditions OP 35 13, Evaluation of Offsite Radiological Conditions (latest revision)

Initial plant PAR completed on form 3511.01 (attached)

ERFIS Source Term Data printout (attached)

ERFIS PAR printout (attached)

Simulator Setup:

Any full power IC with ERRS available. Insert malfunction RMOlF at 0.4%, stack Hi-Range monitor.

Evaluation SATKJNSAT SATfUNSAT SATIUNSAT SAT/UNSAT SATfUNSAT SATKJNSAT SATAJNSAT JPM-20036 Rev. 1 1, 11/05 Page 4 of 7 Performance Steps TJME START:

Step 1:

Standard:

Obtain Procedure OP 3511, Section I1 and review precautions Operator obtains and reviews procedure Step 2:

Standard:

Obtain Procedure OP 3513,Section I and review precautions Operator obtains procedure and reviews precautions Step 3:

Obtain current off-site dose pro-jection results and meteorolopical data (wind direction and stability class) from OP 3513.

Standard:

Operator Goes to OP 3513 as directed by OP 351 1, step II.A. 1 Step 4:

If ODPS is operable, then implement Appendix G to access off-site dose projection information from ODPS.

Standard:

Operator Goes to OP 3513, Appendix G as directed by OP 3513, step I.A.4.

Step 5:

Press the "ODPS" ERFIS terminal key to access the "ODPS Menu" screen Standard:

Operator presses the white "ODPS" key on an ERFIS keyboard or enters ODPS by clichng through screen menus

• Step 6:

Standard:

Click on the "SOURCE TERM DATA" box to display screen Operator clicks on the "Source Term Data" box.

Step 7:

Click on the PRINTER icon to obtain record of stack release prsiection information (Reactor Trip Status and Stack).

Standard:

Clicks on the PRINT icon on the ERFIS screen Interim Cue: Provide the candidate with the attached ERFIS Source Term Data printout. If asked, the printout has the current date and time.

SATiUNSAT SATKJNSAT SATIUNSAT JPM-20036 Rev. 11, 11/05 Page 5 of 7 Step 8:

Press the "ODPS" ERFIS terminal key to return to the "ODPS Menu" screen Standard:

Operator presses white "ODPS" key.

• Step 9:

Click on the "PROTECTIVE ACTION RECOMMENDATIONS LIVE STACK MIUI-IR box to display screen Standard:

Operator clicks on the Protective Action box to generate the PAR Step 10:

When "PROTECTIVE ACTION RECOMMENDATION" screen is displayed, click on the PRINTER icon to obtain stack release off-site dose pro-jection information.

Standard:

Operator clicks on the PRINT icon.

Interim Cue: Provide the candidate with the attached ERFIS PAR printout. If asked, the printout has the current date and time.

SAT/UNSAT Step 11:

Press the "ODPS" ERFIS terminal kev to return to the "ODPS Menu" screen Standard:

Operator presses white "ODPS" key SAT/UNSAT Step 12:

If only one release point exists (stack or mound), then continue with the following actions:

Implement OP 3511 Section 11, Step A.2 to formulate Protective Action Recommendations for State authorities References OP 351 1, Section 2 Step A.2.

Standard:

SATKJNSAT Step 13:

Compare the calculated dose pro-jection results with EPA Protective Action Guidelines delineated below to determine whether EPA Standard:

Protective Action Guidelines have been exceeded Notes that Total Effective Dose is >I.

SATKJNSAT SATIUNSAT SATIUNSAT SATrUNSAT JPM-20036 Rev. 11, 11/05 Page 6 of 7

• Ster, 14:

Standard:

Selects Table 5.

Determine appromiate table to use.

• Step 15:

Choose towns affected by the PAR Standard: Selects Sector A for wind direction and stability class.

• Step 16:

Record appropriate PAR information in Section I1 of VYOPF 3511.01 Standard:

Operator records PAR data on OP 35 1 1.01 with evacuation recommended for Vernon, Hinsdale, Bernardston and Northfield.

Step 17:

Forward completed VYOPF 3511.01 to the Site Recovery Manager or senior manager in charge.

Standard:

Provides copy of Protective Action Recommendation to the PED.

Interim Cue: No further actions are required for this JPM.

• Critical Step TIME FINISH:

Terminating Cue:

Operator completes 35 1 1.01 with appropriate offsite protective action recommendations.

Evaluator Comments:

System Generic WAs:

2.4.44 SR04.4

JPM-20036 Rev. 1 1, 11/05 Page 7 of 7 EXAMINEE HANDOUT Initial Conditions:

The following plant conditions exist:

- A reactor transient has occurred that caused fuel damage

- Reactor is shutdown

- Elevated release is in progress

- NO ground release has occurred

- Release began two hours ago

- General Emergency EAL has just been declared

- Chemistry technician is taking a silver zeolite air sample from the stack

- Site Boundary Team dispatched

- PAR based on plant conditions has been completed per OP 35 1 1, section I.

Initiating Cues:

The PED has requested that you determine off-site protective action recommendations based on Radiological Dose information using ODPS per OP 351 1, section II.

PROTECTIVE ACTION RECOMMENDATION WORKSHEET INFORMATION CURRENT AT:

t (Timemate)

PROTECTIVE ACTION RECOMMENDATIONS SECTION I: PLANT CONDITIONS (Fill in with appropriate letter designation for affected towns from Table 3)

S= Shelter in Place OR E= Evacuate VERMONT TOWNS Brattleboro Guilford

> Vernon NEW HAMPSHIRE TOWNS Hinsdale 7

Winchester MASSACHUSETTS TOWNS Bernardston 5 Northfield SECTION 11: RADIOLOGICAL DOSE (Fill in with letter designation for affected towns)

E= Evacuate (Check if appropriate)

OR NO PARS Based on Radiological Dose VERMONT TOWNS Brat tleboro Dumerston Guilford Halifax Vernon NEW HAMPSHIRE TOWNS Chesterfield Hinsdale Richmond Swanzey Winchester MASSACHUSETTS TOWNS B emards ton Colrain Gill Greenfield Leyden Northfield Warwick rhe following was used (Check as applicable):

INomogam OODPS nMETPAC OField Data Performed By:

Verified By:

(The following information to be filled in by Senior Manager in charge or designated alternate) r Approved By:

L L f'(a-iyi -f:

72,JJ (Time/date) c k-~'f'/~C~~('/

MPED UTSC Coordinator USite Recovery Manager (Check one)

Transmit approved PAR to State Authorities as delineated in OP 3540 (PED or TSC Coordinator using OP 3540.06) or OP 3546 (Site Recovery Manager using OP 3546.02)

VYOPF 351 1.01 OP 351 I Rev. 14 Page 1 of 1

s PPCS

.O M/54'

!22804 PROTECTIVE ACTION RECOMMENDATIONS PLANT MODE RUN THIS STRAIGHTLINE PROJECTION USES SOURCE TERM DATA AND 15 MINUTE AVERAGES OF UPPER PRIMARY METEOROLOGICAL TOWER DATA FROM 10 :

STACK DOSE RATE OF 39999.5000 MR/HR.

WIND DIRECTION FROM:

2 DEGREES MET WIND SPEED:

2 MPH DELTA TEMPERATURE:

-3.20 F

DATA STABILITY CLASS:

A SITE BOUNDARY PRECIPITATION:

0.50 IN/QTR HR TOTAL EFF. EQUIV:

1869 MR/HR ADULT THYROID :

106 MR/HR 8

HOUR DOSE D I S T (MI) 7

.35 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 TOTAL EDE (REM) 14.949 2.372 0.912 0.566 0.423 0.343 0.291 0.254 0.225 0.202 0.184 ADULT THY (REM) 0.845 0.239 0.034 0.006 0.001 0

• 000 0.000 0.000 0.000 0

• 000 0.000

.35 MILES AT 10 :

41 2.00 MILES AT ARRIVAL TIMES 5.00 MILES AT 13 :

4 10.00 MILES AT 45 AND THE PAR EVAC EVAC EVAC W A C EVAC EVAC NONE NONE NONE NONE NONE 11 :

34 15 :

34

VYOPF3513.01 SOURCE TERM DATA PLANT MODE RUN ELAPSED TIME SINCE ON o /

o/

0 PLANT T R I P REACTOR T R I P STATUS NORM AT 0 :

0:

0 0 MINUTES STACK HlGH RANGE ELEVATED RADIATION RELEASE ON 11/ 2 5 /

4 39999.5000 MR/HR

> 0.1445 MR/HR YES AT 10:

34:

3 NOTE:

A RELEASE I S ASSUMED TO BE I N PROGRESS IF AN ELEVATED STACK MR/HR VALUE I N EXCESS OF 0.1445 I S PRESENT FOR LONGER THAN 10 SECONDS. T H I S AFFECTS THE CALCULATION OF PLUME ARRIVAL TIMES ONLY.

AVG STACK FLOW (FT-108-22) 135690 SCFM UNMONITORED A NONZERO DOWNWIND S I T E BOUNDARY DOSE RATE OF:

0.0000 MR/HR HAS BEEN MANUALLY ENTERED FOR o /

o /

0 AT 0: 0: 0