Text

PVNGS-2012-03-DRAFT-Operating Test
	ML12152A349
Person / Time
Site:	Palo Verde
Issue date:	03/16/2012
From:	; Division of Reactor Safety IV
To:	; Arizona Public Service Co
	Thomas Farina
References
	Download: ML12152A349 (533)
	v • d • e

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1290020301, Conduct of Shift Operations TASK STANDARD: Determine Current License Status K/A: 2.1.4 K/A RATING: RO: 3.3 SRO: 3.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40DP-9OP02, Conduct of Shift Operations SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10/04/2011 Revised By: Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#:

SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40DP-9OP02. This JPM was written using Revision 53 of 40DP-9OP02 This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION Page 2 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

You are currently licensed at PVNGS.

You have been assigned to work control for last 4 months.

Today is December 27th.

You attended LOCT training November 8th -11th but did not take the written exam.

The LOCT cycle completed Friday, December 2nd.

Attached is a spreadsheet of shifts you covered in the last quarter.

You met all license maintenance requirements for the 3rd quarter.

You have been asked to take the dayshift on December 31st and January 1st.

INITIATING CUE:

You are directed to determine if you:

1. are current in Training

2. meet requirements to assume RO duties on December 31st

3. meet requirements to assume RO duties on January 1st.

Provide your answers on the attached sheet.

Page 3 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

3.6.1.1 of 40DP-9OP02 Examinee determines that it has been less than 6 weeks since the An Operator's training is current completion of the last training cycle when all required material in an and they are therefore current in LOCT Training Cycle is completed. LOCT.

If any LOCT material is missed during a training cycle, make-up training shall be completed no later than 6 weeks from the end of the training cycle that the training was part of.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

3.6.2 of 40DP-9OP02 Examinee determines that since they are current in training and met license ACTIVE NRC Operators License maintenance requirements in the 2nd exists when an operator has a valid quarter they can take the shift on license and has actively performed December 31st.

the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

3.6.2 of 40DP-9OP02 Examinee determines that they CAN NOT take the shift on January 1st ACTIVE NRC Operators License because they did not perform 5-12 exists when an operator has a valid hour shift in the 4th quarter.

license and has actively performed the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 6 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Answer Key October 15th 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift (RO)

October 16th 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months shift 0630 to 1630 (RO)

November 24th 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift (CO)

December 11th 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1200 to 1830 (CO)

December 25th 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift (RO)

1. Are you current in Training YES / NO If NO what must be done to become current?

2. Can you assume RO duties on December 31st? YES / NO If NO why not?

3. Can you assume RO duties on January 1st ? YES / NO If NO why not?

The operator did not perform at least 5 -12 hour shifts of license proficiency time in the 4th quarter therefore the operator CAN NOT assume the RO duties in the next quarter.

Answer Key Page 7 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 10/04/2011 New JPM for 2012 NRC Initial Exam REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

You are currently licensed at PVNGS.

You have been assigned to work control for last 4 months.

Today is December 27th.

You attended LOCT training November 8th -11th but did not take the written exam.

The LOCT cycle completed Friday, December 2nd.

Attached is a spreadsheet of shifts you covered in the last quarter.

You met all license maintenance requirements for the 3rd quarter.

You have been asked to take the dayshift on December 31st and January 1st.

INITIATING CUE:

You are directed to determine if you:

1. are current in Training

2. meet requirements to assume RO duties on December 31st

3. meet requirements to assume RO duties on January 1st.

Provide your answers on the attached sheet.

Page 9 of 10

A-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam October 15th 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift October 16th 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months shift 0630 to 1630 November 24th 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift December 11th 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1200 to 1830 December 21st 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months day shift

1. Are you current in Training YES / NO If NO what must be done to become current?

2. Can you assume RO duties on December 31st? YES / NO If NO why not?

3. Can you assume RO duties on January 1st ? YES / NO If NO why not?

Page 10 of 10

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 18 of 63 Revision Conduct of Shift Operations 40DP-9OP02 53 3.6 Licensed Operator Watchstanding Proficiency 3.6.1 A VALID NRC Operators License exists when the holder of that license is current in Licensed Operator Continuing Training (LOCT).

3.6.1.1 An Operator's training is current when all required material in an LOCT Training Cycle is completed. If any LOCT material is missed during a training cycle, make-up training shall be completed no later than 6 weeks from the end of the training cycle that the training was part of.

3.6.1.2 If the operator fails to make up the classroom training and simulator training within 6 weeks of the end of the training cycle, the operator shall be removed from license duties until the make-up training is completed.

3.6.2 An ACTIVE NRC Operators License exists when an operator has a valid license and has actively performed the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

Actively Performed means that the operator held a position on the shift crew that required the individual to be licensed as defined in the Technical Specifications and that the operator carried out and was responsible for the duties covered by that position.

For maintenance of an active SRO license any shift spent in either the SM or CRS position will be credited.

An SRO must stand at least one complete shift per calendar quarter in an SRO-only supervisory position. The remainder of the shifts required in a calendar quarter may be performed in either a credited SRO or RO position.

For time to be credited it must be a continuous shift (i.e., 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of watch shift responsibilities spent on each of 3 different shifts does not equal one 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift).

Overtime may be credited if the overtime work is in a position appropriately credited for watchstanding proficiency. Overtime as an extra helper after the official watch has been turned over to another watchstander does not count toward proficiency time.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 19 of 63 Revision Conduct of Shift Operations 40DP-9OP02 53 3.6.3 A third Reactor/Control Operator in excess of those required by technical specifications may be credited with license proficiency hours if the following administrative controls are in place:

The licensee shall list all licensed shift crew positions, including titles, descriptions of duties and which positions are required by technical specification.

For those shift crew positions in excess of those required by technical specifications, a description of how the position is meaningfully and fully engaged in the function and duties of the license position required by technical specification.

If theses administrative controls are not met, the individual shall not be given watch-standing proficiency credit for shift positions in excess of technical specification requirements.

3.6.3.1 At the conclusion of an individual shift, the Shift Manager will determine and concur that the 3rd RO was engaged in the functions and duties of a licensed operator in the Control Room and therefore can utilize the shift time towards their proficiency. This determination will be made by verifying that the 3rd RO:

Completed the full 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift

Participated in shift turnover both at the beginning and end of shift

Participated in licensed operator functions and performed licensed operator duties in the Control Room. Examples of these functions and duties include:

Control Board manipulations and monitoring,

Performing peer checks and Independent Verifications,

Responding to alarms or off-normal conditions,

Providing briefings as needed,

Performing permit and clearance activities.

3.6.3.2 Should the Shift Manager determine that the 3rd RO did not satisfy these requirements, then their completed shift time could not be used towards their proficiency requirement.

3.6.4 Only one excess Reactor/Control Operator above the minimum licensed positions required by technical specifications can be credited per shift per Unit.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 20 of 63 Revision Conduct of Shift Operations 40DP-9OP02 53 3.6.5 Each licensed individual is responsible to report the completion of the license proficiency hours each quarter to the Nuclear Training department, Operations Training. Failure to complete this notification will result in the suspension of qualifications for licensed duties.

3.6.5.1 Open CORA\AutoLog.

3.6.5.2 From the Tools Menu, select the License Hot Time Tracking Tool.

3.6.5.3 Generate an Individual Licensed Operator Proficiency report and 3.6.5.4 Send it to the Training System Administrator, Nuclear Training Department, Operations Training.

This report should be sent as early in the quarter as possible after you have completed the required proficiency time, to allow enough time for the data to be entered into training records.

3.6.6 An individual is classified active for the current calendar quarter if they meet any one of the following conditions:

The individual meets the requirements of step 3.6.2.

The individual has completed the Operator License Reactivation Job Qualification Card in the current or previous calendar quarter.

(NLR10-xx-001, xx references the revision number.)

The individual has been issued (not renewed) an Operators License (RO or SRO) in the current or previous calendar quarter.

3.6.7 Each individual attempting to reactivate an inactive but valid license shall complete the Operator License Reactivation Job Qualification Card prior to resuming licensed operator duties.

3.6.8 An SRO being reactivated to assume an SM position shall function under instruction as the SM.

3.6.9 An SRO being reactivated to assume the CRS position can function under instructions as either the CRS or SM.

3.6.10 SRO licensed personnel functioning as ROs being reactivated to assume an SRO position shall perform 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months under direction of the SM/CRS prior to assuming an SRO position.

3.6.11 An SRO/RO that reactivates their SRO license also reactivates their ability to perform RO duties.

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 270130401, Implement Reactor Coolant System draining operations TASK STANDARD: Determine Pzr level and RCS volume to be drained to the RWT K/A: 2.1.25 K/A RATING: RO: 3.9 SRO: 4.2 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9ZZ16, RCS Drain Operations SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10/05/2011 Revised By: Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

40OP-9ZZ16. This JPM was written using Revision 71 of 40OP-9ZZ16. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Page 2 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

The plant is in mode 5.

Pressurizer pressure is 50 PSIA.

Pressurizer temperature is 150 °F.

RCN-LI-103 indicates 30%.

RCA-LI-110X indicates 42%.

RCB-LI-110Y indicates 38%.

Preparations are being made to lower RCS level.

INITIATING CUE:

The CRS directs you to determine the following per 40OP-9ZZ16:

1. ACTUAL PRZR level based on current indications

2. Using appendix E, calculate the expected change in RWT level if the RCS were drained from actual level to the top of the Reactor Vessel Flange level.

Use the spaces on the cue sheet to document your answers.

Page 3 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

Precautions and Limitations 3.1.4 Using Appendix A examinee determines that :

Correct channels RCA-LI-110X

& RCB-LI-110Y using Appendix RCA-LI-110X level is 32% +/- 2%.

B- RCB-LI-110Y level is 30% +/- 2%.

Pressurizer Indicated Vs. Actual Level For RCA-LI-110X And RCBLI-110Y.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Precautions and Limitations 3.1.4 Using Appendix A examinee determines that :

Correct RCN-LI-103 using Appendix C - Pressurizer RCN-LI-103 level is 31% +/- 2%.

Indicated Vs. Actual Level For RCN-LI-103.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Using appendix E the examinee Determine amount of water (in determines the change in RWT gallons) to be drained by in the level if the RCS were drained pressurizer by interpreting from the table or the chart the amount from ~30% pressurizer level to of water at ~ 30% level.

flange level (114 feet).

Examinee should determine actual level based on instrument reading from the previous step.

Gallons should be between 9300-10140 gallons.

The examinee determines the level increase in the RWT by using the graph to determine the gallons of water drained from RCS is 9300-10140 gallons divided by 7538 gallons / % in the RWT = a change of 1.23 to 1.35%

Acceptable answer 1.23 to 1.35

% change in RWT Level.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 6 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam ANSWER KEY

1. Actual pressurizer level per:

RCN-LI-103 _________31% (+2%)___

RCA-LI-110X _________32% (+2%)___

RCB-LI-110Y _________30% (+2%)___

2. Expected change in RWT level ______1.23 to 1.35%

ANSWER KEY Page 7 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 10/06/2011 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 9

A-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

The plant is in mode 5.

Pressurizer pressure is 50 PSIA.

Pressurizer temperature is 150 °F.

RCN-LI-103 indicates 30%.

RCA-LI-110X indicates 42%.

RCB-LI-110Y indicates 38%.

Preparations are being made to lower RCS level.

INITIATING CUE:

The CRS directs you to determine the following per 40OP-9ZZ16:

1. ACTUAL PRZR level based on current indications

2. Using appendix E, calculate the expected change in RWT level if the RCS were drained from actual level to the top of the Reactor Vessel Flange level.

Provide your answers in the spaces below:

1. Actual pressurizer level per:

RCN-LI-103 ____________

RCA-LI-110X ____________

RCB-LI-110Y ____________

2. Expected change in RWT level _____________ %

Page 9 of 9

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 219 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix B Page 1 of 1 Appendix B - Pressurizer Indicated Vs. Actual Level For RCA-LI-110X And RCB-LI-110Y Pressurizer Indicated Vs. Actual Level for RCA-LI-110X and RCB-LI-110Y Pressurizer Indicated vs. actual level for deviation from normal operating to cold pressurizer conditions.

2400 psia, 662°F 2250 psia, 653°F 100 2000 psia, 636°F 90 1500 psia, 596°F 80 500 psia, 467°F 70 14.7 psia, 60 Actual Level (%)

70°F 50 40 30 20 10 0

10 20 30 40 50 60 70 80 90 100 Indicated Level (%)

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 220 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix C Page 1 of 1 Appendix C - Pressurizer Indicated Vs. Actual Level For RCN-LI-103 Pressurizer Indicated Vs. Actual Level for RCN-LI-103 2250 psia, 653°F 2000 psia, 636°F 1500 psia, 596°F 1000 psia, 545°F 750 psia, 511°F 500 psia, 467°F 250 psia, 401°F 100 14.7 psia, 60°F 90 80 70 60 Actual Level (%)

50 40 30 20 10 0

10 20 30 40 50 60 70 80 90 100 Indicated Level (%)

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 241 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix E Page 1 of 4 Appendix E - Determination of Volume to be Drained Both RWLIS Narrow and Wide range indication start at plant elevation 99 ft.7 in.

Between elevation 99 ft. 7 in. & 102 ft. 11in. use Narrow range channel RCN-LI-752A.

For elevations above 102 ft. 11 in. use Wide range channel RCN-LI-752B.

With SG nozzle dams installed, about 17,000 gallons will be drained to lower level from 112 ft. 6 in. to 101 ft.9 in.

Each RSG tube bundle contains about 15,497 gallons.

106,100 gallons 20% WR. 120' 7 1/4" 100,700 93,800 93,300 86,000 77,500 71,500 70,500 32,800 27,800

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 242 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix E Page 2 of 4 Determination Of Volume To Be Drained (2) RCS INVENTORY (3) HUT (3) RWT (1) RWLIS FOR GIVEN REFERENCE LEVEL LEVEL INDICATION ELEVATION cubic ft /

GAIN - ft GAIN - %

gallons 50% PZR Level 131 ft 5 in WR 14,183 / 106,100 +8.4 +14.1 10% PZR Level 117 ft WR 13,463 / 100,700 +7.9 +13.4 Top of Rx Vessel Flange 114 ft WR 12,533 / 93,800 +7.4 +12.4 2% PZR Level Refueling Water Level 113 ft 6 in WR 12,473 / 93,300 +7.3 +12.4 Enter Reduced Inventory 111 ft WR 11,499 / 86,000 +6.8 +11.4 Limited to 107 ft WR 10,365 / 77,500 +6.1 +10.3 1 SDC Pump / Loop Limited to 1 SDC Pump 104 ft WR 9,559 / 71,500 +5.6 +9.5

& 1 SDC Loop Top of the Hot Leg -

103 ft 1 in WR 9,420 / 70,500 +5.5 +9.4 Enter Mid-Loop Ops 101 ft 4 in Centerline of RCS Hotleg 4,380 / 32,800 +2.6 +4.4 WR & NR (1) WR. is Wide Range RCN-LI-752B, and NR. is Narrow Range RCN-LI-752A.

(2) Values were determined as follows: gal = c.f. x 7.4805 gal/c.f. then rounding the product to nearest 100 gal.

(3) HUT level assumes 12,704 gallons/foot in tank.

RWT level assumes 7,538 gallons/% in tank.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 243 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix E Page 3 of 4 Volume to be drained = Initial Volume minus Final Volume.

Example: Draining the RCS from 50% Pzr level to Mid-Loop condition using gallons:

Ivol - Fvol = Voldrained: 106,100 - 32,800 = 73,300 gallons drained.

D HUT level: 73,300 divided by 12,704 gal/foot = + 5.8 ft. increase in HUT level.

D RWT level: 73,300 divided by 7,538 gal/% = + 9.7% level increase in RWT level.

Using the previous example another way to determine the HUT/RWT level increase is to use the starting RCS inventory at 50% Pzr level, 8.4 ft. for the HUT or 14.1% for the RWT then subtract the final RCS inventory value at midloop, 2.6 ft. for the HUT or 4.4% for the RWT, or 8.4 ft. minus 2.6 ft. = 5.8 ft. level increase in HUT and 14.1% minus 4.4 = 9.7% level increase in RWT level. These level increases are in addition to existing tank levels.

Volume to be drained may be determined several hours prior to actual drain. Under these circumstances, normal plant operations such as VCT divert/makeup may cause a change in assumed initial conditions. The result is an unexpected volume change. Document assumed initial and final levels below:

Assumed Conditions Initial Pzr. Level: Final RWLIS:

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 244 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix E Page 4 of 4 Significant Plant Elevations RWLIS Level Plant Reference Point Significance Indication (Note 1) 149 ft. Pressurizer Manway 141 ft. Versa-Vent Removal 141 ft RCE-V007 - RVHV Vent Valve 131 ft. 5 in. W.R. 50% Pzr Level 117 ft. W.R. 10% Pzr Level Enter PARTIAL DRAIN condition. Required to monitor and record RCS level indication.

114 ft. 1 in. ICI Seal Table 114 ft. W.R. Top Rx Vessel Flange Enter Lowered Inventory 113 ft. 6 in. W.R. Normal level when entering Mode 6

<111 ft. W.R. Enter REDUCED INVENTORY CONDITION

<107 ft. W.R. May continue to operate both SDC loops, but are limited to 1 SDC pump per loop.

<104 ft. W.R. 104 ft is top of RCP bowl Limited to 1 SDC pump and loop.

103 ft. 1 in. W.R. (103 ft. 1 in. down to 102 ft.) Maintain SDC flow rate between 3780 - 4600 gpm.

103 ft. 1 in.W.R. Top of Hot Leg SG tubes begin to drain. ENTER MID-LOOP 102 ft. 11 in. Theoretical level to remove SG Primary Manways 102 ft. 4 in. N.R. Hot Leg Lip Elevation at which RCS fluid will start spilling over into the SG bowls from the Hot Leg.

102 ft. N.R. (102 ft. down to 101 ft. 6 in.) Maintain SDC flow rate between 3780 - 4150 gpm.

102 ft. N.R. Cold Leg Lip Elevation at which RCS fluid will start spilling over into the SG bowls from the cold leg.

101 ft. 10 in. N.R. Optimum level for Steam Generator nozzle dam installation.

101 ft, 6 in. N.R. 2 in. above RCS Hot Leg Minimum Level for MID-LOOP Operations.

Centerline 99 ft. 7 in. N.R./W.R. Bottom of Hot Leg Bottom range of Control Room RWLIS indication.

Note 1 - From 117 ft. 8 3/8 in. to 102 ft. 11in., use Wide Range indicator RCN-LI-752B.

From 102 ft. 11in. to 99 ft. 7 in., use Narrow Range indicator RCN-LI-752A.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 245 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 Appendix F Page 1 of 2 Appendix F - Shiftly Verification

1.0 Requirements

1.1 This Appendix shall be performed when RCS level is less than or equal to 111 ft.

with fuel in the vessel.

1.2 This Appendix is required when any of the following exists:

End of shift.

Prior to rendering a current makeup path unusable.

When directed by the Shift Manager.

1.3 Completed appendix shall be attached to the Shift Managers Turnover Sheet.

2.0 Verification Checklist:

_____ 2.1 Record the SDC Train in service: __________

_____ 2.2 Makeup flow rate required to prevent boiling has been determine. REFER TO Step 7.2.13.

Reqd HPSI Makeup __________ gpm/cold leg

_____ 2.3 Ensure that the status board at the RP Island has been updated with the current time-to-boil data prior to reduced inventory and mid-loop operations and updated shiftly.

_____ 2.4 Record the two designated makeup sources and Appendices used to align/check the source. (REFER TO the completed Appendix for directions on how to initiate flow from the selected source.)

When Required Makeup Train (circle)

HPSI Makeup to Cold Leg Cold leg is intact A B (Appendix G)

Gravity Makeup Flowpath ALWAYS required A B (Appendix H)

HPSI Makeup to HOT Leg Anytime the cold leg is NOT A B (Appendix S) intact

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1290310301 Perform a Tech Review of a Permit TASK STANDARD: 3 errors found during a permit Tech Review K/A: 2.2.13 K/A RATING: RO: 4.1 SRO: 4.3 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40DP-9OP29, Permit and Tagging Process, Various Plant Drawings SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 10/04/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

A computer available for access to procedures and plant drawings.

Page 2 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 is 100% power The A High Pressure Safety Injection (HPSI) Pump (SIA-P02) has a severe seal leak on the pump. The CRS has directed that a permit be hung to isolate and drain the A HPSI pump.

Permit 12-0003 was generated manually due to the Site Work Management System (SWMS) being down.

The CRS has addressed Tech Specs.

INITIATING CUE:

The CRS has directed you to perform a Tech Review of Permit 12-0003.

Identify the errors (Non-clerical - not typos) on the permit.

Page 3 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Reviews Permit to determine scope Examinee reviews Permit and of work to be performed. determines work scope to be repair seal leak on 1-M-SIA-P02.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Identifies one (1) error on the permit Examinee determines the following with Tag 2. inaccuracy/inadequacy.

Tag 2 is the wrong circuit breaker (breaker is for the A LPSI pump)

The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Identifies one (1) error on the permit Examinee determines the following with Tag 5. inaccuracy/inadequacy.

Tag 5 has the wrong position (CLOSED) for the breaker for the Recirc Valve SIA-UV-666. The breaker position should be OPEN The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Identifies one (1) error on the permit Examinee determines the following with Tag 9. inaccuracy/inadequacy.

Tag 9 has the wrong valve number. It identifies the drain valve as SIA-V550 (which is the drain valve for SIA-P01) and it could be SIA-V980, 955 or 956.

The order of identification of the errors in steps 2, 3, and 4 of this JPM is not critical.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Page 6 of 10

A-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 7 of 10

FOR 2012 NRC EXAM ONLY Tag Assignment Sheet Unit No: __1____ Permit No: __12-0003__ Page __1__ of __1__

TAG PLACEMENT TAG REMOVAL Tag Tag No. Equipment ID.

Color Hang Order Component Placed Verified Restore Restore Restored Position By By Order Position By 1J-SIA-HS001 Handswitch for 1 Yellow 1 N/A SIA-P02 (HPSI A pump) 2 1E-PBA-S03F, 4.16KV Breaker Wrong Breaker Red 3 RACKED OUT for 1-M-SIA-P01 1P-SIA-V470 3 Red 6 CLOSED SIA-P02 Suction Valve 1P-SIA-UV-666, SIA-P02 DO NOT 4 Red 7 Recirc Valve OPERATE 1E-PHA-M3507, 480VAC 4 Wrong Position 5 Breaker to SIA-UV666 (SIA- Red P02 Recirc Valve) CLOSED 1J-SIA-HS-666, Handswitch for 6 SIA-UV666 (SIA-P02 Recirc Yellow 2 N/A Valve) 1P-SIA-V476, SIA-P02 7 Red 5 CLOSED Discharge Valve 8 1P-SIA-V1024 Yellow 9 N/A SIA-P02 Vent Valve 1P-SIA-V550 Wrong Valve 9 Yellow 8 N/An SIA-P01 Drain Valve

Special instructions on yellow tag ANSWER KEY Page 8 of 10

RA-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 9 of 10

RA-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 is 100% power The A High Pressure Safety Injection (HPSI) Pump (SIA-P02) has a severe seal leak on the pump. The CRS has directed that a permit be hung to isolate and drain the A HPSI pump.

Permit 12-0003 was generated manually due to the Site Work Management System (SWMS) being down.

The CRS has addressed Tech Specs.

INITIATING CUE:

The CRS has directed you to perform a Tech Review of Permit 12-0003.

Identify the errors (Non-clerical - not typos) on the permit.

Page 10 of 10

2012 NRC EXAM ONLY NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 65 of 79 Revision Power Block Permit and Tagging 40DP-9OP29 45 Appendix B Page 2 of 3 Palo Verde 2 Permit Form 1

Nuclear Generating Station Page of Facility No. Permit No. System UNIT 1 12-003 SI EQ I.D. EQ Description 1MSIAP02 High Pressure Safety Injection Pump 'A' Reason For Permit:

Isolate the pump due to severe pump seal leakage Equip Conditions Required For Work Special Instructions De-energized X Yes No Depressurized X Yes No Continuously Vented Yes X No Drained X Yes No Purged Yes X No Isolated X Yes No SWMS Search Yes X No TSCCR X Yes No TSCCR No.

3712771 Prepared By: Ext: Date: Time:

JOE TAGGER 2648 3/19/2012 0650 Tag Placement Authorized (responsible supervisor) Ext: Date: Time:

EQ Conditions Established (operator) Ext: Date: Time:

Tag Removal Authorized: (responsible supervisor) Ext: Date: Time:

Permit Cancelled: (responsible supervisor) Ext: Date: Time:

Requestor/Ext. (Print) Work Document Signature/Date/Time Operations Tech. Rev:

Unit 1 Shift Manager Authorized:

N/A X82-1206 Accepted:

Released:

PV-E0213 Ver. 3 40DP-9OP29

FOR 2012 NRC EXAM ONLY Tag Assignment Sheet Unit No: __1____ Permit No: __12-0003____ Page __1__ of __1__

TAG PLACEMENT TAG REMOVAL Tag Equipment ID. Tag Color No. Hang Component Placed Verified Restore Restore Restored Order Position By By Order Position By 1J-SIA-HS001 Handswitch for 1 Yellow 1 N/A SIA-P02 (HPSI A pump) 1E-PBA-S03F, 4.16kV VAC RACKED 2 Red 3 Breaker for 1-M-SIA-P01 OUT 1P-SIA-V470 3 Red 6 CLOSED SIA-P02 Suction Valve 1P-SIA-UV-666, SIA-P02 Recirc DO NOT 4 Red 7 Valve OPERATE 1E-PHA-M3507, 480VAC 5 Breaker to SIA-UV666 (SIA-P02 Red 4 CLOSED Recirc Valve) 1J-SIA-HS-666, Handswitch for 6 SIA-UV666 (SIA-P02 Recirc Yellow 2 N/A Valve) 1P-SIA-V476, SIA-P02 7 Red 5 CLOSED Discharge Valve 1P-SIA-V981 8 Yellow 9 N/A SIA-P02 Seal Cavity Vent Valve 1P-SIA-V550 9 Yellow 8 N/A SIA-P01 Drain Valve CANDIDATE

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: Determine proper REP task, determine RCA entry requirements TASK STANDARD: Proper REP task determined, RCA entry requirements determined K/A: 2.3.7 K/A RATING: RO: 3.5 SRO: 3.6 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

NGW01, Initial Radiation Worker Practices SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Phil Capehart Date: 06/07/2005 Revised By: Alan Malley Date: 10/12/2010 Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

A copy of the Emergency Response REP 9-9999-0.

Page 2 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIATING CUE:

You have been directed to align SDC after control room fire.

The OSC has been manned and RP has mandated the use of the Emergency Response REP, 9-9999-0.

INITIATING CUE:

Your tasks are to locate the Emergency Response REP 9-9999-0 and determine:

1. the proper task for this evolution.

2. if a RP Pre-Job Brief is required prior to entering the RCA?

3. RP coverage during job performance.

4. dress-out requirements and dosimetry.

5. required EPD settings.

Page 3 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

Examinee reviews REP and survey Examinee determines entry on and determines task he can enter on. TASK1 is required.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Examinee determines if RP pre-job Determines must perform RP pre-Brief is required for entry into the job brief.

RCA.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.

Examinee determines RP coverage RP coverage is:

requirements during job

Intermittent performance.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam STEP CUE STANDARD

4.

Examinee determines dress-out PC and respiratory protection requirements and Dosimetry equipment requirements per direction from the RPM / RPC / RAC or designee.

Dosimetry -

Record TLD

EPD SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5.

Determine the REP required EPD Examinee determines EPD is settings. required with alarm settings of :

500mRem dose and

5,000 mRem/hr Dose Rate (as stated on the REP)

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparednessorganization for resolution.

NORMAL TERMINATION POINT Page 6 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam ANSWER KEY

1. Determine proper task for this evolution.

Proper task is TASK 1.

2. Is a RP Pre-Job Brief required prior to entering the RCA?

Yes.

3. Determine RP coverage during job performance.

Intermittent.

4. Determine dress-out requirements and dosemetry.

PC and respiratory protection equipment requirements per direction from the RPM / RPC

/ RAC or designee.

Dosemetry - Record TLD and EPD.

5. Determine required EPD settings.

Examinee determines EPD is required with Dose alarm settings of 500mRem and Dose Rate alarm setting of 5,000 mrem/hr.

(may list alarm warning at 400 mRem).

ANSWER KEY Page 7 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 0 06/08/05 6 New Admin Task JPM 1 7/11/05 NRC Revised to combine with JPM JP2 2 10/12/11 6 Revised to latest JPM format and REP REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam CANDIDATE INITIATING CUE:

You have been directed to align SDC after control room fire.

The OSC has been manned and RP has mandated the use of the Emergency Response REP, 9-9999-0.

INITIATING CUE:

Your tasks are to locate the Emergency Response REP 9-9999-0 and determine:

1. the proper task for this evolution.

2. if a RP Pre-Job Brief is required prior to entering the RCA?

3. RP coverage during job performance.

4. dress-out requirements and dosimetry.

5. required EPD settings.

USE THE ANSWER SHEET ON THE NEXT PAGE TO DOCUMENT YOUR ANSWERS.

CANDIDATE Page 9 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam Page 10 of 11

A-4 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam CANDIDATE

1. Determine the proper task for this evolution.

2. Is a RP Pre-Job Brief required prior to entering the RCA?

3. Determine RP coverage during job performance.

4. Determine dress-out requirements and dosemetry.

5. Determine required EPD settings.

CANDIDATE Page 11 of 11

PVNGS RADIATION EXPOSURE PERMIT REP Title REP Number EMERGENCY RESPONSE 9-9999 Rev. 00 Comments: JOB SCOPE: Emergency response.

Locations Buildings Elevations Rooms All buildings with RCAs ALL N/A Radiological Conditions Unit LHRA Work Area Dose Rates as communicated in Formal LHRA(s) N/A Pre-job briefing and recorded in RP Logbook.

Pre-job or Historical survey(s) attached. N/A N/A Review current work area survey(s). Prior to entering RCA N/A Tasks (1) LHRA - Emergency Plan implementation and Plant support tasks.

(2) LHRA - Emergency Plan implementation and Plant support tasks as authorized by RPM or RPC.

(3) VHRA - Life-saving actions and Plant protective measures as explicitly authorized by Site Emergency Coordinator.

(4) RA - Drill Support.

Global Instructions Prerequisites:

General:

RP Hold Points:

Attachments ALARA Plan 9-9999 Rev 00.pdf Classification / Estimates 1.16 Task: REACTOR OPERATION + SURVEIL REP Type: REP Status: Begin Date: Close On Date:

SREP, JHES Cat. 1 ACTIVE 7/31/2009 Estimated Dose: 100 mrem Estimated Hours: 735.00 Actual Dose: Actual Hours:

Prepared By: GYGER, JEFFREY M Leader:

Approvals Approver Title Name Date Department Leader MCDONNELL, JAMES P 08/28/2009 Section Leader WAGNER, MARTHA M 08/28/2009 Technician GYGER, JEFFREY M 08/28/2009 8/28/2009 11:49:30AM Page 1 of 1

PVNGS RADIATION EXPOSURE PERMIT Task Number One REP No.: 9-9999 Rev.: 00 Task

Description:

LHRA - Emergency Plan implementation and Plant support tasks.

INCLUDES:

Radiation exposure not to exceed PVNGS Administrative Hold Points.

HRA Entry: YES LHRA Entry: YES Minimum Available Dose: 200 mRem Dosimeter Settings Dose (mRem) Rate (mRem/hr) Time (HH:MM) Chirp Rate Warning: 400 Warning: 5000 Alarm: 500 Alarm: 5000 Alarm: 13:00 0.1 mrem Authorization List Required: NO Authorization Expires: NO Requirements Requirement Groups Requirement Descriptions ALARA Review NO PROTECTIVE AND MONITORING (PC, Other: -

Respiratory, Dosimetry) -- Additional exposure monitoring equipment per direction from the RPM / RPC /

RAC or designee.

-- PC and Respiratory protective equipment requirements per direction from the RPM / RPC / RAC or designee.

Review and implement REP Standard Instructions [75RP-9RP02, App. P, attached]

RP COVERAGE CONTINUOUS IN LHRA INTERMITTENT RPTs: Implement Radiological Controls Directions contained in associated ALARA Plan(s).

RP PRE-JOB BRIEFING YES Additional Instructions Prerequisites:

Review available radiological survey data with RP prior to entry.

Complete radiation protection briefing and obtain RP authorization prior to each RCA entry as directed by RPM, RPC, or RAC.

Entry to areas where no current radiological survey exists requires RP evaluation and authorization.

LHRA entry requires RPM, RPC, RAC, or authorized designee approval.

General:

Dosimetry requirements may be modified and EPD setpoints adjusted per RPM, RPC, RAC or authorized designee.

The 10 CFR 20.1201(a) Occupational Dose Limits apply to non-emergency conditions. All reasonable efforts should be made to observe these limits during emergency conditions.

RP Hold Points:

Attachments N/A 8/28/2009 12:07:18PM Page 1 of 4

PVNGS RADIATION EXPOSURE PERMIT Task Number Two REP No.: 9-9999 Rev.: 00 Task

Description:

LHRA - Emergency Plan implementation and Plant support tasks as authorized by RPM or RPC.

INCLUDES:

Potential to exceed PVNGS radiation exposure Administrative Hold Points anticipated.

HRA Entry: YES LHRA Entry: YES Minimum Available Dose: 0 mRem Dosimeter Settings Dose (mRem) Rate (mRem/hr) Time (HH:MM) Chirp Rate Warning: 800 Warning: 5000 Alarm: 1000 Alarm: 5000 Alarm: 13:00 10 mrem Authorization List Required: NO Authorization Expires: NO Requirements Requirement Groups Requirement Descriptions ALARA Review YES PROTECTIVE AND MONITORING (PC, Other: -

Respiratory, Dosimetry) -- Additional exposure monitoring equipment per direction from the RPM / RPC /

RAC or designee.

-- PC and Respiratory protective equipment requirements per direction from the RPM / RPC / RAC or designee.

-- Administration of Potassium Iodide (KI) for projected Thyroid CDE doses in excess of 25 REM as authorized by Emergency Coordinator.

Review and implement REP Standard Instructions [75RP-9RP02, App. P, attached]

RP COVERAGE CONTINUOUS IN LHRA INTERMITTENT RPTs: Implement Radiological Controls Directions contained in associated ALARA Plan(s).

RP PRE-JOB BRIEFING YES Additional Instructions Prerequisites:

Review available radiological survey data with RP prior to entry.

Complete radiation protection briefing and obtain RP authorization prior to each RCA entry as directed by RPM, RPC, or RAC.

An Emergency Classification of "Notification of Unusual Event" (NUE) or an Emergency requiring immediate attention or higher has been declared.

RPM or RPC authorization required prior to entry on this task.

Entry to areas where no current radiological survey exists requires RP evaluation and authorization.

General:

Dosimetry requirements may be modified and EPD setpoints adjusted per RPM, RPC, RAC or authorized designee.

The 10 CFR 20.1201(a) Occupational Dose Limits apply to non-emergency conditions. All reasonable efforts should be made to observe these limits during emergency conditions.

The RPM or RPC may authorize personnel radiation exposure within the Occupational Dose limits specified in 10 CFR 20.1201(a).

RP Hold Points:

Attachments N/A 8/28/2009 12:07:18PM Page 2 of 4

PVNGS RADIATION EXPOSURE PERMIT Task Number Three REP No.: 9-9999 Rev.: 00 Task

Description:

VHRA - Life-saving actions and Plant protective measures as explicitly authorized by Site Emergency Coordinator.

INCLUDES:

Potential to exceed 10CFR20 radiation exposure limits anticipated.

HRA Entry: YES LHRA Entry: YES Minimum Available Dose: 0 mRem Dosimeter Settings Dose (mRem) Rate (mRem/hr) Time (HH:MM) Chirp Rate Warning: 20000 Warning: 250000 Alarm: 25000 Alarm: 250000 Alarm: 13:00 10 mrem Authorization List Required: NO Authorization Expires: NO Requirements Requirement Groups Requirement Descriptions ALARA Review YES PROTECTIVE AND MONITORING (PC, Other: -

Respiratory, Dosimetry) -- Additional exposure monitoring equipment per direction from the RPM / RPC /

RAC or designee.

-- PC and Respiratory protective equipment requirements per direction from the RPM / RPC / RAC or designee.

-- Administration of Potassium Iodide (KI) for projected Thyroid CDE doses in excess of 25 REM as authorized by Emergency Coordinator.

Review and implement REP Standard Instructions [75RP-9RP02, App. P, attached]

RP COVERAGE CONTINUOUS RPTs: Implement Radiological Controls Directions contained in associated ALARA Plan(s).

RP PRE-JOB BRIEFING YES Additional Instructions Prerequisites:

Review available radiological survey data with RP prior to entry.

Complete radiation protection briefing and obtain RP authorization prior to each RCA entry as directed by RPM, RPC, or RAC.

An Emergency Classification of "Notification of Unusual Event" (NUE) or higher has been declared.

Emergency Coordinator has authorized entry on this task.

Entry to areas where no current radiological survey exists requires RP evaluation and authorization.

LHRA entry requires RPM, RPC, RAC or authorized designee approval.

General:

NOTE: Each emergency responder to obtain a pre-set fast response EPD [located in 140 auxiliary building RCA access control EPD racks, right hand column, labeled "Emergency use EPDs, REP 9-9999 Task 3"].

Dosimetry requirements may be modified and EPD setpoints adjusted per RPM, RPC, RAC, EC or authorized designee.

The 10 CFR 20.1201(a) Occupational Dose Limits apply to non-emergency conditions. All reasonable efforts should be made to observe these limits during emergency conditions.

The Emergency Coordinator, after consultation with Radiation Protection staff, must authorize any projected personnel radiation exposure in excess of the limits specified in 10 CFR 20.1201(a).

RP Hold Points:

Attachments N/A 8/28/2009 12:07:18PM Page 3 of 4

PVNGS RADIATION EXPOSURE PERMIT Task Number Four REP No.: 9-9999 Rev.: 00 Task

Description:

RA - Drill Support.

INCLUDES:

Drill support entry, radiation exposure not to exceed EPD setpoints.

HRA Entry: NO LHRA Entry: NO Minimum Available Dose: 15 mRem Dosimeter Settings Dose (mRem) Rate (mRem/hr) Time (HH:MM) Chirp Rate Warning: 12 Warning: 75 Alarm: 15 Alarm: 75 Alarm: 13:00 0.1 mrem Authorization List Required: NO Authorization Expires: NO Requirements Requirement Groups Requirement Descriptions ALARA Review YES PROTECTIVE AND MONITORING (PC, Other: -

Respiratory, Dosimetry) PC and Respiratory protection equipment requirements per direction from RPM

/ RPC / RAC or designee.

Review and implement REP Standard Instructions [75RP-9RP02, App. P, attached]

RP COVERAGE INTERMITTENT RPTs: Implement Radiological Controls Directions contained in associated ALARA Plan(s).

RP PRE-JOB BRIEFING YES Additional Instructions Prerequisites:

Review available radiological survey data with RP prior to entry.

Entry to areas where no current radiological survey exists requires RP evaluation and authorization.

General:

RP Hold Points:

NO HRA, LHRA, or VHRA entries on this task.

Attachments N/A 8/28/2009 12:07:18PM Page 4 of 4

Radiation Exposure Permits 75RP-9RP02 Revision 27 Appendix P Page 1 of 1 ( Sample )

Radiation Exposure Permit Standard Instructions All RCA entrants shall comply with the following PVNGS REP Standard Instructions except where REP provides specific alternate direction:

Monitoring and Protective Equipment:

Dosimetry - EPD/TLD Protective Clothing -

RP Authorized Work at CA Boundaries -

HCA / HPCA entry - Double Set Lab Coat and Gloves

Wet work - Wet set

CA entry - Full Set General:

Contact RP prior to each RCA entry.

Review current radiological survey data for work area prior to entry.

Notify RP prior to contaminated system opening, contaminated surface destroying activities, or insulation removal.

Stand by in low dose "Cold Area" when not actively involved in job.

To limit exposure to airborne radioactive material when working in High Contamination Areas, apply engineered controls as directed by RP. This typically involves misting work area surfaces and maintaining damp while working.

Work at CA Boundaries (e.g. Removing Tools, Equipment or Materials from CAs) requires RP Authorization.

Radiation Workers PC requirements may be modified with RP Leader authorization.

Personnel may enter a HCA / HPCA wearing a modified Double Set (consisting of a Full Set with outer shoe covers and gloves) to perform minor tasks with low probability of personnel contamination as determined and authorized by an RP Leader prior to each entry.

Within contaminated areas, RP authorization required for body position other than standing.

RP personnel shall observe the following REP Standard Instructions in addition to the above:

EPD dose rate setpoint may be adjusted as determined prudent by RP Leader based on review of work plan and radiological conditions. RP Leader to document all setpoint adjustments in RP electronic log.

Ensure worker dosimetry is positioned appropriately to monitor highest whole body exposure (Ref.

75RP-9RP16).

Task Specific TEDE /ALARA Screening required for: Work area conditions >500,000 dpm/100cm2

(), >500 dpm/100cm2 (), Contaminated system breach, Contaminated surface destroying activity or where a job/work area air sample yields >1.0 DAC (excluding Noble gas).

RP Technicians entering an HPCA / HCA to perform RP monitoring tasks with low probability of personnel contamination may wear a modified Double Set consisting of a Full Set with outer shoe covers and gloves.

RP Technicians, meeting the experience requirements of Section 4.5.2 of ANSI/ANS 3.1-1978, may relax RP Technicians Protective Clothing requirements for minor tasks with low probability of contamination.

If individual is unable to self monitor (read dosimeter) due to any instance including but not limited to:

telemetric dosimeter use, re-positioning of dosimetry by RP, multi-dosimeter use, or outer set of PCs being worn, then RP will assume exposure monitoring for that individual (Ref: 75RP-9RP16, 75RP-9RP29, 75DP-0RP02).

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 67 of 67

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ALARA PLAN Plan #: 9-9999 Revision #: 00

Title:

EMERGENCY RESPONSE Section One REP Task Number REP Task Description LHRA - Emergency Plan implementation and Plant support tasks.

1 LHRA - Emergency Plan implementation and Plant support tasks as authorized by 2 RPM or RPC.

VHRA - Life-saving actions and Plant protective measures as explicitly authorized 3 by Site Emergency Coordinator.

RA - Drill Support.

4 Radiological Controls Directions Task 1 2 3 4 _

PREREQUISITE:

HRA Entry - RP Pre-job brief and RP authorization required as directed by RPM, RPC, or 1 2 3 RAC.

LHRA / VHRA Entry - Formal RP Pre-job brief and RP authorization required as directed 1 2 3 by RPM, RPC, or RAC.

Fast entry EPDs are set to Task-2 set points.

2 The EDE / TEDE ratio will be used to track internal exposure.

1 2 3 Task 1 2 3 4 _

GENERAL:

Page 2 of 6

ALARA PLAN Plan #: 9-9999 Revision #: 00

Title:

EMERGENCY RESPONSE Section One Task 1 2 3 4 _ RP HOLD POINT:

Page 3 of 6

ALARA PLAN Plan #: 9-9999 Revision #: 00

Title:

EMERGENCY RESPONSE Section Two NOTE:

There are no REP requirements contained in this section. The following is provided as supplemental background information.

Operating Experience / Lessons Learned FUEL BUILDING RADIOLOGICAL CONDITIONS AFTER LOCA After a Loss of Coolant Accident (LOCA) a Recirculation Actuation Signal (RAS) will occur. Highly radioactive water will fill the suction lines to the Safety Injection pumps. Back-leakage from the suction lines past check valves to the Refueling Water Tank is assumed and this will cause radioactive material to build up in the Refueling Water Tank. The Refueling Water Tank is vented to the Fuel Building normal ventilation. The normal building ventilation exhaust is isolated after a Safety Injection Actuation Signal so the Refueling Water Tank radioactive material (airborne nobles gasses and iodines) will migrate into the Fuel Building and remain there.

After a design basis LOCA, the disposition to CRDR 97-Q-0265 indicates that the following tasks may need to be performed in the Fuel Building:

Obtaining iodine and particulate samples from RU-145/146

Restart of the spent fuel pool (PC) cooling pumps

Alignment of EW to the spent fuel pool heat exchangers

Makeup to the spent fuel pool

Periodic checks of spent fuel pool temperature and level Very high airborne levels may build up in the Fuel Building after a LOCA and continue to rise for several days after shutdown. Calculation 13-NC-CH-0314 rev 3 indicates 10,000 Rem/hr Thyroid CDE, 80 Rem/hr skin dose, and 7 Rem/hr TEDE are possible 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months after shutdown. Use of PCs, plastics, and SCBAs would be required for entries into the Fuel Building.

SPRAY POND VALVE OPERATION Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of a LOCA, Operations will need to open the Essential Spray Pond cross-tie valves. The valves are located at the Essential Spray Ponds. This job should be performed when the Essential Spray Ponds are upwind of the affected unit to minimize radiation exposure to Operations personnel.

Page 4 of 6

ALARA PLAN Plan #: 9-9999 Revision #: 00

Title:

EMERGENCY RESPONSE Section Three REP development Worksheet NOTE: Pre-job development information only. There are no REP requirements contained in this section.

ALARA Measures:

1. Temporary Shielding 12. Special Anti-Cs (beta protection or other)

2. Component/System Flushing 13. Reduced PC/Anticipated PCE authorization

3. Remote monitoring 14. TEDE ALARA Screening/Evaluation

4. Remote radiation survey techniques 15. Pre-Job Decontamination

5. Robotic support 16. Contamination fixatives

6. Planning Walk down with Work Group 17. Wrap/Sleeve/Cover components

7. Relocate Component (low dose area) 18. Contamination containment tent/enclosure

8. Minimize Crew size 19. HEPA filtration (ventilation syst. or vacuum)

9. Mock-up practice 20. Other:

10. Specialized Tooling [e.g., long-handled] 21. Other:

11. Re-schedule to optimal ALARA window 22. Other:

Comments:

Job Estimate:

Eff.

REP # Actual Actual Activity Description Location Craft # Entries mR/

Task Persons [hours] [mRem]

hr All 2009 Actual dose received All areas N/A N/A 126 682 N/A 0.000 All 2008 Actual dose received All areas N/A N/A 322 1,415 N/A 0.000 All 2007 Actual dose received All areas N/A N/A 227 873 N/A 0.001 All 2006 Actual dose received All areas N/A N/A 105 325 N/A 0.000 All 2005 Actual dose received All areas N/A N/A 119 391 N/A 0.000 All 2004 Actual dose received All areas N/A N/A 239 725 N/A 0.004

///////

TOTAL Averages 735 0.000

/

Developmental survey(s): N/A Page 5 of 6

ALARA PLAN Plan #: 9-9999 Revision #: 00

Title:

EMERGENCY RESPONSE Section Three REP development Worksheet NOTE: Pre-job development information only. There are no REP requirements contained in this section.

Estimate basis / assumptions: Historical averages from the last six years. Although little to no radiation exposure has been received over the last six years on this REP, 100 mRem is used in this estimate to allow minor surveillance activities.

Job-REP required (estimate >300 mRem) ? : YES NO New REP # :

Assign to existing REP # : 9-9999 Do identified ALARA Measures or Radiological Controls Directions necessitate a REP revision (new or upgraded; Protective, Surveillance, or Controls requirements to the existing REP/ALARA Plan) ? :

YES NO N/A Page 6 of 6

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1290020301, Conduct of Shift Operations TASK STANDARD: Determine Shift Manning Requirements K/A: 2.1.4 K/A RATING: RO: 3.3 SRO: 3.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

40DP-9OP02, Conduct of Shift Ops SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10/12/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

40DP-9OP02 available. This JPM was written using Revision 53 of 40DP-9OP02 This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Page 2 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

Page 3 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INITIAL CONDITIONS:

You are the CRS for a crew that is scheduled to take the Unit 1 dayshift tomorrow April 1st (new quarter).

Unit 1 is in Mode 1.

STA position will be filled by a non-licensed STA

Unit 2 is providing the Fire Team Advisor.

The crew was in the 4th week of the training cycle.

The training cycle completed 7 weeks ago, there was no evaluated scenario.

The table below reflects your crews status of Training and License Maintenance times.

Operator Training Shifts previous Quarter SM Attended all classes Every shift for the quarter in the SM Passed written exam position CRS Attended all classes One (1) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as CRS Passed written exam Remaining shifts in RO positions RO Attended all training Every shift in an RO positions Passed written exam CO Attended all classes Short term disability Passed written exam 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months shift as RO 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months shift as CO Four (4) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts as RO TRO Attended all classes Every shift in an RO positions Did not take written exam INITIATING CUE:

You are directed to determine:

1. The current status of the 5 licensed positions.

2. If the crew meets the procedural requirements to assume the shift.

3. If not, what position(s) need to be filled to meet these requirements?

Page 4 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 5 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Obtain 40DP-9OP02, Conduct of Obtain 40DP-9OP02, Conduct of Shift Operations. Shift Operations.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

3.6.1.1/.2 of 40DP-9OP02 Examinee determines that the TRO is not current in LOCT training due to An Operator's training is current not completing their training within 6 when all required material in an weeks of the end of the cycle.

LOCT Training Cycle is completed.

If any LOCT material is missed during a training cycle, make-up training shall be completed no later than 6 weeks from the end of the training cycle that the training was part of.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.

3.6.2 of 40DP-9OP02 Examinee determines that the CRS meets the requirements of at least one ACTIVE NRC Operators License 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift in the SRO position.

exists when an operator has a valid license and has actively performed the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

4.

3.6.2 of 40DP-9OP02 Examinee determines that the CO does not meet Watchstanding ACTIVE NRC Operators License Proficiency requirements as they did exists when an operator has a valid not stand five (5) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts n the license and has actively performed previous quarter.

the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

3.1 of 40DP-9OP02 Examinee determines that at least one more Reactor Operator is The minimum required shift crew required to meet minimum shift manning per Unit is: manning requirements.

1 Shift Manager.

1 Control Room Supervisor.

2 Reactor/Control Operators.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 7 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam ANSWER KEY INITIAL CONDITIONS:

You are the CRS for a crew that is scheduled to take the Unit 1 dayshift tomorrow April 1st (new quarter).

Unit 1 is in Mode 1.

STA position will be filled by a non-licensed STA

Unit 2 is providing the Fire Team Advisor.

The crew was in the 4th week of the training cycle.

The training cycle completed 7 weeks ago, there was no evaluated scenario.

The table below reflects your crews status of Training, License Maintenance times and Medical requirements.

Operator Training Shifts previous Quarter SM Attended all classes Every shift for the quarter in the SM Passed written exam position CRS Attended all classes One (1) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as CRS Passed written exam Remaining shifts in RO positions RO Attended all training Every shift in an RO positions Passed written exam CO Attended all classes Short term disability Passed written exam 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months shift as RO 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months shift as CO Four (4) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts as RO TRO Attended all classes Every shift in an RO positions Did not take written exam INITIATING CUE:

You are directed to determine:

1. The current status of the 5 licensed positions.

2. If the crew meets the procedural requirements to assume the shift.

3. If not, what positions need to be filled to meet these requirements?

Provide your answers on the attached sheet.

Page 8 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam ANSWER KEY

1. The current status of the 5 licensed positions.

Operator Qualified Qualified License Training? Maintenance time?

SM YES / NO YES / NO CRS YES / NO YES / NO RO YES / NO YES / NO CO YES / NO YES / NO TRO YES / NO YES / NO

2. Does the crew meet the procedural requirements to assume the shift.

YES / NO

3. If not, what position(s) need to be filled to meet these requirements?

There is only one qualified reactor Operator for the shift.

At least one more Reactor Operator is required to meet minimum shift requirements.

ANSWER KEY Page 9 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 10/12/2011 New JPM for 2012 NRC Initial Exam REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 10 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Candidate Handout INITIAL CONDITIONS:

You are the CRS for a crew that is scheduled to take the Unit 1 dayshift tomorrow April 1st (new quarter).

Unit 1 is in Mode 1.

STA position will be filled by a non-licensed STA

Unit 2 is providing the Fire Team Advisor.

The crew was in the 4th week of the training cycle.

The training cycle completed 7 weeks ago, there was no evaluated scenario.

The table below reflects your crews status of Training, License Maintenance times and Medical requirements.

Operator Training Shifts previous Quarter SM Attended all classes Every shift for the quarter in the SM Passed written exam position CRS Attended all classes One (1) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift as CRS Passed written exam Remaining shifts in RO positions RO Attended all training Every shift in an RO positions Passed written exam CO Attended all classes Short term disability Passed written exam 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months shift as RO 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months shift as CO Four (4) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts as RO TRO Attended all classes Every shift in an RO positions Did not take written exam INITIATING CUE:

You are directed to determine:

1. The current status of the 5 licensed positions.

2. If the crew meets the procedural requirements to assume the shift.

3. If not, what position(s) need to be filled to meet these requirements?

Provide your answers on the attached sheet.

Page 11 of 12

A-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Candidate Handout

1. The current status of the 5 licensed positions.

Operator Qualified Qualified License Training? Maintenance time?

SM YES / NO YES / NO CRS YES / NO YES / NO RO YES / NO YES / NO CO YES / NO YES / NO TRO YES / NO YES / NO

2. Does the crew meet the procedural requirements to assume the shift.

YES / NO

3. If not, what positions need to be filled to meet these requirements?

Candidate Handout Page 12 of 12

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 15 of 63 Revision Conduct of Shift Operations 40DP-9OP02 55 3.0 SHIFT MANNING 3.1 Shift Composition 3.1.1 The minimum required shift crew manning is

1 Shift Manager per Unit.

1 Control Room Supervisor per Unit.

2 Reactor/Control Operators per Unit.

In addition to the 2 Reactor/Control Operators per Unit, one Unit shall have an additional Reactor/Control Operator (may be filling a Nuclear Auxiliary Operator position) to fulfill the requirement of Site Fire Team Advisor.

4 Auxiliary Operators per Unit.

1 Auxiliary Operator for Area 9. (Unit 1 only)

At least 1 Auxiliary Operator per Site crew will be Radwaste Operator qualified.

1 Shift Technical Advisor (STA) per Unit or 2 STAs for the site and 1 NRC Communicator (RO or SRO not assigned a watchstation).

3.1.2 Except for the Shift Manager, the composition of the shift crew may be one less than the minimum manning required for sections 3.1.1 for a period not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore crew manning to the minimum requirements of section 3.1.1 This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crew member being late or absent.

NOTE ----------------------------------------

Within the unit is defined as the area containing each unit bounded by the protected area fence and the fences running north and south between the spray ponds and the adjacent unit.

3.1.3 At least 2 Reactor/Control Operators and 3 Auxiliary Operators shall be present within each unit at all times.

3.1.4 Auxiliary Operators are considered to be part of the shift crew composition if they are on site and in direct communication with the Control Room via radio or pager 3.1.5 Conduct of all core alterations shall be observed and directly supervised by a Refueling SRO/LSRO who has no other concurrent responsibilities during this operation.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 of 63 Revision Conduct of Shift Operations 40DP-9OP02 55 3.1.6 Each on-shift crew shall have a designated communicator. This individual will be stationed when continuous communications with the NRC is required (Alert or higher) or requested and shall be an STA or another Licensed Individual. This communicator is independent of and in addition to the Emergency Plan (STSC) Communicator.

3.2 Staffing Requirements for the Control Room 3.2.1 When fuel is in the vessel, at least one Licensed Individual shall be in the At the Controls Area shown below.

Control Room Layout AUXILIARY BLDG CABLE HVAC CABLE RADWASTE SHAFT SHAFT SHAFT CORRIDOR BLDG BLDG B06 B07 B05 SM OFFICE B04 AT THE CONTROLS Briefing AREA Area STSC B03 B02 B01 CABLE RISER SHAFT HVAC HVAC SHAFT SHAFT DOWN UP DIESEL GENERATOR BLDG 3.2.2 The RO shall not leave the At the Controls Area without proper relief except during an emergency effecting plant safety which requires entering other areas within the Control Room. At least one RO/CO or CRS is expected to be in the At the Controls Area and normally in the B02 to B06 horseshoe area.

3.2.3 The CRS should normally be in a position to visually observe the Control Boards.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 18 of 63 Revision Conduct of Shift Operations 40DP-9OP02 55 3.6 Licensed Operator Watchstanding Proficiency 3.6.1 A VALID NRC Operators License exists when the holder of that license is current in Licensed Operator Continuing Training (LOCT).

3.6.1.1 An Operator's training is current when all required material in an LOCT Training Cycle is completed. If any LOCT material is missed during a training cycle, make-up training shall be completed no later than 6 weeks from the end of the training cycle that the training was part of.

3.6.1.2 If the operator fails to make up the classroom training and simulator training within 6 weeks of the end of the training cycle, the operator shall be removed from license duties until the make-up training is completed.

3.6.2 An ACTIVE NRC Operators License exists when an operator has a valid license and has actively performed the functions of an operator or senior operator on a minimum of five 12-hour shifts per calendar quarter.

Actively Performed means that the operator held a position on the shift crew that required the individual to be licensed as defined in the Technical Specifications and that the operator carried out and was responsible for the duties covered by that position.

For maintenance of an active SRO license any shift spent in either the SM or CRS position will be credited.

An SRO must stand at least one complete shift per calendar quarter in an SRO-only supervisory position. The remainder of the shifts required in a calendar quarter may be performed in either a credited SRO or RO position.

For time to be credited it must be a continuous shift (i.e., 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of watch shift responsibilities spent on each of 3 different shifts does not equal one 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift).

Overtime may be credited if the overtime work is in a position appropriately credited for watchstanding proficiency. Overtime as an extra helper after the official watch has been turned over to another watchstander does not count toward proficiency time.

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1270130401 Implement reactor coolant system draining operations TASK STANDARD: Determine if time shutdown is met and makeup flow to prevent boiling K/A: 2.1.20 K/A RATING: RO: 4.6 SRO: 4.6 K/A: 2.1.25 K/A RATING: RO: 3.9 SRO: 4.2 APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9ZZ16, RCS Drain Operations; Unit 3 Safety Analysis Operational Data Manual SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 09/08/2009 Revised By: Alan Malley Date: 07/07/2011 Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

40OP-9ZZ16, RCS Drain Operations available. This JPM was written using Revision 71 of 40OP-9ZZ16. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Unit 3 Safety Analysis Operational Data Manual available. This JPM was written using Revision 4 of the Unit 3 Safety Analysis Operational Data Manual. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Page 2 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 3 was shutdown 91 hours0.00105 days 0.0253 hours 1.50463e-4 weeks 3.46255e-5 months ago.

The Decay heat load is 15.5 MWs.

The crew is preparing to drain the RCS for a Hot Mid-Loop.

You are an extra SRO in Unit 3.

It is anticipated that the crew will have to reduce Shutdown Cooling flow to 3780 gpm during Mid-Loop operations.

RWT temperature as read on 1-J-CHN-TT-210 is 70 °F.

EW Heat Exchanger temperature as read on 3-J-EWN-TT-083 and TT-084 is 86 °F.

INITIATING CUE:

The Control Room Supervisor has directed that you perform the following two tasks:

1. Perform prerequisite step 7.2.12 of 40OP-9ZZ16 (RCS Drain Operations) to determine if Essential Cooling Water temperature vs. Time Post Shutdown requirements of the Safety Analysis Operational Data portion of the Core Data Book is met before SDC flow is lowered to 3780 gpm.

2. Perform prerequisite step 7.2.13 of 40OP-9ZZ16 (RCS Drain Operations) to determine makeup flow rate required to prevent boiling using HPSI cold leg injection.

Provide your answers below:

1. Prerequisite step 7.2.12 is met / is not met.

(Circle one)

2. Required makeup flow to prevent boiling - __________ gpm per cold leg.

Page 3 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

Step 7.2.12 of 40OP-9ZZ16: Examinee refers to the Safety Analysis Operation Data Manual to Essential Cooling Water temperature verify Essential Cooling Water vs. Time Post Shutdown temperature Vs Time Post Shutdown requirements of the Safety Analysis requirements are met.

Operational Data portion of the Core Data Book are met before SDC flow Examinee may refer to step 4.2 of is lowered to 3780 gpm. REFER TO 40OP-9ZZ16.

Step 4.2 for additional information Examinee determines that for an EW temperature of 86 °F the time for shutdown has to be 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months , therefore being 91 hours0.00105 days 0.0253 hours 1.50463e-4 weeks 3.46255e-5 months after shutdown does meet the requirements.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam STEP CUE STANDARD

2.

Step 7.2.13 of 40OP-9ZZ16: Examinee determines HSPI Cold leg injection flow should be ~ 212 gpm Makeup flow rate required to prevent (+ 10 gpm) per cold leg using boiling has been determined by one Appendix W and the 70°F line for of the following: 15.5 MWs.

Hot Mid Loop (pre core offload)

This is applicable for HPSI makeup via the cold leg and should be N/Ad if this makeup path is not selected.

Decay heat load, in MW, has been determined. Target decay heat load is equal to or less than 16.0 MW.

Required HPSI makeup flow per loop has been determined from Appendix W - Makeup Flow to Prevent Boiling.

(REFER TO Step 4.30 for additional discussion)

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 6 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 07/07/2011 6 Converted from a NRC Initial License Exam JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 7 of 8

A-6 PVNGS JOB PERFORM ANCE M EASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 3 was shutdown 91 hours0.00105 days 0.0253 hours 1.50463e-4 weeks 3.46255e-5 months ago.

The Decay heat load is 15.5 MWs.

The crew is preparing to drain the RCS for a Hot Mid-Loop.

You are an extra SRO in Unit 3.

It is anticipated that the crew will have to reduce Shutdown Cooling flow to 3780 gpm during Mid-Loop operations.

RWT temperature as read on 1-J-CHN-TT-210 is 70 °F.

EW Heat Exchanger temperature as read on 3-J-EWN-TT-083 and TT-084 is 86 °F.

INITIATING CUE:

The Control Room Supervisor has directed that you perform the following two tasks:

1. Perform prerequisite step 7.2.12 of 40OP-9ZZ16 (RCS Drain Operations) to determine if Essential Cooling Water temperature vs.

Time Post Shutdown requirements of the Safety Analysis Operational Data portion of the Core Data Book is met before SDC flow is lowered to 3780 gpm.

2. Perform prerequisite step 7.2.13 of 40OP-9ZZ16 (RCS Drain Operations) to determine makeup flow rate required to prevent boiling using HPSI cold leg injection.

Provide your answers below:

1. Prerequisite step 7.2.12 is met / is not met.

(Circle one)

2. Required makeup flow to prevent boiling - __________ gpm per cold leg.

Page 8 of 8

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 22 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71 4.0 PERSONAL INDOCTRINATION 4.1 Plant activities may preclude the performance of specific steps in the order presented. The Shift Manager may re-sequence or delay steps as necessary to accomplish the procedure objectives, except for those portions of the procedure requiring the securing of plant draining at specified plant elevations since these will be used to allow for entire RCS pressure equalization/level stabilization.

4.2 The analyses that supports SDC operation at reduced flow rate (3780 gpm) have been revised to reduce conservatism and permit more expedient entry into Mid-Loop.

Table 2.8.1 has been added to the Safety Analysis Operational Data portion of the Core Data Book which defines the criteria necessary to reduce SDC flow.

Supplements to Table 2.8.1 for specific unit and outage applications may be applicable and incorporated in the SAOD.

SAOD Table 2.8.1 is applicable anytime the plant is in mode 5 or mode 6 and it is required to reduce SDC flow. The table is independent of RCS level.

This table shows the required number of hours post shutdown, as a function of Essential Cooling Water temperature, after which a single train of SDC can provide sufficient cooling at reduced flow (i.e.: 3780 gpm), to maintain the RCS at or below 135°F in accordance with LCO 3.4.8, LCO 3.9.4, and LCO 3.9.5.

Flow may be reduced to 3780 gpm to preclude vortexing at the SDC suction nozzle during Mid-Loop operations.

Normal SDC flow is defined by Tech Specs as 3780 to 5000 gpm (indicated). In most situations, SDC flow is maintained at or near 4,000 gpm. If Operations had 1 train SDC available and elected to reduce flow to 3780 shortly after shutdown, it is likely that RCS temperature will increase. Compensatory action is to increase SDC flow.

There are some situations where SDC flow could NOT be significantly increased. For example we have administrative controls preventing SDC flow greater than 4150 gpm while in mid-loop. The analyses supporting the data in the SAOD demonstrate that the SDC will provide sufficient cooling capacity thereby providing some assurance that the plant will be cooled in lieu of increasing flow.

By meeting the SAOD Essential Cooling Water temperature/time post shutdown requirements, there is assurance that the core will be maintained at refueling mode temperature (135°F) in the unlikely event that SDC flow is reduced and Operations does NOT have to ability to increase SDC flow to mitigate an increasing RCS temperature.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 74 of 335 Revision RCS Drain Operations 40OP-9ZZ16 71

____ 7.2.10 Verify the Containment Equipment Hatch is in place and closed prior to entering Reduced Inventory Operations.

____ 7.2.11 The Mid-Loop Operations Coordinator is stationed and the requirements of 40DP-9ZZ30, Reduced Inventory Operations are met. This step does not need to be completed until just prior to lowering RCS level below 111 ft. as indicated by the RWLIS.

____ 7.2.12 Essential Cooling Water temperature vs. Time Post Shutdown requirements of the Safety Analysis Operational Data portion of the Core Data Book are met before SDC flow is lowered to 3780 gpm. REFER TO Step 4.2 for additional information

____ 7.2.13 Makeup flow rate required to prevent boiling has been determined by one of the following:

Hot Mid Loop (pre core offload) Cold Mid Loop (post core reload)

____ This is applicable for HPSI ____ This is applicable for HPSI makeup via the cold leg and makeup via the cold leg and should be N/Ad if this makeup should be N/Ad if this makeup path is not selected. path is not selected NOTE ____ Determine hours after shutdown.

RCP SEAL REPLACEMENT ONLY:

Recent RETRAN analysis has shown that with RCS level equal to or greater than 10% (117 ft.)

and SG tubes full, there is sufficient inventory available to mitigate a Loss of SDC as long as decay heat is less than 19.4 MW (48 hrs shutdown) and the pressurizer manway is removed. The 16 MW limit may be N/Ad.

____ Decay heat load, in MW, has been ____ REFER TO 40EP-9EO10, determined. Target decay heat Standard Appendices, Appendix load is equal to or less than 16.0 203 to determine required makeup MW. flow.

____ Required HPSI makeup flow per ____ Required HPSI makeup flow per loop has been determined from loop has been determined from Appendix W - Makeup Flow to Appendix W - Makeup Flow to Prevent Boiling. (REFER TO Step Prevent Boiling. (REFER TO Step 4.30 for additional discussion) 4.30 for additional discussion) 7.2.13.1 Log required makeup flow below.

Reqd HPSI Makeup __________ gpm.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL 40OP-9ZZ16 Appendix W Page 1 of 1 RCS Drain Operations Revision 71 Page 314 of 335 Appendix W - Makeup Flow to Prevent Boiling 1.0 General Information 1.1 This table correlates decay heat to the required HPSI flow to EACH loop to prevent boiling in the RCS.

Minimum Flow Requirements to Prevent Core Boiling 350 TRWT = 100oF 300 TRWT = 90oF TRWT = 80oF TRWT = 70oF 250 HPSI Flow per Cold-Leg (gpm) 200 150 100 50 0

20.00 18.00 16.00 14.00 12.00 10.00 8.00 6.00 4.00 Decay Heat (MW)

ANALYSIS TITLE SHEET Page _____ 1 43 of _____

Document Contains: ANALYSIS NUMBER REV.

Proprietary Information? Yes No X SAOD Unit 3 4 Association Changes? Yes No X QR NQR X Analysis

Title:

SAOD 3990 MWt - Unit 3 Analysis

Description:

This document supersedes revision 3 of the SAOD Unit 3 manual in SWMS.

due to the implementation of the replacement steam generators and power uprate per ACT 3105774. .

This revision also updates references.

Revision 4 Dependent Engineer N/A Date Responsible Engineer Arshad Taufiq, Digitally signed by Taufiq, Arshad M (Z93839)

DN: cn=Taufiq, Arshad M(Z93839),

Date Taufiq Arshad M email=Arshad.Taufiq@aps.com Reason: I am the author of this document (Z93839) Date: 2007.12.13 15:52:25 -07'00' C

R R Operations (STAs)

O E N/A Date S V S I E

Outage Mgmt D W N/A I Date S

C I NED P N/A Date L

I N

E Other (Ops Standards)

N/A Date Mentor N/A Date Digitally signed by Kilic, Arif N Independent Reviewer Ness Kilic, Arif (Z99533)

DN: cn=Kilic, Arif N(Z99533),

email=Arif.Kilic@aps.com Date Kilic N(Z99533) Reason: I have reviewed this document Date: 2007.12.13 16:15:02 -07'00' Digitally signed by Blackmore, Responsible Section Leader Brian Blackmore, Brian S(Z99910)

DN: cn=Blackmore, Brian S BlackmoreBrian S (Z99910)

Date Reason: Flagged TA section leader (Z99910) Date: 2007.12.13 16:32:44

-07'00' Responsible Department Leader N/A Date NUCLEAR FUEL MANAGEMENT ANALYSES CONTROL, 05DP-0NF09

By: Arshad Taufiq Safety Analysis Operational Data SAOD 3990 MWt Manual 3990 MWt Rev. 04 Reviewer: Ness Kilic Page 2 of 43 ANALYSIS

SUMMARY

SHEET Description (continued from N/A Analysis Title Sheet)

The SAOD manual simply documents the results from various calculations and analysis packages in a convenient document readily accessible to Opera-Conclusion tions. No calculations are performed in this manual and no computer codes are used for this manual. The conclusions drawn in the various referenced calculations remain valid.

Contingency Clearing Org.

None Contingencies Associations Procedural not required at this time.

Type Number Description Update the Unit 3 SAOD for Power Uprate/Steam Generator Incorporated ACT 3105774 Replacement. This ACT is a mode Impacts 2 restraint for Unit 3 restart Document No. Revision Status SAOD Unit 3 3 Superceded Superseded or Archived Documents Type Number Description of Impact/Change (ACT, DBCP etc.)

Initiated Impacts or None Changes to Design Documents

By: Arshad Taufiq Safety Analysis Operational Data SAOD 3990 MWt Manual 3990 MWt Rev. 04 Reviewer: Ness Kilic Page 3 of 43 Analysis Revision History Sheet Revision 4 Updates the Unit 3 SAOD for Power Uprate/Steam Generator Replacement per ACT 3105774 and updates references Revision 3 Provided clarification for RCS loop check valve restric-tions and updated references.

Revision 2 Clarification was provided to allow emergent RCS loop check valve work during U3R11.

Revision 1 Steam Generator manway and nozzle dam operating guid-ance were clarified in this revision.

Revision 0 This document superseded revision 20 of the SAOD manual in SWMS. This document replaced the old SAOD format.

The update was done in preparation for SGR/PUR as requested by Operations and to reflect new decay heat values. In addition, the stagnant boron mixing section and table 2.7.1 were deleted (no longer used).

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 4 of 43 Table of Contents Section ........................................................................................................................... Page 1.0 OBJECTIVE ......................................................................................................................5 2.0 METHOD OF SOLUTION AND RESULTS..................................................................5 2.1 Decay Heat Constraints for Outages....................................................................5 2.2 Midloop Operation ................................................................................................7 2.3 RCS Drained to Reactor Vessel Flange with Reactor Head Removed ...........13 2.4 RCS Drained to Reactor Vessel Flange with Reactor Head Installed ............19 2.5 RCS Filled to 120 (Vessel Full) and Reactor Vessel Head Installed ..............25 2.6 RCS Filled to Refueling Level Operation ..........................................................31 2.7 Spent Fuel Pool Operation ..................................................................................35 2.8 Minimum Time to Reduced Flow SDC Operations..........................................36 2.9 RCS Forced Flow and RWT Temperature Requirements ..............................38 3.0 IMPACT REVIEW..........................................................................................................40

4.0 REFERENCES

.................................................................................................................40 Appendix A 10CFR 50.59 Applicability Determination....................................................41 Appendix B Reload Design Verification............................................................................41 Appendix C Design Docuement Interfaces and Associatiosn .................................. . 41 Appendix D Design Verfication........................................................................................42

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 5 of 43 1.0 OBJECTIVE The Safety Analysis Operational Data (SAOD) manual provides information to Operations and Outage Planning for certain outage shutdown activities. Specifically, this manual provides outage decay heat values, reactor coolant system expected heat up rates, outage time to boil values, outage time to core uncovery values, makeup flow for boiloff, minimum time to reduced flow shutdown cooling operations, and RCS forced flow and RWT temperature requirements to maintain sub-cooled conditions following a loss of shutdown cooling (HPSI once-through cooling).

This information is provided to clarify the time constraints needed for the refueling outage activi-ties that are adversely affected by decay heat following reactor shutdown. It is essential that these constraints be observed in order to ensure that the unit remains in an analyzed condition for postu-lated events involving a loss of shutdown cooling at reduced inventories.

Questions concerning SAOD Sections 1.0 through 2.7 should be referred to the Transient Analysis section leader. Questions regarding SAOD Sections 2.8 through 2.9 should be referred to the Design Mechanical NSSS section leader.

2.0 METHOD OF SOLUTION AND RESULTS The SAOD manual simply documents the results from various calculations and analysis packages in a convenient document readily accessible to Operations. No calculations are performed in this manual and no computer codes are used for this manual. The assumptions and input data are docu-mented in the source calculations which are referenced with each table provided.

2.1 Decay Heat Constraints for Outages The following constraints are required to support the assumptions in the Loss of Shutdown Cooling (LSDC) analyses. (Reference 2, 7, & 12)

The pressurizer manway may be removed to provide a hot leg vent path, when the reactor vessel is full (120 ft. elevation) and core decay heat rate is < 20 MW. At 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months post-shutdown, the decay heat rate is not expected to exceed 20.021 MW for a rated thermal power of 3990 MWt. A LSDC event with the pressurizer manway removed and Reactor Coolant System level at 131 ft. 5 inches (~ 50% pressurizer level) would not result in uncovering the reactor core for at least a 1-hour period.

RCS drain operations should not commence unless indicated RWT level is > 73% (>

50% for cold core post refueling conditions).

1-hour after SDC is lost, it is assumed that operators will have reestablished either SDC or forced flow cooling of the RCS using High Pressure Safety Injection (HPSI). The 1-hour period is based on the anticipated maximum time that it may take to place a Gas Turbine Generator (GTG) in service.

1. Even though 20.02 is slightly larger than 20 MW, the 0.1% difference is considered negligible in comparison to the analytical conservatisms described in reference 2.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 6 of 43

The reactor vessel may be drained down (to the 1038 elevation), when the pressur-izer manway is removed and the core decay heat rate is < 20 MW. This occurs at a time > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after shutdown. With the pressurizer manway removed and the RCS drained to the 1038 elevation (with water in the steam generator tubes), a LSDC event would not result in uncovering of the reactor core for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , even if no credit was given for gravity feed or HPSI during that hour.

The reactor vessel may be drained down to midloop (1016 to 1031) when the pressurizer manway is removed and the core decay heat is < 16 MW. A decay heat of 16 MW occurs 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months after plant shutdown. With the Unit at midloop no credit can be given for liquid in the SG tubes. A LSDC event would not result in uncovering of the reactor core for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

The steam generator manways may be removed and nozzle dams installed when the core decay heat is < 16 MW. This occurs at t > 87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months after shutdown. If a LSDC event were to occur while the plant was in this configuration, then operator intervention would be critical to achieve a 1-hour coping period. For this level of decay heat the analysis assumes the following:

1 For hot core mid-loop the hot leg steam generator (SG) manways should be removed close to the same time without delay (minimizing the time reduces steam entrainment concerns) with the man-way for the hot leg used for gravity feed removed last.

2 The hot leg nozzle dams should be installed sequentially without delay (minimizing the time reduces potential steam entrainment inventory losses) with the nozzle dam on the leg used for gravity feed installed first.

3 Both cold leg nozzle dams should be installed on a SG before installation of the hot leg dam. Addi-tionally, the last nozzle dam installed should be on the hot leg opposite that to which RWT gravity feed is aligned. Installing cold leg dams prior to hot leg dams ensures a flow path for HPSI once through cooling.

After nozzle dam installation, the RCS may be reflooded as high as elevation 120 ft.

(approximately 20% pressurizer level). At a decay heat rate of 16 MW and nozzle dams installed, a LSDC event will not result in an RCS peak pressure that exceeds the nozzle dams rating of 50 psig (i.e., ASME B&PV Code Level D Service Limit), if RCS level is at or below the 120 ft. elevation. This conclusion is valid both for early initiation of cold leg HPSI flow (at 10 minutes), or for hot leg gravity feed for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months followed by cold leg HPSI.

If plant operators initiate gravity feed from the RWT to the RCS in response to a LSDC event, the DC-powered valve (J-SIC-UV-0653 or J-SID-UV0654, depending upon the train selected) should initially be throttled approximately 30% open and then throttled as needed so that RWT level decreases approximately 3% every 15 minutes.

No cold leg openings (e.g. RCP impeller work or shaft replacement, RCS cold leg check valves SIEV2x7) before decay heat rate is < 14 MW. This occurs around 118 hours0.00137 days 0.0328 hours 1.951058e-4 weeks 4.4899e-5 months after shutdown.

RCP seal work when RCS level is above the bottom of the hot leg is allowed only if main-tenance uses a shaft blocking device to prevent lifting the shaft and creating a large cold leg breach.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 7 of 43 2.2 Midloop Operation NOTES 2.2.0 Key Reactor Core Parameters Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening The key reactor core parameters following a loss of shutdown cooling (SDC) with a large (RCP impeller) or small (RCP seal) cold leg opening are based in part on a computer analysis using the RETRAN code.

Decay heat power is based on Branch Technical Position 9-2 utilizing a 550 EFPD cycle length at 100% power. (3990 MWt)(Reference TA-13-C00-1999-009)

Time to boil is based on the time for the water in the vessel to reach 210 0F. This is a function of decay heat, mass of water in vessel and initial RCS bulk temperature (inlet Shutdown Cooling Heat Exchanger temperature). It is determined by subtracting the RCS bulk temperature from 210 0F , and then dividing by the heatup rate.

Heatup rate is determined by dividing the decay heat by the specific heat capacity for water and by the mass of water available in the vessel at the start of the event.

Time to core uncovery is conservatively assumed to be the amount of time it takes to boil off the water volume below the bottom of the hot leg and above the top of the core. The time associated with the pressurization effects, which result in water lost out the cold leg opening, is neglected. The water lost out the cold leg opening is conservatively assumed to result in a water level at the bottom of the hot leg. Thus, time to core uncovery is a function of decay heat, this volume of water and the pressure over the water. Time to core uncovery does not include the time associated with reaching the boiling temperature.

Makeup rate is the amount of flow required to reach the core to compensate for water loss through boil off. Note that this is the volume that must be delivered to the core in order to maintain constant inventory. Flow diverted out any cold leg opening must be accounted for (i.e. flowrate indications may not be actual flowrates reaching the core).

NOTE: VALUES NOT EXPLICITLY FOUND IN THE TABLES SHALL BE DETERMINED VIA LINEAR INTERPOLATION PERFORMED BY THE SHIFT TECHNICAL ADVISOR

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 8 of 43 TABLE 2.2.1 Key Reactor Core Parameters Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening Prior to Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MW th) (days) (MW th) 1.0 24.44 8.97 173.5 10 10.42 3.82 74.0 2.0 20.02 7.35 142.1 11 10.05 3.69 71.4 3.0 17.25 6.33 122.5 12 9.72 3.57 69.0 3.5 16.19 5.94 114.9 13 9.43 3.46 67.0 4.0 15.30 5.62 108.6 14 9.16 3.36 65.0 4.5 14.54 5.34 103.2 15 8.92 3.27 63.3 5.0 13.88 5.09 98.5 16 8.70 3.19 61.8 5.5 13.31 4.88 94.5 17 8.48 3.11 60.2 6.0 12.83 4.71 91.1 18 8.29 3.04 58.9 6.5 12.39 4.55 88.0 19 8.10 2.97 57.5 7.0 12.01 4.41 85.3 20 7.93 2.91 56.3 7.5 11.67 4.28 82.9 25 7.15 2.62 50.8 8.0 11.37 4.17 80.7 30 6.53 2.40 46.4 8.5 11.10 4.07 78.8 40 5.59 2.05 39.7 9.0 10.85 3.98 77.0 50 4.92 1.81 34.9 9.5 10.62 3.90 75.4 80 3.76 1.38 26.7 Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 9 of 43 TABLE 2.2.2 Key Reactor Core Parameters Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening After Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MWth) (days) (MWth) 1.0 19.06 7.00 135.3 10 8.13 2.98 57.7 2.0 15.62 5.73 110.9 11 7.84 2.88 55.7 3.0 13.46 4.94 95.5 12 7.58 2.78 53.8 3.5 12.63 4.63 89.7 13 7.36 2.70 52.2 4.0 11.93 4.38 84.7 14 7.14 2.62 50.7 4.5 11.34 4.16 80.5 15 6.96 2.55 49.4 5.0 10.83 3.97 76.9 16 6.79 2.49 48.2 5.5 10.38 3.81 73.7 17 6.61 2.43 47.0 6.0 10.01 3.67 71.1 18 6.47 2.37 45.9 6.5 9.66 3.55 68.6 19 6.32 2.32 44.9 7.0 9.37 3.44 66.5 20 6.19 2.27 43.9 7.5 9.10 3.34 64.6 25 5.58 2.05 39.6 8.0 8.87 3.25 63.0 30 5.09 1.87 36.2 8.5 8.66 3.18 61.5 40 4.36 1.60 31.0 9.0 8.46 3.11 60.1 50 3.84 1.41 27.2 9.5 8.28 3.04 58.8 80 2.93 1.08 20.8 Current outage schedules do not support reloads in less than 10 days.

Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 10 of 43 Ness Kilic TABLE 2.2.3 Time to Boil Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening Prior to Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 12.3 11.1 10.0 8.9 8.4 7.8 10 28.8 26.1 23.5 20.9 19.6 18.3 2.0 15.0 13.6 12.2 10.9 10.2 9.5 11 29.8 27.1 24.4 21.7 20.3 19.0 3.0 17.4 15.8 14.2 12.6 11.8 11.1 12 30.8 28.0 25.2 22.4 21.0 19.6 3.5 18.5 16.8 15.1 13.5 12.6 11.8 13 31.8 28.9 26.0 23.1 21.7 20.2 4.0 19.6 17.8 16.0 14.2 13.4 12.5 14 32.7 29.7 26.8 23.8 22.3 20.8 4.5 20.6 18.7 16.9 15.0 14.1 13.1 15 33.6 30.5 27.5 24.4 22.9 21.4 5.0 21.6 19.6 17.7 15.7 14.7 13.7 16 34.5 31.3 28.2 25.1 23.5 21.9 5.5 22.5 20.5 18.4 16.4 15.4 14.3 17 35.3 32.1 28.9 25.7 24.1 22.5 6.0 23.4 21.2 19.1 17.0 15.9 14.9 18 36.2 32.9 29.6 26.3 24.7 23.0 6.5 24.2 22.0 19.8 17.6 16.5 15.4 19 37.0 33.6 30.3 26.9 25.2 23.5 7.0 25.0 22.7 20.4 18.2 17.0 15.9 20 37.8 34.4 30.9 27.5 25.8 24.1 7.5 25.7 23.3 21.0 18.7 17.5 16.3 25 41.9 38.1 34.3 30.5 28.6 26.7 8.0 26.4 24.0 21.6 19.2 18.0 16.8 30 45.9 41.7 37.6 33.4 31.3 29.2 8.5 27.0 24.5 22.1 19.6 18.4 17.2 40 53.6 48.7 43.9 39.0 36.6 34.1 9.0 27.6 25.1 22.6 20.1 18.8 17.6 50 60.9 55.4 49.8 44.3 41.5 38.8 9.5 28.2 25.7 23.1 20.5 19.2 18.0 80 79.7 72.5 65.2 58.0 54.4 50.7 Source of Data: SA-13-C00-1996-004, Appendix A

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 11 of 43 Ness Kilic TABLE 2.2.4 Time to Boil Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening After Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 15.7 14.3 12.9 11.4 10.7 10.0 10 36.9 33.5 30.2 26.8 25.1 23.5 2.0 19.2 17.4 15.7 14.0 13.1 12.2 11 38.2 34.8 31.3 27.8 26.1 24.3 3.0 22.3 20.3 18.2 16.2 15.2 14.2 12 39.5 35.9 32.3 28.8 27.0 25.2 3.5 23.7 21.6 19.4 17.3 16.2 15.1 13 40.7 37.0 33.3 29.6 27.8 25.9 4.0 25.1 22.8 20.5 18.3 17.1 16.0 14 42.0 38.1 34.3 30.5 28.6 26.7 4.5 26.4 24.0 21.6 19.2 18.0 16.8 15 43.1 39.2 35.2 31.3 29.4 27.4 5.0 27.7 25.2 22.7 20.1 18.9 17.6 16 44.2 40.2 36.1 32.1 30.1 28.1 5.5 28.9 26.2 23.6 21.0 19.7 18.4 17 45.3 41.2 37.1 33.0 30.9 28.8 6.0 30.0 27.2 24.5 21.8 20.4 19.1 18 46.4 42.1 37.9 33.7 31.6 29.5 6.5 31.0 28.2 25.4 22.6 21.1 19.7 19 47.4 43.1 38.8 34.5 32.3 30.2 7.0 32.0 29.1 26.2 23.3 21.8 20.4 20 48.5 44.1 39.6 35.2 33.0 30.8 7.5 32.9 29.9 26.9 23.9 22.5 21.0 25 53.7 48.9 44.0 39.1 36.6 34.2 8.0 33.8 30.7 27.7 24.6 23.0 21.5 30 58.8 53.5 48.1 42.8 40.1 37.4 8.5 34.6 31.5 28.3 25.2 23.6 22.0 40 68.7 62.5 56.2 50.0 46.9 43.7 9.0 35.4 32.2 29.0 25.8 24.1 22.5 50 78.1 71.0 63.9 56.8 53.3 49.7 9.5 36.2 32.9 29.6 26.3 24.7 23.0 80 102.2 92.9 83.6 74.3 69.7 65.0 Current outage schedules do not support reloads in less than 10 days. Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 12 of 43 TABLE 2.2.5 Time to Core Uncovery Following a Loss of SDC During Midloop Operation with A Large or Small Cold Leg Opening (3990 MW Core)

Notes: (1) Caution; No cold leg openings (i.e. RCP impeller work or shaft replacement) before 14 MW (Source TA-03-C09-2001-004)

(2) Table values can be used to estimate time to core uncovery after boiling begins assuming no leg openings. RCP seal replacement with the RCP shaft on the stop seal is allowed as long as a blocking device is installed on the shaft in the event LSDC occurs. This condition prevents a large cold leg breach.

(3) Times do not include time to boil.

Time to Core Time to Core Decay Heat Uncovery After Decay Heat Uncovery After (MW) Boiling Starts (MW) Boiling Starts (minutes) (minutes) 24.44 18 10.42 42 20.02 22 10.05 44 17.25 25 9.72 45 16.19 27 9.43 46 15.30 28 9.16 48 14.54 30 8.92 49 13.88 31 8.70 50 13.31 33 8.48 52 12.83 34 8.29 53 12.39 35 8.10 54 12.01 36 7.93 55 11.67 37 7.15 61 11.37 38 6.53 67 11.10 39 5.59 79 10.85 40 4.92 89 10.62 41 3.76 117 Source of Data: TA-13-C00-2001-006, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 13 of 43 2.3 RCS Drained to Reactor Vessel Flange with Reactor Head Removed NOTES 2.3.0 Key Reactor Core Parameters Following a Loss of SDC With The RCS Drained to the Reactor Vessel Flange Reactor Head and Upper Guide Structure Removed The key reactor core parameters following a loss of shutdown cooling (SDC) with the RCS drained to the 114 elevation and head or UGS off are for 550 EFPD at 100% RTP. These results are based in part on a computer analysis using the RETRAN code.

Decay heat power is based on Branch Technical Position 9-2 utilizing a 550 EFPD cycle length at 100% power. (3990 MWt)(Reference TA-13-C00-1999-009)

Time to boil is based on the time for the water in the vessel to reach 210 0F. This is a function of decay heat, mass of water in vessel and initial RCS bulk temperature (inlet Shutdown Cooling Heat Exchanger temperature). It is determined by subtracting the RCS bulk temperature from 210 0F, and then dividing by the heatup rate.

Heatup rate is determined by dividing the decay heat by the specific heat capacity for water and by the mass of water available in the vessel at the start of the event.

Time to core uncovery is based on the time it takes the water above the top of the core to drop to the top of the core. Time to core uncovery is the time for the mass above the core to boil off and does not include the time associated with reaching the boiling temperature. Time to core uncovery is a function of decay heat, this volume of water, and the pressure over the water.

Makeup rate is the amount of flow required to reach the core to compensate for water loss through boil off. Note that this is the volume that must be delivered to the core in order to maintain constant inventory. Flow diverted out any cold leg opening must be accounted for (i.e. flowrate indications may not be actual flowrates reaching the core).

NOTE: VALUES NOT EXPLICITLY FOUND IN THE TABLES SHALL BE DETERMINED VIA LINEAR INTERPOLATION PERFORMED BY THE SHIFT TECHNICAL ADVISOR

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 14 of 43 TABLE 2.3.1 Key Reactor Core Parameters Following a Loss of SDC With the RCS Drained to the Reactor Vessel Flange Reactor Head and Upper Guide Structure Removed Prior to Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MW th) (days) (MW th) 1.0 24.44 5.67 173.5 10 10.42 2.42 74.0 2.0 20.02 4.64 142.1 11 10.05 2.33 71.4 3.0 17.25 4.00 122.5 12 9.72 2.26 69.0 3.5 16.19 3.76 114.9 13 9.43 2.19 67.0 4.0 15.30 3.55 108.6 14 9.16 2.13 65.0 4.5 14.54 3.37 103.2 15 8.92 2.07 63.3 5.0 13.88 3.22 98.5 16 8.70 2.02 61.8 5.5 13.31 3.09 94.5 17 8.48 1.97 60.2 6.0 12.83 2.98 91.1 18 8.29 1.92 58.9 6.5 12.39 2.87 88.0 19 8.10 1.88 57.5 7.0 12.01 2.79 85.3 20 7.93 1.84 56.3 7.5 11.67 2.71 82.9 25 7.15 1.66 50.8 8.0 11.37 2.64 80.7 30 6.53 1.51 46.4 8.5 11.10 2.58 78.8 40 5.59 1.30 39.7 9.0 10.85 2.52 77.0 50 4.92 1.14 34.9 9.5 10.62 2.46 75.4 80 3.76 0.87 26.7 Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 15 of 43 TABLE 2.3.2 Key Reactor Core Parameters Following a Loss of SDC With the RCS Drained to the Reactor Vessel Flange Reactor Head and Upper Guide Structure Removed After Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MWth) (days) (MWth) 1.0 19.06 4.42 135.3 10 8.13 1.89 57.7 2.0 15.62 3.62 110.9 11 7.84 1.82 55.7 3.0 13.46 3.12 95.5 12 7.58 1.76 53.8 3.5 12.63 2.93 89.7 13 7.36 1.71 52.2 4.0 11.93 2.77 84.7 14 7.14 1.66 50.7 4.5 11.34 2.63 80.5 15 6.96 1.61 49.4 5.0 10.83 2.51 76.9 16 6.79 1.57 48.2 5.5 10.38 2.41 73.7 17 6.61 1.53 47.0 6.0 10.01 2.32 71.1 18 6.47 1.50 45.9 6.5 9.66 2.24 68.6 19 6.32 1.47 44.9 7.0 9.37 2.17 66.5 20 6.19 1.44 43.9 7.5 9.10 2.11 64.6 25 5.58 1.29 39.6 8.0 8.87 2.06 63.0 30 5.09 1.18 36.2 8.5 8.66 2.01 61.5 40 4.36 1.01 31.0 9.0 8.46 1.96 60.1 50 3.84 0.89 27.2 9.5 8.28 1.92 58.8 80 2.93 0.68 20.8 Current outage schedules do not support reloads in less than 10 days.

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

Source of Data: SA-13-C00-1996-004, Appendix A

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 16 of 43 Ness Kilic TABLE 2.3.3 Time to Boil Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange Reactor Head and Upper Guide Structure Removed Prior to Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 19.4 17.6 15.9 14.1 13.2 12.3 10 45.5 41.4 37.2 33.1 31.0 29.0 2.0 23.7 21.5 19.4 17.2 16.1 15.1 11 47.2 42.9 38.6 34.3 32.2 30.0 3.0 27.5 25.0 22.5 20.0 18.7 17.5 12 48.8 44.3 39.9 35.5 33.3 31.0 3.5 29.3 26.6 24.0 21.3 20.0 18.6 13 50.3 45.7 41.1 36.6 34.3 32.0 4.0 31.0 28.2 25.4 22.5 21.1 19.7 14 51.8 47.1 42.4 37.6 35.3 32.9 4.5 32.6 29.6 26.7 23.7 22.2 20.8 15 53.2 48.3 43.5 38.7 36.2 33.8 5.0 34.2 31.1 27.9 24.8 23.3 21.7 16 54.5 49.5 44.6 39.6 37.2 34.7 5.5 35.6 32.4 29.1 25.9 24.3 22.7 17 55.9 50.8 45.7 40.7 38.1 35.6 6.0 37.0 33.6 30.2 26.9 25.2 23.5 18 57.2 52.0 46.8 41.6 39.0 36.4 6.5 38.3 34.8 31.3 27.8 26.1 24.4 19 58.5 53.2 47.9 42.6 39.9 37.2 7.0 39.5 35.9 32.3 28.7 26.9 25.1 20 59.8 54.4 48.9 43.5 40.8 38.0 7.5 40.6 36.9 33.2 29.5 27.7 25.9 25 66.3 60.3 54.3 48.2 45.2 42.2 8.0 41.7 37.9 34.1 30.3 28.4 26.5 30 72.6 66.0 59.4 52.8 49.5 46.2 8.5 42.7 38.8 34.9 31.1 29.1 27.2 40 84.8 77.1 69.4 61.7 57.8 54.0 9.0 43.7 39.7 35.8 31.8 29.8 27.8 50 96.4 87.6 78.8 70.1 65.7 61.3 9.5 44.6 40.6 36.5 32.5 30.4 28.4 80 126.1 114.6 103.2 91.7 86.0 80.2 Source of Data: SA-13-C00-1996-004, Appendix A

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 17 of 43 Ness Kilic TABLE 2.3.4 Time to Boil Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange Reactor Head and Upper Guide Structure Removed After Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 24.9 22.6 20.3 18.1 17.0 15.8 10 58.3 53.0 47.7 42.4 39.8 37.1 2.0 30.4 27.6 24.8 22.1 20.7 19.3 11 60.5 55.0 49.5 44.0 41.2 38.5 3.0 35.2 32.0 28.8 25.6 24.0 22.4 12 62.5 56.9 51.2 45.5 42.6 39.8 3.5 37.5 34.1 30.7 27.3 25.6 23.9 13 64.5 58.6 52.7 46.9 44.0 41.0 4.0 39.7 36.1 32.5 28.9 27.1 25.3 14 66.4 60.3 54.3 48.3 45.2 42.2 4.5 41.8 38.0 34.2 30.4 28.5 26.6 15 68.1 62.0 55.8 49.6 46.5 43.4 5.0 43.8 39.8 35.8 31.9 29.9 27.9 16 69.9 63.5 57.2 50.8 47.6 44.5 5.5 45.7 41.5 37.4 33.2 31.1 29.1 17 71.7 65.2 58.6 52.1 48.9 45.6 6.0 47.4 43.1 38.8 34.5 32.3 30.2 18 73.3 66.7 60.0 53.3 50.0 46.7 6.5 49.1 44.6 40.1 35.7 33.5 31.2 19 75.0 68.2 61.4 54.6 51.2 47.8 7.0 50.6 46.0 41.4 36.8 34.5 32.2 20 76.7 69.7 62.7 55.7 52.3 48.8 7.5 52.1 47.4 42.6 37.9 35.5 33.1 25 85.0 77.3 69.6 61.8 58.0 54.1 8.0 53.5 48.6 43.7 38.9 36.5 34.0 30 93.1 84.6 76.2 67.7 63.5 59.2 8.5 54.8 49.8 44.8 39.8 37.3 34.8 40 108.7 98.9 89.0 79.1 74.1 69.2 9.0 56.0 50.9 45.8 40.7 38.2 35.7 50 123.6 112.3 101.1 89.9 84.2 78.6 9.5 57.2 52.0 46.8 41.6 39.0 36.4 80 161.7 147.0 132.3 117.6 110.2 102.9 Current outage schedules do not support reloads in less than 10 days. Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 18 of 43 TABLE 2.3.5 Time to Core Uncovery Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange, Reactor Head and Upper Guide Structure Removed (3990 MW Core)

Note: Times do not include time to boil.

Time to Core Time to Core Decay Heat Uncovery After Decay Heat Uncovery After (MW) Boiling Starts (MW) Boiling Starts (minutes) (minutes) 24.44 146 10.42 343 20.02 178 10.05 356 17.25 207 9.72 368 16.19 221 9.43 380 15.30 234 9.16 391 14.54 246 8.92 401 13.88 258 8.70 411 13.31 269 8.48 422 12.83 279 8.29 432 12.39 289 8.10 442 12.01 298 7.93 451 11.67 307 7.15 501 11.37 315 6.53 548 11.10 322 5.59 641 10.85 330 4.92 728 10.62 337 3.76 953 Source of Data: TA-13-C00-2001-006, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 19 of 43 2.4 RCS Drained to Reactor Vessel Flange with Reactor Head Installed NOTES 2.4.0 Key Reactor Core Parameters Following a Loss of SDC With The RCS Drained to the Reactor Vessel Flange Reactor Vessel Head On The key reactor core parameters following a loss of shutdown cooling (SDC) with the RCS drained to the 114 elevation and head or UGS in place are for 550 EFPD at 100% RTP. These results are based in part on a computer analysis using the RETRAN code.

Decay heat power is based on Branch Technical Position 9-2 utilizing a 550 EFPD cycle length at 100% power. (3990 MWt)(Reference TA-13-C00-1999-009)

Time to boil is based on the time for the water in the vessel to reach 210 0F. This is a function of decay heat, mass of water in vessel and initial RCS bulk temperature (inlet Shutdown Cooling Heat Exchanger temperature). It is determined by subtracting the RCS bulk temperature from 210 0F, and then dividing by the heatup rate.

Heatup rate is determined by dividing the decay heat by the specific heat capacity for water and by the mass of water available in the vessel at the start of the event.

Time to core uncovery is conservatively assumed to be the amount of time it takes to boil off the water volume below the bottom of the hot leg and above the top of the core. The time associated with the pressurization effects, steaming, entrainment, and surge line flooding are neglected. Thus, time to core uncovery is a function of decay heat, this volume of water and the pressure over the water.

Time to core uncovery does not include the time associated with reaching the boiling temperature.

Makeup rate is the amount of flow required to reach the core to compensate for water loss through boil off. Note that this is the volume that must be delivered to the core in order to maintain constant inventory. Flow diverted out any cold leg opening must be accounted for (i.e. flowrate indications may not be actual flowrates reaching the core).

NOTE: VALUES NOT EXPLICITLY FOUND IN THE TABLES SHALL BE DETERMINED VIA LINEAR INTERPOLATION PERFORMED BY THE SHIFT TECHNICAL ADVISOR

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 20 of 43 TABLE 2.4.1 Key Reactor Core Parameters Following a Loss of SDC With the RCS Drained to the Reactor Vessel Flange Reactor Vessel Head On Prior to Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MW th) (days) (MW th) 1.0 24.44 5.67 173.5 10 10.42 2.42 74.0 2.0 20.02 4.64 142.1 11 10.05 2.33 71.4 3.0 17.25 4.00 122.5 12 9.72 2.26 69.0 3.5 16.19 3.76 114.9 13 9.43 2.19 67.0 4.0 15.30 3.55 108.6 14 9.16 2.13 65.0 4.5 14.54 3.37 103.2 15 8.92 2.07 63.3 5.0 13.88 3.22 98.5 16 8.70 2.02 61.8 5.5 13.31 3.09 94.5 17 8.48 1.97 60.2 6.0 12.83 2.98 91.1 18 8.29 1.92 58.9 6.5 12.39 2.87 88.0 19 8.10 1.88 57.5 7.0 12.01 2.79 85.3 20 7.93 1.84 56.3 7.5 11.67 2.71 82.9 25 7.15 1.66 50.8 8.0 11.37 2.64 80.7 30 6.53 1.51 46.4 8.5 11.10 2.58 78.8 40 5.59 1.30 39.7 9.0 10.85 2.52 77.0 50 4.92 1.14 34.9 9.5 10.62 2.46 75.4 80 3.76 0.87 26.7 Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 21 of 43 TABLE 2.4.2 Key Reactor Core Parameters Following a Loss of SDC With the RCS Drained to the Reactor Vessel Flange Reactor Vessel Head On After Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MWth) (days) (MWth) 1.0 19.06 4.42 135.3 10 8.13 1.89 57.7 2.0 15.62 3.62 110.9 11 7.84 1.82 55.7 3.0 13.46 3.12 95.5 12 7.58 1.76 53.8 3.5 12.63 2.93 89.7 13 7.36 1.71 52.2 4.0 11.93 2.77 84.7 14 7.14 1.66 50.7 4.5 11.34 2.63 80.5 15 6.96 1.61 49.4 5.0 10.83 2.51 76.9 16 6.79 1.57 48.2 5.5 10.38 2.41 73.7 17 6.61 1.53 47.0 6.0 10.01 2.32 71.1 18 6.47 1.50 45.9 6.5 9.66 2.24 68.6 19 6.32 1.47 44.9 7.0 9.37 2.17 66.5 20 6.19 1.44 43.9 7.5 9.10 2.11 64.6 25 5.58 1.29 39.6 8.0 8.87 2.06 63.0 30 5.09 1.18 36.2 8.5 8.66 2.01 61.5 40 4.36 1.01 31.0 9.0 8.46 1.96 60.1 50 3.84 0.89 27.2 9.5 8.28 1.92 58.8 80 2.93 0.68 20.8 Current outage schedules do not support reloads in less than 10 days.

Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 22 of 43 Ness Kilic TABLE 2.4.3 Time to Boil Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange Reactor Vessel Head On Prior to Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 19.4 17.6 15.9 14.1 13.2 12.3 10 45.5 41.4 37.2 33.1 31.0 29.0 2.0 23.7 21.5 19.4 17.2 16.1 15.1 11 47.2 42.9 38.6 34.3 32.2 30.0 3.0 27.5 25.0 22.5 20.0 18.7 17.5 12 48.8 44.3 39.9 35.5 33.3 31.0 3.5 29.3 26.6 24.0 21.3 20.0 18.6 13 50.3 45.7 41.1 36.6 34.3 32.0 4.0 31.0 28.2 25.4 22.5 21.1 19.7 14 51.8 47.1 42.4 37.6 35.3 32.9 4.5 32.6 29.6 26.7 23.7 22.2 20.8 15 53.2 48.3 43.5 38.7 36.2 33.8 5.0 34.2 31.1 27.9 24.8 23.3 21.7 16 54.5 49.5 44.6 39.6 37.2 34.7 5.5 35.6 32.4 29.1 25.9 24.3 22.7 17 55.9 50.8 45.7 40.7 38.1 35.6 6.0 37.0 33.6 30.2 26.9 25.2 23.5 18 57.2 52.0 46.8 41.6 39.0 36.4 6.5 38.3 34.8 31.3 27.8 26.1 24.4 19 58.5 53.2 47.9 42.6 39.9 37.2 7.0 39.5 35.9 32.3 28.7 26.9 25.1 20 59.8 54.4 48.9 43.5 40.8 38.0 7.5 40.6 36.9 33.2 29.5 27.7 25.9 25 66.3 60.3 54.3 48.2 45.2 42.2 8.0 41.7 37.9 34.1 30.3 28.4 26.5 30 72.6 66.0 59.4 52.8 49.5 46.2 8.5 42.7 38.8 34.9 31.1 29.1 27.2 40 84.8 77.1 69.4 61.7 57.8 54.0 9.0 43.7 39.7 35.8 31.8 29.8 27.8 50 96.4 87.6 78.8 70.1 65.7 61.3 9.5 44.6 40.6 36.5 32.5 30.4 28.4 80 126.1 114.6 103.2 91.7 86.0 80.2 Source of Data: SA-13-C00-1996-004, Appendix A

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 23 of 43 Ness Kilic TABLE 2.4.4 Time to Boil Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange Reactor Vessel Head On After Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 24.9 22.6 20.3 18.1 17.0 15.8 10 58.3 53.0 47.7 42.4 39.8 37.1 2.0 30.4 27.6 24.8 22.1 20.7 19.3 11 60.5 55.0 49.5 44.0 41.2 38.5 3.0 35.2 32.0 28.8 25.6 24.0 22.4 12 62.5 56.9 51.2 45.5 42.6 39.8 3.5 37.5 34.1 30.7 27.3 25.6 23.9 13 64.5 58.6 52.7 46.9 44.0 41.0 4.0 39.7 36.1 32.5 28.9 27.1 25.3 14 66.4 60.3 54.3 48.3 45.2 42.2 4.5 41.8 38.0 34.2 30.4 28.5 26.6 15 68.1 62.0 55.8 49.6 46.5 43.4 5.0 43.8 39.8 35.8 31.9 29.9 27.9 16 69.9 63.5 57.2 50.8 47.6 44.5 5.5 45.7 41.5 37.4 33.2 31.1 29.1 17 71.7 65.2 58.6 52.1 48.9 45.6 6.0 47.4 43.1 38.8 34.5 32.3 30.2 18 73.3 66.7 60.0 53.3 50.0 46.7 6.5 49.1 44.6 40.1 35.7 33.5 31.2 19 75.0 68.2 61.4 54.6 51.2 47.8 7.0 50.6 46.0 41.4 36.8 34.5 32.2 20 76.7 69.7 62.7 55.7 52.3 48.8 7.5 52.1 47.4 42.6 37.9 35.5 33.1 25 85.0 77.3 69.6 61.8 58.0 54.1 8.0 53.5 48.6 43.7 38.9 36.5 34.0 30 93.1 84.6 76.2 67.7 63.5 59.2 8.5 54.8 49.8 44.8 39.8 37.3 34.8 40 108.7 98.9 89.0 79.1 74.1 69.2 9.0 56.0 50.9 45.8 40.7 38.2 35.7 50 123.6 112.3 101.1 89.9 84.2 78.6 9.5 57.2 52.0 46.8 41.6 39.0 36.4 80 161.7 147.0 132.3 117.6 110.2 102.9 Current outage schedules do not support reloads in less than 10 days. Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 24 of 43 TABLE 2.4.5 Time to Core Uncovery Following a Loss of SDC with the RCS Drained to the Reactor Vessel Flange, Reactor Vessel Head On (3990 MW Core)

Note: Times do not include time to boil and assume no cold leg openings.

Time to Core Time to Core Decay Heat Uncovery After Decay Heat Uncovery After (MW) Boiling Starts (MW) Boiling Starts (minutes) (minutes) 24.44 18 10.42 42 20.02 22 10.05 44 17.25 25 9.72 45 16.19 27 9.43 46 15.30 28 9.16 48 14.54 30 8.92 49 13.88 31 8.70 50 13.31 33 8.48 52 12.83 34 8.29 53 12.39 35 8.10 54 12.01 36 7.93 55 11.67 37 7.15 61 11.37 38 6.53 67 11.10 39 5.59 79 10.85 40 4.92 89 10.62 41 3.76 117 Source of Data: TA-13-C00-2001-006, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 25 of 43 2.5 RCS Filled to 120 (Vessel Full) and Reactor Vessel Head Installed NOTES 2.5.0 Key Reactor Core Parameters Following a Loss of SDC With The RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On The key reactor core parameters following a loss of shutdown cooling (SDC) with the RCS drained to the 120 elevation (vessel full) and head on are for 550 EFPD at 100% RTP. These results are based in part on a computer analysis using the RETRAN code.

Decay heat power is based on Branch Technical Position 9-2 utilizing a 550 EFPD cycle length at 100% power. (3990 MWt)(Reference TA-13-C00-1999-009)

Time to boil is based on the time for the water in the vessel to reach 210 0F. This is a function of decay heat, mass of water in vessel and initial RCS bulk temperature (inlet Shutdown Cooling Heat Exchanger temperature). It is determined by subtracting the RCS bulk temperature from 210 0F, and then dividing by the heatup rate.

Heatup rate is determined by dividing the decay heat by the specific heat capacity for water and by the mass of water available in the vessel at the start of the event.

Time to core uncovery is based on the time it takes the water above the top of the core to drop to the top of the core. Total time to uncover is the summation of Time to Boil plus the time for the mass above the core to boil off. This also considers the pressurization effects, steaming, entrainment and surge line flooding.

Time to core uncovery is conservatively assumed to be the amount of time it takes to boil off the water volume below the bottom of the hot leg and above the top of the core. The time associated with the pressurization effects, steaming, entrainment, and surge line flooding are neglected. Thus, time to core uncovery is a function of decay heat, this volume of water and the pressure over the water.

Time to core uncovery does not include the time associated with reaching the boiling temperature.

Makeup rate is the amount of flow required to reach the core to compensate for water loss through boil off. Note that this is the volume that must be delivered to the core in order to maintain constant inventory. Flow diverted out any cold leg opening must be accounted for (i.e. flowrate indications may not be actual flowrates reaching the core).

NOTE: VALUES NOT EXPLICITLY FOUND IN THE TABLES SHALL BE DETERMINED VIA LINEAR INTERPOLATION PERFORMED BY THE SHIFT TECHNICAL ADVISOR

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 26 of 43 TABLE 2.5.1 Key Reactor Core Parameters Following a Loss of SDC With the RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On Prior to Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MW th) (days) (MW th) 1.0 24.44 4.99 173.5 10 10.42 2.13 74.0 2.0 20.02 4.08 142.1 11 10.05 2.05 71.4 3.0 17.25 3.52 122.5 12 9.72 1.98 69.0 3.5 16.19 3.30 114.9 13 9.43 1.92 67.0 4.0 15.30 3.12 108.6 14 9.16 1.87 65.0 4.5 14.54 2.97 103.2 15 8.92 1.82 63.3 5.0 13.88 2.83 98.5 16 8.70 1.77 61.8 5.5 13.31 2.72 94.5 17 8.48 1.73 60.2 6.0 12.83 2.62 91.1 18 8.29 1.69 58.9 6.5 12.39 2.53 88.0 19 8.10 1.65 57.5 7.0 12.01 2.45 85.3 20 7.93 1.62 56.3 7.5 11.67 2.38 82.9 25 7.15 1.46 50.8 8.0 11.37 2.32 80.7 30 6.53 1.33 46.4 8.5 11.10 2.26 78.8 40 5.59 1.14 39.7 9.0 10.85 2.21 77.0 50 4.92 1.00 34.9 9.5 10.62 2.17 75.4 80 3.76 0.77 26.7 Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 27 of 43 TABLE 2.5.2 Key Reactor Core Parameters Following a Loss of SDC With the RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On After Core Reload (3990 MW Core)

Time after Decay Heatup Makeup Time after Decay Heatup Makeup Reactor Heat Rate Flowrate Reactor Heat Rate Flowrate Shutdown Load (F/Min.) (gpm)** Shutdown Load (F/Min.) (gpm)

(days) (MWth) (days) (MWth) 1.0 19.06 3.89 135.3 10 8.13 1.66 57.7 2.0 15.62 3.19 110.9 11 7.84 1.60 55.7 3.0 13.46 2.74 95.5 12 7.58 1.55 53.8 3.5 12.63 2.58 89.7 13 7.36 1.50 52.2 4.0 11.93 2.43 84.7 14 7.14 1.46 50.7 4.5 11.34 2.31 80.5 15 6.96 1.42 49.4 5.0 10.83 2.21 76.9 16 6.79 1.38 48.2 5.5 10.38 2.12 73.7 17 6.61 1.35 47.0 6.0 10.01 2.04 71.1 18 6.47 1.32 45.9 6.5 9.66 1.97 68.6 19 6.32 1.29 44.9 7.0 9.37 1.91 66.5 20 6.19 1.26 43.9 7.5 9.10 1.86 64.6 25 5.58 1.14 39.6 8.0 8.87 1.81 63.0 30 5.09 1.04 36.2 8.5 8.66 1.77 61.5 40 4.36 0.89 31.0 9.0 8.46 1.73 60.1 50 3.84 0.78 27.2 9.5 8.28 1.69 58.8 80 2.93 0.60 20.8 Current outage schedules do not support reloads in less than 10 days.

Source of Data: SA-13-C00-1996-004, Appendix A

- The makeup flowrate listed is to compensate for boil off (not required flow to prevent boiling)

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 28 of 43 Ness Kilic TABLE 2.5.3 Time to Boil Following a Loss of SDC with the RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On Prior to Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 22.1 20.1 18.1 16.0 15.0 14.0 10 51.7 47.0 42.3 37.6 35.3 32.9 2.0 26.9 24.5 22.0 19.6 18.4 17.1 11 53.7 48.8 43.9 39.0 36.6 34.1 3.0 31.3 28.4 25.6 22.7 21.3 19.9 12 55.5 50.4 45.4 40.3 37.8 35.3 3.5 33.3 30.3 27.2 24.2 22.7 21.2 13 57.2 52.0 46.8 41.6 39.0 36.4 4.0 35.2 32.0 28.8 25.6 24.0 22.4 14 58.9 53.5 48.2 42.8 40.1 37.5 4.5 37.1 33.7 30.3 27.0 25.3 23.6 15 60.5 55.0 49.5 44.0 41.2 38.5 5.0 38.8 35.3 31.8 28.3 26.5 24.7 16 62.0 56.3 50.7 45.1 42.3 39.4 5.5 40.5 36.8 33.1 29.5 27.6 25.8 17 63.6 57.8 52.0 46.2 43.4 40.5 6.0 42.0 38.2 34.4 30.6 28.7 26.7 18 65.0 59.1 53.2 47.3 44.3 41.4 6.5 43.5 39.6 35.6 31.7 29.7 27.7 19 66.6 60.5 54.5 48.4 45.4 42.4 7.0 44.9 40.8 36.7 32.7 30.6 28.6 20 68.0 61.8 55.6 49.5 46.4 43.3 7.5 46.2 42.0 37.8 33.6 31.5 29.4 25 75.4 68.6 61.7 54.8 51.4 48.0 8.0 47.4 43.1 38.8 34.5 32.3 30.2 30 82.6 75.1 67.6 60.1 56.3 52.5 8.5 48.6 44.2 39.7 35.3 33.1 30.9 40 96.5 87.7 78.9 70.2 65.8 61.4 9.0 49.7 45.2 40.7 36.1 33.9 31.6 50 109.6 99.6 89.7 79.7 74.7 69.7 9.5 50.8 46.2 41.5 36.9 34.6 32.3 80 143.4 130.4 117.3 104.3 97.8 91.3 Source of Data: SA-13-C00-1996-004, Appendix A

By : Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev.4 Reviewer Page 29 of 43 Ness Kilic TABLE 2.5.4 Time to Boil Following a Loss of SDC with the RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On After Core Reload (3990 MW Core)

Time after Time after Time to Boil (minutes) Time to Boil (minutes)

Reactor Reactor Shutdown Shutdown Shutdown Cooling Heat Exchanger Inlet Temperature (F) Shutdown Cooling Heat Exchanger Inlet Temperature (F)

(days) (days) 100 110 120 130 135 140 100 110 120 130 135 140 1.0 28.3 25.7 23.1 20.6 19.3 18.0 10 66.3 60.3 54.3 48.3 45.2 42.2 2.0 34.5 31.4 28.3 25.1 23.5 22.0 11 68.8 62.5 56.3 50.0 46.9 43.8 3.0 40.1 36.4 32.8 29.1 27.3 25.5 12 71.1 64.7 58.2 51.7 48.5 45.3 3.5 42.7 38.8 34.9 31.1 29.1 27.2 13 73.3 66.6 60.0 53.3 50.0 46.7 4.0 45.2 41.1 37.0 32.9 30.8 28.8 14 75.5 68.6 61.7 54.9 51.5 48.0 4.5 47.5 43.2 38.9 34.6 32.4 30.3 15 77.5 70.5 63.4 56.4 52.8 49.3 5.0 49.8 45.3 40.8 36.2 34.0 31.7 16 79.5 72.2 65.0 57.8 54.2 50.6 5.5 51.9 47.2 42.5 37.8 35.4 33.1 17 81.5 74.1 66.7 59.3 55.6 51.9 6.0 53.9 49.0 44.1 39.2 36.7 34.3 18 83.4 75.8 68.2 60.6 56.9 53.1 6.5 55.8 50.7 45.7 40.6 38.0 35.5 19 85.3 77.6 69.8 62.1 58.2 54.3 7.0 57.6 52.3 47.1 41.9 39.2 36.6 20 87.2 79.3 71.3 63.4 59.4 55.5 7.5 59.2 53.9 48.5 43.1 40.4 37.7 25 96.7 87.9 79.1 70.3 65.9 61.5 8.0 60.8 55.3 49.7 44.2 41.5 38.7 30 105.9 96.2 86.6 77.0 72.2 67.4 8.5 62.3 56.6 51.0 45.3 42.5 39.6 40 123.7 112.4 101.2 89.9 84.3 78.7 9.0 63.7 57.9 52.1 46.3 43.4 40.5 50 140.5 127.7 115.0 102.2 95.8 89.4 9.5 65.1 59.2 53.3 47.3 44.4 41.4 80 183.9 167.1 150.4 133.7 125.4 117.0 Current outage schedules do not support reloads in less than 10 days. Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 30 of 43 TABLE 2.5.5 Time to Core Uncovery Following a Loss of SDC with the RCS Filled to 120 (Vessel Full) and Reactor Vessel Head On (3990 MW Core)

Note: Times do not include time to boil and assume no cold leg openings.

Time to Core Time to Core Decay Heat Uncovery After Decay Heat Uncovery After (MW) Boiling Starts (MW) Boiling Starts (minutes) (minutes) 24.44 18 10.42 42 20.02 22 10.05 44 17.25 25 9.72 45 16.19 27 9.43 46 15.30 28 9.16 48 14.54 30 8.92 49 13.88 31 8.70 50 13.31 33 8.48 52 12.83 34 8.29 53 12.39 35 8.10 54 12.01 36 7.93 55 11.67 37 7.15 61 11.37 38 6.53 67 11.10 39 5.59 79 10.85 40 4.92 89 10.62 41 3.76 117 Source of Data: TA-13-C00-2001-006, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 31 of 43 2.6 RCS Filled to Refueling Level Operation NOTES 2.6.0 Key Reactor Core Parameters Following a Loss of SDC With The RCS Filled to Refueling Level The key reactor core parameters following a loss of shutdown cooling (SDC) with the RCS filled to the refueling level are for 550 EFPD at 100% RTP. These results are based in part on a computer analysis using the RETRAN code.

Decay heat power is based on Branch Technical Position 9-2 utilizing a 550 EFPD cycle length at 100% power. (3990 MWt)(Reference TA-13-C00-1999-009)

Time to boil is based on the time for the water in the vessel to reach 210 0F. This is a function of decay heat, mass of water in vessel and initial RCS bulk temperature (inlet Shutdown Cooling Heat Exchanger temperature). It is determined by subtracting the RCS bulk temperature from 2100, and then dividing by the heatup rate. The only value of RCS bulk temperature provided is 135 degrees F, the maximum allowed temperature for Mode 6.

Heatup rate is determined by dividing the decay heat by the specific heat capacity for water and by the mass of water available in the vessel at the start of the event.

Time to core uncovery is based on the time it takes the water above the top of the core to drop to the top of the core. Time to core uncovery is the time for the mass above the core to boil off and does not include the time associated with reaching boiling temperature. Time to core uncovery is a function of decay heat, this volume of water and the pressure over the water.

Makeup rate is the amount of flow required to reach the core to compensate for water loss through boil off. Note that this is the volume that must be delivered to the core in order to maintain constant inventory. Flow diverted out any cold leg opening must be accounted for (i.e. flowrate indications may not be actual flowrates reaching the core).

NOTE: VALUES NOT EXPLICITLY FOUND IN THE TABLES SHALL BE DETERMINED VIA LINEAR INTERPOLATION PERFORMED BY THE SHIFT TECHNICAL ADVISOR

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 32 of 43 TABLE 2.6.1 Time to Boil and Heatup Rates Following a Loss of SDC With the RCS Filled to the Refueling Level Prior to Core Reload (3990 MW Core)

Time after Decay Heatup Time Time after Decay Heatup Time Reactor Heat Rate to Reactor Heat Rate to Shutdown Load (F/Min.) Boil Shutdown Load (F/Min.) Boil (days) (MW th) (hours) (days) (MW th) (hours) 1.0 24.44 0.42 3.0 10 10.42 0.18 7.0 2.0 20.02 0.34 3.6 11 10.05 0.17 7.2 3.0 17.25 0.30 4.2 12 9.72 0.17 7.5 3.5 16.19 0.28 4.5 13 9.43 0.16 7.7 4.0 15.30 0.26 4.7 14 9.16 0.16 7.9 4.5 14.54 0.25 5.0 15 8.92 0.15 8.1 5.0 13.88 0.24 5.2 16 8.70 0.15 8.4 5.5 13.31 0.23 5.5 17 8.48 0.15 8.6 6.0 12.83 0.22 5.7 18 8.29 0.14 8.8 6.5 12.39 0.21 5.9 19 8.10 0.14 9.0 7.0 12.01 0.21 6.1 20 7.93 0.14 9.2 7.5 11.67 0.20 6.2 25 7.15 0.12 10.2 8.0 11.37 0.20 6.4 30 6.53 0.11 11.1 8.5 11.10 0.19 6.5 40 5.59 0.10 13.0 9.0 10.85 0.19 6.7 50 4.92 0.08 14.8 9.5 10.62 0.18 6.8 80 3.76 0.06 19.3 Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 33 of 43 TABLE 2.6.2 Time to Boil and Heatup Rates Following a Loss of SDC With the RCS Filled to the Refueling Level After Core Reload (3990 MW Core)

Time after Decay Heatup Time Time after Decay Heatup Time Reactor Heat Rate to Reactor Heat Rate to Shutdown Load (F/Min.) Boil Shutdown Load (F/Min.) Boil (days) (MWth) (hours) (days) (MWth) (hours) 1.0 19.06 0.33 3.8 10 8.13 0.14 8.9 2.0 15.62 0.27 4.7 11 7.84 0.13 9.3 3.0 13.46 0.23 5.4 12 7.58 0.13 9.6 3.5 12.63 0.22 5.8 13 7.36 0.13 9.9 4.0 11.93 0.21 6.1 14 7.14 0.12 10.2 4.5 11.34 0.20 6.4 15 6.96 0.12 10.4 5.0 10.83 0.19 6.7 16 6.79 0.12 10.7 5.5 10.38 0.18 7.0 17 6.61 0.11 11.0 6.0 10.01 0.17 7.3 18 6.47 0.11 11.2 6.5 9.66 0.17 7.5 19 6.32 0.11 11.5 7.0 9.37 0.16 7.8 20 6.19 0.11 11.7 7.5 9.10 0.16 8.0 25 5.58 0.10 13.0 8.0 8.87 0.15 8.2 30 5.09 0.09 14.3 8.5 8.66 0.15 8.4 40 4.36 0.07 16.7 9.0 8.46 0.15 8.6 50 3.84 0.07 18.9 9.5 8.28 0.14 8.8 80 2.93 0.05 24.8 Current outage schedules do not support reloads in less than 10 days.

Source of Data: SA-13-C00-1996-004, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 34 of 43 TABLE 2.6.3 Time to Core Uncovery Following a Loss of SDC RCS at Refueling Level (3990 MW Core)

Note: Times do not include time to boil and assume no cold leg openings.

Time to Core Time to Core Decay Heat Uncovery After Decay Heat Uncovery After (MW) Boiling Starts (MW) Boiling Starts (hours) (hours) 24.44 34.9 10.42 81.8 20.02 42.6 10.05 84.8 17.25 49.4 9.72 87.7 16.19 52.6 9.43 90.4 15.30 55.7 9.16 93.0 14.54 58.6 8.92 95.5 13.88 61.4 8.70 98.0 13.31 64.0 8.48 100.5 12.83 66.4 8.29 102.8 12.39 68.8 8.10 105.2 12.01 71.0 7.93 107.5 11.67 73.0 7.15 119.2 11.37 75.0 6.53 130.5 11.10 76.8 5.59 152.5 10.85 78.5 4.92 173.2 10.62 80.2 3.76 226.7 Source of Data: TA-13-C00-2001-006, Appendix A

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 35 of 43 2.7 Spent Fuel Pool Operation NOTES 2.7.0 Spent Fuel Pool Parameters for a Loss of SDC Spent Fuel Pool (SFP) parameters will be determined on a cycle to cycle basis due to changing inven-tories in the SFP.

Information concerning the existing decay heat load currently in the SFP can be found in the unit specific As-Left Decay Heat Projection analysis maintained by Reactor Engineering. The decay heat loads for the reactor core (for periods of time during or after core offload) are included in SAOD sections 2.2 through 2.6.

Once the decay heat has been determined, the Heatup Rate (HUR) in 0F/hr can be calculated from:

kW ( BTU ) ( hr )

DH 1000 ----------- 3412 -------------------------------

MW t kW HUR = -------------------------------------------------------------------------------------

2, 114, 850lbm C p Time to Boil (TTB) in hours can be calculated from:

210 - T initial TTB = ------------------------------

HUR where:

DH: total SFP decay heat, current decay heat load + additional off-loaded fuel, in MWt 2,114,850 lbm is the assumed mass of water in the SFP, this is less than value based on these references (

References:

(1) NRC letter from M.B. Fields to G.R. Overbeck, March 2, 2000, addresses minimum SFP capacity of 320,000 gallons; (2) Updated Final Safety Analysis Report, Table 9.1-2, Maximum SFP temperature of 167 0F)

Cp: 1.0 BTU/lbm 0F 210 0F assumed boiling point of SFP water Tinitial: SFP temperature at time of loss of cooling in 0F

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 36 of 43 2.8 Minimum Time to Reduced Flow SDC Operations NOTES 2.8.0 Minimum Time to Reduced Flow SDC Operations Following Reactor Shutdown to Maintain RCS Temperature at or Below 135 Deg. F Table 2.8.1 presents the EW cooling water temperature and post-shutdown time criteria prior to reducing SDC system total flow rate to 3780 gpm (indicated) to support reduced inventory conditions while providing sufficient cooling capacity to maintain the RCS temperature at or below 135 0F. Specifically, this table correlates the time after shutdown where the core decay heat is equal to or less than the cooling capacity of the SDC system at the corresponding EW cooling water temperature and with the RCS temperature at 135 0F.

The data presented in Table 2.8.1 is predicated on stable RCS temperature prior to reducing SDC flow rate. Upon reduction of SDC flow rate and prior to reducing RCS water level, Operations shall monitor RCS temperature to verify that sufficient cooling capacity exists to maintain RCS temperature at or below 135 0F. Engineering recommends that RCS temper-ature be monitored for a period of not less than one hour (reference letter 448-00525).

Data presented in Table 2.8.1 is based on the SDC performance analyses contained in PVNGS calculation 13-MC-SI-231 for a rated thermal power of 3990 MW. EW temperature instrument uncertainty included in Table 2.8.1 is based on total loop uncertainty for instru-ments 1,2,3JEWNTI083/84 as indicated on the ERFDADS display. Verification of actual EW temperature by alternative means using appropriate M&TE is considered acceptable.

Notes 2.8.0 and Table 2.8.1 are maintained by Design Mechanical Engineering, NSSS.

Questions concerning this information should be directed to the Design Mechanical NSSS section leader.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 37 of 43 TABLE 2.8.1 Minimum Time to Reduced Flow SDC Operations Following Reactor Shutdown To Maintain RCS Temperature at or Below 135 Deg. F Note: Refer to Note 2.8.0 for information regarding the use of this table EW Inlet EW Inlet Decay Heat / Time After Temperature Temperature SDC capacity Shutdown (Actual - 0F) (Indicated - 0F) (MW) (Hrs)

(1,2,3JEWN083/84) 92 87 15.5 91 91 86 15.9 87 90 85 16.3 82 89 84 16.6 79 88 83 17.0 75 87 82 17.4 71 Source of Data: 13-MC-SI-231, Revision 4

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 38 of 43 2.9 RCS Forced Flow and RWT Temperature Requirements NOTES 2.9.0 RCS Forced Flow and RWT Temperature Requirements To Maintain Subcooled Conditions Following a Loss of Shutdown Cooling Table 2.9.1 presents the Refueling Water Tank fluid temperature and time requirements following reactor shutdown to be satisfied prior to reduced inventory conditions. These criteria must be satisfied prior to reducing RCS water level to ensure that sufficient cooling is available to maintain the core covered and subcooled by HPSI forced cooling in the event of a loss of shutdown cooling. The RWT temperature requirements in Table 2.9.1 ensure that the total heat dissipated by a single train of HPSI injection is equal to or greater than the corresponding core decay heat at the specified time after shutdown.

The data presented in Table 2.9.1 is based on the forced flow cooling analysis contained in PVNGS calculation 13-MC-SI-231 for a rated thermal power of 3990 MW. RWT temper-ature instrument uncertainty included in Table 2.9.1 is based on total loop uncertainty for instruments 1,2,3CHNTI200 as indicated on the ERFDADS display. Operations will establish the need to circulate the RWT volume to ensure that the tank is thermally well mixed.

Notes 2.9.0 and Table 2.9.1 are maintained by Design Mechanical Engineering, NSSS.

Questions concerning this information should be directed to the Design Mechanical NSSS section leader.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 39 of 43 TABLE 2.9.1 RCS Forced Flow and RWT Temperature Requirements To Maintain Subcooled Conditions Following a Loss of Shutdown Cooling Note: Refer to Note 2.9.0 for information regarding the use of this table RWT Temperature RWT Temperature Decay Heat Time After (Actual - 0F) (Indicated - 0F) (MW) Shutdown (Hrs) 74 72 18.0 65 76 74 17.7 68 78 76 17.4 71 80 78 17.1 75 82 80 16.8 77 84 82 16.5 80 86 84 16.2 83 88 86 15.9 86 90 88 15.6 90 Source of Data: 13-MC-SI-231, Revision 4

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 40 of 43 3.0 IMPACT REVIEW The SAOD provides information to the operations staff and shift technical advisors should a loss of shutdown cooling occur, but does not affect any procedures they use.

This document satisfies the design control requirements but is not a QR analysis package. This doc-ument is a collection of data from QR analyses. Changes to these referenced analyses require the performance of the impact review and other analysis package requirements (i.e. AD documentation, etc.).

During the revision of SAOD Unit 1 (Rev 2) where the document was updated to incorporate the information from 3876 Mwt configuration to 3990 Mwt (same scope as this analysis), Operations, Outage Management, OPS standards, Design Engineering, System Engineering, and NFM were contacted to determine the potential impacts. No impact to any outside organization or procedure resulted for the Unit 1 SAOD revision. Likewise, no impacts result from this revision. Also no SABD exists for the SAOD.

4.0 REFERENCES

1) TA-13-C00-1999-009, Outage Decay Heats, Revision 4, 10/11/2006.

2 TA-13-C00-2001-005, Loss of Shutdown Cooling Analyses for RCS Drain Operations and Nozzle Dam Installation, Revision 1, 3/28/2003 3 TA-13-C00-2001-006, SAOD Input Data of Estimated Times to Vaporize RCS Inventory Above the Reactor Core, Revision 1, 5/7/2003.

4 SA-13-C00-1996-004, Stretch Power SAOD, Revision 4, 8/5/2003.

5 13-MC-SI-231, Calculation of Minimum Time to Reduced Flow Shutdown Cooling Oper-ation, Revision 4, 4/06/2005 6 Deleted.

7 Letter 162-09970-KCP dated March 5, 2002. (Note; this letter was supplemented by the let-ter in reference 12 below).

8 TA-03-C09-2001-004, Loss of Shutdown Cooling Analysis for RCP Removal During U3C9 SNOW Outage, Revision 1, 2/20/2001.

9 NRC letter from M.B. Fields to G.R. Overbeck, March 2, 2000.

10 UFSAR revision 14 dated June 2007.

11 Letter 448-00525-MAB/JAB dated August 17, 2001.

12 Letter 162-10794-CAH/DAM dated February 25, 2004 and CRDR 2686238

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 41 of 43 Appendix A 10 CFR 50.59 Applicability Determination This document satisfies the design control requirements but is not a QR analysis package. This doc-ument is a collection of data from QR analyses. Changes to these referenced analyses require AD documentation and are performed under those analyses packages. For example Reference 1 per-formed applicability determination for change of that document. Per 93DP-0LC17 Section 2.1.1, Relocating design information that already exists in design output documents to another location is considered editorial in nature and there is no requirement to review the 50.59 or 72.48 screen-ing/evaluation performed to place the information in the design documents. Thus this analysis does not require a 10 CFR 50.59 Screening of Procedure.

In addition, the other changes specified in this analysis revision are considered administrative and do not require a 10 CFR 50.59 Screening per 93DP-0LC17, section 2.1.3. These applicable changes include reformatting the analysis documentation to comply with current NFM design and procedures 05DP-0NF09 and 05DP-0NF22.

This Applicability Determination was performed by Arshad Taufiq Appendix B Reload Verification Not Applicable since the information provided in SAOD is not part of the Reload process Appendix C Design Document Interfaces and Associations Not Applicable since this document is a collection of data from QR analysis. Changes to these referenced analyses require the performance of the design verifications e.g. see Ref. 1 Appendix C for design document interface summary. Procedure 05DP-0NF09, Step 3.2.4.3 says in part, Asso-ciations are not required at this time, but may be specified for use in NFM at the SLs discretion.

NFM-TA section leader has concurred that the Interface & Associations are not required for this revision.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 42 of 43 APPENDIX D Design Review and Verification Results of Review Design Review Area YES N/A1

1. Were the inputs correctly selected and properly documented? X

2. Are assumptions necessary to perform the analysis adequately described and reasonable? Where necessary, are they identified for subsequent reverification? contingencies? X

3. Are the appropriate quality and quality assurance requirements specified?

X

4. Are the applicable standards, acceptance criteria, and regulatory requirements properly identified?

Are their requirements met? X

5. Have applicable operating experience, conditions, issues, & plant configuration been considered?

X

6. Are the systems, structures, and components credited/used/considered/specified in the analysis allowed/suitable for the required application? X

7. Was an appropriate design method used? Were the input and assumptions correctly incorporated in X

the design process?

8. Is the output reasonable compared to design inputs? Are the conclusions appropriately drawn?

X

9. Have the design interface requirements been satisfied? Are the impacts on other design documents X

properly identified? Have change mechanisms been initiated?

10. If the analysis results need verification by further testing, are the criteria for verification that the design requirements have been satisfactorily accomplished identified? X

11. Are the requirements for record preparation, review, approval, retention etc. met?

X Comments/Explanations:

For Questions 2, 4, and 10: This document is a collection of data from several QR analyses. No new assumptions, acceptance criteria, or verification requirements are established by this document.

Review Performed By: Ness Kilic Date:12/13/2007 1.N/A (Not Applicable) - If marked, an explanation shall be provided in the Comments/Explanation Box.

By: Arshad Taufiq Safety Analysis Operational Data SAOD Unit 3 Manual 3990 MWt Rev 4 Reviewer: Ness Kilic Page 43 of 43 Design Verification Comment Sheet Comment Response Response Number Reviewers Comment Required? Preparers Response Accepted?

1 Some of the source analyses provide the NO Appendices specified YES 3990 MW data in Appendices. It may help the user to specify the appendices where the data is extracted from 2 Procedural (AD): Section 2.1.6 of 93DP- YES Non-applicability now is based on Section YES 0LC17 is applicable to specific analyses. 2.1.1 of the AD procedure This analysis does not meet those criteria.

Recommend use of other justification for non-applicability 3 Procedural (Analysis Control): Need SLs YES TA-SL concurred with no changes to YES decision to include Associations in App. Associations. DRC is included C. Also package needs DRC.

REVIEWER: A. N. Kilic DATE: 12/13/07 SCOPE OF REVIEW AND VERIFICATION: This document is a collection of data from sever-al QR analyses. Thus, the review consisted of verification that the information is correctly and completely extracted from the source documents and translated into SAOD for applicable unit.

TYPE OF VERIFICATION (check all that apply):

Design Review (attach Design Review Checklist) X Alternate Calculations (attach Design Review Checklist and alternate calculations)

Qualification Testing (attach Design Review Checklist and test results)

Other (specify and attach supporting documentation and Design Review Checklist)

VERIFICATION NOTES: (Attach relevant information)

A-7 PVNGS JOB PERFORM ANCE M EASURE JPM BASIS INFORMATION TASK: 1290190102 Ensure Compliance with Tech Specs TASK STANDARD: Status of MSIV LCOs determined K/A: 2.2.22 K/A RATING: RO: 3.4 SRO: 4.1 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

Technical Specifications SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Jordan Johnston Date: 05/18/2007 Revised By: Alan Malley Date: 01/12/2012 Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE

1. SIMULATOR SETUP:

Tech Specs available Computer available Page 2 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 is in Mode 1 and has had a series of events associated with the Main Steam Isolation Valves (MSIVs).

INITIATING CUE:

Your task is to evaluate MSIV status for the time line (attached) and determine what LCO and action should have been applied for each time.

The following chart gives a chronological order of conditions that existed with Unit 1s MSIVs.

Fill out all LCO actions that are entered.

Time MSIV Accumulator Pressure LCO and action entered number Train T=0 170 A 4950 T=1 hr 180 A 4975 T=2 hrs 171 B 4950 T=3 hrs 170 A 5200 Page 3 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE JPM START TIME:

STEP CUE STANDARD

1.

Examinee determines LCO and Examinee enters LCO 3.7.2 condition for T=0 time. condition a.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Examinee determines LCO and Examinee enters LCO 3.7.2 condition for T= 1 hr. time. condition c.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.

Examinee determines LCO and Examinee enters LCO 3.7.2 condition for T= 2 hr. time. condition e.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3.

Examinee determines LCO and Examinee enters LCO 3.7.2 condition for T= 3 hr. time. condition b.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

Page 5 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparednessorganization for resolution.

NORMAL TERMINATION POINT Page 6 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE ANSWER KEY Time MSIV Accumulator Pressure LCO and action entered number Train T=0 170 A 4950 LCO 3.7.2 condition a T=1 hr 180 A 4975 LCO 3.7.2 condition c T=2 hrs 171 B 4950 LCO 3.7.2 condition e T=3 hrs 170 A 5200 LCO 3.7.2 condition b ANSWER KEY Page 7 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 1 01/12/2012 6 Reformatted and modified times and conditions.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 9

A-7 PVNGS JOB PERFORM ANCE M EASURE CANDIDATE INITIAL CONDITIONS:

Unit 1 is in Mode 1 and has had a series of events associated with the Main Steam Isolation Valves (MSIVs).

INITIATING CUE:

Your task is to evaluate MSIV status for the time line (attached) and determine what LCO and action should have been applied for each time.

The following chart gives a chronological order of conditions that existed with Unit 1s MSIVs.

Fill out all LCO actions that are entered.

Time MSIV Accumulator Pressure LCO and action entered number Train T=0 170 A 4950 T=1 hr 180 A 4975 T=2 hrs 171 B 4950 T=3 hrs 170 A 5200 CANDIDATE Page 9 of 9

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1290020301, Conduct On Shift Operations IAW Conduct of Shift Operations TASK STANDARD: Determine hold points exceeded, approval needed, and which AO will perform the task K/A: 2.3.4 K/A RATING: RO: 3.2 SRO: 3.7 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 20 minutes

REFERENCES:

75DP-9RP01, Radiation Exposure and Access Control SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT OTHER X JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10-11-2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

1. 75DP-9RP01 This JPM was written using Revision 17 of 75DP-9RP01. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

2. Calculator

3. Pen and Paper Page 2 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

Page 3 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INITIAL CONDITIONS:

You are the Outage SRO. You will be assigning a job to one AO from a work pool of three (listed below).

The job is to depressurize and drain piping associated with Main Spray valve 100F.

RP surveys show the AO will be in a 150 mr/hr field. The job will take 45 minutes.

Evaluate the information about each AO below and answer the questions below.

2010 Exposure G. Norman A. Palmer F. Couples (in mrem) RW Operator Shift AO FIN Operator Previous 4 years 8227 527 832 dose (2007-2010) 1st Quarter (2011) 1446 103 414 Most exposure was from Spent resin operations 2nd Quarter (2011) 113 62 317 rd 3 Quarter (2011) 122 24 188 th 4 Quarter (to date) 65 1207 982 Most exposure was from Most exposure was from RCP lineups at outage EDT sludge lancing support.

beginning INITIATING CUE:

Use the worksheet on the following page to document answers.

List any hold point that may occur during this job (assuming each one performed the evolution).

List whose approval would be necessary for any hold points that would be exceeded.

(Assume authorization for current dose levels have already been obtained.)

Ascertain which AO will perform the job based on total dose.

Page 4 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 5 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

Examinee determines total dose Examinee calculates that 112.5 received for the job. mrem will be accumulated on this job.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Examinee determines the hold Examinee determines hold points points that will be exceeded for exceeded are:

each operator.

G. Norman - would exceed 10 rem cumulative exposure in 5 years.

A. Palmer - would exceed 1500 mrem for the calendar year.

F. Couples - would exceed 2000 mrem for the calendar year.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Examinee determines whose Examinee determines the approval required approval need for each operator is as follows:

G. Norman - Vice President, Nuclear Operations A. Palmer - RP Dept. Leader F. Couples - RP Director SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Examinee ascertains which Examinee determines A. Palmer, Auxiliary Operator will perform Shift AO has the lowest year to the job based on ALARA criteria. date exposure.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 7 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam ANSWER KEY List any hold point that may occur during this job (assuming each one performed the evolution):

Norman 10 rem in 5 years Palmer 1500 mrem for the calendar year Couples 2000 mrem for the calendar year List whose approval would be necessary for any hold points that would be exceeded:

Norman V.P. Nuclear Operations Palmer RP Department Leader Couples RP Director Ascertain which AO will perform the job based on ALARA criteria:

AO to perform work A. Palmer ANSWER KEY Page 8 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 003 10/11/2011 6 Modified JPM from 2010 NRC Initial Exam REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 9 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Examinee Handout INITIAL CONDITIONS:

You are the Outage SRO. You will be assigning a job to one AO from a work pool of three (listed below).

The job is to depressurize and drain piping associated with Main Spray valve 100F.

RP surveys show the AO will be in a 150 mr/hr field. The job will take 45 minutes.

Evaluate the information about each AO below and answer the questions below.

2010 Exposure G. Norman A. Palmer F. Couples (in mrem) RW Operator Shift AO FIN Operator Previous 4 years 8227 527 832 dose (2007-2010) 1st Quarter (2011) 1446 103 414 Most exposure was from Spent resin operations 2nd Quarter (2011) 113 62 317 rd 3 Quarter (2011) 122 24 188 th 4 Quarter (to 65 1207 982 date) Most exposure was from Most exposure was from RCP lineups at outage EDT sludge lancing beginning support.

INITIATING CUE:

Use the worksheet on the following page to document answers.

List any hold point that may occur during this job (assuming each one performed the evolution).

List whose approval would be necessary for any hold points that would be exceeded. (Assume authorization for current dose levels have already been obtained.)

Ascertain which AO will perform the job based on total dose.

Page 10 of 11

A-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Candidate Worksheet Exposure G. Norman A. Palmer F. Couples (in mrem) RW Operator Shift AO FIN Operator Previous 4 years dose 8227 527 832 2007-2010 1st Quarter (2011) 1446 103 414 Most exposure was from Spent resin operations 2nd Quarter (2011) 113 62 317 rd 3 Quarter (2011) 122 24 188 th 4 Quarter (to date) 65 1207 982 Most exposure was from Most exposure was from RCP lineups at outage EDT sludge lancing support.

beginning List any hold point that may occur during this job (assuming each one performed the evolution):

G. Norman A. Palmer F. Couples List whose approval would be necessary for any hold points that would be exceeded:

G. Norman A. Palmer F. Couples Ascertain which AO will perform the job based on total dose:

AO to perform work Page 11 of 11

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 This procedure provides the minimum administrative controls for personnel exposure to radiation or radioactive materials including Radiological Control Area (RCA) access/egress, administrative exposure hold points and Radiation Exposure Permit (REP) generation.

This procedure contains the following appendices which define requirements for pre-natal exposure, requesting new administrative exposure hold points, reporting personnel overexposures to the NRC, authorizing waivers of RCA access prerequisites, and requesting RCA access for visitors:

Appendix A - Request for a Higher Administrative Exposure Hold Point Appendix B - Pre-Natal Dose Limit Statement Appendix C - Criteria for Reporting Personnel Overexposures to the USNRC Appendix E - Radiation Protection Requirement Waiver Appendix F -Visitor Request for RCA Access Appendix G - Embryo / Fetus Dose Assessment Appendix H - Off Site Support Agency Radiological Determination Matrix Appendix I - Supplemental Exposure Notification Information Use:

Activity can be performed from memory. All

Review the procedure before using, if not done recently.

Document is available and referenced for review as needed.

The procedure can be carried out section by section, allowing resequencing of steps within the section.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 1 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 Table of Contents Section Page Number

1.0 Purpose and Scope

3 1.1 Purpose 3 1.2 Scope 3 2.0 Responsibilities 3 3.0 Procedure 8 3.1 General 8 3.2 Personnel Radiation Dosimetry 9 3.3 Dosimetry for Visitors 13 3.4 Radiation Exposure Permits (REP) 16 3.5 Restricted Area Access and Egress 18 3.6 Radiological Controlled Area Entry 19 3.7 Monitoring/Coverage of Radiological Work 20 3.8 Radiological Controlled Area Exit 21 3.9 Special Area Access 23 3.10 Radiation Exposure Limitations and Controls 26 3.11 Assignment of Higher Administrative Exposure Hold Points 30 3.12 Personnel Overexposures 32 3.13 Director, Site Radiation Protection Review of Radworker Error 32 3.14 Documentation 32 4.0 Definitions and Abbreviations 33 4.1 Definitions 33 4.2 Abbreviations 36 5.0 References 37 5.1 Implementing 37 5.2 Developmental 37 6.0 Summary of Changes 39 7.0 Appendices 39 Appendix A - Request for a Higher Administrative Exposure Hold Point 40 Appendix B - Pre-Natal Dose Limit Statement 41 Appendix C - Criteria for Reporting Personnel Overexposure to the USNRC 42 Appendix D - Commitment Action Tracking System 43 Appendix E - Radiation Protection Requirement Waiver 44 Appendix F - Visitor Request for RCA Access 45 Appendix G - Embryo / Fetus Dose Assessment 47 Appendix H - Off Site Support Agency Radiological Determination Matrix 49 Appendix I - Supplemental Exposure Notification 50 NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 2 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 1.0 PURPOSE and SCOPE 1.1 Purpose This procedure provides administrative controls for working with or in the vicinity of radiation or radioactive materials within the Restricted Area to ensure that personnel radiation exposure is maintained as low as is reasonably achievable (ALARA).

(RCTS2 002495-01, RG 8.8R3, RCTS2 010602-01, FSAR 12.3.1.2 )

1.2 Scope 1.2.1 This procedure encompasses responsibilities for entering and exiting a Radiological Controlled Area (RCA), administrative exposure hold points, Radiation Exposure Permit (REP) generation, authorizing waivers of RCA access prerequisites, and requesting RCA access for visitors.

1.2.2 Planned Special Exposures shall be conducted and authorized in accordance with 75RP-9RP19, "Planned Special Exposures."

2.0 RESPONSIBILITIES 2.1 Individuals Although Radiation Protection (RP) personnel oversee radiological controls within the station, each individual involved in work within the Restricted Area must remain constantly aware of potential radiological problems.

Each individual's actions directly affect his/her exposure to radiation when working in the vicinity of radiation sources.

Each individual has the following responsibilities:

2.1.1 Not to loiter in Radiological Controlled Areas (RCA).

2.1.2 Not to move or adjust any Radiation Protection boundary, barrier or posting without the approval of Radiation Protection.

2.1.3 Remaining aware of their individual exposure status and ensuring they remain below their administrative exposure hold point (see Section 3.10, Radiation Exposure Limitations and Controls).

2.1.4 Complying fully with the instructions of RP personnel in all matters pertaining to radiation protection.

2.1.5 Complying with standard operating procedures, warning signs, and barriers that concern radiation/contamination control.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 3 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 2.1.6 Reading the applicable Radiation Exposure Permit (REP) for their specific job or task and obeying all instructions and requirements (i.e., dosimetry and protective clothing requirements).

2.1.7 Correctly wearing designated dosimetry devices, protective clothing, and respiratory protection equipment as prescribed by procedures or instructions.

RP Personnel may relieve individuals of the responsibility to Self Monitor dosimetry due to contamination control or when employing remote monitoring technologies.

2.1.8 Promptly notifying RP personnel of any known or suspected change in radiological conditions.

2.1.9 Ensuring activities do not create unnecessary radiological problems for others, and being alert for the possibility that activities of others may change the work area's radiological conditions.

2.1.10 Notifying RP supervision of any aspects of radiation protection that they believe are not being properly administered.

2.1.11 Promptly notifying RP personnel of any known or suspected overexposure, or lost or damaged dosimetry.

2.1.12 Reporting all open wounds to RP prior to entering the RCA and reporting any wounds or skin contamination received while in the RCA.

2.1.13 Notifying Dosimetry of any medical diagnosis or treatment involving the intake of radioactive pharmaceuticals (e.g., I-131, Tc-99m, Tl-201), or medical treatments such as cobalt implantation before entering the Restricted Area.

2.1.14 Not smoking, eating, drinking, chewing, or having possession of such items while in a RCA, unless authorized by RP Management.

2.1.15 Immediately leaving the affected area and contacting RP when an Area Radiation Monitor alarms.

2.1.16 Preventing the spread of contamination by contacting RP personnel for direction on the removal of tools, equipment, and/or trash from contaminated areas and following RP instructions for the disposition of these items.

2.1.17 Surveying for personal contamination when leaving a contaminated area or radiological control point, as directed by RP.

2.1.18 Ensuring that prior to removing tools and equipment from the RCA, those tools and equipment are surveyed by RP personnel, as applicable.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 4 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 2.1.19 Notifying the supervisor and providing Dosimetry with a completed Appendix B, "Pre-Natal Dose Limit Statement" if a female decides to declare her pregnancy or her intent to become pregnant or she suspects she may be pregnant.

2.1.20 Providing bioassay samples for the purpose of detection of radionuclides when requested by RP personnel.

2.1.21 Notifying Dosimetry of any personal information changes such as name, address, department number, employer, etc., to allow updates of the dosimetry records.

2.1.22 Informing Dosimetry of any occupational exposure received at an offsite facility while an employee of PVNGS.

See Appendix I - Supplemental Exposure Notification (CRAI 2977470) 2.1.23 Keeping RP informed of the nature of work being performed in the RCA and any of changes that should occur to the work scope.

2.1.24 Ensuring monitoring is performed as follows, or as directed by RP, if protective clothing is worn while working in an RCA.

Whole body monitoring by PCM or equivalent (e.g., CM-11, FHZ380AB) is performed at approximately eight (8) hr intervals.

Monitoring for hot particles when exiting an HPCA with a stay time not to exceed six (6) hours if an HPCA was entered 2.1.25 Obtaining an exit bioassay analysis count prior to terminating at PVNGS 2.1.26 Performing RCA access and egress via ARACS for those REPs which allow automated access.

2.2 Work Group Section Leaders Work Group Section Leaders are responsible for planning and coordinating tasks to be performed within a RCA with RP. Other responsibilities include:

2.2.1 Evaluating each work order to determine the requirement for a REP, based upon system, location, and radiological conditions.

2.2.2 Providing work orders, as requested by RP, via electronic routing location code 360 for RP evaluation and REP assignment. (IIR 010301-01)

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 2.2.3 The exception to Step 2.2.2 will be those work orders determined to be emergent work.

If the work order requires a REP, the planner should contact RP as soon as practicable to allow time for RP preparation.

2.2.4 High Profile / High Risk Activities (REP JHES Cat 1) require Work Group Leaderships (or designee) increased involvement in the REP Planning and REP ALARA Review processes. See 75RP-9RP02, Radiation Exposure Permits. (CRAI 3152607, 3152614, SOER 01-01 #3) 2.2.5 Ensuring that RP related steps, hold points, and comments resulting from work order reviews are incorporated into the work order or resolved in conjunction with RP.

2.2.6 Ensuring that employees under their supervision have completed required radiation protection training and are fully qualified for use of respiratory protection equipment, if applicable.

2.2.7 Ensuring their personnel are familiar with the task to be performed so that maximum task benefit is derived when worker exposure to radiation is involved.

2.2.8 Ensuring that workers assigned to the tasks have sufficient remaining exposure available to contribute significantly to the completion of the task and that requests for new administrative exposure hold points are submitted to RP in a timely manner with proper justification.

2.2.9 Coordinating the activities of their workers with those of other work groups to achieve maximum efficiency in the task as a whole and to minimize the potential for unnecessary exposure due to poor communications or lack of proper planning/scheduling.

2.2.10 Ensuring that workers under their supervision comply fully with RP personnel in matters pertaining to radiation protection and that they follow the specific instructions and requirements on the REP.

2.2.11 Routinely monitoring the activities of their personnel during job performance to ensure that proper radiological protection measures are being used.

REP JHES Cat 1 activities require increased levels of work group supervisory oversight. (CRAI 3152616, SOER 01-01 #3 )

2.2.12 Ensuring that parts, tools, and equipment necessary to perform the task are proper for the job, readily available, and have proper power sources available.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 2.2.13 Developing man-Rem estimates for each job.

2.3 Director, Site Radiation Protection The Director, Site Radiation Protection, is responsible for:

2.3.1 Establishing the radiation exposure control procedures. ( RCTS2 010553-01 )

2.3.2 Ensuring the investigation of all actual or suspected personnel overexposures.

2.3.3 Approving requests for administrative exposure hold points above 2 rem/year.

2.4 Radiation Protection Department Leaders Radiation Protection Department Leaders are responsible for approving requests for administrative exposure hold points above 1.5 rem/year.

2.5 ALARA Committee Chairman The ALARA Committee Chairman is responsible for approving requests for administrative exposure hold points greater than 2500 mrem/yr up to 4000 mrem/yr and any new hold point which would allow an individual's cumulative lifetime exposure (in rem) to exceed the individual's age (in years).

2.6 Vice President, Nuclear Production The Vice President, Nuclear Production is responsible for approving any administrative exposure hold points which would allow an individual to accumulate more than 10 rem in 5 years.

2.7 Radiation Protection Radiation Protection sections, as applicable, are responsible for:

2.7.1 Controlling the initiation, revision, and termination of REPs.

2.7.2 Specifying REP requirements, such as the personnel dosimetry, protective clothing, and respiratory protection equipment requirements.

2.7.3 When necessary, issuing dosimetry to individuals as specified by the REP.

2.7.4 Relieving the Radworker of the responsibility to self-monitor dosimetry when the worker is unable to self-monitor.

2.7.5 Evaluating radiological conditions throughout the site.

2.7.6 Updating radiological postings and access control requirements.

2.7.7 Documenting (via manual records or by computer access control system) personnel access/egress into RCAs on those REPs which do not allow automated access via ARACS and when ARACS is not available.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 2.8 Dosimetry The Dosimetry Section is responsible for:

2.8.1 Providing, when necessary, TLDs to monitor an individual's exposure.

2.8.1.1 By issuing personnel record thermoluminescence dosimeters (TLDs) and performing a periodic change-out and evaluation of these record TLDs.

2.8.1.2 By providing special dosimetry to RP for issue to individuals.

2.8.2 Making available to site departments involved in radiological work, a periodic listing of the exposure to date for departmental personnel.

2.8.3 Performing whole body counts.

2.9 Operations Shift Manager The Operations Shift Manager is responsible for ensuring that RP is informed of changes in plant conditions which are known to have significant impact on radiological conditions.

3.0 PROCEDURE 3.1 General 3.1.1 Administrative controls are placed on access to the RCA due to the proximity of direct sources of radiation and the possibility of entering areas that are contaminated or contain airborne radioactivity.

3.1.2 Computerized access control systems are used as tools to control personnel access to the RCA. The systems provide exposure data and user messages to assist RP personnel in this task. ( QATS 390346-08, UFSAR 12.5.2.2.7 )

3.1.2.1 When the computerized system(s) are available, their services may be used during the performance of this procedure.

3.1.2.2 When the computerized system(s) are not available, methods of control should be performed in accordance with guidance provided in the appropriate RP written instruction.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.2 Personnel Radiation Dosimetry 3.2.1 The Radiation Protection requirements for issuing an individual a record TLD include:

A current NRC Form 4 or

A written signed statement from the individual indicating occupational exposure received during the current year and previous years.

3.2.2 The Radiation Protection requirements for unescorted access within an RCA include:

3.2.2.1 Successful completion of Radiological Work Practices (RWP) training.

3.2.2.2 Whole body count performed at PVNGS.

3.2.2.3 If necessary, the 3.2.2.1 and/or 3.2.2.2 RP requirement(s) for unescorted access may be waived with approval of the Director, Site Radiation Protection.

Document the approval and any assigned restrictions on Appendix E, "Radiation Protection Requirement Waiver."

3.2.3 Personnel requiring entry into the Restricted Area who may be expected to receive radiation exposure in excess of 100 mrem/year DDE or 10% of the exposure limits specified in 10CFR20.1201(a) shall be issued a personnel dosimetry device. ( RCTS2 010512-01, RG 8.4R0, RCTS2 041015-01, FSAR 12.5.3.3, RP 046012-01, 10CFR20.1502(a), ICR 00120 - ANI recommendation)

Record TLDs are normally issued at the Dosimetry Office, and thereafter should be returned and picked up at the security entrance to the Restricted Area.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.2.4 Personnel will obtain dosimetry (as specified on the REP) which shall be worn at all times within an RCA. ( RCTS 010827-01, RCTS2 010523-01, RG 8.2R0, RCTS2 041026-01, FSAR 12.5.3.6 )

An approved exception to this requirement is when Special Dosimetry is issued that includes HEAD Dosimetry. With RP permission, Head Dosimetry may be hand carried by the Radworker to the job site.

An approved exception to this requirement is during RCA egress when dosimetry is removed and surveyed.

An approved exception to this requirement is when Protective Clothing is being doffed.

3.2.4.1 Self-indicating dosimeters (SID), such as an Electronic Personal Dosimeter (EPD), provides an individual's current exposure status in between record TLD evaluations.

( RCTS2 010679-01, RCTS2 041027-01, FSAR 12.5.3.6 )

The exposure information obtained from the SID is used for job exposure tracking and by departments for budgeting job exposure for their personnel.

3.2.4.2 RP may also require an alarming dosimeter or special dosimetry to be worn on certain jobs.

Special dosimetry is used for monitoring the extremities, monitoring neutron radiation fields, or obtaining localized readings in an abnormal, varying, or non-uniform radiation environment.

3.2.4.3 DMC-2000 EPDs equipped with a PAM-1 (or equivalent) are:

Required in High Radiation Areas when the workers ability to hear an alarm is impaired by high noise environment, hearing protection use, use of audio headset or personal hearing loss. (CRAI 3218552) (CRAI # 2817781)

To be considered in Radiation Area in situations where a workers hearing is impaired (for instance while using audio headsets) based on plant conditions and the probability of radiological conditions changing during the work.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17

RP Leader's authorization is required to deviate from these requirements on a case by case basis. (CRAI 3218533)

In addition to having workers wear an external alarming device; the following additional dose control measures should be emphasized:

More frequent monitoring of dosimetry, Reduced stay times in high noise/high radiation work areas. (ICR 00349 and ICR 00483) 3.2.5 Placement of dosimetry devices should be as follows:

3.2.5.1 Dosimetry devices (e.g., TLDs, SIDs) should normally be worn on the front of the body between the thigh and head, unless directed otherwise by RP.

3.2.5.2 TLDs should be worn on the outside of protective clothing when skin is exposed and shallow-dose equivalent is of concern (e.g.,

noble gas environment).

3.2.5.3 TLDs should be placed under the protective clothing if all skin is covered (i.e., full PCs plus respirator).

3.2.5.4 Special dosimetry shall be worn as specified on the REP.

SIDs should be worn on the same approximate location of the body as the special dosimetry.

3.2.5.5 SIDs should be worn so that they are easily retrieved and read.

3.2.5.6 The neutron TLD should normally be worn face out on the front and center of the body between the thigh and the head.

The neutron TLD should be held tightly to the body by either a pouch or belt, or by use of tape.

3.2.6 Personnel are responsible for the safekeeping of their dosimetry devices and shall not tamper with nor cause the dosimetry to be exposed to radiation except during the performance of work requirements. Examples include: do not pass dosimetry device (TLD or EPD) through the security x-ray and do not wear dosimetry following the administration of radiopharmaceuticals unless directed by Radiation Protection.

(CRAI 3165248)

Lost or damaged dosimetry shall be immediately reported to NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 11 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 Radiation Protection and a report filed in accordance with 75RP-9ME23, "Lost or Damaged Dosimetry," by RP personnel.

3.2.6.1 Off-scale readings from SIDs shall be reported to RP personnel immediately for a dose evaluation.

3.2.6.2 If an individual's dosimeter alarms, the individual shall:

warn other workers in the vicinity (ACT 3075200)

relocate to a low dose area

contact RP to determine requirements for remaining in the RCA (e.g., reset/replace dosimeter, have TLD read).

3.2.7 When working in a contaminated area, dosimetry devices should be worn so as to prevent them from becoming contaminated.

Dosimetry devices should be protected from contamination (both radiological and non-radiological) as much as practical, without interfering with the devices proper operation. Whirl pack or zip-lock bags are normally used for this purpose.

When practical, dosimetry should not be covered up such that it cannot be seen and/or heard or impair self-monitoring of exposure by the worker.

In the event that dosimetry is worn under protective clothing impairing the workers ability to see and/or hear the dosimetry, RP Personnel shall assume responsibility for monitoring the workers exposure. (ICR 00483 and ICR 00432) 3.2.8 Exposures received by personnel monitored by dosimetry devices, as outlined in this section, should be recorded under the applicable REP number. ( RCTS2 009656-01, RG 8.10R1R 2.A )

3.2.9 Visitors entering the RCA should be issued dosimetry and be continuously escorted to ensure that radiological requirements are met.

3.2.10 For assistance in determining dosimetry and training requirements, exposure limits, etc. for Off Site Agencies assigned to PVNGS, consult Appendix H Off Site Support Agency Radiological Determination Matrix. (CRAI 2853889 and ICR 450)

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.3 Dosimetry for Visitors Issue, exchange, evaluate, and terminate Visitor dosimetry as follows:

3.3.1 Dosimetry Device - Use an EPD to monitor exposure.

3.3.2 Access Restrictions

RCA entries - Must be escorted by a qualified radworker.

Exposure allowed - 100 mrem TEDE per visit.

No entries allowed into the following areas:

High Radiation Area (HRA)

Locked High Radiation Area (LHRA)

Airborne Radioactivity Area (ARA)

Hot Particle Control Area (HPCA)

High Contamination Area (HCA)

Contaminated Area (CA) entry - Allowed if approved by an RP Department Leader.

3.3.3 Requesting RCA ACCESS 3.3.3.1 The requester shall ensure completion of Section A of Appendix F, "Visitor Request for RCA Access" and provide the completed form to the appropriate RP leader for approval.

3.3.3.2 The appropriate RP leader will complete Section B.

3.3.3.3 The Visitor and Escort will complete Section C.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.3.4 Dosimetry Issue - (Section D of Appendix F) 3.3.4.1 Ensure the requirements in 3.3.3 have been completed.

3.3.4.2 Verify if a record TLD has been previously issued to the individual during the current year. (A computer access control system may be used to perform verification.)

The name of the individual completing the verification shall be entered on the line provided in Appendix F, Part 2, line b.

3.3.4.3 If the following are met, issue an EPD:

The individual was not issued a record TLD at PVNGS during the current year, and

The individual's current year TEDE is less than 1800 mrem or

RP management approval has been obtained for those individuals whose current year TEDE is greater than 1800 mrem and were not previously issued a record TLD at PVNGS during the year.

3.3.4.4 If the individual does not meet the items in 3.3.4.3, the visitor process cannot be used to allow entry into an RCA.

If the individual was previously issued a record TLD at PVNGS during the current year, they must be issued another record TLD in accordance with 75RP-9ME21 TLD Issue, Exchange and Termination to enter an RCA.

3.3.4.5 Enter the appropriate information in Section D, Dosimetry Device Issue and Results of Appendix F for each RCA entry. (e.g., Issue Date, EPD Serial Number, RP Initials) 3.3.4.6 The visitor's escort is responsible for ensuring the visitor obtains an EPD prior to entering an RCA.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.3.5 Documentation Use Section D, Dosimetry Device Issue and Results of Appendix F to keep track of the visitor's RCA entries.

The visitor's escort is responsible for maintaining possession of the paperwork and ensuring it is properly filled out for each RCA entry.

3.3.6 Exposure Evaluation Evaluate the visitors exposure after each RCA entry by:

Recording the EPD exit reading on Appendix F, and

Calculating the exposure received for the entry, and

Calculating the "Accumulated Total Dose" (in mrem)

Ensuring the "Accumulated Total Dose" remains below 100 mrem.

3.3.6.1 Do not allow further RCA entries if they would cause the visitor's accumulated total dose to exceed 100 mrem.

3.3.6.2 If the individual requires further RCA entries and does not have sufficient visitor exposure remaining, then issue the individual a TLD in accordance with 75RP-9ME21 TLD Issue Exchange and Termination.

3.3.7 Reporting of Exposure 3.3.7.1 Forward the completed Appendix F to Dosimetry.

3.3.7.2 Reporting of visitor exposure is not required.

If requested, a copy of Appendix F may be provided to the individual after it has been reviewed by Dosimetry.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.4 Radiation Exposure Permits (REP) 3.4.1 General 3.4.1.1 REPs are the principal administrative means to manage radiation exposure received by personnel at PVNGS.

( RCTS2 010665-01, FSAR 12.5.3.2.C )

3.4.1.2 A REP should specify the job to be performed, the radiological conditions at the job location (except Standing REPs), the protective clothing, dosimetry and respiratory protection requirements for the job, the Reg. Guide 1.16 work classification for the job, and the date(s) and time that the REP is valid.

( RG 1.16, C.1.b.3 )

Additionally, any special instructions for completing the job in a radiologically safe manner should be specified on the REP.

3.4.1.3 An active REP shall be required for the following:

Any job or task within a RCA.

( RCTS2 010664-01, FSAR 12.5.3.2.C )

Any use of radioactive sources which could result in significant exposures to individuals

( RCTS 010913-01; RCTS2 010683-01, FSAR 12.5.3.7 )

3.4.1.4 RP has the capability to expedite entries by individuals into RCAs should it become necessary to meet critical operational needs.

This can be done by providing an RP technician to escort personnel in lieu of generating a new REP.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.4.2 Initiating a REP 3.4.2.1 Personnel needing to perform work requiring a REP should provide the RP Operations ALARA Planning Section, with information pertaining to the work to be performed (e.g.,

component ID, location, scope of work, etc.).

3.4.2.2 The work group supervisor or designee may be required to supply a list of personnel authorized to enter on that REP.

3.4.2.3 Copies of REPs are posted or made available at the access point(s) to RCAs where work is to be performed. The original will be kept on file by RP while that REP is active.

3.4.3 Revising a REP All revisions to REPs should be made by RP personnel, who should ensure all copies are revised.

3.4.4 Terminating a REP 3.4.4.1 When all work covered by the REP is completed, the originator should notify RP.

3.4.4.2 RP personnel should terminate all associated REPs and ensure all copies are removed.

3.4.4.3 When the expiration date of the REP has been reached, RP should terminate the REP unless requested by the originator to extend the REP.

3.4.4.4 RP may terminate the REP if they determine the radiological conditions at the job site have changed (or will change), or if the REP is improperly used (i.e., scope of the original job has changed).

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.5 Restricted Area Access and Egress 3.5.1 Personnel issued a TLD shall pick up and wear the TLD upon entering a Restricted Area. ( RCTS2 010660-01, FSAR 12.5.3.2.A )

Visitors without a designated TLD storage location should pick up their dosimetry at the Dosimetry Office during normal working hours or from RP at the applicable unit.

3.5.2 All personnel issued a TLD shall return their TLD to the designated storage location upon exiting a Restricted Area except as noted below. (CRAI 3165249) 3.5.2.1 Individuals whose work involves radioactive material outside of an established Restricted Area.

NOTE The Emergency Plan exception is applicable for drills as well as an actual emergency.

3.5.2.2 Individuals required to exit a Restricted Area due to the Emergency Plan for:

Assembly and Accountability, or

Evacuation, or

Emergency Plan assignment(s) 3.5.2.2 Security personnel while working in Protected Area Security Access Facilities and the Sally Ports. (CRAI 3391284) 3.5.3 All personnel exiting the Protected Area through the Security Building should be monitored by passing through a radiation portal monitor.

3.5.4 If the portal monitors alarms, the individual shall attempt monitoring a second time.

3.5.4.1 If a portal monitor alarms on the second monitoring attempt, the individual shall ensure RP Operations in Unit 2 is notified ( with the exception of those individuals who have a valid Portal Monitor Release form ) ( RP ICR 00216, RP ICR 00219 )

When notified, RP will perform an evaluation of the situation and take the appropriate actions.(CRDR 2548498)

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.6 Radiological Controlled Area Entry 3.6.1 Normal Unit RCA access is established at the 140' Access Control Area located adjacent to the Unit RP Island using an Access Control Turnstile, although other RCAs may exist within the Restricted Area.

(RCTS2 010661-01, FSAR 12.5.3.2.B, CRAI 2510316 )

CAUTION Minimize Unit RCA Entries from other than the 140 Aux RP Control Point. (CRAI 3065824)

Personnel who must enter a Unit RCA other than at the Aux. 140',

must be approved by RP prior to entry.

Personnel who must enter a non-unit RCA located inside or outside the permanent Restricted Area boundary (e.g., Service Bldg.,

LLRMSF, ISFSI ) must be approved by RP prior to entry.

3.6.2 The RP requirements for unescorted entry into an RCA are:

Have a TLD and SID,

Up to date whole body count (WBC),

RWP training is current,

Read the appropriate REP,

Received any associated Pre-Job Briefing, and

Signed onto the appropriate REP via a REP Sign-in Sheet or electronic signature as applicable.

3.6.2.1 By signing the REP, individuals indicate they have read and understand the REP requirements and will comply with them.

( RCTS 010915-01 )

3.6.2.2 Personnel should read their appropriate REP prior to each subsequent entry.

3.6.2.3 If necessary, the requirements for a WBC and/or RWP may be waived to allow an RCA entry with approval of the Director, Site Radiation Protection.

Document the approval and any restrictions on Appendix E.

3.6.3 If there are any questions about the REP, radiological conditions of the work area, specific requirements set by RP, or if required by the REP, contact RP.

3.6.4 Personnel should obtain any protective clothing, additional dosimetry and/or respiratory protection equipment required by the REP.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.7 Monitoring/Coverage of Radiological Work 3.7.1 Work group supervision (e.g., section leaders, team leaders) should routinely monitor the activities of their personnel during job performance to ensure that proper radiological protection measures are being used.

Improper work practices should be immediately stopped and reported to RP personnel for an evaluation of any radiological impact.

3.7.2 RP personnel should monitor the performance of radiation workers periodically and correct improper work practices on the spot.

Issuance of a Palo Verde Action Request (PVAR), see 01DP-0AP12 may also be necessary based on the severity of any violations.

3.7.3 Continuous surveillance by RP personnel may be necessary when potentially extreme radiological conditions exist in a work area.

( RCTS 039536-02, NRC IR 529/88-22-01, LER 2-88-011-01 )

Examples of these types of conditions include, but are not limited to, the following:

a) High radiation levels See section 3.9 for specific requirements.

(e.g., more than 1 rem/hr whole body, 5 rem/hr extremity, etc.)

b) High potential for uptakes of radioactivity, such as:

High loose surface contamination levels (e.g., above 1.0E6 dpm/100 cm2 or 1000 dpm Alpha ) or

High particulate/iodine airborne radioactivity levels (e.g., 10 DAC or greater).

c) Radiological conditions which are unknown or may change significantly or rapidly due either to the nature of the work to be performed or the operation of plant systems, or as determined by RP.

3.7.3.1 Jobs requiring continuous surveillance should clearly identified on the applicable REP.

3.7.4 APS employees meeting the minimum RP experience requirements of Section 4.5.2 of ANSI/ANS 3.1 --- 1978 may change a workers REP and/or Task while in the RCA. (CRAI 3314054) 3.7.4.1 A second RP Technician meeting the minimum RP experience requirements of Section 4.5.2 of ANSI/ANS 3.1 --- 1978 shall perform a peer check verifying:.

EPD display is in run mode and displays 0.0.

DMC viewer software shows the dosimeter is in RUN mode and the correct REP and task are displayed.

Document REP and/or task change in the appropriate log book.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.8 Radiological Controlled Area Exit:

3.8.1 Personnel Monitoring at RCA Exits ( e.g., Aux. Bldg. 140 )

Personnel exiting an RCA are required to be monitored by a contamination monitor (e.g., personnel contamination monitor- PCM ) and, if operable, a radiation portal monitor (e.g., PM-7 ).

If the RCA does not have an operable PCM, then direct personnel to perform a whole body frisk and proceed to another location having an operable PCM for monitoring, as appropriate. ( RP ICR 00097 )

If the RCA does not encompass or contain a Contaminated Area, then when authorized by the cognizant RP Department Leader, personnel contamination monitoring and monitoring of personal items at the RCA exit is not required.

3.8.2 Personnel Monitoring for Radioactive Material Transfer between RCAs

( e.g., exiting through an RCA Yard gate )

Personnel involved in the transfer of radioactive material may perform a whole body frisk prior to exiting an RCA under the following conditions:

a) Personnel have not entered a Contaminated Area or have been monitored by a PCM upon exiting a Contaminated Area.

b) RP must observe the whole body frisk being performed.

c) Personnel are monitored by a PCM prior to exiting the receiving locations RCA.

If the receiving location does not have an operable PCM, then ensure monitoring by a PCM occurs as soon as practicable after completion of the transfer. ( RP ICR 00224 )

3.8.3 Except for Security gun belts, tool belts should be removed prior to entering a PCM.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 NOTE Plant personnel should be reminded that all PCM alarms are to be treated as actual contamination alarms until proven otherwise by Radiation Protection.

3.8.4 If the PCM alarms, take the following actions, as appropriate:

PCM alarm during initial monitoring:

If you receive a PCM alarm during the initial monitoring, notify RP and remain near the PCM.

3.8.5 Make applicable items to be removed from the RCA available for survey by RP personnel.

NOTE Additional guidance on PCM alarm response is provided in 75DP-0RP02, Radioactive Contamination Control.

3.8.6 If the RCA portal monitor alarms when exiting (e.g., PM-7), the individual shall notify Radiation Protection.

The RP representative will evaluate the situation and take the appropriate actions.

3.8.7 Except as specified in step 3.8.8 and 3.8.9, personnel should return all dosimetry other than their permanent whole body TLD to RP upon exiting an RCA. ( QATS 391132-05 )

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.8.8 Operations, Radiation Protection, Chemistry, Security, and Fire Protection (including roving firewatch) personnel may retain their dosimetry (e.g.,

EPD, Special dosimetry) provided:

They are logged in on an appropriate REP and,

The potential exists to need immediate access to an RCA and,

They do not leave the permanent Restricted Area.

3.8.9 Personnel may retain their dosimetry for work in RCAs located outside of the permanent Restricted Area boundary (e.g., LLRMSF ) provided:.

They are logged in on an appropriate REP, and,

The dosimetry is returned to the appropriate issue point when the work is completed (or prior to leaving the site for the day).

3.9 Special Area Access NOTE RP Personnel or personnel escorted by RP may be exempt from the REP issuance requirement during the performance of their assigned duties, provided they are otherwise following plant RP procedures for entry into High Radiation Areas.

3.9.1 High Radiation Area Access ( RP 046013-01, 10CFR20.1601(a)(3) )

3.9.1.1 Access into a High Radiation Area requires the issuance of a specific REP authorizing entry.

( RCTS2 010601-01, RCTS 011131-01, Tech Spec 5.7.1)

RP shall ensure that an individual authorized access has sufficient remaining exposure to work in the area.

Access into an HRA is NOT Authorized for individuals using Appendix F, Visitor Access Request (i.e., provided monitoring by EPD only).

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.9.1.2 Any individual or group permitted to enter a High Radiation Area shall be provided with, or accompanied by one or more of the following: ( RCTS 011132-01, Tech Spec 5.7.1 )

(a) Radiation dose rate meter.

(b) Alarming dosimeter (e.g. EPD) - Entry with an alarming dosimeter may be made after the dose rate levels in the area have been determined and personnel have been made aware of them by receiving a specific high radiation area briefing from RP personnel.

(c) An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the REP.

3.9.2 Locked High Radiation Area Access ( Tech Spec 5.7.2, RCTS2 010663-01 )

In addition to the HRA requirements stated in 3.9.1.1 and 3.9.1.2 above, access to Locked High Radiation Areas (areas where radiation levels could result in an individual receiving a dose equivalent in excess of 1000 mrem in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ), shall be controlled as follows:

3.9.2.1 Doors shall remain locked except during periods of access by personnel under an approved REP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas.

( RCTS 010594-01, Tech Spec 5.7.2 )

3.9.2.2 In lieu of the stay time specification of the REP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. (Tech Spec 5.7.2 )

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.9.3 Very High Radiation Areas ( RP 046014-01, 10CFR20.1602 )

In addition to the HRA and LHRA requirements above, personnel access to a Very High Radiation Area (areas where radiation levels from sources external to the body could result in an individual receiving an absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 1 meter from any surface that the radiation penetrates) shall be controlled as follows:

3.9.3.1 Access shall be under a REP which is specific to the individual VHRA and requires continuous surveillance by RP.

3.9.3.2 Entry shall be authorized by an RP department leader.

3.9.3.3 The Operations Control Room Supervisor shall be contacted prior to entry into a VHRA.

3.9.4 Contaminated Area Access/Egress Contaminated Area access and egress should be performed in accordance with the Radioactive Contamination Control procedure. Special clothing requirements should be determined by RP and should be specified on the REP. ( RCTS2 010616-01, FSAR 12.5.1.3.B )

3.9.5 Airborne Radioactivity Area Access Respiratory protection equipment should be determined by RP and specified on the REP. ( RCTS2 010673-01, FSAR 12.5.3.5 )

01DP-0IS08, "PVNGS Respiratory Protection Equipment Usage" provides additional guidance and restrictions.

3.9.6 Containment Building Access After shutdown, the containment is accessible for limited periods of time and all access is controlled, using an Access Control Turnstile. Areas within the containment building should be surveyed by RP personnel to determine allowable working times and establish any special access requirements which may be necessary.

(RCTS2 010606-01, FSAR 12.3.2.2.2, CRAI 2510316)

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.10 Radiation Exposure Limitations and Controls 3.10.1 10CFR20.1201 Occupational Dose Limits ( RP 046002-01, 10CFR20.1201(a) )

3.10.1.1 Annual Occupational radiation dose to adults (except for planned special exposures) shall be limited to:

(a) 5 rem total effective dose equivalent (TEDE) or 50 rem total organ dose equivalent (TODE), whichever is more limiting and, (b) 15 rem lens dose equivalent (lens of the eye) and, (c) 50 rem shallow-dose equivalent (skin or any extremity).

3.10.1.2 Occupational dose limits authorized by 10CFR20.1201 shall be reduced by 1.25 rem TEDE and 12.5 rem shallow-dose equivalent for each quarter that occupational radiation exposure records are not available (i.e., no signed statement of previous occupational exposure or incomplete NRC Form 4).

( RP 046036-05, 10CFR20.2104(e)(1) )

3.10.1.3 Personnel with an incomplete NRC Form 4 shall not be available for planned special exposures.

3.10.2 PVNGS Annual Exposure Goal To keep exposures ALARA, PVNGS has established an annual exposure goal of 2 rem TEDE for each individual receiving occupational radiation exposure at PVNGS (not to exceed 10 rem TEDE in any 5 year period).

The annual exposure may be increased up to 2.5 rem TEDE to accommodate occupational radiation exposure received at other licensed facilities within the current year.

3.10.3 Administrative Exposure Hold Points To further maintain exposures ALARA, individuals are assigned an initial administrative exposure hold point of 1.5 rem/year TEDE.

To ensure exposures are kept ALARA, management must approve requests for assignment of higher administrative hold points (see 3.11)

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.10.4 Exposure of Pregnant Women 3.10.4.1 Declared Pregnant Woman: Female radiation workers who choose to declare their pregnancy or suspect they might be pregnant should fill out and sign a "Pre-Natal Dose Limit Statement" (Appendix B), acknowledging their exposure limitation to 50 mrem per month during pregnancy and an exposure limitation to the embryo/fetus of 500 mrem for the entire gestation period. ( RCTS2 010505-01, RG 8.13 R3, RP 046008-01, RP 046008-02, 10CFR20.1208(a) & (b) )

(a) Fill out the top section of the "Pre-Natal Dose Limit Statement," read the block for Declared Pregnant Woman, then sign the Employees Signature line.

(b) Obtain the Section Leaders Acknowledgement signature.

The females direct supervisor should assign her tasks which ensure the dose restriction are adhered to.

(c) Deliver the "Pre-Natal Dose Limit Statement" to Dosimetry after signature by the supervisor. ( ICR00130 )

(d) Upon receipt of the Appendix B, Dosimetry will perform the following in order to establish baseline monitoring for the declared pregnant woman: ( RP ICR 00232 )

Whole body count the individual

Issue a new TLD and process the individuals current TLD ( if they have been issued one )

Establish a lower Administrative Exposure Hold Point NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 27 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.10.4.2 Declared Fertile Woman: Female radiation workers who choose to declare their intention to become pregnant (declared fertile woman) should fill out and sign a "Pre-Natal Dose Limit Statement" acknowledging their exposure limitation to 50 mrem per month.

(a) Fill out the top section of the "Pre-Natal Dose Limit Statement," read the block for Declared Fertile Woman, then sign the Employees Signature line.

(b) Obtain the Section Leaders Acknowledgement signature.

The females direct supervisor should assign her tasks which ensure the dose restriction are adhered to.

(c) Deliver the "Pre-Natal Dose Limit Statement" to Dosimetry after signature by the supervisor. ( RP ICR 00130 )

(d) Upon receipt of the Appendix B, Dosimetry will perform the following in order to establish baseline monitoring for the declared pregnant woman: ( RP ICR 00232 )

Whole body count the individual

Issue a new TLD and process the individuals current TLD ( if they have been issued one )

Establish a lower Administrative Exposure Hold Point (e) Declared fertile women that become pregnant should declare their pregnancy acknowledging their exposure limitation for the gestation period in accordance with step 3.10.4.1, Declared Pregnant Woman.

(f) Declared fertile women whose status has not changed after six months should resubmit the "Pre-Natal Dose Limit Statement" in accordance with step 3.10.4.2, Declared Fertile Woman.

3.10.4.3 If the dose equivalent to the female radiation worker has exceeded 500 mrem or is within 50 mrem of the 500 mrem gestation limit, by the time she declares her pregnancy, then she may receive an additional 50 mrem during the remainder of her pregnancy. ( RP 046008-04, 10CFR20.1208(d) )

3.10.4.4 NRC Regulatory Guide 8.13 states any monthly dose of less than 0.1 rem may be considered as not a substantial variation above a uniform monthly dose rate and as such will not require licensee justification. ( 10CFR20.1208(b), ICR 00088, RG 8.13, C.5 )

If a monthly dose greater than 0.1 rem is received, then a justification for the exposure should be written.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.10.4.5 If a female radiation worker no longer requires a pre-natal dose limit, she needs to inform Dosimetry, in writing, using the following method:

(a) Obtain a new Appendix B, Pre-Natal Dose Limit Statement

Fill out the personnel information at the top of the form.

Place signature in the section titled Dose Limit Correction.

(b) Obtain the Section Leaders Acknowledgement signature.

(c) Deliver the "Pre-Natal Dose Limit Statement" to Dosimetry after signature by the supervisor.

(d) Upon receipt of the Appendix B informing a pre-natal dose limit is no longer required, Dosimetry will perform the following in order to close out dose monitoring for the embryo/fetus:

Whole body count the individual

Issue a new TLD and process the individuals current TLD used to establish the baseline monitoring.

Returned the individual to their normal administrative exposure hold point.

3.10.5 Exposure of Visitors 3.10.5.1 Visitors who have not been issued permanent dosimetry and who require entry into an RCA shall be limited to 100 mrem/visit TEDE at PVNGS.

3.10.5.2 Normally, visitors should enter the RCA using Standing REPs (SREPs), and enter only those areas and perform those functions permitted by those SREPs.

3.10.5.3 Refer to Section 3.3, Dosimetry for Visitors for additional information, requirements, and restrictions.

3.10.6 Exposure of Minors No individual under 18 years of age should be permitted to receive occupational exposure to radiation or airborne radioactivity at PVNGS.

( RP 046007-01, 10-CFR20.1207, RCTS2 010506-01, RG 8.13 )

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.11 Assignment of Higher Administrative Exposure Hold Points 3.11.1 Requests for a Higher Hold Point 3.11.1.1 Management approval is needed to obtain a higher hold point.

Appendix A, "Request for a Higher Administrative Exposure Hold Point", is used to request the new hold point. These are available at the RP Island, Dosimetry office, or as an electronic form in the Palo Verde Site Specific Forms Menu under Radiation Protection.

If the request is due to an individual exceeding an assigned hold point, RP management ensures a documented evaluation is performed for the cause.

3.11.1.2 The requesting supervisor completes the Originator section of the form, ensuring the ALARA concept is maintained within their department and the request for a higher individual administrative exposure hold point is warranted. (i.e., No other qualified personnel are available who have sufficient remaining exposure below their hold point.)

3.11.1.3 Submit Appendix A to RP for concurrence, (i.e., the job scope and radiological conditions warrant the new exposure hold point).

3.11.1.4 If concurrence is obtained from RP, the request is forwarded to Dosimetry. A Dosimetry technician performs a records search to obtain appropriate information necessary to complete the Dosimetry section of the form.

(a) All occupational exposure received at licensed facilities other than PVNGS during the current year should be verified unless an exception is authorized by the Director, Site Radiation Protection.

(b) The technician completing this section should sign and date in the designated space.

3.11.1.5 The requesting supervisor should route Appendix A to applicable management in the approval chain.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.11.2 Approvals 3.11.2.1 The individual for whom the higher administrative exposure hold point is requested signs the request to verify all occupational exposure is accounted for in their PVNGS Dosimetry Records. ( RCTS 040337-02, NRC IR 528/90-55-01 NCV )

NOTE In the event that any management in the approval chain declines to sign the request, no further approval can be sought through other management.

3.11.2.2 In addition to the following approvals, any request for a higher administrative exposure hold point which would allow a worker's cumulative lifetime exposure (in rem) to exceed the worker's age (in years) are reviewed and approved by the ALARA Committee Chairman.

(a) For a Hold Point higher than 1500 mrem/year, RP Department Leader approval required.

(b) For a Hold point higher than 2000 mrem/year, Director, Site Radiation Protection approval required.

(c) For a Hold Point higher than 2500 mrem/year up to 4000 mrem/year, the ALARA Committee review and approval is required (as signified by the signature of an ALARA Committee Chairman).

(d) For any Hold Point that would cause an individual's exposure to exceed 10 rem cumulative site exposure in 5 years the Vice President, Nuclear Operations approval is required.

3.11.2.3 The request is then returned to the Dosimetry Office for processing.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 3.12 Personnel Overexposures 3.12.1 Personnel who exceed or suspect they have exceeded any exposure limit in 3.10.1.1, shall immediately report to the appropriate RP Department or the Dosimetry Office.

3.12.2 RP should obtain all pertinent information concerning the potential overexposure from the individual and initiate reporting in accordance with 90DP-0IP10, "Condition Reporting"

The Director, Site Radiation Protection, ensures the incident is investigated.

3.12.3 The individual should then be directed to the Dosimetry Office.

3.12.4 Dosimetry evaluates the individual's record TLD and restricts the individual from entering the RCA until the record TLD is reissued.

3.12.5 Any overexposure meeting the criteria of Appendix C, "Criteria for Reporting Personnel Overexposure to the USNRC", shall be reported as described in Appendix C.

3.12.6 Any report, as described in Appendix C, shall require a written report to be provided to the affected individuals(s) no later than the time of official written notification to the NRC. This report should be prepared in accordance with the Radiological Reports procedure. ( RCTS 039454-01 )

3.13 Director, Site Radiation Protection Review of Radworker Error 3.13.1 At the discretion of the Director, Site Radiation Protection, review and resolution of Radworker Error (including inappropriate, unauthorized possession or use of contraband materials in the RCA) should include:

(CRAI 3214174) 3.13.1.1 The affected Radworkers Director (and Site Coordinator for Non Utility Radworkers) and the Director, Site Radiation Protection meet, review and discuss the circumstances surrounding the Radworker Error.

3.13.1.2 The decision to lift the Radworkers RCA Access restriction is at the sole discretion of the Director, Site Radiation Protection.

3.14 Documentation Turnover documents to NIRM in accordance with the appropriate NIRM Turnover Instruction(s).

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 4.0 DEFINITIONS and ABBREVIATIONS 4.1 Definitions 4.1.1 Administrative Exposure Hold Point - An administrative control measure used as an aid to maintain individual and collective doses ALARA and prevent exceeding regulatory dose limits.

4.1.2 Annual Limit On Intake (ALI) - Means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to any individual organ or tissue. (ALI values for intake by ingestion and by inhalation of selected radionuclides are given in Table 1, Columns 1 and 2, of Appendix B to 20.1001-20.2401).

4.1.3 Automated Radiological Access Control System (ARACS) - is a computer based system which utilizes worker information, REP data and TLD data to facilitate individual automated RCA access and egress transactions. ( ICR 00114 )

4.1.4 Committed Dose Equivalent (HT,50) - Means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

4.1.5 Committed Effective Dose Equivalent (HE,50) - Is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues (HE,50 = WT HT,50).

4.1.6 Declared Fertile Woman - A woman who has voluntarily informed the licensee, in writing, of her intent to become pregnant.

4.1.7 Declared Pregnant Woman - A woman who has voluntarily informed the licensee, in writing, of her pregnancy and the estimated date of conception.

The declaration remains in effect until the declared pregnant woman withdraws the declaration in writing or is no longer pregnant.

4.1.8 Deep-Dose Equivalent (DDE) - External whole-body exposure, the dose equivalent at a tissue depth of one centimeter (1000 mg/cm2).

4.1.9 Derived Air Concentration (DAC) - Means the concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2,000 hours0 days 0 hours 0 weeks 0 months under conditions of light work (inhalation rate 1.2 cubic meters of air per hour), results in an intake of one ALI. DAC values are given in Table 1, Column 3, of Appendix B to 20.1001-20.2401.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 4.1.10 Emergent Work - Work orders of a priority nature, not appearing on the approved work list.

4.1.11 Electronic Personal Dosimeter (EPD) - an electronic dosimetry device which provides convenient monitoring of accumulated exposure by workers in an RCA, and has the capability to alarm, both audibly and visibly, at preset dose and dose rate values. The EPD can function as both a SID and an alarming dosimeter.

4.1.12 Electronic Signature - A process within the computerized access control system to document an individual worker's acknowledgement that they have read and understand the REP. Answering "yes" to the computer screen prompt asking the individual "Have you read and understood the REP" constitutes the worker's "signature" of acknowledgement.

4.1.13 Individual Qualified in Radiation Protection Procedures - Individuals are considered qualified in radiation protection procedures when they are certified as capable of successfully accomplishing the following activities as required by federal regulations, license conditions, and facility procedures pertaining to radiation protection: ( HPPOS-015 )

1. Conducting and evaluating special and routine radiation, contamination and airborne radioactivity surveys.

2. Establishing protective barriers and posting appropriate radiological signs.

3. Establishing a means of limiting exposure rates and accumulated radiation doses, including the use of protective clothing and respiratory protection equipment.

4. Performing operability checks of radiation monitors and survey meters.

5. Recommending appropriate immediate actions in the event of a radiological problem, and performing necessary activities until the arrival of health physics personnel.

6. Conducting other routine radiological duties as required on backshifts or weekends.

4.1.14 Lens Dose Equivalent (LDE) - The external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm2).

4.1.15 Personnel Contamination Monitor (PCM) - An instrument used to provide automatic WHOLE BODY MONITORING of personnel for external radioactive contamination.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 4.1.16 Radiation Exposure Permit (REP) - An administrative control which describes a specific job or task within a Radiological Controlled Area, identifies radiological conditions, and specifies the radiation protection measures required for performance of a task.

4.1.17 Radiological Controlled Area (RCA) - Any area so posted, which features positive controls for the purpose of protecting personnel from radiation exposure and radioactive contamination.

4.1.18 Restricted Area - An area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure of radiation and radioactive materials. The restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area. At PVNGS, the permanent restricted area boundary coincides with the security protected area boundary. Satellite or temporary restricted areas may also need to be established outside the permanent restricted area.

4.1.19 Self Indicating Dosimeter (SID) - a dosimetry device used to monitor a worker's radiation exposure between TLD processing periods, which is easily read by the worker in the field. Examples consist of pocket ion chamber type and electronic personal dosimeter type.

4.1.20 Shallow Dose Equivalent (SDE) - applies to the external exposure of the skin of the whole body or the skin of an extremity and is taken as the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm2).

4.1.21 Total Effective Dose Equivalent (TEDE) - The sum of the effective dose equivalent, EDE, (for external exposures) and the committed effective dose equivalent, CEDE, (for internal exposure). (CRAI 3120698)

(This change to 10CFR20.1003, Definitions, as documented in the Federal Register, Vol. 72, No.

232, Tuesday, December 4, 2007, delineates that Effective Dose Equivalent (EDE) may be substituted for Deep Dose Equivalent (DDE) for external exposures. While EDE is the primary quantity in the definition of TEDE for external exposures, licensees are required to use the DDE in place of EDE when measuring dose from external exposure unless the EDE is determined by a dosimetry method approved by the NRC.)

4.1.22 Total Organ Dose Equivalent (TODE) - The sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye.

4.1.23 Visitor - Individual who has been assigned a Visitor ACAD or badge from Security and requires an escort while in the Restricted Area.

4.1.24 Visitor Escort - An individual currently issued a TLD with an active status assigned to continuously escort a visitor in restricted areas and radiological controlled areas.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 4.2 Abbreviations 4.2.1 ACAD - Automated Control Access Device.

4.2.2 ARA - - Airborne Radioactivity Area 4.2.3 ARACS - Automated Radiological Access Control System 4.2.4 CA - Contaminated (Contamination) Area (CRAI 3373967) 4.2.5 EPD - Electronic Personal Dosimeter 4.2.6 ISFSI - Independent Spent Fuel Storage Installation 4.2.6 HCA - - High Contamination Area 4.2.7 HPCA - Hot Particle Control Area 4.2.8 HPPOS - NRC Health Physics Position (from NUREG/CR-5569) 4.2.9 HRA - - High Radiation Area 4.2.10 JHES - A job classification system which dictates required levels of RP management review and approval for REP's, based upon the radiological conditions and hazards associated with the job.

4.2.11 LHRA - - Lock High Radiation Area 4.2.12 LLRMSF - Low Level Radioactive Material Storage Facility 4.2.13 PCM - Personnel Contamination Monitor 4.2.14 RCA - - Radiological Controlled Area 4.2.15 SID - Self Indicating Dosimeter 4.2.16 TEDE - - Total Effective Dose Equivalent 4.2.17 VHRA - Very High Radiation Area 4.2.18 WBC - Whole Body Count NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 36 of 50

Radiation Exposure and Access Control 75DP-9RP01 Revision 17

5.0 REFERENCES

5.1 Implementing 5.1.1 01DP-0IS08, PVNGS Respiratory Protection Equipment Usage 5.1.2 01DP-0AP12, Palo Verde Action Request Processing 5.1.3 75DP-0RP02, Radioactive Contamination Control 5.1.4 75RP-9ME21, TLD Issue, Exchange and Termination 5.1.5 75RP-9ME23, Lost or Damaged Dosimetry 5.1.6 75RP-9RP09, Release of Vehicles, Equipment, and Material from Radiological Controlled Areas.

5.1.7 75RP-9RP19, Planned Special Exposures 5.1.8 84DP-0RM31, Handling of Proprietary, Confidential and Highly Confidential Information.

5.1.9 75RP-9RP02, Radiation Exposure Permits.

5.2 Developmental 5.2.1 Title 10 Code of Federal Regulations Part 20, Standards for Protection Against Radiation.

5.2.2 USNRC Regulatory Guide 8.4, Direct-Reading and Indirect-Reading Pocket Dosimeters; Rev. 0, Feb 1973.

5.2.3 USNRC Regulatory Guide 8.8, Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As is Reasonably Achievable, Rev. 3, June 1978.

5.2.4 USNRC Regulatory Guide 8.13, Instruction Concerning Prenatal Radiation Exposure, Rev. 3, June 1999.

5.2.5 USNRC Regulatory Guide 8.36, Radiation Dose to the Embryo/Fetus, July 1992 5.2.6 USNRC I.E. Circular No. 81-07, Control of Radioactively Contaminated Material; May 1981.

5.2.7 PVNGS Updated Final Safety Analysis Report.

5.2.8 PVNGS Technical Specifications Units 1, 2, and 3.

5.2.9 IE Information Notice No.86-107, "Entry Into PWR Cavity With Retractable Incore Detector Thimbles Withdrawn," Dec. 29, 1986.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 5.2.10 INPO Significant Operating Experience Report (SOER) 85-3, "Excessive Personnel Radiation Exposures," April 30, 1985.

5.2.11 IE Information Notice No. 84-19, "Two Events Involving Unauthorized Entries Into PWR Reactor Cavities." March 21, 1984.

5.2.12 IE Information Notice No. 82-51, "Overexposure in PWR Cavities,"

December 21, 1982.

5.2.13 IE Circular No. 76-03, "Radiation Exposure in Reactor Cavities,"

September 13, 1976.

5.2.14 INPO 05-008, "Guidelines for Radiological Protection at Nuclear Power Stations," December 2005.

5.2.15 Commitment Action Tracking System (CATS) Actions (Appendix D).

5.2.16 INPO Significant Event Report (SER) 88-37, "Personnel Radiation Overexposure Due To Work Generated Hot Spots," December 22, 1988.

5.2.17 American Nuclear Insurers (ANI) "Nuclear Insurance Inspection Report,"

Document #L060800.266, dated June 14, 2000 5.2.18 National Council on Radiation Protection and Measurements, "Limitations of Exposure to Ionizing Radiation," NCRP Report No. 16, 1993.

5.2.19 USNRC Regulatory Guide 8.38, Control of Access to High and Very High Radiation Areas in Nuclear Power Plants, May 2006.

5.2.20 USNRC NUREG-1736, Consolidated Guidance: 10 CFR 20 - Standards for Protection Against Radiation, October 2000 5.2.21 USNRC NUREG/CR-5569 ORNL/TM-12067, Health Physics Positions Data Base, May 1992 5.2.22 Site Integrated Business Plan CRAI 3084518, Review recommendation #3 of SOER 01-01.

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Radiation Exposure and Access Control 75DP-9RP01 Revision 17 6.0

SUMMARY

OF CHANGES Rev Description 16 1.) 3.2.4.3 - Revised step to match wording in 75RP-9ME27.

2.) 3.7.4 - Revised requirements for changing EPD setpoints while in the RCA. (CRAI 3314054) 3.) Appendix D - Added CRAI 3314054.

17 4.) 4.1.17 - Changed definition of RCA to allow RCA posting use outside of the Protected Area (ACT 3033630) 5.) 3.11.2.2 and App A - Changed VP Nuclear Production to VP Nuclear Operations. (ACT3382938) 6.) 2.2.13 - Step added: Develop man-rem dose estimates for each job.

(ACT 3354775) 7.) 3.3.4.3 - Reduced annual limit that RP Management approval required to issue new TLD from 2500 to 1800 mRem. (ACT 3333202) 8.) Initial line added to App. A form for technician performing record search described in step 3.3.4.2. Bullet added to 3.3.4.2 (ACT 3100983) 9.) App. F, Visitor Access Request form Section B note added to complete Part 2 prior to approval. Steps 3.3.3.1 - 3.3.3.3 added. (ACT 2991367) 10.) 4.2.4 - Changed to allow Contamination Area as well as Contaminated Area. (CRAI 3373967) 11.) App. A - Footnote added to clarify that lifetime exposure need not be obtained for workers not in a PSE program. (CRAI 3120700) 12.) 4.1.2.1 - Updated definition of TEDE to new rule. (CRAI 3120698) 13.) 3.5.2.2 - Changed to allow MSF to retain TLDs when working in the sally port. (CRAI 3391284) 7.0 APPENDICES Appendix A - Request for a Higher Administrative Exposure Hold Point Appendix B - Pre-Natal Dose Limit Statement Appendix C - Criteria for Reporting Personnel Overexposure to the USNRC Appendix D - Commitment Action Tracking System Appendix E - Radiation Protection Requirement Waiver Appendix F - Visitor Request for RCA Access Appendix G - Embryo / Fetus Dose Assessment Appendix H - Off Site Support Agency Radiological Determination Matrix Appendix I - Supplemental Exposure Notification NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 39 of 50

Radiation Exposure and Access Control 75DP-9RP01 Page 40 of 50 Rev 17 Appendix A ( Sample ) Page 1 of 1 Request for a Higher Administrative Exposure Hold Point ORIGINATOR

1. A higher Administrative Exposure Hold Point is requested for:

Name: Social Security No1: HPID No:

Exposure Hold Point Requested:

_____________________ mrem for the year of __________________

2. No other qualified personnel are available who have sufficient exposure remaining below their hold point:

Supervisor's Name: Signature: Extension: Date:

3. Reasons for request ( include REP No.):

RADIATION PROTECTION RP Concurrence: Job scope and radiological conditions warrant the higher administrative exposure hold point.

Signature: Date:

DOSIMETRY

1. Radiation Exposure (mrem): ( Fill in as applicable )

EXPOSURE CURRENT CURRENT EXPOSURE ADDITIONAL PERIOD EXPOSURE HOLD POINT REMAINING INFORMATION Current Record Dose APS Dose =

Year Included estimate of: Offsite Dose =

5 Year Lifetime2 Is exposure greater than age? Yes No

for assigning a hold point > 2500 mrem/year, all dose for current year must be record dose.

2. Dosimetry records search completed by:

Name: Date:

APPROVALS I have reviewed my exposure records at PVNGS Dosimetry and find them to be correct and complete.

X

( Date )

( Radiation Worker )

X

( Date )

( Radiation Protection Department Leader for new hold point up to 2000 mrem )

X

( Date )

( Director, Site Radiation Protection for new hold point up to 2500 mrem )

X

( Date )

( ALARA Committee Chairman

for new hold point up to 4000 mrem, or cumulative lifetime exposure will exceed workers age in years )

X

( Date )

V.P. Nuclear Operations for new hold point that would cause worker to exceed 10 rem cumulative site exposure in 5 years )

RECORDS

1. New Administrative Exposure Hold Point assigned for the period of. .

Effective beginning: .

2. Personnel Exposure file / RRAC System updated:

RP Technician Signature Date

3. Form Distribution (a) Original to: Worker's Exposure File (b) Copies to: Dosimetry, Radiation Protection, Originator 1

SSN use requires marking Appendix A as CONFIDENTIAL, see 84DP-0RM32 2

Lifetime exposures need not be obtained for individuals not participating in a planned special exposure program. (CRAI 3120700)

Radiation Exposure and Access Control 75DP-9RP01 Page 41 of 50 Rev 17 Appendix B ( Sample ) Page 1 of 1 Pre-Natal Dose Limit Statement Employee Name: Social Security No.1: Employee No.:

Telephone Extension: HPID No.: Employee Date of Birth:

I understand federal regulation 10 CFR 20.1208, "Dose equivalent to an embryo / fetus," contains the radiation exposure limits applicable to the embryo / fetus during the duration of the pregnancy.

Check one:

Declared Pregnant Woman I hereby notify APS of my pregnancy and request that my allowable exposure be limited to 500 mrem for the duration of my pregnancy and 50 mrem per month.

I also request that, if my exposure at the time of declaration exceeds 500 mrem or is within 50 mrem of the 500 mrem gestation limit, my allowable exposure for the remainder of my pregnancy be limited to 50 mrem.

The estimated date of my conception is and my estimated due date is .

Declared Fertile Woman I hereby notify APS of my fertile female status and request that my allowable exposure for the next six months be limited to 50 mrem per month.

I understand that after six months my allowable exposure will be re-established to 1500 mrem per year unless I submit an updated Pre-Natal Dose Limit Statement.

As a Declared Pregnant Woman / Declared Fertile Woman, I understand I am responsible for limiting my radiation exposure. I will also inform Dosimetry of any exposure to radiation I receive outside Palo Verde Nuclear Generating Station, while employed at the Palo Verde Nuclear Generating Station.

Employees Signature Date Section Leaders Acknowledgement Date DOSE LIMIT CORRECTION I am informing Dosimetry that I no longer require a pre-natal dose limit.

I understand that my administrative hold point at Palo Verde Nuclear Generating Station will be reestablished to 1500 mrem per year.

Employees Signature Date Section Leaders Acknowledgement Date DOSIMETRY - Initiate Baseline Monitoring DOSIMETRY - Close out Embryo / Fetus Monitoring When Pre-Natal Dose Limits Requested When Limits are No Longer Required (ICR 00282)

Whole Body Count performed _______ Whole Body Count performed _______

Dosimetry Initial Dosimetry Initial Individuals TLD processed _______ Individuals TLD processed _______

Dosimetry Initial Dosimetry Initial Establish lower Admin Exposure Hold Point _______ Establish Normal Admin Exposure Hold Point ______

Dosimetry Initial Dosimetry Initial Dosimetry Senior RP Technician Date Dosimetry Senior RP Technician Date 1

SSN use requires marking Appendix B as CONFIDENTIAL, see 84DP-0RM32

Radiation Exposure and Access Control 75DP-9RP01 Page 42 of 50 Rev 17 Appendix C Page 1 of 1 Criteria for Reporting Personnel Overexposure to the USNRC NOTE All reporting to the USNRC should be performed in accordance with 75DP-0RP04, Radiological Reports.

TEDE LDE SDE IMMEDIATE NOTIFICATION 25 rem 75 rem 250 rads 10CFR20.2202(a)

NOTIFICATION Within 5 rem 15 rem 50 rem 24 HOURS 10CFR20.2202(b)

WRITTEN 1. Any incident for which an IMMEDIATE NOTIFICATION or REPORT NOTIFICATION within 24 Hours is required.

Within

2. 0.5 rem TEDE to an embryo/fetus.

30 DAYS 10CFR20.2203

3. 0.1 rem TEDE in one year to a member of the public.

Radiation Exposure and Access Control 75DP-9RP01 Page 43 of 50 Rev 17 Appendix D ( Sample ) Page 1 of 1 Commitment Action Tracking System Partition Commitment/ Procedure Partition Commitment/ Procedure Action # Step Action # Step IIR 010301 01 2.2.2 CRAI 3373967 4.2.4 QATS 390346 08 3.1.2 CRAI 3120700 App. A QATS 391132 05 3.8.7 CRAI 3120698 4.1.2.1 RCTS 010594 01 3.9.2.1 CRAI 3391284 3.5 RCTS 010827 01 3.2.4 RCTS 010913 01 3.4.1.3 RCTS 010915 01 3.6.2.1 RCTS 011131 01 3.9.1.1 RCTS 011132 01 3.9.1.2 RCTS 039454 01 3.12.6 RCTS 039536 02 3.7.3 RCTS 040337 02 3.11.2.1 RCTS2 002495 01 1.1 RCTS2 009656 01 3.2.8 RCTS2 010505 01 3.10.4.1 RCTS2 010506 01 3.10.6 RCTS2 010512 01 3.2.3 RCTS2 010523 01 3.2.4 RCTS2 010553 01 2.3.1 RCTS2 010601 01 3.9.1.1 RCTS2 010602 01 1.1 RCTS2 010606 01 3.9.6 RCTS2 010616 01 3.9.4 RCTS2 010660 01 3.5.1 RCTS2 010661 01 3.6.1 RCTS2 010663 01 3.9.2 RCTS2 010664 01 3.4.1.3 RCTS2 010665 01 3.4.1.1 RCTS2 010673 01 3.9.5 RCTS2 010679 01 3.2.4.1 RCTS2 010683 01 3.4.1.3 RCTS2 041015 01 3.2.3 RCTS2 041026 01 3.2.4 RCTS2 041027 01 3.2.4.1 RP 046002 01 3.10.1 RP 046007 01 3.10.6 RP 046008 01 3.10.4.1 RP 046008 02 3.10.4.1, 3.10.4.4 RP 046008 04 3.10.4.3 RP 046012 01 3.2.3 RP 046013 01 3.9.1 RP 046014 01 3.9.3 RP 046036 05 3.10.1.2 CRAI 3314054 3.7.4 CRAI 3120698 4.1.21 CRAI 3120700 Appendix A

Radiation Exposure and Access Control 75DP-9RP01 Page 44 of 50 Rev 17 Appendix E ( Sample ) Page 1 of 1 RADIATION PROTECTION REQUIREMENT WAIVER

Purpose:

Radiation Protection has requirements in place to control unescorted access into a Radiological Controlled Area (RCA)

Two of these Radiation Protection 1. A Whole Body Count (WBC), and requirements are: 2. Successful completion of Radiological Work Practices (RWP) training On a case-by-case basis, the Director, Site Radiation Protection may allow an individual unescorted access into an RCA without completing all of the required items. If needed, the WBC and/or RWP requirement(s) may be waived with approval from the Director, Site Radiation Protection.

The approval and any assigned restrictions are documented using this form.

Section A Waiver Request Name:

First Middle Last SSN1: HPID #: Job

Title:

Employer: Phone:

Waiver requested for: Whole Body Count Radiological Work Practices Reason for request:

Requested by ( Print ) Name: Date:

Dept.: Ext.:

Section B Approval and Restrictions Approval to waive the requested RP requirement(s) is indicated below with the following restrictions assigned:

Whole Body Count - Yes / No / n/a Radiological Work Practices - Yes / No / n/a Assigned Restrictions: ( check all that apply )

Waiver expiration date:

Allowed dose to be received during waiver period: mrem Individual must be escorted within the RCA by a qualified radworker No entries into High Radiation Areas (i.e., HRA, LHRA, VHRA )

No entries into Airborne Radioactivity Areas (ARA)

No entries into Hot Particle Controlled Areas (HPCA)

Additional:

Reason for Approving the Waiver:

Director, Site Radiation Protection:

Name Signature: Date:

Individuals acknowledgement of the assigned restrictions: ( must be signed prior to allowing unescorted RCA access )

Name Signature: Date:

1 SSN use requires marking Appendix E as CONFIDENTIAL, see 84DP-0RM32

Radiation Exposure and Access Control 75DP-9RP01 Page 45 of 50 Rev 17 Appendix F ( Sample ) Page 1 of 2 VISITOR REQUEST for RCA ACCESS Page 1 of 2 Section A Visitor Access Request Part 1. Visitor Information Date :

Name:

First Middle Last ( Jr., Sr. )

Date of Birth : Sex: SSN1 or ID #

Home Address :

Street City State Zip Employer Name: Employer Phone:

Employer Address:

Street City State Zip Part 2. Current Year Exposure History : Year: ________________

a. Is the visitor's current year Total Effective Dose Equivalent greater than 1800 mrem ? Yes No

b. Has the visitor been monitored with a record TLD at PVNGS during the current year? Yes No

( If "yes" the individual cannot enter an RCA at PVNGS as a visitor, must be issued a record TLD. ) Search Verified By: _____________

If all questions above are answered as "No", an RP Section Leader can approve the visitor's RCA access request.

If current year TEDE is greater than 1800 mrem, RP Department Leader approval is required to allow RCA access.

Part 3. RCA Entry Information RCA Entry Date(s) Requested - Beginning: Ending:

Reason for Entry : (Include discussion of plant areas planned to be accessed, e.g., Aux 120', Fuel Bldg 140', etc.)

Will the visitor need to enter any Contaminated Areas (CA) while within an RCA ? Yes No

( If "Yes" then RP Department Leader approval is required prior to allowing entry into CAs )

Requested by (Print) Name : Date :

Dept. : Ext.:

Part 4 Visitor Acknowledgement (ACT 2991367) I have verified the information provided in Section A of this request is accurate Signature of Visitor : _____________________________________________________________ Date : ________

Section B Approval for RCA Entry (Section A must be completed prior to approval.)

RP Section Leader: Visits of 1 day or less and all Part 2 answers are "No" Date:

Name (print): Signature:

RP Department Leader: Visits of greater than 1 day and/or TEDE is greater than 2500 mrem Date:

Name (print): Signature:

RP Department Leader: Approval for visitor to enter Contaminated Areas if needed Date:

Name (print): Signature:

1 SSN use requires marking page 1 of Appendix F as CONFIDENTIAL, see 84DP-0RM32

Radiation Exposure and Access Control 75DP-9RP01 Page 46 of 50 Rev 17 Appendix F ( Sample ) Page 2 of 2 VISITOR REQUEST for RCA ACCESS Page 2 of 2 Section C Visitor and Escort Acknowledgement This section must be completed and signed by each visitor and escort prior to allowing entry into an RCA at PVNGS.

RCA Access Requirements:

1. Visitor shall be escorted by a qualified radworker at all times while within an RCA to ensure all radiological requirements are met.

2. Visitor shall be limited to 100 mrem TEDE per visit at PVNGS.

3. Visitor shall not enter any High Radiation Areas ( i.e., HRA, LHRA, & VHRA ).

4. Visitor shall not enter any Airborne Radioactivity Areas ( ARA ).

5. Visitor shall not enter any High Contamination Areas ( HCA ) or Hot Particle Control Areas ( HPCA ).

6. Visitor shall not enter any Contaminated Areas ( CA ) without approval from an RP Department Leader.

7. Visitor shall not perform any task or activity which has not been approved by Radiation Protection.

8. Visitor shall wear the assigned dosimetry device at all times while within an RCA.

9. The visitor shall wear the dosimetry device on the front portion of the body between the waist and head.

10. If the visitor loses the assigned dosimetry device, immediately inform the escort and exit the RCA.

11. The visitor's dose shall be recorded after each RCA entry.

12. The visitor shall comply with all instructions given for their safety by their assigned escort and/or Radiation Protection personnel.

13. The visitor shall inform Dosimetry if they have had any recent medical treatment which involved radioactivity introduced into the body.

Part 1. Visitor Acknowledgement Name:

First Middle Last ( Jr., Sr.)

I acknowledge that I have read, understand, and will comply with the above RCA access requirements.

Signature of Visitor: Date:

Part 2. Escort Acknowledgement Escort's HPID # :

Name:

First Middle Last (Jr., Sr.)

I acknowledge that I have read, understand, and will comply with the above RCA access requirements.

In addition, if needed, I will ensure other escorts of this visitor are briefed and understand the requirements.

Signature of Escort: Date:

Section D Dosimetry Device Issue and Results Date EPD RCA Access Radiation Visitor Accumulated RP or Escort Signature Serial Authorization Exposure Dose Total Dose Issue Record "Visitor Dose" and calculate Number Verified by Permit and ( mrem ) ( mrem ) "Accumulated Total Dose"

( REP )

Each Entry after each RCA entry RP Initials Send completed form to Dosimetry

Radiation Exposure and Access Control 75DP-9RP01 Page 47 of 50 Rev 17 Appendix G Page 1 of 2 Embryo/Fetus Dose Assessment Regulatory Guide 8.36 clearly recognized that the calculation of prenatal radiation dose from internal radioactivity has many associated difficulties. When the regulatory guide was first published, it was expected that embryo/fetus dose assessments would evolve over the years, but little has been written since then. In ICRP 56, it states that embryo/fetus dose can be approximated by the dose to the uterus: i.e., the dose to the embryo/fetus due to internal activity in the mother can be estimated using the committed dose equivalent (CDE) to the uterus. For the primary radionuclides encountered at PVNGS, the uterine CDE is approximately equal to or less than the committed effective dose equivalent (CEDE) to the mother.

Therefore, control of the mothers internal dose would provide the control of the embryo/fetus dose.

Further, if an intake occurred that was estimated to be greater than 50 mrem, an outside expert in the field could be contacted.

The uptake of radionuclides by a pregnant worker, however, is a rare event. Site RP procedures are designed to minimize uptakes through engineering controls, decontamination, occupancy factors, and workplace airborne evaluations. Monitoring is required at 10% of the limit, i.e., if an individual is likely to exceed 50 mrem of internal dose to the embryo/fetus. As stated above, control of internal dose to the declared pregnant women (DPW), or declared fertile woman (DFW) will control the dose to the embryo/fetus. It has been concluded that DPWs and DFWs are NOT likely to exceed 10% of the limit.

The following PVNGS historical information is provided to support that conclusion:

No radworker has incurred 20 DAC-hours in a year since 1994. Onsite efforts have been directed to the reduction of internal exposure through workplace monitoring, engineering controls, and occupancy factors.

Most intakes at PVNGS have followed the ingestion pathway. Therefore, an intake of 20 DAC-hrs would usually not approach 50 mrem CEDE and an embryo/fetus would not be expected to receive 50 mrem.

DFWs and DPWs have less opportunity for uptake because they work in less hazardous and lower dose rate environments through general cooperation between the supervisor and the worker.

Federal Guidance Report No. 11 shows that dose factor for the uterus is approximately equal to or less than the effective dose factor for the whole body for the radionuclides typically encountered at PVNGS.

Internal exposure tracking is performed for all radworkers. Therefore, although it is not required monitoring, internal exposures to a DPW or DFW would be tracked.

To assess an internal activity at time of declaration, the DFW / DPW should be whole body counted at the time of declaration and their TLD should be processed. All subsequent intakes would be tracked and further external dose would be with a new TLD.

Radiation Exposure and Access Control 75DP-9RP01 Page 48 of 50 Rev 17 Appendix G Page 2 of 2 Embryo / Fetus Dose Assessment From NRC Regulatory Guide 8.36, Radiation Dose to the Embryo/Fetus, July 1992 C.2 - Simplified Method for Determining Embryo/Fetus Dose from Material Intakes Based on these premises (uterus dose similar to fetal dose and the data in Revision 1 to NUREG/CR-5631 (Ref. 2)), a set of dose factors has been developed for use in calculating an embryo/fetus dose.

Except for those radionuclides addressed in Revision 1 to NUREG/CR-5631 (Ref. 2), the dose factors presented in Appendix A to this guide represent the committed dose equivalent to the uterus per introduction of unit activity into the first transfer compartment (i.e., blood) of the woman.1 For the radionuclides in Revision 1 to NUREG/CR-5631, the dose factors in Appendix A represent the maximum dose equivalent to the embryo/fetus for the gestation period from the introduction of unit activity into the first transfer compartment of the woman at any time during the gestation period.

1

The committed dose equivalent factors for the uterus presented in Appendix A were calculated based on the modeling employed during the development of the ICRP 30 (Ref. 3) data. It is recognized that the metabolism of the pregnant woman may not be adequately represented by the standard metabolic model. However, partly because of the lack of more definitive data, this modeling has been used for determining the dose commitment factors for the uterus that may be used for evaluating compliance with the embryo/fetus dose limit.

Radiation Exposure and Access Control 75DP-9RP01 Page 49 of 50 Rev 17 Appendix H Page 1 of 1 Off Site Support Agency Radiological Determination Matrix Normal Operations Situation Badging Limits Part 19.12 Training Off Site support agencies are at N/A Public Dose Limits N/A After 7 days, complete training and obtain site PVNGS but not entering the 10CFR20.1301(a)(1) badge.

Restricted Area apply Off Site Support agencies are at N/A Public Dose Limits If Occupational, 10CFR19.12 After 7 days, complete training and obtain PVNGS entering the Restricted 10CFR20.1301(a)(1) applies unescorted access.

Area but not the RCA apply Off Site Support agencies are at 75DP-9RP01, PVNGS may classify these personnel If Occupational, 10CFR19.12 Escort, Complete Rad Worker Training or PVNGS entering the Restricted Sections 3.2. and as occupational workers. If so, the applies Waive Training Area and the RCA 3.3 Occupational Dose Limits of 10CFR20.1201 apply Emergencies Situation Badging Limits Part 19.12 Training KI Evacuation Offsite support agencies are at N/A Protective Action Guide for N/A N/A Responsibility of the Evacuate the site PVNGS and not supporting an public EPA 400 Section 2.3, State of Arizona with other non-emergency in progress Table 2.1 apply essential personnel Offsite support agencies are at N/A Emergency Worker Limits N/A N/A N/A N/A PVNGS: of EPA 400 Section 2.5, Supporting an emergency in Table 2.2 apply progress, Not entering the Restricted Area, AND there is no RAD release in progress Offsite support agencies are at E Plan section 6.7.1. Emergency Worker Limits N/A Briefing E Plan Section N/A PVNGS supporting an emergency in Emergency workers carry of EPA 400 Section 2.5, provided in 6.6.3.3. EC progress when radiation exposure is dosimeters in addition to Table 2.2 apply EPIP-99 authorizes use of KI.

likely. TLDs. PVNGS may PVNGS may provide to other agencies if provide to other requested. agencies if requested.

Radiation Exposure and Access Control 75DP-9RP01 Page Page 50 of 50 Rev 17 Appendix I (sample) Page 1 of 1 Supplemental Exposure Notification Name: ______________________________________________ Employee ID: ____________ HP ID: ______________

Department: __________________________________ Home Unit #: ____________ Mail Station: _____________ Ext: _____________

Date of Last Whole Body Count: _____________________ Type: _________________

Reason for Notice: _______________________________________________________________________________________________

Leaders Name: _________________________________________ Mail Station: _____________ Ext: ______________

Expected Return Date: _________________________

I am aware that my access to the RCA will be suspended until I return to the Dosimetry Department and receive a Post Trip Whole Body Count. I am aware that I might be required to complete an exposure request for the purpose of ascertaining what if any exposure I may have received as a part of this trip. I am aware that if I am qualified for E-Plan that I may be delayed from responding in the event of a drill or actual emergency. I am also aware that if I fail to return to the Dosimetry Department within 30 days of the expected return date that a PVAR may be issued stating that I am not in compliance with 75DP-9RP01 Radiation Exposure and Access Control.

Signature Date Action Completed by: Date:

Pre Trip Whole Body Count Performed Open Exception Entered into ARACS Post Trip Whole Body Count Performed Request Letter Signed (If Required)

Open Exception Closed File active forms with WBC Operator, File completed forms in workers file.

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1240100202 Classify events requiring emergency plan implementation TASK STANDARD: An Alert is declared within 15 minutes. NAN Form EP-0541 is completed per the EP procedures and notification initiated within 14 minutes.

K/A: 2.4.40 K/A RATING: RO: 2.7 SRO: 4.5 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): SRO VALIDATION TIME: 15 minutes

REFERENCES:

EP-0900 Appendix L (Emergency Coordinator - STSC), EP-0901(Classifications),

EP-0902 (Notifications), and EP-0905 (Protective Actions), EAL Charts SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER X JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 02/12/2008 Revised By: Alan Malley Date: 05/20/2011 Technical Review Operations Approval EP Review Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. This JPM can be performed in the simulator or as an Admin JPM.

2. SPECIAL TOOLS/EQUIPMENT:

EP-0900 Appendix L, EP-0901, EP-0902, EP-0905. This JPM was written using revision 00 of these procedures. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM. EAL Chart available

Form EP-0803 B (PAR Flowchart) available (Sample of Form in EP-0903, Appendix A)

Form EP-0804 B (Release Evaluation Flowchart) available (Sample of Form in EP-0905, Section 5.1.4)

A copy of form 541 is available (if not performed in the simulator). The current revision of the form is 541AA but other revisions may be used if it does not affect the information needed for completion of this JPM.

Page 2 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

You are the Unit 1 CRS.

The plant is under a tornado warning from the National Weather Service.

The crew has implemented 40AO-9ZZ21, Acts of Nature, and the applicable actions have been completed OR in progress.

Site Security reports a tornado has touched down and caused structural damage to the Auxiliary Building with no injury to plant personnel.

The SM was at the morning meeting in Unit 2 and is waiting until tornado has left immediate area before returning to the Unit.

INITIATING CUE:

You are to perform the duties of the Emergency Coordinator until relieved.

THIS IS A TIME CRITICAL JPM Page 3 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. The examinee enters EP-0901, Examinee refers to the EAL charts to Classifications to classify the event. determine the classification.

Start Time: __________

(Begins when examinee receives and acknowledges Initiating CUE)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Examinee determines classification. The examinee determines the classification is an ALERT based on EAL HA1.2.

End Time: ___________

Classification Time: _________

(this time must be < 15 minutes)

Notification Start Time: _________

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

The examinee enters EP-0902 to The examinee completes form 541 make notifications. and hands the form to the STSC Inform Cue (when the examinee communicator. The form must calls for the Area 2 operator): contain the following information:

I am the Area 2 operator Fills out NAN Form EP-0541 as follows:

o Step 1 marked This is a drill box.

When Requested Cue: o Step 2 - ALERT, date and time, Status code [HA1.2].

The STA has performed and independent review and o Step 3 - ERFDADS data and concurs with your Authenticator Code are already classification. filled in on the form.

o Step 4 - No Radioactive release is in progress.

o Step 5 -PAR is NONE.

Inform Cue: After examinee hands the communicator form 541: o Step 6 signed with time and date.

This concludes this JPM.

Evaluator Note: Critical portion of this step is to correctly identify an ALERT, status codes; NO release is occurring and no PAR with the correct date and time on the form.

End Time:___________

Notification Time:__________

(this time must be less than 14 minutes to allow the communicator 1 minute to start notifications)

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

Page 6 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 7 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 002 3-9-05 3 Revised for new EPIP-01 003 9-18-07 6 Shortened to 18 steps, remaining steps do not apply to NUE or Alert classification 004 10/19/07 6 Removed affected Unit reference from step 17 005 10/26/07 3 006 12/05/07 6 Changed cue in step 4 to other units entering NUE, EAL 6-7 007 02/29/08 3 Revision 26 of EPIP-01 008 10/09/2009 3, 6 Incorporated NEI 99-01 EALs per Rev. 32 of EPIP-01 and Rev. 28 of EPIP-99, revised evaluator cue(s) and Initiating CUE to current JPM standard, and updated to current JPM format template.

009 05/20/2011 3 Revised for changes in E-Plan procedures and to upgrade to a new format.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 9

A-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

You are the Unit 1 CRS.

The plant is under a tornado warning from the National Weather Service.

The crew has implemented 40AO-9ZZ21, Acts of Nature, and the applicable actions have been completed OR in progress.

Site Security reports a tornado has touched down and caused structural damage to the Auxiliary Building with no injury to plant personnel.

The SM was at the morning meeting in Unit 2 and is waiting until tornado has left immediate area before returning to the Unit.

INITIATING CUE:

You are to perform the duties of the Emergency Coordinator until relieved.

THIS IS A TIME CRITICAL JPM Page 9 of 9

FORM EP-0541 AA PVNGS EMERGENCY PREPAREDNESS PALO VERDE NAN EMERGENCY MESSAGE FORM

1. (check one) This is a drill This is an actual event

2. This is Palo Verde Nuclear Generating Station Notification of a(n) (Check highest applicable classification level for event notifications)

(Check Event Termination for terminating event)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Declared at on / / EAL:

(time) (MM/DD/YY) (driving current classification only)

EVENT TERMINATION AT (time)

/

(MM/DD/YY)

/

3. The wind speed is 22 MPH from 320 degrees (35 foot elevation - 15 min avg) (35 foot elevation - 15 min avg)

Authenticator Code Bravo Zulu This is (name) STSC Comm. (Check one)

NAN Comm

4. There is NO radioactive release due to this event.

A radioactive release is occurring which does NOT exceed federally approved limits due to this event.

A radioactive release is occurring that exceeds federally approved limits due to this event.

5. The following action is recommended:

There are NO PROTECTIVE ACTIONS required.

Shelter 2-mile radius Evacuate 2-mile radius and 5-miles in sectors Evacuate 5-mile radius and 10-miles in sectors Recommend consideration of Kl as a protective measure for: emergency workers general public

[check appropriate box(es)]

Other

6. Approval / /

(EC/EOD signature) (time) (MM/DD/YY)

7. Independent review completed (If time permits while still meeting 15 minutes reporting requirement)

(Checked by EC/EOD qualified person)

8. Responding Agency Alternate Link Time Message Recd

NAN Radio B/U

NAN Radio B/U EP-0541 AA

P-1 PVNGS JOB PERFORMANCE MEASURE JPM BASIS INFORMATION TASK: 1250440201 Respond to a Control Room Fire TASK STANDARD: First 7 steps of Appendix W of 40AO-9ZZ19 to align SDC for service completed.

K/A: 4.2 067 AA2.16 K/A RATING: RO: 3.3 SRO: 4.0 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): AO/RO VALIDATION TIME:

REFERENCES:

40AO-9ZZ19, Control Room Fire, Appendix W SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 09-30-2012 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE

1. SPECIAL TOOLS/EQUIPMENT:

A copy of 40AO-9ZZ19, Control Room Fire, Appendix W (up to Step 7) available.

This JPM was written using Revision 26 of 40AO-9ZZ19. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Page 2 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

A Control Room fire has occurred.

The CRS has entered 40AO-9ZZ19, Control Room Fire.

The plant is being cooled down to SDC conditions.

INITIATING CUE:

The CRS directs you to perform Appendix W, Placing SDC Train B in Service.

The vent hoses have been installed per Attachment W-2.

Page 3 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix W: Examinee enters current date and time.

Enter Appendix Entry Time and Date:

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Appendix W: INFORM CUE: Vent hoses have been installed per Attachment W-2 Ensure vent hoses have been installed per Attachment W-2, Periodic Venting of SDC Train B.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE STEP CUE STANDARD

3.

Step 3 of Appendix W: If Requested Cue (before valve Examinee uses the handswitch on operation): breaker PHB-M3804 to close SIB-Close SIB-HV-689, CS B HV-689.

Discharge. (PHB-M3804) Red light is ON, Green light is OFF.

INFORM CUE (after handswitch operation):

Red light is OFF, Green light is ON SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 4 of Appendix W: If Requested Cue (before valve Examinee attempts to close SIB-HV-operation): 695 from the breaker handswitch.

Close SIB-HV-695, LPSI-CS From Valve does not close so examinee SDHX B X-Tie. (PHB-M3810) Red light is ON, Green light is goes to contingency step 4.1.

OFF.

INFORM CUE (after handswitch operation):

Red light is ON, Green light is OFF SAT / UNSAT Comments (required for UNSAT):

Page 6 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE STEP CUE STANDARD

5.

Step 4.1 of Appendix W: Inform Cue (after examinee Examinee engages clutch on SIB-simulates closing valve): HV-695 and turns handwheel in the Manually close SIB-HV-695 (SDC counter-clockwise direction.

Hx Valve Gallery) The handwheel has been rotated in the closed direction and has stopped moving as expected.

ALTERNATE PATH SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.

Step 5 of Appendix W: If Requested Cue (before valve Examinee uses the handswitch on operation): breaker PHB-M3609 to close SIB-Close SIB-UV-668, LPSI Pump B UV-668.

Recirc. (PHB-M3609) Red light is ON, Green light is OFF.

INFORM CUE (after handswitch operation):

Red light is OFF, Green light is ON SAT / UNSAT Comments (required for UNSAT):

Page 7 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE STEP CUE STANDARD

7.

Step 6 of Appendix W: If Requested Cue (before valve Examinee uses the handswitch on operation): breaker PHB-M3805 to close SIB-Close SIB-HV-692, LPSI Pump HV-692.

Suction from RWT. (PHB-M3805) Red light is ON, Green light is OFF.

INFORM CUE (after handswitch operation):

Red light is OFF, Green light is ON SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.

Step 7 of Appendix W: If Requested Cue (before valve Examinee uses the handswitch on operation): breaker PHB-M3412 to close SIB-Close SIB-HV-658, SDHX B HV-658.

Outlet to RC Loops 2A/2B Valve. Red light is ON, Green light is (PHB-M3412) OFF.

INFORM CUE (after handswitch operation):

Red light is OFF, Green light is ON SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Page 8 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 9 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 0 09/30/2012 6 Record created.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 10 of 11

P-1 PVNGS JOB PERFORMANCE MEASURE EXAMINEE HANDOUT INITIAL CONDITIONS:

A Control Room fire has occurred.

The CRS has entered 40AO-9ZZ19, Control Room Fire.

The plant is being cooled down to SDC conditions.

INITIATING CUE:

The CRS directs you to perform Appendix W, Placing SDC Train B in Service. The vent hoses have been installed per Attachment W-2.

Page 11 of 11

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 166 of 195 CONTROL ROOM FIRE Appendix W Page 1 of 11 Appendix W, Placing SDC Train B in Service INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. Enter Appendix Entry Time and Date:

___ 2. Ensure vent hoses have been installed per Attachment W-2, Periodic Venting of SDC Train B.

___ 3. Close SIB-HV-689, CS B ___ 3.1 Manually close SIB-HV-689.

Discharge. (PHB-M3804) (CS Pump Room B)

___ 4. Close SIB-HV-695, LPSI-CS ___ 4.1 Manually close SIB-HV-695 From SDHX B X-Tie. (SDC Hx Valve Gallery)

(PHB-M3810)

___ 5. Close SIB-UV-668, LPSI Pump B ___ 5.1 Manually close SIB-UV-668.

Recirc. (PHB-M3609) (LPSI B Pump Room)

___ 6. Close SIB-HV-692, LPSI Pump ___ 6.1 Manually close SIB-UV-692.

Suction from RWT. (PHB-M3805) (LPSI B Pump Room)

___ 7. Close SIB-HV-658, SDHX B ___ 7.1 Manually close SIB-HV-658.

Outlet to RC Loops 2A/2B Valve. (SDHX B Room)

(PHB-M3412)

___ 8. Ensure that BOTH of the following LPSI Injection Valves are closed:

SIB-UV-615 (PHB-M3606)

SIB-UV-625 (PHB-M3621)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 167 of 195 CONTROL ROOM FIRE Appendix W Page 2 of 11 Appendix W, Placing SDC Train B in Service INSTRUCTIONS CONTINGENCY ACTIONS

___ 9. Open SIB-UV-652, SDC Suction ___ 9.1 Manually open SIB-UV-652.

Valve. (PHB-M3604) (90 CTMT outside 2A RCP Room)

___ 10. Unlock and close PKD-B44, Power Supply Disconnect for SID-UV-654.

(Battery Room D)

___ 11. Open SID-UV-654, Loop 2 to ___ 11.1 Manually open SID-UV-654.

Shutdown Cooling LPSI Pump (90 CTMT East)

Suction Valve, using the local keyswitch.

(Battery Room D)

___ 12. Open SIB-UV-656, RC Loop 2 ___ 12.1 Manually open SIB-UV-656 SDC-LPSI Pump Suction Valve. (East Pen Room)

(PHB-M3605)

___ 13. Open SIB-HV-690, RC Loop B ___ 13.1 Manually open SIB-HV-690 Warmup Bypass Valve. (East Pen Room)

(PHB-M3806)

___ 14. Open SIB-HV-694, LPSI-CS to ___ 14.1 Manually open SIB-HV-694 SDHX B X-Tie Valve. (SDC Valve Gallery)

(PHB-M3414)

___ 15. Open SIB-HV-696, SDHX B Outlet ___ 15.1 Manually open SIB-HV-696 to RC Loops 2A/2B Valve. (SDC Valve Gallery)

(PHB-M3415)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 168 of 195 CONTROL ROOM FIRE Appendix W Page 3 of 11 Appendix W, Placing SDC Train B in Service INSTRUCTIONS CONTINGENCY ACTIONS

___ 16. Throttle SIB-HV-307, LPSI-SDHX ___ 16.1 Manually throttle SIB-HV-307 to B Bypass Valve to approximately approximately 20% open.

20% open. (LPSI B Pump Room)

(PHB-M3803)

___ 17. Inform the CRS that LPSI B is ready to be started.

___ 18. WHEN LPSI B is running, ___ 18.1 WHEN LPSI B is running, THEN throttle SIB-HV-307, to THEN manually throttle establish a flowrate of 4000 - 5000 SIB-HV-307 to establish a flowrate gpm as indicated by a d/p of 2.5 - of 4000 - 5000 gpm as indicated 3.3 psid on the temporary flow by a d/p of 2.5 - 3.3 psid on the instrument. (PHB-M3803) temporary flow instrument.

(LPSI B Pump Room)

___ 19. Perform the following to begin heating up the SDC Loop:

a. Throttle open SIB-UV-615, a.1 Manually open SIB-UV-615.

LPSI Header to RC Loop 2A (88 East Wrap) to begin the heatup.

(PHB-M3606)

b. WHEN the SDC Loop b.1 WHEN the SDC Loop heatup rate has stabilized, heatup rate has stabilized, THEN throttle open THEN manually open SIB-UV-625, LPSI Header to SIB-UV-625.

RC Loop 2B to continue the (88 East Wrap) heatup.

(PHB-M3621)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 169 of 195 CONTROL ROOM FIRE Appendix W Page 4 of 11 Appendix W, Placing SDC Train B in Service INSTRUCTIONS CONTINGENCY ACTIONS

___ 20. IF the heatup rate on the SDHX exceeds 19°F/min, THEN adjust warmup flow through the SDC Loop to reduce the heatup rate.

___ 21. Maintain ALL of the following while SDC is in service:

SDC flowrate

Desired RCS cooldown rate

A SDHX heatup rate less than 19°F/min

___ 22. Incrementally adjust ALL of the following valves to stop the warm up bypass flow:

SIB-UV-615 (PHB-M3606)

SIB-UV-625 (PHB-M3621)

SIB-HV-690 (PHB-M3806)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 170 of 195 CONTROL ROOM FIRE Appendix W Page 5 of 11 Appendix W, Placing SDC Train B in Service INSTRUCTIONS CONTINGENCY ACTIONS

___ 23. WHEN closed indication for SIB-HV-690 is received, THEN perform the following:

a. Hold the handswitch in the closed position for five seconds. (PHB-M3806)

b. Direct a second operator to hold the handswitch closed for an additional five seconds.

___ 24. Incrementally adjust ALL of the following valves to fully open the loop injection valves:

SIB-UV-615 (PHB-M3606)

SIB-UV-625 (PHB-M3621)

SIB-HV-307 (PHB-M3803)

___ 25. Adjust SIB-HV-658 (PHB-M3412) and SIB-HV-307 (PHB-M3803) as needed to maintain BOTH of the following:

SDC flowrate 4000 - 5000 gpm as indicated by a d/p of 2.5 - 3.3 psid on the temporary flow instrument

Desired RCS cooldown rate

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 171 of 195 CONTROL ROOM FIRE Appendix W Page 6 of 11 Attachment W-1, SDC-B Simplified Drawing Page 1 of 1 UV-625 UV-615 HV-658 UV-671 HV-307 HV-696 HV-695 HV-694 HV-689 HV-679 HV-668 HV-693 RWT CS B LPSI B HPSI B HV-690 CHB-HV-530 HV-692 RAS UV-656 UV-654 UV-652

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 172 of 195 CONTROL ROOM FIRE Appendix W Page 7 of 11 Attachment W-2, Periodic Venting of SDC Train B [Ref. Step 4.13] Page 1 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

NOTE -----------------------------------------------------------

Implement this Appendix, as necessary, per the following criteria:

As soon as possible after lowering SDCHX inlet temperature below 190°F.

Once per shift when heating up or cooling down.

Once every three days while at steady state condition (no change in temperature or pressure) after three successive gas free vents have occurred at steady state.

___ 1. Remove pipe cap from the following vent valves:

SIB-V886 (Upper Level in the East Penetration Room)

SIB-V870 (Upper Level in the East Penetration Room)

SIB-V019 (CS Pump B Room)

Unit-1 Only SIB-V1029 (Upper level of the East Penetration Room)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 173 of 195 CONTROL ROOM FIRE Appendix W Page 8 of 11 Attachment W-2, Periodic Venting of SDC Train B Page 2 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 2. Install a hose adaptor on the following vent valves:

SIB-V886

SIB-V870

SIB-V019

Unit-1 Only SIB-V1029

___ 3. Connect hoses as follows:

a. Connect one hose end to hose adaptor of the following valves:

SIB-V886

SIB-V870

SIB-V019

Unit-1 Only SIB-V1029

b. Connect other hose end to ONE of the following:

Floor drain

As directed by Radiation Protection

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 174 of 195 CONTROL ROOM FIRE Appendix W Page 9 of 11 Attachment W-2, Periodic Venting of SDC Train B [ Page 3 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 4. Ensure SDC temperature is less than 190°F.

(SIB-TI-352X at RSP).

___ 5. Inform Radiation Protection that SDC header B is to be vented.

___ 6. Perform the following to vent through SIB-V886:

a. Open SIB-V886 1/4 to 1/2 turn.

b. Check no air is present, b.1 Open SIB-886 to 2 turns.

during the vent.

c. Maintain SIB-V886 open for 2 to 3 minutes after a solid stream of water is observed.

d. Close SIB-V886.

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 175 of 195 CONTROL ROOM FIRE Appendix W Page 10 of 11 Attachment W-2, Periodic Venting of SDC Train B Page 4 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 7. Perform the following to vent through SIB-V870

a. Unlock SIB-V870 per 40AC-0ZZ06, Locked Valve, Breaker and Component Control.

b. Open SIB-V870 1/4 to 1/2 turn.

c. Check no air is present, c.1 Open SIB-V870 to 2 turns.

during the vent.

d. Maintain SIB-V870 open for 2 to 3 minutes after a solid stream of water is observed.

e. Close SIB-V870.

___ 8. Perform the following to vent through SIB-V019

a. Open SIB-V019 1/4 to 1/2 turn.

b. Check no air is present, b.1 Open SIB-V019 to 2 turns.

during the vent.

c. Maintain SIB-V019 open for 2 to 3 minutes after a solid stream of water is observed.

d. Close SIB-V019.

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 176 of 195 CONTROL ROOM FIRE Appendix W Page 11 of 11 Attachment W-2, Periodic Venting of SDC Train B Page 5 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 9. Unit-1 Only Perform the following to vent through SIB-V1029

a. Open SIB-V1029 1/4 to 1/2 turn.

b. Check no air is present, b.1 Open SIB-V1029 to 2 turns.

during the vent.

c. Maintain SIB-V1029 open for 2 to 3 minutes after a solid stream of water is observed.

d. Close SIB-V1029.

___ 10. Verify the following valves closed using independent verification per 02DP-0ZZ01, Verification of Plant Activities:

a. SIB-V886

b. SIB-V870

c. SIB-V019

d. Unit-1 Only SIB-V1029

___ 11. Inform the Shift Manager/CRS that venting of the SDC header B is complete.

End of Appendix

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1240023901 Perform operation of AFA-P01 at the Remote Shutdown Panel TASK STANDARD: Feeding the Steam Generators with AFA-P01 from the Remote Shutdown Panel K/A: 3.4-061-A3.01 K/A RATING: RO: 4.2 SRO: 4.2 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40AO-9ZZ18, Shutdown Outside Control Room, Appendix E SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) Yes APPROVAL Developed By: Alan Malley Date: 10/02/2007 Revised By: Alan Malley Date: 08/24/2011 Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

A copy of Appendix E of 40AO-9ZZ18. This JPM was written using Revision 11 of 40AO-9ZZ18. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Replacement locking devices (obtained from Shift Manager) to relock the RSP after each JPM.

Page 2 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

The CRS has entered 40AO-9ZZ18, Shutdown Outside Control Room.

INITIATING CUE:

The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed the Steam Generators using AFA-P01 (Train A Auxiliary Feedwater Pump) from the Remote Shutdown Panel.

Page 3 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix E: Examinee enters date and time Enter Appendix Entry Time and Date:________________

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Appendix E: Examinee NAs this step since initiating cue directed use of AFA-IF AFB-P01 will be used, THEN P01.

perform the following:..

SAT / UNSAT Comments (required for UNSAT):

Note prior to step 3:

AFA-HS-52A, Turbine Driven AFW Pump Speed Control Transfer, switch position must be changed as rapidly as possible to minimize the chances of an overspeed trip.

Page 5 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3. Step 3.a of Appendix E: Inform Cue: Examinee simulates turning the After the examinee simulates speed potentiometer in the counter-IF AFA-P01 will be used, THEN turning the speed potentiometer clockwise direction until the dial is at perform the following: counter-clockwise provide the minimum.

Adjust AFA-SK-52B, Auxiliary following cue:

Feedwater Pump A Speed to The potentiometer has stopped minimum. moving and reads 0.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Step 3.b of Appendix E: Inform Cue: Examinee simulates turning the speed control transfer switch left to After the examinee simulates Place AFA-HS-52A, Speed Control the REMOTE SHUTDOWN turning the speed control transfer Transfer, to the REMOTE position.

handswitch to the REMOTE SHUTDOWN position. SHUTDOWN position provide the following cue:

The handswitch is pointing to the left.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

5.

Step 3.c of Appendix E: If Requested Cue: Examinee simulates opening either SGA-UV-134 or SGA-UV-138.

The CRS states you can use either Open ONE of the following valve.

Steam Supply Valves: Inform Cue:

SGA-UV-134 After the examinee simulates

SGA-UV-138 turning handswitch for either SGA-UV-134 or SGA-UV-138 provide the following cue for the appropriate valves:

The indication for SGA-UV-134(8)A red light is on. 30 seconds later the red light for SGA-UV-134 came on and both Green lights are off.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.

Step 3.d of Appendix E: Inform Cue: The examinee adjusts the potentiometer to raise speed to 3590-As the examinee goes to increase Adjust turbine speed using AFA-SK- 3600 rpm in Unit 1 and 3 or 3560-on the speed potentiometer use a 52B to ONE of the following: 3570 in Unit 2..

pen to indicate the following:

Unit 1 & 3 only - Unit 1 and 3 Cue:

3590-3600 rpm

Speed is 3600 rpm Unit 2 only Unit 2 Cue:

3560-3570 rpm

Speed is 3560 rpm SAT / UNSAT Comments (required for UNSAT):

Page 7 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

7.

Step 3.e of Appendix E: Inform Cue: Examinee simulates placing the handswitches for AFA-UV-37 and When the examinee takes the Open BOTH of the following AFW AFC-UV-36.

handswitches for AFA-UV-37 and Pump A to Steam Generator AFC-UV-36 to open provide the Downstream Valves: following cue:

AFA-UV-37 The red lights for AFA-UV-37 and

AFC-UV-36 AFC-UV-36 are on and the green lights are off.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

8.

Step 3.f of Appendix E: Inform Cue: Examine determines SG WR level and throttles open both SG Upstream When examinee looks at SG level Maintain steam generator levels 35- valves.

transmitters provide the following 80% WR with ANY of the following cue using a pen to indicate Steam AFA Pump A to Steam Generator Generator Wide Range Levels are Upstream Valves:: 30% WR.

AFA-HV-32 If requested Cue:

AFC-HV-33 The as found position of AFA-HV-32 and AFC-HV-33 are as indicated on the panel.

Inform Cue:

When the examinee simulates jogging open AFA-UV-32 and AFC-HV-33 provide the following cue:

AFA-UV-32 and AFC-HV-33 red and green lights are on.

Inform Cue:

When examine looks at position indication for valves use a pen to show valve position (depending on what operator says was the final valve position).

Inform Cue:

When examine looks at AF flow indicator use a pen to indicate flow is 350 gpm.

Inform Cue:

After feed is established provide the following cue:

Another operator will finish Appendix E.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Page 9 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 10 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 02 03/28/07 6 Updated initiating cue to include that FWPT and Main Turbine shafts have stopped turning. Editorial updates.

03 12/02/09 6 Updated to new format and removed non-critical steps at the end of the JPM.

04 08/24/2011 6 Updated to new format.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 11 of 12

P-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

The CRS has entered 40AO-9ZZ18, Shutdown Outside Control Room.

INITIATING CUE:

The CRS directs you to perform Appendix E, Auxiliary Feed Pump Operations, to start and feed the Steam Generators using AFA-P01 (Train A Auxiliary Feedwater Pump) from the Remote Shutdown Panel.

Page 12 of 12

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ18 Revision 11 Page 40 of 100 SHUTDOWN OUTSIDE CONTROL ROOM Appendix E Page 1 of 4 Appendix E, Auxiliary Feed Pumps Operation INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. Enter Appendix Entry Time and Date:

___2. IF AFB-P01 will be used, THEN perform the following:

a. Direct an operator to start AFB-P01 locally at PBB-S04S.

b. Open BOTH of the following AFW Pump B to Steam Generator Downstream Valves:

AFB-UV-34

AFB-UV-35

c. Maintain steam generator levels 35 - 80% WR with ANY of the following AFW Pump B to Steam Generator Upstream Valves:

AFB-HV-30

AFB-HV-31

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ18 Revision 11 Page 41 of 100 SHUTDOWN OUTSIDE CONTROL ROOM Appendix E Page 2 of 4 Appendix E, Auxiliary Feed Pumps Operation INSTRUCTIONS CONTINGENCY ACTIONS CAUTION AFA-HS-52A, Turbine Driven AFW Pump Speed Control Transfer, switch position must be changed as rapidly as possible to minimize the chances of an overspeed trip.

___3. IF AFA-P01 will be used, THEN perform the following:

a. Adjust AFA-SK-52B, Auxiliary Feedwater Pump A Speed to minimum.

b. Place AFA-HS-52A, Speed Control Transfer, to the REMOTE SHUTDOWN position.

c. Open ONE of the following Steam Supply Valves:

SGA-UV-134

SGA-UV-138 (continue)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ18 Revision 11 Page 42 of 100 SHUTDOWN OUTSIDE CONTROL ROOM Appendix E Page 3 of 4 Appendix E, Auxiliary Feed Pumps Operation INSTRUCTIONS CONTINGENCY ACTIONS

___3. (continued)

d. Adjust turbine speed using AFA-SK-52B to ONE of the following:

Unit 1 & 3 only -

3590 - 3600 rpm.

Unit 2 only -

3560 - 3570 rpm.

e. Open BOTH of the following AFW Pump A to Steam Generator Downstream Valves:

AFA-UV-37

AFC-UV-36

f. Maintain steam generator levels 35 - 80% WR with ANY of the following AFW Pump A to Steam Generator Upstream Valves:

AFA-HV-32

AFC-HV-33

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ18 Revision 11 Page 43 of 100 SHUTDOWN OUTSIDE CONTROL ROOM Appendix E Page 4 of 4 Appendix E, Auxiliary Feed Pumps Operation INSTRUCTIONS CONTINGENCY ACTIONS CAUTION AFA-HS-52A, Turbine Driven AFW Pump Speed Control Transfer, switch position must be changed as rapidly as possible to minimize the chances of an overspeed trip.

___4. IF control of AFA-P01 will be transferred to the Control Room, THEN perform the following:

a. Set AFA-SK-52B, Remote Shutdown Panel speed control to minimum.

b. Ensure that AFA-SK-52A, Control Room speed control is set to minimum.

c. Place AFA-HS-52A to the CONT ROOM position.

d. Adjust turbine speed using AFA-SK-52A to ONE of the following:

Unit 1 & 3 only -

3590 - 3600 rpm Unit 2 only -

3560 - 3570 rpm End of Appendix

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1250440201 Respond to a control room fire TASK STANDARD: Appendix C of 40AO-9ZZ19 completed.

K/A: 3.6 062 A2.06 K/A RATING: RO: 3.4 SRO: 3.9 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40AO-9ZZ19, Control Room Fire SUGGESTED TESTING ENVIRONMENT: SIMULATOR PLANT X OTHER JPM TYPE Time Critical? (Yes/No) Yes Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 02/16/2011 Revised By: N/A Date: N/A Technical Review Operations Approval E-Plan Review Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Planning organization for resolution.

Page 1 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SPECIAL TOOLS/EQUIPMENT:

o 40AO-9ZZ19, Control Room Fire, Appendix C available. This JPM was written using Revision 25 of 40AO-9ZZ19. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

Page 2 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

o The Control Room has been evacuated due to a fire.

o The CRS has entered 40AO-9ZZ19, Control Room Fire INITIATING CUE:

o The CRS directs you to perform Appendix C, PBB-S04 Energized from Offsite Power.

THIS JPM IS TIME CRITICAL Page 3 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix C: Examinee enters Entry time and date.

Enter Appendix Entry Time AND Date: ________________ START TIME: ______________

SAT / UNSAT Comments (required for UNSAT):

Notes before step 2:

NOTE The telephone number for the B Train Remote Shutdown Panel is:

Unit 1 - 1235 Unit 2 - 2235 Unit 3 - 3235 NOTE Actions directed by this appendix are time critical and must be performed as quickly as possible to ensure that effects of the fire do not prevent safe shutdown of the unit.

NOTE Portable lanterns should be used when performing actions in response to a fire. This will ensure that lighting is available if the emergency lighting system is degraded.

STEP CUE STANDARD

2. Step 2 of Appendix C: INFORM CUE: You have Examinee proceeds to the Emergency Obtain a portable lantern from the obtained the portable lantern from Equipment Cabinet.

Emergency Equipment Cabinet, the Equipment Cabinet.

FPN-C02. (B Switchgear Room, Northwest corner)

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Step 3 of Appendix C: INFORM CUE (as examinee Examinee places the following On PHB-M32, place ALL of the simulates turning each disconnect): disconnects in LOCAL.

following Control Room Circuits Indicate that the disconnect switch Disconnect Switches in LOCAL: is pointing to LOCAL. _____ PHB-M3209, Battery Charger (Switchgear Room B) D PKD-H14

PHB-M3209, Battery Charger _____ PHB-M3205, Control Room D PKD-H14 Circuits Disconnect Switches

PHB-M3205, Control Room (4 switches)

Circuits Disconnect Switches (4 switches)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Step 4 of Appendix C: INFORM CUE (as examinee Examinee simulates placing all 5 Place all of the disconnect switches simulates turning each disconnect): disconnect switches to LOCAL.

on DGB-C01, DG Disconnect Indicate that the disconnect switch Cabinet in LOCAL. (5 switches) is pointing to LOCAL.

(Switchgear Room B)

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

5.

Step 5 of Appendix C: INFORM CUE (as examinee Examinee simulates placing the Ensure the disconnect switches for simulates turning each disconnect): disconnect on each of the following ALL of the following breakers on Indicate that the disconnect switch breakers to LOCAL:

PBB-S04 are in LOCAL: is pointing to LOCAL.

PBB-S04S, Aux Feed Water _____ PBB-S04S Pump AFB-P01 _____ PBB-S04N

PBB-S04N, 4160 - 480 LC _____ PBB-S04M PGB-L36 _____ PBB-S04L

PBB-S04M, Essential Cooling

_____ PBB-S04K Water Pump EWB-P01

PBB-S04L, ESF Service _____ PBB-S04J Transformer NBN-X03 _____ PBB-S04H

PBB-S04K, ESF Service _____ PBB-S04G Transformer NBN-X04 Examiner Note: The following _____ PBB-S04F

PBB-S04J, 4160 - 480 LC PGB-L32 breakers are the only ones not _____ PBB-S04C

PBB-S04H, 4160 - 480 LC manipulated: _____ PBB-S04B PGB-L34

PBB-S04G, Essential Chiller

PBB-S04P - Spare ECB-E01

PBB-S04D - Containment

PBB-S04F, LP Safety Injection Spray Pump B Pump SIB-P01

PBB-S04E - High Pressure

PBB-S04C, Essential Spray Safety Injection Pump B Pond Pump SPB-P01

PBB-S04B, Diesel Generator PEB-G02 SAT / UNSAT Comments (required for UNSAT):

Page 7 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

6.

Place ALL of the following INFORM CUE (as examinee Examinee places all the following disconnect switches in LOCAL: simulates turning each disconnect): disconnects in LOCAL:

CS-2/B2 on PGB-L36B1 Indicate that the disconnect switch

CS-1/B2 on PGB-L34B1 is pointing to LOCAL. _____ CS-2/B2 on PGB-L36B1

CS-2/C4 on PGB-L32C1 _____ CS-1/B2 on PGB-L34B1

CS-1/B2 on PGB-L32B1 _____ CS-2/C4 on PGB-L32C1

_____ CS-1/B2 on PGB-L32B1 SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7. Check that breaker PGB-L32C4, INFORM CUE: The breaker for Examinee checks PGB-L32C4 Charging Pump 2 CHB-P01, is CHB-P01 indicator says OPEN. breaker position indication.

closed.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

8.

IF breaker PGB-L32C4, Charging When Requested cue: Examiner Note: Log the time the Pump 2 CHB-P01, is open, THEN Charging Pump breaker is PERFORM the following: The Charging pump suction has simulated closed.

a. Ensure charging pump suction been aligned to the RWT per Step is aligned to the RWT per Step 6 of Appendix G, Upper Auxiliary Examinee performs the following:

6 of Appendix G, Upper Building Actions.

Auxiliary Building Actions. a. Contacts the CRS at the

b. Close breaker PGB-L32C4, Inform Cue (after examinee Remote Shutdown panel (or Charging Pump 2 CHB-P01. simulates closing PGB-L32C4): the Aux Bldg AO) to determine if charging pump The breaker position indication suction is aligned to the says CLOSED. RWT.

b. Closes breaker PGB-L32C4 for Charging Pump B (Time Critical)

Time: ___________ There should be less than 30 minutes from the time in step one to when the charging pump breaker is closed.

ALTERNATE PATH SAT / UNSAT Comments (required for UNSAT):

Page 9 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

9.

Ensure that ALL of the following Inform Cue as each breaker is Examiner Note: Log the time each breakers are closed: closed (use only cues for breaker is simulated closed.

PBB-S04S, Aux Feed Water indications stated by examinee that Pump AFB-P01 he/she is observing): Examinee simulates closing the

PBB-S04N, 4160 - 480V LC following breakers:

PGB-L36 Red light is on/ green light is off.

PBB-S04M, Essential Cooling ________ PBB-S04S, Aux Feed Water Pump, EWB-P01 Amps pegged high and are now Water Pump AFB-P01

PBB-S04J, 4160 - 480V LC steady at ______ amps. ________PBB-S04N, 4160 - 480V PGB-L32 LC PGB-L36

PBB-S04H, 4160 - 480V LC Breaker made a closing sound. ________PBB-S04M, Essential PGB-L34 Cooling Water Pump,

PBB-S04G, Essential Chiller EWB-P01 ECB-E01

________PBB-S04J, 4160 - 480V

PBB-S04C, Essential Spray LC PGB-L32 Pond Pump SPB-P01

________PBB-S04H, 4160 - 480V LC PGB-L34

________PBB-S04G, Essential Chiller ECB-E01

________PBB-S04C, Essential Spray Pond Pump SPB-P01 (Time Critical)

_______There should be less than 15 minutes from step 1 until PBB-S04C is closed,

_______There should be less than 45 minutes from step 1 until PBB-S04S is closed

_______There should be less than 40 minutes from step 1 until PBB-S04G is closed.

SAT / UNSAT Comments (required for UNSAT):

Page 10 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

10. Inform the CRS that ALL of the Inform Cue: Examinee simulates informing the following are running: CRS.

Charging Pump B The CRS has been informed that

Aux Feed Pump B the following are running:

Spray Pond Pump B

Essential Cooling Water Pump

Charging Pump B B

Aux Feed Pump B

Essential Chiller B

Spray Pond Pump B

Essential Cooling Water Pump B

Essential Chiller B SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11.

IF Diesel Generator B is running, Inform Cue: Examinee simulates pushing DGB-THEN perform the following: (DG HS-30 to stop Diesel Generator B.

Control Panel) DG B is running.

a. Press DGB-HS-30, Emergency Stop.

b. IF a loss of Offsite Power occurs, THEN PERFORM After examinee pushing ONE of the following as Emergency Stop button(use only appropriate: cues for indications stated by

Appendix D, PBB-S04 examinee that he/she is observing):

Energized from DG B

Appendix E, PBB-S04 De-energized.

The DG is slowing.

Use pen to indicate RPMs are lowering.

DG run alarm is off.

Etc.

SAT / UNSAT Comments (required for UNSAT):

Page 11 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

12.

Ensure that DGB-V064, Jacket Inform Cue: The valve has turned Examiner Note: Log the time the Water Standpipe Make-up Header clockwise and has stopped moving valve is simulated closed.

Isolation valve, is closed. (DG B as expected.

Room) Examinee simulates closing DGB-V064.

(Time Critical)

________There should be less than 60 minutes from step 1 until DGB-V064 is closed.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Planning organization for resolution.

NORMAL TERMINATION POINT Page 12 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 0 02/17/2011 6 Record created REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 13 of 14

P-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

o The Control Room has been evacuated due to a fire.

o The CRS has entered 40AO-9ZZ19, Control Room Fire INITIATING CUE:

o The CRS directs you to perform Appendix C, PBB-S04 Energized from Offsite Power.

THIS JPM IS TIME CRITICAL Page 14 of 14

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 43 of 195 CONTROL ROOM FIRE Appendix C Page 1 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. Enter Appendix Entry Time and Date:

NOTE -----------------------------------------------------------

The telephone number for the B Train Remote Shutdown Panel is:

Unit 1 - 1235 Unit 2 - 2235 Unit 3 - 3235

NOTE -----------------------------------------------------------

Actions directed by this appendix are time critical and must be performed as quickly as possible to ensure that effects of the fire do not prevent safe shutdown of the unit.

NOTE -----------------------------------------------------------

Portable lanterns should be used when performing actions in response to a fire. This will ensure that lighting is available if the emergency lighting system is degraded.

___ 2. Obtain a portable lantern from the Emergency Equipment Cabinet, FPN-C02. (B Switchgear Room, Northwest corner)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 44 of 195 CONTROL ROOM FIRE Appendix C Page 2 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

___ 3. On PHB-M32, place ALL of the following Control Room Circuits Disconnect Switches in LOCAL:

(Switchgear Room B)

PHB-M3209, Battery Charger D PKD-H14

PHB-M3205, Control Room Circuits Disconnect Switches (4 switches)

___ 4. Place all of the disconnect switches on DGB-C01, DG Disconnect Cabinet in LOCAL.

(5 switches) (Switchgear Room B)

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 45 of 195 CONTROL ROOM FIRE Appendix C Page 3 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

___ 5. Ensure the disconnect switches for ALL of the following breakers on PBB-S04 are in LOCAL:

PBB-S04S, Aux Feed Water Pump AFB-P01

PBB-S04N, 4160 - 480 LC PGB-L36

PBB-S04M, Essential Cooling Water Pump EWB-P01

PBB-S04L, ESF Service Transformer NBN-X03

PBB-S04K, ESF Service Transformer NBN-X04

PBB-S04J, 4160 - 480 LC PGB-L32

PBB-S04H, 4160 - 480 LC PGB-L34

PBB-S04G, Essential Chiller ECB-E01

PBB-S04F, LP Safety Injection Pump SIB-P01

PBB-S04C, Essential Spray Pond Pump SPB-P01

PBB-S04B, Diesel Generator PEB-G02

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 46 of 195 CONTROL ROOM FIRE Appendix C Page 4 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

___ 6. Place ALL of the following disconnect switches in LOCAL:

CS-2/B2 on PGB-L36B1

CS-1/B2 on PGB-L34B1

CS-2/C4 on PGB-L32C1

CS-1/B2 on PGB-L32B1

___ 7. Check that breaker PGB-L32C4, ___ 7.1 IF breaker PGB-L32C4, Charging Charging Pump 2 CHB-P01, Pump 2 CHB-P01, is closed. is open, THEN PERFORM the following:

a. Ensure charging pump suction is aligned to the RWT per Step 6 of Appendix G, Upper Auxiliary Building Actions.

b. Close breaker PGB-L32C4, Charging Pump 2 CHB-P01.

[Ref. Step 4.13]

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 47 of 195 CONTROL ROOM FIRE Appendix C Page 5 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

___ 8. Ensure that ALL of the following breakers are closed:

PBB-S04S, Aux Feed Water Pump AFB-P01

PBB-S04N, 4160 - 480V LC PGB-L36

PBB-S04M, Essential Cooling Water Pump, EWB-P01

PBB-S04J, 4160 - 480V LC PGB-L32

PBB-S04H, 4160 - 480V LC PGB-L34

PBB-S04G, Essential Chiller ECB-E01

PBB-S04C, Essential Spray Pond Pump SPB-P01

___ 9. Inform the CRS that ALL of the following are running:

Charging Pump B

Aux Feed Pump B

Spray Pond Pump B

Essential Cooling Water Pump B

Essential Chiller B

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ19 Revision 26 Page 48 of 195 CONTROL ROOM FIRE Appendix C Page 6 of 6 Appendix C, PBB-S04 Energized from Offsite Power INSTRUCTIONS CONTINGENCY ACTIONS

___ 10. IF Diesel Generator B is running, THEN perform the following:

(DG Control Panel)

a. Press DGB-HS-30, Emergency Stop.

b. IF a loss of Offsite Power occurs, THEN PERFORM ONE of the following as appropriate:

Appendix D, PBB-S04 Energized from DG B

Appendix E, PBB-S04 De-energized.

___ 11. Ensure that DGB-V064, Jacket Water Standpipe Make-up Header Isolation Valve, is closed.

(DG B Room)

End of Appendix

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 0500010601 Place containment refueling purge subsystem in service TASK STANDARD: Containment Power Access Purge Subsystem placed in service.

K/A: 3.8 029 A2.03 K/A RATING: RO: 2.7 SRO: 3.1 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40OP-9CP01, Containment Purge System SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: John Dedon Date: 09/09/2007 Revised By: Alan Malley Date: 11/17/2011 Technical Review Operations Approval E-Plan Review Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Planning organization for resolution.

Page 1 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#: 108 (This JPM is designed to run with JS-2 for the 2012 NRC exam)

SCENARIOS, MALFUNCTIONS, OVERRIDES,etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

Copy of 40OP-9CP01 available with prerequisites signed off. This JPM was written using Revision 19 of 40OP-9CP01, however, this JPM may be run with later revisions of the procedure if it is verified that the later revisions do not affect this JPM.

If IC-108 is not available perform the following:

rfCH03 f:open - Opens IA supply to CP-UV-4A, IA-VB47

rfCH04 f:open - Opens IA supply to CP-UV-5B, IA-VB45

rfIP38 f:0.00 - Sets Containment pressure to 0.0 psig Page 2 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Containment entry is to be made this shift INITIATING CUE:

The CRS direct you to place the Containment Power Access Purge Subsystem in service per 40OP-9CP01, Containment Purge System, Section 6.0.

An Auxiliary Operator has been briefed and is in the field.

All prerequisites are complete.

The CRS has authorized breaking the ZZ06 locks and the ZZ06 book has been filled out.

Page 3 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Step 6.3.1: INFORM CUE: Examinee contacts Effluent Tech to determine if 74ST-9SQ07 is current.

Ensure that the channel checks in Effluents Tech reports that 74ST-74ST-9SQ07, Radiation Monitoring 9SQ07 is current.

System Shiftly Surveillance Test that are required to meet SR 3.3.8.1 forRU-37 and/or RU-38 are current.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 6.3.2: INFORM CUE: Examinee directs an Auxiliary Operator to unlock and open IAN-Unlock and open IAN-VB45, Air The Auxiliary Operator reports VB45, Air Supply to CPB-UV-5B Supply to CPB-UV-5B and CP-HV- that IAN-VB45, Air Supply to and CP-HV-43 per40AC-0ZZ06.

43 per40AC-0ZZ06. CPB-UV-5B and CP-HV-43 has been unlocked and opened.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

3. Step 6.3.3: INFORM CUE: Examinee directs an Auxiliary Operator tounlock and open IAN-Unlock and open IAN-VB47, Air The Auxiliary Operator reports VB47, Air Supply to CPA-UV-4A.

Supply to CPA-UV-4A per 40AC- that IAN-VB47, Air Supply to 0ZZ06. CPA-UV-4Ahas been unlocked and opened.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

4. Step 6.3.4: INFORM CUE: Examinee directs an Auxiliary Operator to:

IF RU-34 is available,THEN place it The Auxiliary Operator reports in service as follows: that CPB-V024 (Isolation between

open CPB-V024 (Isolation

Ensure CPB-V024 is open. Power Access Purge Duct and RU- between Power Access (Isolation between Power Access 34) has been opened and CPB- PurgeDuct and RU-34).

PurgeDuct and RU-34). V023 (Isolation between Refueling

close CPB-V023 (Isolation

Ensure CPB-V023 is closed. Purge Duct and RU-34) has been between Refueling Purge (Isolation between Refueling closed. Ductand RU-34).

Purge Ductand RU-34).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. Step 6.3.5: Examinee verifies containment pressure less than or equal to 0.03 Ensure Containment Pressure is less psig.

than or equal to 0.03 psig (1" H2O) or negative pressure damage may occur to ductwork when fan CPN-J02starts.

SAT / UNSAT Comments (required for UNSAT):

Note prior to step 6.3.6 NOTE When starting the Containment Power Access Purge Supplyand Exhaust Units, the "CNTMT PRG SYS TRBL" alarm, Annunciator Window 7A10B, alarms temporarily on"Component Low Differential Pressure" and clears in a fewseconds.

Page 6 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

6.

Step 6.3.6: Examinee places CPN-HS-1 in the ACCESS PURGE position.

Place CPN-HS-1, Containment Purge Mode Selector Switch in theACCESS PURGE position to start the Containment Power AccessPurge.

SAT / UNSAT Comments (required for UNSAT):

Note before step 6.3.7 NOTE After CPA-HS-4 and CPB-HS-5 are taken to open:

1. CPA-UV-4B, CPB-UV-5B and CPN-PV-43open. If containment pressure is less thanor equal to 0.03 psig, CPA-UV-4A andCPB-UV-5A also open. If UV-4A/5A doesn'topen, dual indication will be received onHS-4 and HS-5.

2. Dampers M03, M06 and M07 open.

3. Fans CPN-A02 and CPN-J02 start.

STEP CUE STANDARD

7.

Step 6.3.7: Examinee places CPA-HS-4 to the OPEN position.

Place CPA-HS-4, Containment Power Access Purge Isolation ValvesCP-UV-4A/4B to the OPEN position.

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

8. Step 6.3.8: If the examinee should receive dual indication on CPA-HS-4, the IF dual position indication is examinee takes CPA-HS-4 to the received on CPA-HS-4,THEN CPA- OPEN position again.

HS-4 must be taken to the open position again to openCP-UV-4A. Examiner Note: This is not an expected action.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

9.

Step 6.3.9: Examinee places CPB-HS-5 to the OPEN position.

Place CPB-HS-5, Containment Power Access Purge Isolation ValvesCP-UV-5A/5B to the OPEN position.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

10. Step 6.3.10: If the examinee should receive dual indication on CPB-HS-5 the IF dual position indication is examinee takes CPB-HS-5 to the received on CPB-HS-5,THEN CPB- OPEN position again.

HS-5 must be taken to the open position again to openCP-UV-5A. Examiner Note: This is not an expected action.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11. Step 6.3.11: INFORM CUE: Examinee checks that CPN-PV-43 is open.

Check that CPN-PV-43, Vent Valve Another operator will complete the is open by observing the red remainder of this procedure.

ValvePosition Indicator on B07 is illuminated.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Planning organization for resolution.

NORMAL TERMINATION POINT Page 9 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 001 12/04/2003 6 Corrected setting for containment pressure in setup.

002 08/09/2007 6 Updated simulator commands 003 01/12/2011 6 Updated format and procedure revision 004 11/17/2011 6 Added IC for 2012 NRC exam.

REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 10 of 11

S-1 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Containment entry is to be made this shift INITIATING CUE:

The CRS direct you to place the Containment Power Access Purge Subsystem in service per 40OP-9CP01, Containment Purge System, Section 6.0.

An Auxiliary Operator has been briefed and is in the field.

All prerequisites are complete.

The CRS has authorized breaking the ZZ06 locks and the ZZ06 book has been filled out.

Page 11 of 11

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 of 61 Revision CONTAINMENT PURGE SYSTEM 40OP-9CP01 19 6.3.4 IF RU-34 is available, THEN place it in service as follows:

____ 1. Ensure CPB-V024 is open. (Isolation between Power Access Purge Duct and RU-34).

____ 2. Ensure CPB-V023 is closed. (Isolation between Refueling Purge Duct and RU-34).

____ 6.3.5 Ensure Containment Pressure is less than or equal to 0.03 psig (1" H2O) or negative pressure damage may occur to ductwork when fan CPN-J02 starts.

NOTE ----------------------------------------

When starting the Containment Power Access Purge Supply and Exhaust Units, the "CNTMT PRG SYS TRBL" alarm, Annunciator Window 7A10B, alarms temporarily on "Component Low Differential Pressure" and clears in a few seconds.

____ 6.3.6 Place CPN-HS-1, Containment Purge Mode Selector Switch in the ACCESS PURGE position to start the Containment Power Access Purge.

NOTE ----------------------------------------

After CPA-HS-4 and CPB-HS-5 are taken to open:

1) CPA-UV-4B, CPB-UV-5B and CPN-PV-43 open. If containment pressure is less than or equal to 0.03 psig, CPA-UV-4A and CPB-UV-5A also open. If UV-4A/5A doesn't open, dual indication will be received on HS-4 and HS-5.

2) Dampers M03, M06 and M07 open.

3) Fans CPN-A02 and CPN-J02 start.

____ 6.3.7 Place CPA-HS-4, Containment Power Access Purge Isolation Valves CP-UV-4A/4B to the OPEN position.

____ 6.3.8 IF dual position indication is received on CPA-HS-4, THEN CPA-HS-4 must be taken to the open position again to open CP-UV-4A.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 17 of 61 Revision CONTAINMENT PURGE SYSTEM 40OP-9CP01 19

____ 6.3.9 Place CPB-HS-5, Containment Power Access Purge Isolation Valves CP-UV-5A/5B to the OPEN position.

____ 6.3.10 IF dual position indication is received on CPB-HS-5, THEN CPB-HS-5 must be taken to the open position again to open CP-UV-5A.

____ 6.3.11 Check that CPN-PV-43, Vent Valve is open by observing the red Valve Position Indicator on B07 is illuminated.

____ 6.3.12 Log the time that the 8 inch Containment Purge Valves were opened on the release permit.

6.3.13 Notify BOTH of the following of the start time for the release:

____ RMS/Effluents Technician

____ Unit Radiation Protection

____ 6.3.14 IF the Containment Power Access Purge will continue beyond the shift, THEN contact the RMS/Effluents Technician to ensure the Shiftly ST required by SR 3.3.8.1 is current per 74ST-9SQ07, Radiation Monitoring System Shiftly Surveillance Test.

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM BASIS INFORMATION TASK: L225164 Borate the RCS to satisfy the Reactivity Control safety function TASK STANDARD: Boration commenced per Standard Appendix Attachment 103-B K/A: 3.1 004 A4.07 K/A RATING: RO: 3.9 SRO: 3.7 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40EP-9EO10, Standard Appendices, Appendix 103 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Alan Malley Date: 10/04/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM

1. SIMULATOR SETUP:

IC#: 108 (This IC is setup to run with JS-1 for the 2012 NRC exam)

SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None

SPECIAL INSTRUCTIONS:

o Set the boric acid totalizer to 100 gallons o Ensure the power reset alarm is cleared on CHN-FQIS-210Y,Boric Acid Makeup Totalized Flow Control

REQUIRED CONDITIONS:

o Reactor Tripped with >1 CEA stuck out

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40EP-9EO10, Standard Appendices, Appendix 103 available. This JPM was written using Revision 69 (the pages for Appendix 103 will say Rev 69 at top of page) of 40EP-9EO10. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

If IC-108 is not available for this JPM perform the following:

ImfcmCNCV08CHNFIC210Y_1 f:0 - fails the boric acid controller output to 0.

Page 2 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 was tripped manually,

More than 1 full-strength CEA did not fully insert.

INITIATING CUE:

The CRS directs you to borate per Standard Appendix 103 using the normal boration flowpath.

Page 3 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix 103: Examinee determines Attachment 103-A is the Normal Boration PERFORM ANY of the Path.

following Attachments based on current plant conditions:

Normal Boration Path

Attachment 103-A SAT / UNSAT Comments (required for UNSAT):

Page 5 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

2. Step 1 of Attachment 103-A: Examinee ensures CHN-FIC-210Y is set to less than 40 gpm.

Set the boric acid makeup flowrate on CHN-FIC-210Y, Boric Acid Makeup to VCT Flow Control, to40 gpm or less.

Flowrate Setpoint SAT / UNSAT Comments (required for UNSAT):

Page 6 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

3. Step 2 of Attachment 103-A: The examinee sets the Target makeup on CHN-FQIS-210Y to a Set the Target makeup volume minimum of 5000 gallons.

(gallons) on CHN-FQIS-210Y,Boric Acid Makeup Totalized Flow Control, to a minimum of 5000 gallons.

Target SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 3 of Attachment 103-A: Examinee places CHN-HS-210 to BORATE.

Place CHN-HS-210, Makeup Mode Select Switch, in BORATE.

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

5. Step 4 of Attachment 103-A: Examinee checks Boric Acid Makeup Pump is running.

Check one Boric Acid Makeup Pump is running.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6. Step 5 of Attachment 103-A: Examinee ensures CHN-UV-527 is open.

Ensure CHN-UV-527, Makeup to CHRG PMPS (VCT Bypass), is open.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

7. Step 6 of Attachment 103-A: The examinee pushes the left pushbutton if it is reading END.

If the left pushbutton onCHN-If not the examinee N/As this FQIS-210Y indicates End, then step.

press the End pushbutton.

Left pushbutton SAT / UNSAT/ NA Comments (required for UNSAT):

STEP CUE STANDARD

8. Step 7 of Attachment 103-A: The examinee pushes the left pushbutton if it is reading If the left pushbutton onCHN-RESET. If not the examinee FQIS-210Y indicates Reset, N/As this step.

then press the Reset pushbutton.

SAT / UNSAT/ NA Comments (required for UNSAT):

Page 9 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

9. Step 8 of Attachment 103-A: The examinee pushes the START pushbutton.

Press the Start pushbutton onCHN-FQIS-210Y.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

10. Step 9 of Attachment 103-A: Inform Cue (After examinee Examinee determines that flow is determines this path will not not indicated on CHN-FIC-210Y.

Check for BOTH of the work): The examinee may attempt to following:

operate CHN-FIC-210Y in a) CHN-FIC-210X indicates no The CRS directs you to use manual, but the controller will not Reactor Makeup Water Attachment 103B function in manual.

flow.(CHN-FV-210X closed) b) Proper flow indicated onCHN-FIC-210Y.

ALTERNATE PATH STARTS HERE.

SAT / UNSAT Comments (required for UNSAT):

Page 10 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

11. Step 1 of Attachment 103-B: Examinee verifies CHE-HV-532 open.

Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

12.

Step 2 of Attachment 103-B: Examinee places CHN-HS-527 in CLOSE.

Place CHN-HS-527, VCT Bypass in the CLOSE position.

SAT / UNSAT Comments (required for UNSAT):

Page 11 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

13. Step 3 of Attachment 103-B: Examinee ensures CHN-FIC-210X in manual with a 0%

Ensure CHN-FIC-output.

210X,ReactorMakeup Water to VCT Flow Control, is in manual with 0%output.

Output SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

14. Step 4 of Attachment 103-B: Examinee verifies CHN-HV-536 closed.

Ensure CHE-HV-536, RWT to Charging Pumps, is closed.

SAT / UNSAT Comments (required for UNSAT):

Page 12 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

15.

Step 5 of Attachment 103-B: Examinee opens CHN-UV-514.

Open CHN-UV-514, Boric Acid Makeup to Charging Pumps.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

16.

Step 6 of Attachment 103-B: Examinee closes CHN-UV-510.

Close CHN-UV-510, BAMP Recirc to RWT.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

17. Step 7 of Attachment 103-B: Examinee starts a BAMP unless it is still running from earlier Start a BAMP.

attempt to borate.

SAT / UNSAT Comments (required for UNSAT):

Page 13 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

18. Step 8 of Attachment 103-B: Inform Cue: Examinee may ask CRS if he wants additional charging pumps Start additional Charging Pumps The CRS does not desire to running or may N/A this step.

as needed.

start an additional charging pump.

Another operator will complete this attachment.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 14 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 15 of 16

S-2 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 was tripped manually,

More than 1 full-strength CEA did not fully insert.

INITIATING CUE:

The CRS directs you to borate per Standard Appendix 103 using the normal boration flowpath.

Page 16 of 16

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 974 of 1350 STANDARD APPENDICES Appendix 103 Page 1 of 18 Appendix 103, RCS Makeup / Emergency Boration INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. PERFORM ANY of the following Attachments based on current plant conditions:

Normal Boration Path

Attachment 103-A CHN-UV-514

Attachment 103-B

RWT > 73%

BAMP available

Attachment 103-C

RWT > 73%

BAMP NOT available CHE-HV-536

Attachment 103-D

RWT > 73%

PC Cleanup Pump NOT aligned to RWT

Attachment 103-E

RWT > 92%

PC Cleanup Pump Recircing RWT

Attachment 103-F

83%< RWT <92%

PC Cleanup Pump Recircing RWT

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 975 of 1350 STANDARD APPENDICES Appendix 103 Page 2 of 18 03-A Normal Boration Path Page 1 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Set the boric acid makeup flow rate on CHN-FIC-210Y, Boric Acid Makeup to VCT Flow Control, to 40 gpm or less.

___ 2. Set the Target makeup volume (gallons) on CHN-FQIS-210Y, Boric Acid Makeup Totalized Flow Control, to a minimum of 5000 gallons.

___ 3. Place CHN-HS-210, Makeup Mode Select Switch, in BORATE.

___ 4. Check one Boric Acid Makeup Pump is running.

___ 5. Ensure CHN-UV-527, Makeup to CHRG PMPS (VCT Bypass), is open.

___ 6. IF the left pushbutton on CHN-FQIS-210Y indicates End, THEN press the End pushbutton.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 976 of 1350 STANDARD APPENDICES Appendix 103 Page 3 of 18 03-A Normal Boration Path Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 7. IF the left pushbutton on CHN-FQIS-210Y indicates Reset, THEN press the Reset pushbutton.

___ 8. Press the Start pushbutton on CHN-FQIS-210Y.

___ 9. Check for BOTH of the following:

a. CHN-FIC-210X indicates no Reactor Makeup Water flow.

(CHN-FV-210X closed)

b. Proper flow indicated on CHN-FIC-210Y.

___ 10. Adjust the boric acid makeup setpoint on CHN-FIC-210Y to greater than or equal to 44 gpm.

End of Attachment

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 977 of 1350 STANDARD APPENDICES Appendix 103 Page 4 of 18 03-B CHN-UV-514 / BAMP Page 1 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

___ 2. Place CHN-HS-527, VCT Bypass in the CLOSE position.

___ 3. Ensure CHN-FIC-210X, Reactor Makeup Water to VCT Flow Control, is in manual with 0%

output.

___ 4. Ensure CHE-HV-536, RWT to Charging Pumps, is closed.

___ 5. Open CHN-UV-514, Boric Acid Makeup to Charging Pumps.

___ 6. Close CHN-UV-510, BAMP Recirc to RWT.

___ 7. Start a BAMP.

___ 8. Start additional Charging Pumps as needed.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 978 of 1350 STANDARD APPENDICES Appendix 103 Page 5 of 18 03-B CHN-UV-514 / BAMP Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 9. WHEN it is desired to restore charging pump suction to the VCT, THEN perform the following:

a. Ensure CHN-UV-501 is open.

b. Close CHN-UV-514.

c. Stop ANY running BAMP(s).

d. Place CHN-HS-510 in the Open/Auto position.

End of Attachment

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 979 of 1350 STANDARD APPENDICES Appendix 103 Page 6 of 18 03-C CHN-UV-514 / No BAMP Page 1 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

___ 2. Place CHN-HS-527, VCT Bypass in the CLOSE position.

___ 3. Ensure CHN-FIC-210X, Reactor Makeup Water to VCT Flow Control, is in manual with 0%

output.

___ 4. Ensure CHE-HV-536, RWT to Charging Pumps, is closed.

___ 5. Ensure no more than two Charging Pumps are running.

___ 6. Ensure that the third Charging Pump handswitch is in PTL.

___ 7. Direct an operator to open CHN-V164, Boric Acid Filter Bypass.

(120 ft. Filter Gallery Room)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 980 of 1350 STANDARD APPENDICES Appendix 103 Page 7 of 18 03-C CHN-UV-514 / No BAMP Page 2 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 8. IF a PC Cleanup Pump is in service taking a suction from the RWT, THEN direct an operator to perform the following:

a. IF Fuel Pool Cleanup Pump A is being used for RWT transfer or cleanup, THEN perform the following:

1) Stop FUEL POOL CLEANUP PUMP 1.

(Local Control Panel PCN-E02, 120' Fuel Bldg)

2) Close PCN-V043, CLEANUP PMP A DISCH ISO.

(100' FB Fuel Pool Clng, Cleanup Pumps & HX Room)

b. IF Fuel Pool Cleanup Pump B is being used for RWT transfer or cleanup, THEN perform the following:

1) Stop FUEL POOL CLEANUP PUMP 2.

(Local Control Panel PCN-E02, 120' Fuel Bldg)

2) Close PCN-V059, CLEANUP PMP B DISCH ISO (100' FB Fuel Pool Clng, Cleanup Pumps & HX Room)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 981 of 1350 STANDARD APPENDICES Appendix 103 Page 8 of 18 03-C CHN-UV-514 / No BAMP Page 3 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 9. Direct an Operator to open BOTH of the following:

Open CHN-V753, BAMP Discharge to PC System Isolation.

(70' Aux Bldg BAMP Rm)

Open CHN-V144, SFP to BAMP Suction Header Isolation valve.

(70' Aux Bldg BAMP Rm)

___ 10. Open CHN-UV-514, Boric Acid Makeup to Charging Pumps.

___ 11. Close CHN-UV-510, BAMP Recirc to RWT.

___ 12. Place and hold CHN-HS-501, VCT Outlet to CLOSE.

___ 13. Direct an operator to open NHN-M7208, CHN-UV-501.

___ 14. WHEN NHN-M7208 is open, THEN release CHN-HS-501.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 982 of 1350 STANDARD APPENDICES Appendix 103 Page 9 of 18 03-C CHN-UV-514 / No BAMP Page 4 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 15. IF one Charging Pump is running, AND the second pump will be started, THEN perform the following:

a. Ensure at least 20 seconds since last pump start or suction valve manipulation.

b. Start the second Charging Pump.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 983 of 1350 STANDARD APPENDICES Appendix 103 Page 10 of 18 03-C CHN-UV-514 / No BAMP Page 5 of 5 INSTRUCTIONS CONTINGENCY ACTIONS

___ 16. WHEN it is desired to restore charging pump suction to the VCT, THEN perform the following:

a. Direct an operator to close breaker NHN-M7208.

b. Ensure CHN-UV-501 is open.

c. Close CHN-UV-514.

d. Direct an operator to close ALL of the following:

CHN-V164, Boric Acid Filter Bypass.

(120' Filter Gallery Room).

CHN-V753, BAMP Discharge to PC System Isolation.

(70' Aux Bldg BAMP Rm)

CHN-V144, SFP to BAMP Isolation valve.

(70' Aux Bldg BAMP Rm)

e. Place CHN-HS-510 in the Open/Auto position.

End of Attachment

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 984 of 1350 STANDARD APPENDICES Appendix 103 Page 11 of 18 03-D CHE-HV-536 / No PC Cleanup Page 1 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

___ 2. Place CHN-HS-527, VCT Bypass, in the CLOSE position.

___ 3. Ensure CHN-FIC-210X, Reactor Makeup Water to VCT Flow Control, is in manual with 0%

output.

___ 4. Place CHN-HS-210, Makeup Mode Select Switch in MANUAL.

___ 5. Ensure the BAMPs are stopped.

___ 6. Open CHE-HV-536, RWT to Charging Pumps.

___ 7. Close CHN-UV-501, Volume Control Tank Outlet.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 985 of 1350 STANDARD APPENDICES Appendix 103 Page 12 of 18 03-D CHE-HV-536 / No PC Cleanup Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 8. IF one Charging Pump is running, AND the second pump will be started, THEN perform the following:

a. Ensure at least 20 seconds since last pump start or suction valve manipulation.

b. Start the second Charging Pump.

___ 9. WHEN it is desired to restore charging pump suction to the VCT, THEN perform the following:

a. Open CHN-UV-501.

b. Close CHE-HV-536.

End of Attachment

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 986 of 1350 STANDARD APPENDICES Appendix 103 Page 13 of 18 03-E CHE-HV-536 / RWT >92% / PC Cleanup Page 1 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

___ 2. Place CHN-HS-527, VCT Bypass in the CLOSE position.

___ 3. Ensure CHN-FIC-210X, Reactor Makeup Water to VCT Flow Control, is in manual with 0%

output.

___ 4. Place CHN-HS-210, Makeup Mode Select Switch in MANUAL.

___ 5. Ensure the BAMPs are stopped.

___ 6. Ensure no more than two Charging Pumps are running.

___ 7. Ensure that the third Charging Pump handswitch is in PTL.

___ 8. Open CHE-HV-536, RWT to Charging Pumps.

___ 9. Close CHN-UV-501, Volume Control Tank Outlet.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 987 of 1350 STANDARD APPENDICES Appendix 103 Page 14 of 18 03-E CHE-HV-536 / RWT >92% / PC Cleanup Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

___ 10. IF additional Charging Pumps will be started, THEN perform the following:

a. Ensure at least 20 seconds since the last pump start or suction valve manipulation.

b. Start additional Charging Pumps as needed.

___ 11. WHEN it is desired to restore charging pump suction to the VCT, THEN perform the following:

a. Open CHN-UV-501.

b. Close CHE-HV-536.

End of Attachment

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 988 of 1350 STANDARD APPENDICES Appendix 103 Page 15 of 18 03-F CHE-HV-536 / RWT 83 - 92% / PC Cleanup Page 1 of 4 INSTRUCTIONS CONTINGENCY ACTIONS

___ 1. Ensure that CHE-HV-532, RWT to Boric Acid Makeup Pumps, is open.

___ 2. Place CHN-HS-527, VCT Bypass, in the CLOSE position.

___ 3. Ensure CHN-FIC-210X, Reactor Makeup Water to VCT Flow Control, is in manual with 0%

output.

___ 4. Place CHN-HS-210, Makeup Mode Select Switch in MANUAL.

___ 5. Ensure the BAMPs are stopped.

___ 6. Ensure no more than two Charging Pumps are running.

___ 7. Ensure the third Charging Pump handswitch is in PTL.

___ 8. Open CHE-HV-536, RWT to Charging Pumps.

___ 9. Close CHN-UV-501, Volume Control Tank Outlet.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 989 of 1350 STANDARD APPENDICES Appendix 103 Page 16 of 18 03-F CHE-HV-536 / RWT 83 - 92% / PC Cleanup Page 2 of 4 INSTRUCTIONS CONTINGENCY ACTIONS

___ 10. IF one Charging Pump is running, AND the second pump will be started, THEN perform the following:

a. IF Emergency Boration is not required, THEN perform the following:

1) Open CHN-UV-501, Volume Control Tank Outlet.

2) GO TO substep c.

b. IF Emergency Boration is in progress, THEN direct an operator to perform the following:

1) IF Fuel Pool Cleanup Pump A is being used for RWT transfer or cleanup, THEN perform the following:

Stop FUEL POOL CLEANUP PUMP 1.

(Local Control Panel PCN-E02, 120' FB)

Close PCN-V043, CLEANUP PMP A DISCH ISO.

(100' FB Fuel Pool Clng, Cleanup Pumps

& HX Room)

(continue)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 990 of 1350 STANDARD APPENDICES Appendix 103 Page 17 of 18 03-F CHE-HV-536 / RWT 83 - 92% / PC Cleanup Page 3 of 4 INSTRUCTIONS CONTINGENCY ACTIONS

____ 10. (Continued)

2) IF Fuel Pool Cleanup Pump B is being used for RWT transfer or cleanup, THEN perform the following:

Stop FUEL POOL CLEANUP PUMP 2.

(Local Control Panel PCN-E02, 120' Fuel Building)

Close PCN-V059, CLEANUP PMP B DISCH ISO (100' Fuel Bldg Fuel Pool Cooling, Cleanup Pumps & HX Room)

c. Ensure at least 20 seconds since last pump start or suction valve manipulation.

d. Start the second Charging Pump.

e. IF CHN-UV-501 was opened, THEN close CHN-UV-501.

(continue)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 991 of 1350 STANDARD APPENDICES Appendix 103 Page 18 of 18 03-F CHE-HV-536 / RWT 83 - 92% / PC Cleanup Page 4 of 4 INSTRUCTIONS CONTINGENCY ACTIONS

____ 10. (Continued)

f. IF the Fuel Pool Cleanup Pump has been stopped, AND the third Charging Pump will be started, THEN perform the following:

1) Ensure at least 20 seconds since the last pump start or suction valve manipulation.

2) Start the third Charging Pump.

___ 11. WHEN it is desired to restore charging pump suction to the VCT, THEN perform the following:

a. Open CHN-UV-501.

b. Close CHE-HV-536.

End of Attachment

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: L211045 Placing the second Feedwater pump on-line.

TASK STANDARD: Second Feedwater pump on-line in automatic K/A: 3.4 039 A4.03 K/A RATING: RO: 2.8 SRO: 2.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9FT02, FEEDWATER PUMP TURBINE B SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 09/09/2011 Revised By: Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#: 109 (This IC is setup to run JS-3 and JS-4 for the 2012 NRC exam).

SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40OP-9FT02. This JPM was written using Revision 38 of 40OP-9FT02. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

IF IC-109 is not available, perform the following to setup for this JPM:

Reset to IC-16

Startup the B feedpump using section 4.3 of 40OP-9FT02 until feedpump speed is ~ 1000 rpm.

Page 2 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 is at 50% power.

40OP-9FT02, Main Feedwater Pump B has been completed thru section 4.3 in preparation of placing the B MFP in service.

INITIATING CUE:

The CRS directs you to place the second Feedpump (MFP B) on-line per Section 4.4 of 40OP-9FT02, Main Feedwater Pump B.

Page 3 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

NOTE The bias adjustment on SGN-FIC-1108, FWPT Speed Setpoint Controller, will add or subtract RPM from its input signal from the Master Controller.

STEP CUE STANDARD 1 Step 4.4.1 Ensure BOTH of the following:

___ SGN-FIC-1108, FWPT Examinee verifies places SGN-Speed Setpoint Controller is in FIC-1108 in auto.

auto.

Examiner Note: Auto is R on

____ FWPT B bias is set with the controller.

100 RPM of FWPT A.

Examinee adjust FWPT B bias to within 100 RPM of FWPT A.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD Step 4.4.2

2. Examinee verifies current SG WHEN performing Step 4.4.3 levels.

through Step 4.4.5, THEN ensure proper steam generator levels are maintained.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Step 4.4.3 Examinee adjusts FTN-HS-54 potentiometer until FWPT B Adjust FTN-HS-54, Manual discharge pressure matches Speed Control, to match pump FWPT A discharge pressure.

discharge pressure with the other FWPT discharge pressure.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Step 4.4.4 Examinee verifies open FWN-HV-32, FWPT B discharge valve.

Ensure FWN-HV-32, FWPT Discharge Valve, for FWN-P01B is open.

SAT / UNSAT Comments (required for UNSAT):

NOTE:

Any of the following may be useful when placing the second feed pump in service.

DFWCS Auto/manual stations display. AM_STNS_C)

DFWCS Feedwater pump display. (FWP_C)

PMS page display FEED PUMP PERFORMANCE (PC-3)

Page 6 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

5. Step 4.4.5 Examinee proceeds to sub steps 1-5.

Perform ALL of the following to place FWPT Speed Setpoint Controllers in Auto:

SAT / UNSAT Comments (required for UNSAT):

NOTE Using this option may adversely affect Steam Generator levels if the controller is adjusted too fast.

STEP CUE STANDARD

6.

Step 4.4.5 Examinee adjusts FTN-HS 54 until FWPT B actual speed is

1. Slowly adjust FTN-HS- within 10 RPM of the output on 54, Manual Speed SGN-FIC-1108 Control, to match FWPT actual speed with the output as read on SGN-FIC-1108, FWPT Speed Setpoint Controller.

(within 10 RPM of each other).

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

7. Step 4.4.5 Examinee circles or NAs this step.

2. IF it is desired to adjust the deviation meter with the bias, THEN ensure FWPT speed is greater than 4155 RPM.

SAT / UNSAT Comments (required for UNSAT):

NOTE:

Step 4.4.5.3 may be performed in parallel with the rest of this section.

STEP CUE STANDARD

8. Step 4.4.5 When Requested Cue: Examinee informs the CRS that FWPT B is at minimum speed

3. Notify the FW Pump The CRS will make the and that an Engineering Engineer that FW Pump notification to Engineering. notification should be made.

"B" is at minimum pump speed operation (shaft seal operation).

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

9.

Step 4.4.5 Examinee adjusts the bias on SGN-FIC-1108, FWPT Speed

4. Adjust the bias on SGN- Setpoint Controller, until there is FIC-1108, FWPT Speed a zero (0) deviation on FTN-SDI-Setpoint Controller, until 102.

there is a zero deviation on FTN-SDI-102, Manual/Auto Control Deviation.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

10.

Step 4.4.5 Examinee places FTN-HS-100 in AUTO.

5. Place FTN-HS-100, Auto/Manual Selector Switch, in AUTO.

(Control of the FWPT will now be with Speed Setpoint Controllers.)

SAT / UNSAT Comments (required for UNSAT):

Page 9 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

11.

Step 4.4.5 Inform Cue: When FWPT Examinee adjusts the bias on pressure and flows are balanced the A and B FWPT Speed

6. Balance FWPT A and B - This JPM is complete -. Setpoint Controllers (SGN-FIC-discharge pressures, 1107/1108) as needed to balance flows, and differential discharge pressures, flows and pressures between Main differential pressures between the Feedwater Pump Main Feed Pumps.

Discharge Pressure and Main Steam Header Pressure using the bias on SGN-FIC-1107, FWPT Speed Setpoint Controller, and SGN-FIC-1108, FWPT Speed Setpoint Controller.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 10 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 09/09/2011 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 11 of 12

S-3 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 is at 50% power.

40OP-9FT02, Main Feedwater Pump B has been completed thru section 4.3 in preparation of placing the B MFP in service.

INITIATING CUE:

The CRS directs you to place the second Feedpump (MFP B) on-line per Section 4.4 of 40OP-9FT02, Main Feedwater Pump B.

Page 12 of 12

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 24 of 105 Revision FEEDWATER PUMP TURBINE B 40OP-9FT02 37 4.4 Placing the Second Feedwater Pump On-Line

NOTE ----------------------------------------

The bias adjustment on SGN-FIC-1108, FWPT Speed Setpoint Controller, will add or subtract RPM from its input signal from the Master Controller.

4.4.1 Ensure BOTH of the following:

____ SGN-FIC-1108, FWPT Speed Setpoint Controller, is in auto.

____ FWPT B bias is set within 100 RPM of FWPT A.

____ 4.4.2 WHEN performing Step 4.4.3 through Step 4.4.5, THEN ensure proper steam generator levels are maintained.

____ 4.4.3 Adjust FTN-HS-54, Manual Speed Control, to match pump discharge pressure with the other FWPT discharge pressure.

____ 4.4.4 Ensure FWN-HV-32, FWPT Discharge Valve, for FWN-P01B is open.

NOTE ----------------------------------------

Any of the following may be useful when placing the second feed pump in service.

DFWCS Auto/manual stations display. (AM_STNS_C)

DFWCS Feedwater pump display. (FWP_C)

PMS page display FEED PUMP PERFORMANCE (PC-3).

____ 4.4.5 Perform ALL of the following to place FWPT Speed Setpoint Controllers in Auto:

NOTE ----------------------------------------

Using this option may adversely affect Steam Generator levels if the controller is adjusted too fast.

____ 1. Slowly adjust FTN-HS-54, Manual Speed Control, to match FWPT actual speed with the output as read on SGN-FIC-1108, FWPT Speed Setpoint Controller.

(within 10 RPM of each other)

____ 2. IF it is desired to adjust the deviation meter with the bias, THEN ensure FWPT speed is greater than 4155 RPM.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 25 of 105 Revision FEEDWATER PUMP TURBINE B 40OP-9FT02 37

NOTE ----------------------------------------

Step 4.4.5.3 may be performed in parallel with the rest of this section.

____ 3. Notify the FW Pump Engineer that FW Pump "B" is at minimum pump speed operation (shaft seal operation).

____ 4. Adjust the bias on SGN-FIC-1108, FWPT Speed Setpoint Controller, until there is a zero deviation on FTN-SDI-102, Manual/Auto Control Deviation.

____ 5. Place FTN-HS-100, Auto/Manual Selector Switch, in AUTO.

(Control of the FWPT will now be with Speed Setpoint Controllers.)

____ 6. Balance FWPT A & B discharge pressures, flows, and differential pressures between Main Feedwater Pump Discharge Pressure and Main Steam Header Pressure using the bias on SGN-FIC-1107, FWPT Speed Setpoint Controller, and SGN-FIC-1108, FWPT Speed Setpoint Controller.

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM BASIS INFORMATION TASK: 0120020701Fill a Safety Injection Tank TASK STANDARD: SIT 2B level restored to the normal band.

K/A: 3.3 006 A1.13 K/A RATING: RO: 3.5 SRO: 3.7 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 20 minutes

REFERENCES:

40OP-9SI03 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 09/09/2011 Revised By: Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM

1. SIMULATOR SETUP:

IC#: 109 (This IC is setup to run JS-3 and JS-4 for the 2012 NRC exam.)

SCENARIOS, MALFUNCTIONS, OVERRIDES,etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40OP-9SI03. This JPM was written using Revision 33 of 40OP-9SI03. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION 8 Go to simulator diagram page SI1 and click When directed to throttle SIB-UV-667 to reach 1400 on Components/Motor Operated valves psig.

(CRF)/SIBUV667/crMVSI01SIBUV667_9 and adjust slowly as the operator directs. (It should end up ~ f:40) 11 MRF SI05 f:5 When directed to throttle open SIB-V400 Page 2 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Level in SIT 2B has been lowering over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Maintenance has identified a leaking connection.

Engineering is developing a trouble shooting game plan.

HPSI pump B pre-start checks have been completed.

SIE-V463, SIT Fill and Drain Line Containment Isolation is OPEN with a dedicated assigned at the valve to close the valve if required. (A manual SESS has been inserted).

SIB-V219, Mini Flow Recirc Orifice Bypass Valve is OPEN.

HPSI B has been declared Inoperable and unavailable.

SIB-UV-667, HPSI B to the RWT isolation valve has been throttled 9 turns OPEN.

The HPSI discharge header was vented during the previous shift.

SIE-V220, SIT 2B Fill & Drain Header Manual Isol Valve has been verified open.

Manual HPSI B SESS alarm has been inserted

40OP-9SI03, section 6.3 (Filling the Safety Injection Tanks to Establish or Maintain Normal level has been completed thru step 6.3.5.25.

INITIATING CUE:

The CRS directs you tostart HPSI pump B and fill the 2B SIT starting at step 6.3.5.26 of 40OP-9SI03 to maintain/restore normal level in SIT 2B.

Page 3 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM START TIME:

NOTE When HPSI Pump B is started, it will be recircing to the RWT.

CAUTION HPSI pump operation between 85 and 225 gpm for greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months will result in pump damage.

STEP CUE STANDARD

1.

Step 6.3.5.26 If requested cue: Examinee starts HPSI Pump B using SIB-HS-2.

Start HPSI Pump B using SIB-HS-2, HPSI PUMP B P02. The Auxiliary Operator reports everyone is clear of the HPSI pump.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 6.3.5.27 Examinee verifies discharge pressure (approximately 1800 psi)

Verify ALL of the following indicated on SIN-PI-309 and expected responses:

motor run amps <120.

Discharge pressure is indicated on SIN-PI-309, HPSI HEADER B TO RC LOOPS PRESSURE

Unit 1 Only - Motor run current less than 120 amps SAT / UNSAT Comments (required for UNSAT):

Page 5 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

3. Step 6.3.5.28 Examinee verifies no anomalous HPSI Pump indications.

IF anomalous HPSI Pump indications are observed, THEN perform the following:

a. Notify the CRS immediately.

b. Consider stopping HPSI Pump B.

c. Evaluate the reason for anomalous indications.

SAT / UNSAT Comments (required for UNSAT):

NOTE When a HPSI pump is first started, some seal leakage is expected for a short duration.

During normal HPSI pump operation, a dripping seal is normally acceptable, a steady stream is indication of seal damage.

STEP CUE STANDARD

4. Step 6.3.5.29 When Requested Cue: Examinee directs AO to inspect HPSI pump B seals for leakage.

Inspect HPSI Pump B seals for leakage. AO reports only a dripping seal with no indication of unusual leakage at HPSI pump B.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

5. Step 6.3.5.30 Examinee NAs step.

IF leakage is discovered at the pump seals, THEN notify System Engineering.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6. Step 6.3.5.31 If Requested Cue: Examinee verifies that HAB-Z01 is running by either SEAS Verify that HAB-Z01, Aux. Bldg.

AO verifies that HAB-Z01 is window 12L or local indication.

HPSI Pump Room Ess. Air Control Unit, has started by ONE running.

of the following methods:

SEAS window 12L blue light at ESB-UA-2F is not on when status display button on ESB-UA-2D is depressed

Local observation that HAB-Z01 is running.

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

7. Step 6.3.5.32 Examinee NAs step.

IF HAB-Z01 Aux. Bldg. HPSI Pump Room Ess. Air Control Unit, did NOT start when HPSI Pump B started, THEN notify the SM/CRS.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.

Step 6.3.5.33 Examinee directs AO to throttle closed on SIB-UV-667 until SIN-Throttle manually SIB-UV-667, PI-309 indicates approximately HPSI B to the RWT Isolation 1400 psig.

Valve, to adjust HPSI Pump B discharge pressure to 1400 psig indicated on SIN-PI-309, HPSI Examiner Note: Driver action Pmp B HdrDisch Press. required to throttle closed SIB-UV-667.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

9.

Step 6.3.5.34 Examinee opens SIA-UV-682.

Open SIA-UV-682 using SIA-HS-682, MISC DRAIN HEADER TO RWT VLV.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

10. Step 6.3.5.35 When Requested Cue: Examinee directs AO to unlock SIB-V400.

Unlock SIB-V400, SIT Fill and Drain Isolation Valve HPSI SIB-V400 has been unlocked Recirc, per 40AC-0ZZ06, Locked per 40AC-0ZZ06.

Valve, Breaker and Component Control.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11. Step 6.3.5.36 When Requested Cue: Examinee directs AO to throttle open SIB-V400.

Throttle open SIB-V400, SIT Fill and Drain Isolation Valve HPSI AO throttles SIB-V400 as Recirc, slowly to control SIT fill directed.

rate.

SAT / UNSAT Comments (required for UNSAT):

NOTE If a SIT Fill and Drain Manual Isolation Valve is closed to isolate an inoperable and open SIT Fill and Drain Air Operated Valve, opening the SIT Fill and Drain Manual Isolation Valve makes the associated SIT inoperable and LCO 3.5.1 or LCO 3.5.2 is applicable.

Page 9 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

12. Step 6.3.5.37 If Requested Cue: Examinee NAs step.

IF the SIT Fill & Drain Manual Isolation Valve for the SIT to be SIE-V220 has been verified filled is closed, THEN open the open.

SIT Fill & Drain Manual Isolation Valve for the SIT to be filled:

SIE-V220, SIT 2B Fill &

Drain Header Manual Isol Valve SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

13. Step 6.3.5.38 Examinee records current SIT level.

IF the unit is in MODES 1 through 4, THEN record initial SIT level:

SAT / UNSAT Comments (required for UNSAT):

Note:

Annunciator window 2B11A, SIT LVL HI-LO, alarms on SIT hi level at 63% NR level.

Annunciator window 2B11B, SIT LVL HI-HI/LO-LO, alarms on SIT hi-hi level at 69% NR level.

Page 10 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

14.

Step 6.3.5.39 Examinee OPENS SIB-UV-621.

Open the SIT Fill & Drain Valve for the SIT to be filled:

SIB-UV-621 using SIB-HS-621, SIT 2B FILL & DRAIN VLV SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

15.

Step 6.3.5.40 Inform CUE: Examinee monitors SIT 2B level increase using SIN-LI-313 (NR)

Monitor level of the SIT being Another operator will complete and SIB-LI-311 (WR).

filled:

the remaining actions.

SIN-LI- R) SIT 2B LVL, 313 LT-333 SIB-LI311 L) SIT 2B LVL LT--321 SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparednessorganization for resolution.

NORMAL TERMINATION POINT Page 11 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 09/30/11 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 12 of 13

S-4 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM EXAMINEE HANDOUT INITIAL CONDITIONS:

Level in SIT 2B has been lowering over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Maintenance has identified a leaking connection.

Engineering is developing a trouble shooting gameplan.

HPSI pump B pre-start checks have been completed.

SIE-V463, SIT Fill and Drain Line Containment Isolation is OPEN with a dedicated assigned at the valve to close the valve if required. (A manual SESS has been inserted).

SIB-V219, Mini Flow Recirc Orifice Bypass Valve is OPEN.

HPSI B has been declared Inoperable and unavailable.

SIB-UV-667, HPSI B to the RWT isolation valve has been throttled 9 turns OPEN.

The HPSI discharge header was vented during the previous shift.

SIE-V220, SIT 2B Fill & Drain Header Manual Isol Valve has been verified open.

Manual HPSI B SESS alarm has been inserted

40OP-9SI03, section 6.3 (Filling the Safety Injection Tanks to Establish or Maintain Normal level has been completed thru step 6.3.5.25.

INITIATING CUE:

The CRS directs you to start HPSI pump B and fill the 2B SIT starting at step 6.3.5.26 of 40OP-9SI03 to maintain/restore normal level in SIT 2B.

Page 13 of 13

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1260010101 Respond to an alarm TASK STANDARD: RMWT water added to RDT to lower RDT temperature/pressure K/A: 3.5 007 A2.05 K/A RATING: RO: 3.2 SRO: 3.6 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40AL-9RK3A, Panel B03A Alarm Responses SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 09/30/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle SAT / UNSAT

One)

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#: 107 (This IC is designed to run JS-5 and JS-6 together for the 2012 NRC exam)

SCENARIOS, MALFUNCTIONS, OVERRIDES,etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION See Special Instructions

SPECIAL INSTRUCTIONS:

o After the IC is loaded, place the simulator in run and perform the following to bring the Reactor Drain Tank Hi Temperature alarm to the top of the alarm screen:

Go to the Panel Overview for B03 Click on alarm window B03A window 7A.

Override ALARM_OFF the Reactor Drain Tank Hi Temperature alarm.

Then override No_override for the Reactor Drain Tank Hi Temperature alarm.

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

This JPM was written using Revision 27 of 40AL-9RK3A. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION None Page 2 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

A pressurizer relief valve RCE-PSV-201 had been leaking past its seat.

RCS pressure has been reduced to 2210 psia.

Downstream temperatures from RCE-PSV-201 have stabilized.

INITIATING CUE:

The CRS directs you to take action per 40AL-9RK3A, window 3A07B to clear alarm point CHPS268, Reactor Drain Tank Pressure Hi.

Page 3 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

NOTE If the reactor drain tank pressure continues to increase to 10 psig the RDT vent to gas surge header valve CHN-UV-540 and RDT outlet containment isolation valve CHA-UV-560, will close. At approximately120 psid the RDT rupture disc, CHN-PSE-12 will rupture.

STEP CUE STANDARD

1. First Priority Action, step 1 Examinee verifies hi pressure in the RDT, approximately 6.0 psig Check the reactor drain tank pressure Hi Alarm by reading CHN-PI-268 on B03.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. First Priority Action, step 2 Examinee verifies high temperature and proceeds to window 3A07A, IF the RDT Hi Temperature Alarm is Group A (page 42).

received, OR RDT temperature is increasing, THEN GO TO Alarm Response for Window 3A07A, Group A (page 42).

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD First Priority Action (3A07A)

3. If requested cue: Examinee may refer to cue to verify that the Hi temperature and Pressure

1. Consider performing 40AO- were due to a leaking Pressurizer 9ZZ02, Excessive RCS The CRS will address 40AO-9ZZ02. PSV.

Leakage, in conjunction with this procedure.

2. Check the Reactor Drain Tank Temperature is greater than orequal to 140°F OR increasing by reading Temperature indicatorCHN-TI-268 on panel B03.

3. Monitor RDT pressure at CHN-PI-268 on B03.

4. Monitor the pressurizer relief to RDT temperatures atRCN-TI-106, RCN-TI-107, RCN-TI-108 and RCN-TI-109 on B04 to determine if pressurizer relief leakage is the cause of the Hi Temperature.

5. IF a valid alarm is received while shutdown cooling is in service, THEN refer to 40EP-9EO11, Lower Mode Function Recovery.

SAT / UNSAT Comments (required for UNSAT):

NOTE This alarm response will mitigate a high temperature condition in the RDT.It will also address RDT Hi-Lo Level and RDT Hi pressure conditions whichresults from hot water leakage into the RDT.

Page 6 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

5. Second Priority Action, step 1 Examinee verifies GRA-UV-1 and GRB-UV-2 OPEN.

Ensure GRA-UV-1 and GRB-UV-2, Containment Isolation Valves for the RDT/Gas Surge Header, are open.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6.

Second Priority Action, step 2 Examinee opens CHN-UV-540.

Open CHN-UV-540, RDT Vent to Gas Surge Tank, to establish a vent of the RDT.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7.

Second Priority Action, step 3.1 Examinee starts either RMW pump CHN-P03A/B.

Start CHN-P03A or CHN-P03B, RMW pump, from B03.

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

8.

Second Priority Action, step 3.2 Examinee opens CHN-UV-580, Makeup Supply Header to RDT Open CHN-UV-580, Makeup Supply Containment Isolation, from B03.

Header to RDT Containment Isolation, from B03.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

9. Second Priority Action, step 3.3 Inform Cue: Examinee directs an Auxiliary Operator to slowly OPEN CHN-Direct an Auxiliary Operator to AO reports that CHN-V790 is V790, RMW header isolation.

slowly OPEN CHN-V790, RMW open.

header isolation, located on the 110 ft. of the aux. building letdown valve gallery.

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

10. Second Priority Action, step 3.4 Inform Cue: Examinee closes CHN-UV-580.

WHEN RDT temperature is less than After RDT Temperature is less 140 degrees,THEN close CHN-UV- than 140 degrees:

580, Makeup Supply Header to RDT Containment Isolation.

The CRS directs you to stop filling the RDT at this time.

After the examinee closes CHN-UV-580:

Another operator will complete steps to reduce RDT level.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparednessorganization for resolution.

NORMAL TERMINATION POINT Page 9 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 10 of 11

S-5 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

A pressurizer relief valve RCE-PSV-201 had been leaking past its seat.

RCS pressure has been reduced to 2210 psia.

Downstream temperatures from RCE-PSV-201 have stabilized.

INITIATING CUE:

The CRS directs you to take action per 40AL-9RK3A, window 3A07B to clear alarm point CHPS268, Reactor Drain Tank Pressure Hi.

Page 11 of 11

40AL-9RK3A Panel BO3A Alarm Responses Rev. 27 3A07B REAC DRN TK PRESS HI Page 1 of 2 Page 118 of 130 RESPONSE SECTION PT ID POSSIBLE CAUSE SETPOINT CHPS268 Reactor Drain Tank Pressure Hi 5 psig AUTO ACTION

____ 1. None.

NOTE If the reactor drain tank pressure continues to increase to 10 psig the RDT vent to gas surge header valve CHN-UV-540 and RDT outlet containment isolation valve CHA-UV-560, will close. At approximately 120 psid the RDT rupture disc, CHN-PSE-12 will rupture.

FIRST PRIORITY OPERATOR ACTION

____ 1. Check the reactor drain tank pressure Hi Alarm by reading CHN-PI-268 on B03.

____ 2. IF the RDT Hi Temperature Alarm is received, OR RDT temperature is increasing, THEN GO TO Alarm Response for Window 3A07A, Group A (page 42).

SECOND PRIORITY OPERATOR ACTION

____ 1. Ensure GRA-UV-1 and GRB-UV-2, Containment Isolation Valves for the RDT/Gas Surge Header, are open.

____ 2. Vent the RDT to the gas surge header using CHN-UV-540 to maintain RDT pressure below 10 psig.

(CONTINUED)

40AL-9RK3A Panel BO3A Alarm Responses Rev. 27 3A07B REAC DRN TK PRESS HI Page 2 of 2 Page 119 of 130

____ 3. Determine the source of the water being discharged to the RDT and correct the condition causing the discharge. Possible sources include but are not limited to:

_____ 3.1 Pressurizer reliefs.

_____ 3.2 RWT recirc line relief.

_____ 3.3 RCS loop drains.

_____ 3.4 RCP Seal Bleedoff NOTE During RCS fill and vent, CHN-UV-540 could be manually open to allow RDT pressure to increase up to 25 psig while releasing to the Gas Surge Header.

____ 4. IF RDT pressure is above 10 psig, AND the RCS is not being filled and vented per 40OP-9RC02, reactor Coolant System Fill and Vent, THEN notify Radiation Protection that the RDT is being vented into containment.

_____ 4.1 Vent the RDT to containment using CHN-HV-923, RDT Atmospheric Vent Isolation, on B07, until RDT pressure is less than 5 psig on CHN-PI-268 on B03.

____ 5. IF CHN-UV-540, RDT Vent to Gas Surge Tank, is manually open per 40OP-9RC02, reactor Coolant System Fill and Vent, AND RDT pressure is above 25 psig, THEN stop the RCS vent to the RDT until RDT pressure is less than 10 psig.

____ 6. Take further actions as directed by 40AL-9RK3A, 3A07A, Group B.

End of Response

40AL-9RK3A Panel BO3A Alarm Responses Rev. 27 3A07A REAC DRN LOOP TRBL Page 1 of 9 Page 42 of 130 ANNUNCIATOR WINDOW INDEX GROUP PT ID POSSIBLE CAUSE SETPOINT A CHTS268 Reactor Drain Tank Temperature Hi 140°F B CHLS268 Reactor Drain Tank Level Hi-Lo Hi-75%

Lo-52%

C CHPDS258 Reactor Drain Filter Differential Pressure Hi 25 psid D CHYS5 CVCS Reactor Drain Pump 1 Overload CHYS6 CVCS Reactor Drain Pump 2 Overload N/A

40AL-9RK3A Panel BO3A Alarm Responses Rev. 27 3A07A REAC DRN LOOP TRBL Page 2 of 9 Page 43 of 130 RESPONSE SECTION GROUP A PT ID POSSIBLE CAUSE SETPOINT CHTS268 Reactor Drain Tank Temperature Hi 140°F AUTO ACTION

____ 1. None FIRST PRIORITY OPERATOR ACTION

____ 1. Consider performing 40AO-9ZZ02, Excessive RCS Leakage, in conjunction with this procedure.

____ 2. Check the Reactor Drain Tank Temperature is greater than or equal to 140°F OR increasing by reading Temperature indicator CHN-TI-268 on panel B03.

____ 3. Monitor RDT pressure at CHN-PI-268 on B03.

____ 4. Monitor the pressurizer relief to RDT temperatures at RCN-TI-106, RCN-TI-107, RCN-TI-108 and RCN-TI-109 on B04 to determine if pressurizer relief leakage is the cause of the Hi Temperature.

____ 5. IF a valid alarm is received while shutdown cooling is in service, THEN refer to 40EP-9EO11, Lower Mode Function Recovery.

SECOND PRIORITY OPERATOR ACTION NOTE This alarm response will mitigate a high temperature condition in the RDT. It will also address RDT Hi-Lo Level and RDT Hi pressure conditions which result from hot water leakage into the RDT.

____ 1. Ensure GRA-UV-1 and GRB-UV-2, Containment Isolation Valves for the RDT/Gas Surge Header, are open.

____ 2. Open CHN-UV-540, RDT Vent to Gas Surge Tank, to establish a vent of the RDT.

(CONTINUED)

40AL-9RK3A Panel BO3A Alarm Responses Rev. 27 3A07A REAC DRN LOOP TRBL Page 3 of 9 Page 44 of 130 NOTE The following steps may have to be done concurrently or alternately one or more times to control the temperature and level in the reactor drain tank.

____ 3. Perform the following steps to add Reactor Makeup Water to the RDT for cooling the contents of the RDT:

_____ 3.1 Start CHN-P03A or CHN-P03B, RMW pump, from B03.

_____ 3.2 Open CHN-UV-580, Makeup Supply Header to RDT Containment Isolation, from B03.

_____ 3.3 Direct an Auxiliary Operator to slowly OPEN CHN-V790, RMW header isolation, located on the 110 ft. of the aux.

building letdown valve gallery.

_____ 3.4 WHEN RDT temperature is less than 140 degrees, THEN close CHN-UV-580, Makeup Supply Header to RDT Containment Isolation.

____ 4. Perform the following steps to pump the RDT to the CVCS HUT.

_____ 4.1 IF RDT temperature has been reduced to less than 140 degrees, THEN refer to 40OP-9CH01, CVCS Normal Operations, to pump the RDT.

_____ 4.2 Ensure the HUT is NOT being processed through the Reactor Drain Filter.

_____ 4.3 Open CHA-UV-560, RDT outlet isolation valve, from B03.

_____ 4.4 Open CHB-UV-561, RDT containment isolation valve, from B03.

_____ 4.5 Open GAA-UV-2, LP N2 supply to the RDT, from B07.

_____ 4.6 Place CHE-UV-500, VCT inlet valve to the "VCT RESET" position from B03.

_____ 4.7 Place CHE-UV-565, Preholdup IX divert valve to the "BYPASS" position.

(CONTINUED)

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 1250310201 Respond to an Inadvertent MSIS TASK STANDARD: Inadvertent MSIS reset K/A: 3.2 013 A4.01 K/A RATING: RO: 4.5 SRO: 4.8 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10/27/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal postcritique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#: 107 (This IC is setup to run JS-5 and JS-6 together for the 2012 NRC exam)

SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: N/A Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40AO-9ZZ17 available. This JPM was written using Revision 15 of 40AO-9ZZ17.

This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

If IC-107 is not available then perform the following to setup for this JPM:

Imf cm SRRP01IRMSISAB_1 - MSIS relay failure

Imf cm TRRX12SGALT1114_4 - SG 1 high level transmitter failure

Override and OPEN Downcomer Isolation and MSIVs for SG 1

Delete the two malfunctions entered above.

Page 2 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATEany equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 is at 2% power.

An inadvertent MSIS has occurred due to a power supply failure.

The CRS has implemented 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations.

The faulted power supply has been replaced.

INITIATING CUE:

The CRS directs you to reset MSIS, in accordance with appendix B of 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations.

Page 3 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Enter Appendix Entry Time Examinee enters appendix entry and Date: time and date.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Enter actuation(s) to be Examinee enters MSIS.

reset:

SAT / UNSAT Comments (required for UNSAT):

Notes before step 3:

Overriding equipment disables automatic ESFAS operation of the equipment. Depending on plant conditions, this action may make the equipment inoperable.

The HPSI, LPSI and CS pump minimum recirculation flow provides sufficient heat removal for only one hour of pump operation.

Page 5 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3. IF the PPS-ESFAS actuation was Examinee NAs step based on cue caused by failure to reset the SG provided.

or PZR Pressure variable setpoints during a controlled cooldown, THEN perform the following:

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Check the Bistable Trip Lamps at Examinee determines that the the PPS Remote Operators A train SG 1 level HI Module (B05) for the affected Bistable trip lamp is lit.

PPS-ESFAS actuation input parameters on all PPS Channels satisfy ONE of the following

NOT lit

Bypassed SAT / UNSAT Comments (required for UNSAT):

Page 6 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

5.

Contingency Actions 4.1. Examinee resets the A channel Bistable Trip Lamp on B05.

a. Reset the affected Bistable Trip Lamps at the PPS Remote Operators Module (B05).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

6. Step 5 of appendix B Examinee determines that the A train MSIS initiation relay lamp is Check the affected PPS-ESFAS not lit.

actuation Initiation Relay lamps are illuminated at the PPS emote Operators Module (B05) on all PPS Channels.

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

7.

Contingency Action 5.2 Examinee resets the MSIS initiation paths on channel A.

a. Obtain the PPS Initiation Reset key for the affected Train.

b. Unlock the affected Initiation Path Reset Train (PPS Cabinets).

c. Reset the affected Initiation Path by depressing the appropriate Initiation Path Reset pushbutton (PPS Cabinets).

d. Lock the Initiation Path Reset Train (PPS Cabinets).

e. Remove the PPS Initiation Reset key.

f. Check the affected Initiation Signal lamps are illuminated for the affected PPS channels (On status panels above PPS Cabinets).

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

8. Step 6 of appendix B. Examinee determines that the A train MSIS signal lamps are not Check the actuated PPS-ESFAS illuminated.

leg 1-3 and leg 2-4 Actuation Signal lamps are illuminated for PPS Train A and Train B Actuation Signals (On status panels above PPS Cabinet A, SBAC01 and PPS Cabinet B, SBBC01).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

9.

Contingency Action 6.1. Examiner Note: Examinee resets the A train Pressing either pushbutton S64A MSIS Lockout.

Perform the following for the or S74A will reset the MSIS affected Train(s): LOCKOUT.

a. Press the LOCKOUT RESET pushbutton(s) for the affected PPS-ESFAS actuation(s) (Aux Relay Cabinets Bay 6 & 7).

b. Check both red ON lamps are illuminated for the affected PPS-ESFAS Inform Cue: Another operator actuation (Aux Relay will complete this appendix.

Cabinets Bay 6 & 7).

SAT / UNSAT Comments (required for UNSAT):

Page 9 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 10 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 10/27/2011 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 11 of 12

S-6 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 is at 2% power.

An inadvertent MSIS has occurred due to a power supply failure.

The CRS has implemented 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations.

The faulted power supply has been replaced.

INITIATING CUE:

The CRS directs you to reset MSIS, in accordance with appendix B of 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations.

Page 12 of 12

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ17 Revision 15 Page 54 of 89 INADVERTENT PPS-ESFAS ACTUATIONS Appendix B Page 1 of 5 Appendix B, PPS-ESFAS Reset INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. Enter Appendix Entry Time and Date:

___ 2. Enter actuation(s) to be reset:

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ17 Revision 15 Page 55 of 89 INADVERTENT PPS-ESFAS ACTUATIONS Appendix B Page 2 of 5 Appendix B, PPS-ESFAS Reset INSTRUCTIONS CONTINGENCY ACTIONS

NOTE -----------------------------------------------------------

Overriding equipment disables automatic ESFAS operation of the equipment.

Depending on plant conditions, this action may make the equipment inoperable.

NOTE -----------------------------------------------------------

The HPSI, LPSI and CS pump minimum recirculation flow provides sufficient heat removal for only one hour of pump operation.

___3. IF the PPS-ESFAS actuation was caused by failure to reset the SG or PZR Pressure variable setpoints during a controlled cooldown, THEN perform the following:

a. Direct I&C to clear the affected trip signals.

b. Evaluate the need to override and position PPS-ESFAS actuated equipment.

REFER TO the appropriate attachment in Appendix C, PPS-ESFAS Check, for a list of actuated equipment.

c. Override and position equipment as needed.

d. WHEN the trip signals are cleared, THEN continue with this appendix.

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ17 Revision 15 Page 56 of 89 INADVERTENT PPS-ESFAS ACTUATIONS Appendix B Page 3 of 5 Appendix B, PPS-ESFAS Reset INSTRUCTIONS CONTINGENCY ACTIONS

___4. Check the Bistable Trip Lamps at ___ 4.1 Perform the following for any the PPS Remote Operators tripped input parameter:

Module (B05) for the affected PPS-ESFAS actuation input a. Reset the affected Bistable parameters on all PPS Channels Trip Lamps at the PPS satisfy ONE of the following. Remote Operators Module (B05).

NOT lit

b. IF the trip light will NOT reset,

Bypassed AND ANY parameter is tripped on two or more channels, THEN GO TO step 7.1 of this appendix.

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ17 Revision 15 Page 57 of 89 INADVERTENT PPS-ESFAS ACTUATIONS Appendix B Page 4 of 5 Appendix B, PPS-ESFAS Reset INSTRUCTIONS CONTINGENCY ACTIONS

___5. Check the affected PPS-ESFAS ___ 5.1 IF the AFAS 1 or 2 Initiation Relay actuation Initiation Relay lamps lamps are NOT lit, are illuminated at the PPS Remote THEN GO TO step 7.1 of this Operators Module (B05) on all appendix.

PPS Channels.

___ 5.2 Perform the following for any de-energized PPS-ESFAS Initiation Path(s):

a. Obtain the PPS Initiation Reset key for the affected Train.

b. Unlock the affected Initiation Path Reset Train (PPS Cabinets).

c. Reset the affected Initiation Path by depressing the appropriate Initiation Path Reset pushbutton (PPS Cabinets).

d. Lock the Initiation Path Reset Train (PPS Cabinets).

e. Remove the PPS Initiation Reset key.

f. Check the affected Initiation Signal lamps are illuminated for the affected PPS channels (On status panels above PPS Cabinets).

g. IF the Initiation Path will NOT reset, THEN GO TO step 7.1 of this appendix.

PALO VERDE NUCLEAR GENERATING STATION 40AO-9ZZ17 Revision 15 Page 58 of 89 INADVERTENT PPS-ESFAS ACTUATIONS Appendix B Page 5 of 5 Appendix B, PPS-ESFAS Reset INSTRUCTIONS CONTINGENCY ACTIONS

___6. Check the actuated PPS-ESFAS ___ 6.1 Perform the following for the leg 1-3 and leg 2-4 Actuation affected Train(s):

Signal lamps are illuminated for PPS Train A and Train B a. Press the LOCKOUT RESET Actuation Signals pushbutton(s) for the affected (On status panels above PPS-ESFAS actuation(s)

PPS Cabinet A, SBAC01 and (Aux Relay Cabinets PPS Cabinet B, SBBC01). Bay 6 & 7).

b. Check both red ON lamps are illuminated for the affected PPS-ESFAS actuation (Aux Relay Cabinets Bay 6 & 7).

___7. IF the PPS-ESFAS actuation is ___ 7.1 IF the PPS-ESFAS actuation will reset, NOT reset, THEN GO TO ONE of the THEN perform the following:

following steps of this procedure as appropriate: a. Evaluate the need to override and position

Section 3.0, AFAS, step 10. PPS-ESFAS actuated equipment.

Section 4.0, CIAS, step 9. REFER TO the appropriate

Section 5.0, CSAS, step 20. attachment in Appendix C, PPS-ESFAS Check, for a list

Section 6.0, MSIS, step 13. of actuated equipment.

Section 7.0, RAS, step 9. b. Override and position equipment as needed.

Section 8.0, SIAS OR SIAS/

CIAS, step 16.

End of Appendix

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: 0720010401 Perform manual PB switching operations TASK STANDARD: Offsite power has been paralleled to PBA-S03.

K/A: 3.6-062-A4.07 K/A RATING: RO: 3.1 SRO: 3.1 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40OP-9PB01 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Jordan Johnston Date: 04/18/2008 Revised By: Alan Malley Date: 10/21/2011 Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

This JPM is setup to run with either JS-4 or JS-8. Therefore the ICs are for two different situations. Pay close attention to the setup based on which JPM is running in parallel with this JPM.

A. IC#: If running with JS-8 use IC #112 If running with JS-4 use IC #110 B. SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION None C. SPECIAL INSTRUCTIONS:

None D. REQUIRED CONDITIONS:

Diesels carrying the class buses

One offsite power line now supplying the switchyard and down to NAN-X03 E. SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

F. Copy of 40OP-9PB01 available. This JPM was written using Revision 24 of 40OP-9PB01. This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

G. MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION N/A Page 2 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANT JPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

You are the third RO in Unit 1.

NBN-X03 tripped due to a faulty relay on the supply breaker.

The relay has been repaired.

NBN-X03 is now energized.

INITIATING CUE:

The CRS directs you to parallel offsite power back onto PBA-S03 per section 14 of 40OP-9PB01.

Page 3 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*) denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1. Perform Prerequisites (section If requested cue (as area Examinee determines that all 14.2) operator): prerequisites are complete.

Diesel Generator A is supplying power to PBA-S03, isolated from offsite Breaker PBA-S03L is racked in power. and available for operation.

Power is available from ESF Service Transformer NBN-X03.

Diesel Generator B is NOT paralleled with offsite power.

Breaker PBA-S03L is racked in and available for operation.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 14.3.1 and 14.3.1.1: Examinee determines that DG B is not in override.

IF Diesel Generator A is in the emergency mode, THEN perform the following:

1. Ensure DG B is NOT in override.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3. Step 14.3.1.2: If requested Cue (as area Examinee checks that Neutral operator): overvoltage, Overcurrent, and Ensure ALL of the following Negative Sequential Trip are all alarm conditions are reset at Neutral overvoltage, reset.

DGA-B01: Overcurrent, and Negative

NEUTRAL Sequential Trip are all clear at OVERVOLTAGE the Diesel Generator panel

OVERCURRENT

NEG SEQ TRIP SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 14.3.1.3: Examinee N/As step since there are no alarms.

IF ANY of the alarms are not reset, THEN ensure the alarms are reset per 40AL-9DG01, Diesel Generator A Alarm Responses.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

5. Step 14.3.1.4: When Requested Cue: Examinee obtains CRS permission to override DG A.

Obtain Control Room Supervisor The CRS has given you permission to override the permission to override Diesel emergency mode condition. Generator A.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

6.

Steps 14.3.1.5 and 14.3.1.6: Examinee puts DG A in override.

Take DGA-HS-1 to Start

Check the white OVERRIDE light on.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

7.

Step 14.3.2.1: Examinee places PEA-SS-G01D in the DROOP position.

Ensure PEA-SS-G01D, Diesel Generator A Speed Mode Select switch, is in the DROOP position.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.

Step 14.3.2.2: Examinee places PBA-SS-S03L to ON.

Place PBA-SS-S03L, synchronizing switch for normal supply breaker PBA-S03L, in the ON position.

SAT / UNSAT Comments (required for UNSAT):

Note before step 14.3.2.3 Increasing Diesel Generator speed will cause the synchroscope to move in the slow direction and decreasing Diesel Generator speed will cause the synchroscope to move in the fast direction.

Page 7 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

9.

Step 14.3.2.3: Examinee adjusts DG A speed so the synchroscope is moving Adjust DG A speed using PEA- slowly in the Fast direction.

SC-G01, Diesel Generator A Speed switch, to cause the synchroscope to move slowly in the Fast direction.

SAT / UNSAT Comments (required for UNSAT):

Note before step 14.3.2.4 Running Voltmeter MAN-EI-002R represents PBA-S03 Bus voltage. Incoming voltmeter MAN-EI-002I represents ESF Service Transformer voltage.

STEP CUE STANDARD

10.

Step 14.3.2.4: Examinee matches voltages between DG A and NBN-X03 Match the DG voltage with the (ESF Service Transformer)

ESF Service Transformer voltage output.

using PEA-EC-G01, DG A Examiner Note: The meters for Voltage Switch. this evolution are:

MAN-EI-002R for DG (PBA-S03)

MAN-EI-002I for NBN-X03.

SAT / UNSAT Comments (required for UNSAT):

Caution before Step 14.3.2.5 There is no sync-check protection on the normal supply breaker.

Page 8 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

11.

Step 14.3.2.5: Examinee closes PBA-S03L when the synchroscope is at the WHEN the synchroscope needle 12 oclock position.

is at the 12 oclock position, THEN close PBA-S03L.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

12. Step 14.3.2.6: Examinee places the synch switch in the OFF position.

Place the synchronizing switch in the OFF position.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

13. Step 14.3.2.7: INFORM CUE:

Unit 1 only: If it is desired to The Diesel Generator will be continue to operate DG A, go to shut down by another operator.

40OP-9DG01.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Page 9 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 10 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 11 of 12

S-7 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

You are the third RO in Unit 1.

NBN-X03 tripped due to a faulty relay on the supply breaker.

The relay has been repaired.

NBN-X03 is now energized.

INITIATING CUE:

The CRS directs you to parallel offsite power back onto PBA-S03 per section 14 of 40OP-9PB01.

Page 12 of 12

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 44 of 78 Revision 4.16 kV Class 1E Power (PB) 40OP-9PB01 23 14.0 MANUAL TRANSFER OF PBA-S03 FROM DIESEL GENERATOR A TO NBN-X03 14.1 Personnel Indoctrination 14.1.1 This section of the procedure transfers PBA-S03 from its emergency source of power to its normal source of power.

14.1.2 It should take approximately 10-15 minutes to transfer PBA-S03 from its emergency source of power, the emergency diesel generator, to its normal source of power NBN-X03.

14.2 Prerequisites

____ 14.2.1 Diesel Generator A is supplying power to PBA-S03, isolated from offsite power.

____ 14.2.2 Power is available from ESF Service Transformer NBN-X03.

____ 14.2.3 Diesel Generator B is NOT paralleled with offsite power.

____ 14.2.4 Breaker PBA-S03L is racked in and available for operation.

14.3 Instructions

____ 14.3.1 IF Diesel Generator A is in the emergency mode, THEN perform the following:

____ 1. Ensure Diesel Generator B is NOT in OVERRIDE.

____ 2. Ensure ALL of the following alarm conditions are reset at DGA-B01:

NEUTRAL OVERVOLTAGE

OVERCURRENT

NEG SEQ TRIP

____ 3. IF ANY of the alarms are not reset, THEN ensure the alarms are reset per 40AL-9DG01, Diesel Generator A Alarm Responses.

____ 4. Obtain Control Room Supervisor permission to override the emergency mode condition.

____ 5. Take DGA-HS-1, Diesel Generator A START/STOP switch on B01, to the START position.

____ 6. Check the white OVERRIDE light is illuminated.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 45 of 78 Revision 4.16 kV Class 1E Power (PB) 40OP-9PB01 23 14.3.2 Parallel Diesel Generator A to offsite power as follows:

____ 1. Ensure PEA-SS-G01D, Diesel Generator A Speed Mode Select switch, is in the DROOP position.

____ 2. Place PBA-SS-S03L, synchronizing switch for normal supply breaker PBA-S03L, in the ON position.

NOTE ----------------------------------------

Increasing Diesel Generator speed will cause the synchroscope to move in the slow direction and decreasing Diesel Generator speed will cause the synchroscope to move in the fast direction.

____ 3. Adjust DG A speed using PEA-SC-G01, Diesel Generator A Speed switch, to cause the synchroscope to move slowly in the Fast direction.

NOTE ----------------------------------------

Running Voltmeter MAN-EI-002R represents PBA-S03 Bus voltage. Incoming voltmeter MAN-EI-002I represents ESF Service Transformer voltage.

____ 4. Match the Diesel Generator voltage with ESF Service Transformer voltage using PEA-EC-G01, Diesel Generator A Voltage switch.

CAUTION There is no sync-check protection on the normal supply breaker.

____ 5. WHEN the synchroscope needle is at the 12 oclock position, THEN close PBA-S03L.

____ 6. Place the synchronizing switch in the OFF position.

____ 7. UNIT 1 only IF it is desired to continue to operate Diesel Generator A to prevent possible BOP-ESFAS lockup, THEN GO TO 40OP-9DG01 Emergency Diesel Generator A, section 6.0.

____ 8. IF it is desired to shutdown Diesel Generator A THEN GO TO 40OP-9DG01, Emergency Diesel Generator A, section 7.0 to unload and shutdown Diesel Generator A.

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM BASIS INFORMATION TASK: 1240000401 Implement instructions and contingencies for Lower Mode Recovery procedure TASK STANDARD: LM - Placing Train B CS on SDC K/A: 3.4 005 A4.01 K/A RATING: RO: 3.6 SRO: 3.4 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 15 minutes

REFERENCES:

40EP-9EO10, Standard Appendices, Appendix 240 SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) No PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 11/01/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM

1. SIMULATOR SETUP:

IC#: 112 (This IC is setup to run JS-7 and JS-8 together for the 2012 NRC exam)

Run scenario file: 2012 NRC JS-7 and 8

SCENARIOS, MALFUNCTIONS, OVERRIDES,etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION Run scenario file 2012 NRC JS-7 and 8 from the exam jump drive.

SPECIAL INSTRUCTIONS:

o Hang caution tags on LPSI pump A o Hang supplied equipment status tags on SIA-HV-683 and SIB-HV-692

REQUIRED CONDITIONS:

o None

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: ____________________________ Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40EP-9EO10. This JPM was written using Revision 69 of 40EP-9EO10 (SA-240).

This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION 4 (K-1) Closes SIB-V104 CS B Suction Isolation 7 (K-2) Opens SIB-V185 Shutdown Cooling Return to CS Page 2 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 was on SDC using LPSI pump B.

LPSI pump B has tripped due to an 86 fault.

LPSI Pump A is under clearance.

The unit is in Mode 5 with RCS temperature is ~ 150°F.

RCS pressure is ~ 195 psia.

An AO has been briefed and is standing by in the field to operate components as needed.

CS pump B is not aligned for SDC operations.

INITIATING CUE:

The CRS directs you to place Containment Spray pump B on Shutdown Cooling per Standard Appendix 240.

Page 3 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM JPM START TIME:

STEP CUE STANDARD

1. Step 1 of Appendix 240: Examinee verifies that RCS temperature and pressure are Check ALL of the following:

within limits.

CS Pump B is NOT running to support another success path

RCS temperature is less than 185°F [185°F]

RCS pressure is less than 210 [210 psia]

One SDC Pump Operation

RCS level is 101 ft. 6 in.

or more Two SDC Pump Operation

RCS level is 104 ft. 6 in.

or more SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2. Step 2 of Appendix 240: When Requested Cue: Examinee informs RP that CS pump B will be used for SDC Inform Radiation Protection and RP and the effluent tech flow.

RMS Technician that Train B acknowledge that CS pump B SDC is being placed in service. will be used for SDC flow.

SAT / UNSAT Comments (required for UNSAT):

Page 5 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

3. Step 3 of Appendix 240: Examinee verifies that the support systems are running.

Check that ALL of the following support systems are in-service:

SP B

EW B

EC B SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4. Step 4 of Appendix 240: Examinee verifies CS pump B not running and directs an AO to IF CS Pump B is NOT aligned close SIB-104 for standby SDC, THEN perform the following:

Inform CUE:

a. Direct an operator to close Direct the driver to activate SIB-V104, CS B Key-1, wait 30 seconds then SUCTION ISOLATION. report as AO that SIB-104 (CS (CS B Room) pump B Suction Isolation) is CLOSED.

(continued)

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

5.

Step 4.b of Appendix 240: If Requested Cue: Examinee closes:

Close ALL of the following a. SIB-HV-692 is verified

SIB-UV-665 valves: closed and de-energized.

SIB-HV-658

SIB-HV-692, LPSI Pump

SIB-HV-693 B Suction From RWT b. SIB-UV-671 is verified

SIB-UV-668, LPSI Pump closed and de-energized.

SIB-HV-615 B Recirc Valve

SIB-HV-625

SIB-UV-665, Cntmt Spray Pump B Recirc

SIB-HV-658, SDCHX B Outlet to Reactor Coolant Loops 2A/2B

SIB-UV-671, Cntmt Spray B Discharge to Spray Header

SIB-HV-693, Cntmt Spray SDC Hx B Bypass

SIB-HV-695, LPSI Containment Spray from SDC Hx B Crosstie

SIB-UV-615, LPSI B Injection Valve

SIB-UV-625, LPSI B Injection Valve (continued)

SAT / UNSAT Comments (required for UNSAT):

Page 7 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

6.

Step 4.c of Appendix 240: Examinee OPENS:

Open ALL of the following

SIB-HV-690 valves:

SIB-HV-689

SIB-UV-652, Loop 2 to All other valves are verified SDC/LPSI Pump B OPEN.

Suction Valve

SID-UV-654, Loop 2 to SDC LPSI Pump B Suction Valve

SIB-UV-656, Loop 2 to SDC LPSI Pump B Suction Valve

SIB-HV-690, SDC Loop B Warm-up Bypass Valve

SIB-HV-689, Cntmt Spray Pump B Discharge to SDCHX B Valve

SIB-HV-679, CS Pump B Discharge to SDCHX B

SIB-HV-694, LPSI/CS to SDCHX B Cross-tie Vlv

SIB-HV-696, SDCHX B Outlet to Reactor Coolant Loops 2A/2B Valve (continued)

SAT / UNSAT Comments (required for UNSAT):

Page 8 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

7.

Step 4.d of Appendix 240: Examinee throttles SIB-HV-307 to ~ 20% open.

Throttle SIB-HV-307, LPSI to SDCHX B Bypass Valve, to 20%

open.

(continued)

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

8.

Step 4.e of Appendix 240: Inform CUE: Examinee directs AO to open SIB-V185.

Direct an operator to open SIB- Direct the driver to activate V185, SHUTDOWN COOLING Key-2, wait 30 seconds then RETURN TO CS(CS B report as AO that SIB-V185 Room) (SHUTDOWN COOLING RETURN TO CS) is OPEN.

Check SIB-V185,SHUTDOWN COOLING RETURN TO CS is The operator has checked the open using local valve stem local valve stem position and it position indication. indicates SIB-V185 is open.

SAT / UNSAT Comments (required for UNSAT):

Page 9 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

9.

Step 5 of Appendix 240: Examinee starts CS pump B using SIB-HS-6.

WHEN SIB-V185, SHUTDOWN COOLING RETURN TO CS is open, THEN start CS Pump B.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

10. Step 6 of Appendix 240: Examinee verifies CS pump current is less than 95 amps.

Check CS Pump running current is less than 95 amps.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

11. Step 7 of Appendix 240: Examinee NAs this step since the plant is NOT in Mode 4.

IF the plant is in Mode 4, THEN throttle open SIB-HV-307 to establish a SDC flow of 4000 -

4750 gpm.

SAT / UNSAT Comments (required for UNSAT):

Page 10 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

12. Step 8 of Appendix 240: Examinee verifies that flow is between 3780 and 4750 gpm on IF the plant is in Mode 5 or 6, SIB-FI-307 (B02).

THEN throttle open SIB-HV-307 to establish ONE of the following:

One SDC Pump with RCS Lvl 101 ft. 6 in. - 102 ft.

3780 - 4000 gpm One SDC Pump with RCS Lvl 102 ft. - 103 ft. 1 in.

3780 - 4600 gpm One SDC Pump with RCS Lvl greater than 103 ft. 1 in.

3780 - 4750 gpm Two SDC Pumps with RCS Lvl greater than 104 ft. 6 in.

3780 - 4750 gpm per loop SAT / UNSAT Comments (required for UNSAT):

Page 11 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM STEP CUE STANDARD

13.

Step 9 of Appendix 240: Examinee establishes and maintains a SDC flow of 3780 -

Perform the following to establish 4750 gpm as indicated on SIB-FI-SDC flow: 307.

a. Adjust SIB-HV-307 as necessary to maintain the desired SDC flow.

b. Throttle open SIB-UV-615 to between 5- 15%.

c. Throttle closed SIB-HV-690

d. Maintain the SDC Heat Exchanger heatup rate to19°F/min or less.

SIB-TT-352X onSIB- Examiner Note:

TR-352

ERFDADS point Once the examinee has SIT352X established flow thru SIB-UV-615 and has commenced throttling SIB-HV-690 closed, then inform the examinee that another operator will complete Standard Appendix 240.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 12 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 11/01/11 6 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 13 of 14

S-8 PVNGS JOB PERFORMANCE MEASURE 2012 NRC EXAM EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 was on SDC using LPSI pump B.

LPSI pump B has tripped due to an 86 fault.

LPSI Pump A is under clearance.

The unit is in Mode 5 with RCS temperature is ~ 150°F.

RCS pressure is ~ 195 psia.

An AO has been briefed and is standing by in the field to operate components as needed.

CS pump B is not aligned for SDC operations.

INITIATING CUE:

The CRS directs you to place Containment Spray pump B on Shutdown Cooling per Standard Appendix 240.

Page 14 of 14

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1200 of 1350 STANDARD APPENDICES Appendix 240 Page 1 of 9 Appendix 240, LM - Placing Train B CS on SDC INSTRUCTIONS CONTINGENCY ACTIONS

____ 1. Check ALL of the following: ____ 1.1 IF ANY of the following conditions exist:

CS Pump B is NOT running to support another success path

CS Pump is running in support of another success

RCS temperature is less than path 185°F [185°F]

RCS temperature is 185°F

RCS pressure is less than 210 [185°F] or more

[210 psia]

RCS pressure 210 psia or One SDC Pump Operation more

RCS level is 101 ft. 6 in. or

RCS level is NOT appropriate more for the number of SDC Pumps that will be running Two SDC Pump Operation THEN inform the CRS to use

RCS level is 104 ft. 6 in. or another heat removal method.

more

____ 2. Inform Radiation Protection and RMS Technician that Train B SDC is being placed in service.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1201 of 1350 STANDARD APPENDICES Appendix 240 Page 2 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 3. Check that ALL of the following ____ 3.1 IF any of the support systems are support systems are inservice: NOT inservice, AND are available to support

SP B Train B SDC, THEN place the appropriate

EW B support system in service.

EC B

____ 3.2 IF EW B is NOT available, THEN ensure that NC is cross tied to EW B for the SDC Hx that will be placed in service, REFER TO Appendix 244, LM - NC Cross Tie to EW Train B.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1202 of 1350 STANDARD APPENDICES Appendix 240 Page 3 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 4. IF CS Pump B is NOT aligned for standby SDC, THEN perform the following:

a. Direct an operator to close SIB-V104, CS B SUCTION ISOLATION. (CS B Room)

b. Close ALL of the following valves:

SIB-HV-692, LPSI Pump B Suction From RWT Valve

SIB-UV-668, LPSI Pump B Recirc Valve

SIB-UV-665, Containment Spray Pump B Recirc Valve

SIB-HV-658, SDCHX B Outlet to Reactor Coolant Loops 2A/2B Valve

SIB-UV-671, Containment Spray B Discharge to Spray Header

SIB-HV-693, Containment Spray SDC Hx B Bypass Valve

SIB-HV-695, LPSI Containment Spray from SDC Hx B Crosstie Valve

SIB-UV-615, LPSI B Injection Valve

SIB-UV-625, LPSI B Injection Valve (continue)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1203 of 1350 STANDARD APPENDICES Appendix 240 Page 4 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 4. (continued)

c. Open ALL of the following valves:

SIB-UV-652, Loop 2 to SDC/

LPSI Pump B Suction Valve

SID-UV-654, Loop 2 to SDC LPSI Pump B Suction Valve

SIB-UV-656, Loop 2 to SDC LPSI Pump B Suction Valve

SIB-HV-690, SDC Loop B Warm-up Bypass Valve

SIB-HV-689, Containment Spray Pump B Discharge to SDCHX B Valve

SIB-HV-679, CS Pump B Discharge to SDCHX B

SIB-HV-694, LPSI/CS to SDCHX B Cross-tie Valve

SIB-HV-696, SDCHX B Outlet to Reactor Coolant Loops 2A/2B Valve

d. Throttle SIB-HV-307, LPSI to SDCHX B Bypass Valve, to 20% open.

(continue)

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1204 of 1350 STANDARD APPENDICES Appendix 240 Page 5 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 4. (Continued)

e. Direct an operator to perform BOTH of the following:

1) Open SIB-V185, SHUTDOWN COOLING RETURN TO CS (CS B Room)

2) Check SIB-V185, SHUTDOWN COOLING RETURN TO CS is open using local valve stem position indication.

____ 5. WHEN SIB-V185, SHUTDOWN COOLING RETURN TO CS is open, THEN start CS Pump B.

____ 6. Check CS Pump running current ____ 6.1 Reduce SDC flow until CS Pump is less than 95 amps. running current is less than 95 amps without allowing SDC flow to fall below ANY of the following:

Mode 4 - 4000 gpm

Mode 5 - 3780 gpm

Mode 6 - 3780 gpm

____ 6.2 IF CS Pump current can NOT be reduced below 95 amps, THEN inform the CRS to consider another method of heat removal.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1205 of 1350 STANDARD APPENDICES Appendix 240 Page 6 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 7. IF the plant is in Mode 4, THEN throttle open SIB-HV-307 to establish a SDC flow of 4000 - 4750 gpm.

____ 8. IF the plant is in Mode 5 or 6, THEN throttle open SIB-HV-307 to establish ONE of the following:

One SDC Pump with RCS Lvl 101 ft. 6 in. - 102 ft.

3780 - 4000 gpm One SDC Pump with RCS Lvl 102 ft. - 103 ft. 1 in.

3780 - 4600 gpm One SDC Pump with RCS Lvl greater than 103 ft. 1 in.

3780 - 4750 gpm Two SDC Pumps with RCS Lvl greater than 104 ft. 6 in.

3780 - 4750 gpm per loop

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1206 of 1350 STANDARD APPENDICES Appendix 240 Page 7 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 9. Perform the following to establish SDC flow:

a. Adjust SIB-HV-307 to maintain SDC flow.

b. Throttle open SIB-UV-615 to b.1 IF SIB-UV-615 is between 5-15%. unavailable, THEN throttle open SIB-UV-635 to 5-15%.

c. Throttle closed SIB-HV-690

d. Maintain the SDC Heat d.1 IF at any time the SDC Exchanger heatup rate to Heat Exchanger heatup 19°F/min or less. rate exceeds 19°F/min, THEN reduce the flow

SIB-TT-352X on through the SDC Heat SIB-TR-352 Exchanger.

ERFDADS point SIT352X

e. WHEN the SDC Heat Exchanger heatup rate has stabilized, THEN throttle open SIB-UV-625 to between 5-15%.

f. Adjust SIB-HV-658 as necessary to control RCS temperature.

____ 10. Maintain the RCS cooldown rate for the current plant conditions.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1207 of 1350 STANDARD APPENDICES Appendix 240 Page 8 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 11. Perform the following to close SIB-HV-690:

a. Throttle the following valves incrementally to compensate for the closure of SIB-HV-690:

SIB-UV-615

SIB-UV-625

b. Throttle close SIB-HV-690.

c. WHEN SIB-HV-690 is closed, THEN perform the following:

1) Hold SIB-HS-690 in the closed position for five seconds.

2) Direct a second operator to hold SIB-HS-690 closed for an additional five seconds.

____ 12. Perform the following to fully open the LPSI Injection Valves:

a. Throttle the following valves incrementally to maintain the desired SDC flow while fully opening the LPSI Injection Valves:

SIB-HV-307

SIB-HV-658

b. Throttle open the LPSI Injection Valves.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO10 Revision: 69 Page 1208 of 1350 STANDARD APPENDICES Appendix 240 Page 9 of 9 INSTRUCTIONS CONTINGENCY ACTIONS

____ 13. Adjust BOTH of the following valves to control RCS temperature and SDC flow rate:

SIB-HV-658

SIB-HV-306

____ 14. IF the RWLIS is in service, THEN perform the following:

a. IF SDC Loop B is the only SDC loop in service, THEN place the Refueling Water Level Flow Compensation Selector in the CHANNEL B position.

b. IF both SDC loops are in service, THEN place the Refueling Water Level Flow Compensation Selector in the BOTH position.

c. Place the Refueling Water Level Alarm Enable Selector in the BOTH position.

____ 15. Inform the CRS that CS Pump B is on SDC.

End of Appendix

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM BASIS INFORMATION TASK: Verify proper CIAS/CSAS actuation TASK STANDARD: 1240060201 - Ensure that a CIAS/CSAS has actuated and that an isolation valve has closed for each required penetration.

K/A: 3.7 012 A4.02 K/A RATING: RO: 3.3 SRO: 3.4 K/A: K/A RATING: RO: SRO:

APPLICABLE POSITION(S): RO VALIDATION TIME: 10 minutes

REFERENCES:

40EP9EO05, Excessive Steam Demand SUGGESTED TESTING ENVIRONMENT: SIMULATOR X PLANT OTHER JPM TYPE Time Critical? (Yes/No) No Alternative Path? (Yes/No) Yes PRA/SRA related? (Yes/No) No APPROVAL Developed By: Larry Burton Date: 10/27/2011 Revised By: N/A Date:

Technical Review Operations Approval EP Review N/A Training Approval (Only required for Emergency Plan JPMs)

EVALUATION Examinee Name: Date:

Evaluator Name:

Time to complete: Minutes GRADE (Circle One) SAT / UNSAT *

For E-Plan JPMs, a grade of UNSAT requires a PVAR to be written, remediation, and re-evaluation.

PVAR # _____________

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to the Emergency Preparedness organization for resolution.

Page 1 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam

1. SIMULATOR SETUP:

IC#: 111

SCENARIOS, MALFUNCTIONS, OVERRIDES, etc. for Setup:

COMMAND/COMMUNICATION DESCRIPTION cm MVSW03WCBUV61_5 WC-UV-61 fail to auto close cm MVSW03WCAUV62_5 WC-UV-62 fail to auto close Scenario file -- no CSAS Prevents CSAS actuation Scenario file -- no SICI Prevents CIAS and SIAS actuation mf MS01A f:10 SG 1 ESD -10%

SPECIAL INSTRUCTIONS:

o None

REQUIRED CONDITIONS:

o Stop RCPs 1B and 2B.

o Align AFB flow to SG 2.

o Wait for sequencer to finish starting equipment.

SIMULATOR EVALUATION PRE-CHECK Correct IC Alarm Silence Off Procedures available, page checked, and clean For JPMs administered during transients, another instructor available to control plant parameters.

Verified by: N/A Date: ____________________

(NA if Simulator setup not required)

2. SPECIAL TOOLS/EQUIPMENT:

40EP-9EO05 available. This JPM was written using Revision 25 of 40EP-9EO05.

This JPM may be used with later revisions if it is verified that the later revision does not affect this JPM.

3. JPM PERFORMANCE:

MALFUNCTIONS, OVERRIDES, etc. during JPM STEP COMMAND/COMMUNICATION DESCRIPTION Page 2 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam TASK CONDITIONS INFORMATION PRESENTED TO EXAMINEE:

SPECIAL CONSIDERATIONS:

IN-PLANTJPMs ONLY:

o Operation of in-plant equipment is to be SIMULATED ONLY, DO NOT OPERATE any equipment.

o Inform the control room staff of any discovered deficiencies.

o Comply with the REP, if it is not possible to enter an area it may be permissible to discuss the equipment to be operated. Do NOT enter contaminated, airborne, or high radiation areas.

ALL JPMs:

o You may use any source of information normally available.

INITIAL CONDITIONS:

Unit 1 automatically tripped due to an ESD on SG 1.

SPTAs have been completed.

The CRS has implemented 40EP-9EO05, Excess Stream Demand.

INITIATING CUE:

The CRS has directed you to verify plant conditions starting with step 23 of 40EP-9EO05, Excess Steam Demand.

Page 3 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam INFORMATION FOR EVALUATOR'S USE:

o An asterisk (*)denotes a Critical Step o At the discretion of the Examiner/Evaluator, this JPM may be terminated when the Task Standard is met or adequate time has been allowed to complete the JPM. It shall be terminated when the Examinee has verbalized completion of the JPM.

o Any step marked UNSAT requires comments.

o If this is the first JPM of the set then ensure the examinee has been briefed.

o Step sequence is not critical unless noted or will prevent achieving the task standard.

o Notify the unit Shift Manager of in-plant JPM performance.

o Performance of this JPM may require entry into areas with alarmed doors. Security requirements must be observed.

o Locked valves may be involved. No attempt will be made to actually operate any valves.

Page 4 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam JPM START TIME:

STEP CUE STANDARD

1.

Step 23 of 40EP-9EO05 If Requested Cue: Examinee determines that Containment pressure is > 3 psig IF containment pressure is The CRS concurs with manual and manually actuates CIAS.

3 psig or more, THEN check CIAS actuation CIAS is actuated.

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

2.

Step 24 of 40EP-9EO05 If Requested Cue: Examinee checks SESS panels (B02) after CIAS actuation and IF CIAS has actuated, The CRS concurs with closing determines that the Chill Water THEN check that an isolation WCB-UV-61 and WCA-UV-62. (WC) return header has not valve is closed for each properly isolated and closes containment penetration required Examiner Note: Closing either WCB-UV-62 and WCA-UV-61.

to be closed. valve will meet containment closure criteria. Valves will stroke closed once they have been taken to close and picked up the Over-ride light SAT / UNSAT Comments (required for UNSAT):

Page 5 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3. Step 25 of 40EP-9EO05 Examinee leaves the CS pumps running because containment IF the following conditions exist: pressure is > 8.5 psig.

The Containment Spray Pump(s) are operating on the miniflow(s)

Containment pressure is not expected to exceed 8.5 psig within one hour of the CS Pump start THEN stop the Containment Spray Pump(s).

SAT / UNSAT Comments (required for UNSAT):

STEP CUE STANDARD

4.

Step 26 of 40EP-9EO05 If Requested Cue: Examinee determines that Containment pressure is > 8.5 IF containment pressure is The CRS concurs with manual psig and manually actuates 8.5 psig or more, CSAS actuation CSAS.

THEN check CSAS is actuated.

SAT / UNSAT Comments (required for UNSAT):

Page 6 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam STEP CUE STANDARD

3.

Step 27 of 40EP-9EO05 Examinee performs the following:

IF CSAS has actuated, THEN perform the following:

a. Ensure at least one a. Verifies that both CS Containment Spray header flows are > 4350 header flow is greater gpm.

than 4350 gpm.

b. Ensure all RCPs are off. b. Stops RCPs 1A and 2A.

c. Ensure RCP controlled bleedoff flow is isolated.

d. PERFORM Appendix 19, c. Isolates controlled Containment Hydrogen bleedoff by closing (B03)

Control to align the Hydrogen recombiners. o RCN-HS-430 Inform Cue: After the o RCN-HS-431 examinee closes the BO valves : o RCN-HS-432 o RCN-HS-433 Another operator will perform the remaining steps.

SAT / UNSAT Comments (required for UNSAT):

JPM STOP TIME:

NOTE:

Problems/issues identified on E-Plan JPMs during performance will be documented with a formal post-critique using Form 0800 (Electronic Forms under Emergency Preparedness) and forwarded to Emergency Preparedness organization for resolution.

NORMAL TERMINATION POINT Page 7 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam RECORD OF REVISIONS REVISION REVISION REASON COMMENTS NUMBER DATE REVISED 000 10/27/2011 New JPM REASON REVISED Enter the numbers corresponding to the reason revised in the Reason Revised column and brief description of changes in Comments Column. Comments are to be numbered consecutively in each revision.

1. Vendor reference document upgrade

2. Plant modification (include number)

3. Procedure upgrade

4. Internal or External Agency Commitment (indicate item number)

5. Technical Specification Change (indicate amendment number)

6. Other (explain in comments)

Page 8 of 9

S-9 PVNGS JOB PERFORMANCE MEASURE 2012 NRC Exam EXAMINEE HANDOUT INITIAL CONDITIONS:

Unit 1 automatically tripped due to an ESD on SG 1.

SPTAs have been completed.

The CRS has implemented 40EP-9EO05, Excess Stream Demand.

INITIATING CUE:

The CRS has directed you to verify plant conditions starting with step 23 of 40EP-9EO05, Excess Steam Demand.

Page 9 of 9

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO05 Revision 25 Page 14 of 45 EXCESS STEAM DEMAND INSTRUCTIONS CONTINGENCY ACTIONS

22. IF the break is inside Containment, THEN place the Hydrogen Analyzers in service.

23. IF containment pressure is 23.1 Manually actuate CIAS.

3 psig or more, THEN check CIAS is actuated.

CAUTION High radiation levels may result in personnel exposure when attempting local manual valve operation.

24. IF CIAS has actuated, 24.1 Ensure that an isolation valve is closed THEN check that an isolation valve is for each containment penetration closed for each containment required to be closed.

penetration required to be closed.

25. IF the following conditions exist:

The Containment Spray Pump(s) are operating on the miniflow(s)

Containment pressure is not expected to exceed 8.5 psig within one hour of the CS Pump start THEN stop the Containment Spray Pump(s).

26. IF containment pressure is 26.1 Manually actuate CSAS.

8.5 psig or more, THEN check CSAS is actuated.

PALO VERDE NUCLEAR GENERATING STATION 40EP-9EO05 Revision 25 Page 15 of 45 EXCESS STEAM DEMAND INSTRUCTIONS CONTINGENCY ACTIONS

27. IF CSAS has actuated, THEN perform the following:

a. Ensure at least one Containment Spray header flow is greater than 4350 gpm.

b. Ensure all RCPs are off.

c. Ensure RCP controlled bleedoff flow is isolated.

d. PERFORM Appendix 19, Containment Hydrogen Control to align the Hydrogen recombiners.

28. IF SIAS has actuated, THEN perform the following:

a. Energize SIAS Load Shed Panels.

REFER TO Appendix 21, List of SIAS Load Shed Panels.

b. PERFORM Appendix 17, Restoration of Containment Cooling.

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). Auxiliary Feedwater Pump A and Containment Spray A are tagged out.

Event Malf. No. Event Type* Event Description No.

1 None N Shift Turbine Cooling water pumps.

CO/SRO 2 cmTRCV05CHNLT227_4 C Volume Control Tank level transmitter, CHN-LT-227 fails low RO/SRO causing a boration. Crew takes action to return CCP suction to the Volume Control Tank.

3 mfRM01A I Control Room monitor, RU-29, fails high. Crew will bypass CREFAS A.

CO/SRO 4 cmCPCC06EWAP01_5 C Essential Cooling water pump A fails to auto start on CREFAS actuation. RO will start EW pump A.

(In setup) RO/SRO (TS) 5 mfTH06A f:0.02 C Steam Generator 1 Tube Leak ALL 40AO-9ZZ02, Excessive RCS Leakrate (TS) 6 mfED16C C Loss of Class DC power PKC-M43.

CO/SRO 40AO-9ZZ13, Loss of Class Instrument or Control Power (T/S) 7 mfTH06A f:50 M Steam Generator 1 Tube Leak degrades to a Rupture.

ALL 40EP-9EO04, Steam Generator Tube Rupture 8 cmCPSI01SIAP02_5 C HPSI pump A fails to auto start on SIAS/CIAS actuation (In setup) RO/SRO 9 mfRX01 f:0 I Tave fails low, Requires manual control of Main Feedwater CO/SRO flow.

CRITICAL TASK - Reset MSIS during cooldown to prevent unmonitored release to public.

End Faulted SG is isolated per Faulted SG is isolated point Standard Appendix 113, SG 1 Isolation CRITICAL TASK -Isolate faulted SG within 70 minutes of initiation of SGTR.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 1

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 2 Revision 1

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Vibration shop reported that in a review of data they found some unusual readings with Turbine Cooling Water pump A. A vibration technician and AO are have been briefed and are standing by for a TCW pump shift. Appendix D of 40OP-9TC01 has been completed.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing.

CS A is tagged out for scheduled maintenance.

Planned shift activities:

Remove the B Turbine Cooling Water pump from service.

Revision 1

2012 NRC EXAM Scenario 1 Setup Instructions

1. _____ Reset to IC-20

2. _____ Run scenario 2012 NRC Scenario 1 under Scenario scenario files from NRC exam thumb drive

3. _____ Stage radios for operators

4. _____ Alarm Silence to OFF

5. _____ Ensure CVCS and DFWCS alarms are reset

6. _____ Place the simulator in freeze until the crew enters the simulator.

7. _____ Hang Train B protected sign.

8. _____Hang Protected Equipment plaques near the handswitches for AF B and AF N.

9. _____Hang Protected Equipment plaques near the handswitch for CS B.

10. _____ Verify RCS leakrate has stabilized at ~ 0 gpm.

11. _____ Review procedures listed on the next page for marks and missing pages:

Page 1 of 7 Rev 2

2012 NRC EXAM Scenario 1 Procedures to check:

74RM-9EF41, RMS Alarm Response 40OP-9TC01, Turbine Cooling Water, (RU-29, RU-4, RU-7, RU-141 and RU- (Section 4.3) 142) 41AL-1RK5A (Windows 4A, 4B, 4C) 41AL-1ES2A (Window 2D - SEAS 18L -

pages 3 and 248-251) 40AL-9RK3A (Windows 8A, 9A and 8B) 40AO-9ZZ02, Excessive RCS Leakrate (Section 5.0) 40AO-9ZZ13, Loss of Class Instrument or 41AL-1RK2A (Windows 1A and 7A)

Control Power (Section 7.0 and 8.0) 40OP-9CH01, CVCS Normal Operations 41AL-1RK1A (Windows 5A and 5B)

(Section 4.4) (possible) 40EP-9EO01, Standard Post Trip Actions 40EP-9EO04, Steam Generator Tube Rupture 40EP-9EO10, Standard Appendices Tech Specs (3.03, 3.7.7.a and 3.4.14.b)

(Appendices 5, 10, 16, 103 and 113)

Copy of 72ST-9RX03, 40ST-9EC03, Essential Chilled Water &

DNBR/LHR/AZTILT/ASI with COLSS Ventilation Systems Inoperable Action Out of Service available Surveillance (available)

Page 2 of 7 Rev 2

2012 NRC EXAM Scenario 1 Driver Station Menu should look like this:

SCENARIOS TRIGGERS MALFS COMP REMOTES COMP I/O ALARM MALFS REMOTES OVERRIDES OVRDS 0 1 4:0 4:2 3 8 0:0

0:0

If MSIV bypasses are under clearance this will read 2:2 Complete list of malfunctions.

Triggers rpschd Reactor Trip breaker D open Malfs mfED16C k:6 PKC-M43 LOSS OF PWR CLSS 125VDC BUS mfRM01A k:3 RU-29 RADIATION MONITOR OUTPUT HIGH mfRX01 f:0 e:RPSCHC RRS T-AVE FAILURE - LOW mfTH06A k:5 f:0.02 S/G 1 STEAM GENERATOR TUBE RUPTURE Comp Malfs cmAVWD07SCNPV4A_2 POSITIONER CLOSE FAILURE: BLOWDOWN FLASH TK TO HTR k:40 DRN TK 4A cmCPCC06EWAP01_5 FAIL TO AUTO-START: ESSENTIAL COOLING WATER PUMP A cmCPSI01SIAP02_5 FAIL TO AUTO-START: HP SAFETY INJECTION PUMP A cmTRCV05CHNLT227_4 k:2 TRANSMITTER FAILURE BELOW BAD VALUE: VOLUME CONTROL TANK Remotes rfCV24 k:34 f:CLOSE OPR "C" CHG PMP SUCT VLV rfCV25 k:32 f:OPEN OPR "A" CHG PMP ALT SUCT VLV rfCV26 k:33 f:OPEN OPR "B" CHG PMP ALT SUCT VLV rfCV27 k:34 f:OPEN OPR "C" CHG PMP ALT SUCT VLV rfCV28 k:31 f:OPEN OPR RWT CHG PMP ALT SUCT VLV rfCV35 k:33 f:CLOSE OPR "B" CHG PMP SUCT VLV rfCV36 k:32 f:CLOSE OPR "A" CHG PMP SUCT VLV rfFW57 f:CLOSE OPR AUX FPT MAIN STM SPLY VLV rfFW59 f:TRIP MAN ACT OVSP TRIP OF AFA-P01 rfFW60B f:OFF CONTROL POWER TO AFA-HV54 Continued on next page Page 3 of 7 Rev 2

2012 NRC EXAM Scenario 1 rfTP20 k:11 f:CLOSE TC PMP A DISCH crB2RH02SIAP03_2 RACK IN/OUT: CONTAINMENT SPRAY PUMP A f:RACK_OUT crB4CV05CHNUV501_1 k:22 BKR OPEN/CLOSE: CVCS VOLUME CONTROL TANK OUTLET f:OPEN VALVE crB4CV08CHEHV536_1 k:21 BKR OPEN/CLOSE: CVCS RWT GRAVITY FEED LINE TO CHARGING f:OPEN crB4CV08CHNUV514_1 k:23 BKR OPEN/CLOSE: CVCS BORIC ACID MAKEUP TO REGEN HEAT f:OPEN EXCH. VALVE crB4FW08AFAHV32_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4FW08AFAUV37_1 BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE f:OPEN crB4MS13SGAUV134_1 BKR OPEN/CLOSE: SG 1 TO AUX FWP A STM SUPPLY VLV f:OPEN crB4MS13SGAUV138_1 BKR OPEN/CLOSE: SG 2 TO AUX FWP A STM SUPPLY VLV f:OPEN crB4RH02SIAUV664_1 BKR OPEN/CLOSE: CTMT SPRAY PUMPS TO RWT ISO VALVE f:OPEN crB5FW08AFCHV33_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-2 f:OPEN crB5FW08AFCUV36_1 BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE f:OPEN Page 4 of 7 Rev 2

2012 NRC EXAM Scenario 1 Drivers Page EVENT TIME SYNTAX DESCRIPTION MISC.

1 When directed by When directed to close TCN-V531, "B" TC Pump control room to close TCN-P01B Casing Vent Header Isolation Valve wait 1 TCN-V531 minute and report TCN-V531 is closed (not modeled).

When directed by Wait 2 minutes then insert KEY 11 Closes TCN-HCV-25 (A After valve is closed, report TCN-HCV-25, TC Pump A control room to close rfTP20 f:CLOSE TC pump discharge valve) discharge valve is closed.

TCN-HCV-25 (A TC pump discharge valve)

When directed by Mrf TP20 f:OPEN Opens TCN-HCV-25 (A After valve is open, report TCN-HCV-25, TC Pump A control room to open TC pump discharge valve) discharge valve is open.

TCN-HCV-25 (A When directed report no rotation of TC pump A and that TC pump discharge the casing vent valve TCN-528 is OPEN.

valve)

When directed by When directed to open TCN-V528, "B" TC Pump TCN-control room to open P01B Casing Vent Header Isolation Valve wait 1 TCN-V528 minute and report TCN-V528 is open (not modeled).

2 When directed by the KEY 2 Fails VCT level transmitter lead evaluator. cmTRCV05CHNLT227_4 k:2 CHN-LT-227 low When directed by the When directed to open the breaker for CHE- Opens breaker form CHE- Wait 2 minutes (unless sent early) then report that you control room to open HV-536 (NHN-M7209) insert KEY 21 HV-536 are standing by at NHN-M72.

breakers crB4CV08CHEHV536_1 f:Open Report breakers open as operated.

When directed to open the breaker for CHN- Opens breaker form CHN-UV-501 (NHN-M7208) insert KEY 22 UV-501 crB4CV08CHEHV501_1 f:Open When directed to open the breaker for CHN- Opens breaker form CHN-UV-514 (NHN-M1528) insert KEY 23 UV-514 crB4CV08CHEHV514_1 f:Open Continued on next page Page 5 of 7 Rev 2

2012 NRC EXAM Scenario 1 Drivers Page 3 When directed by the KEY 3 Fails RU-29 high When called as Effluent Tech, report that it appears RU-lead evaluator. mfRM01A 29 failed high due to sudden increase in the output and request the control room bypass RU-29.

4 (In Setup) EW A pump fails to auto In sent as area operator to inspect the breaker (PBA-cmCPCC06EWAP01A_5 start S03M) for EWA-P01, wait 3 minutes and report that you see nothing abnormal.

5 When directed by the Key 5 SG Tube leak (~1 gpm) When called as Chemistry about sampling, report you lead evaluator. mfTH06A f:0.02 are not sampling the primary at this time.

If called as RP acknowledge a leak in SG 1 When directed as Aux Operator to close CDN-V099, Condensate Service Hdr Isolation wait 2 minutes then report valve closed.

If directed to close Wait 3 minutes then insert Key 40 Simulates closing SCN-V11 SCN-V11 and V12 cmAVWD07SCNPV4A_2 and V12 If directed to close None Wait three minutes and report CDN-V099 closed.

CDN-V099 6 When directed by the KEY 6 Loss of PKC-M43 If called as the Area Operator to inspect PKC-M43, lead evaluator. mfED16C report that the C Battery breaker is open and the C Charger AC battery is tripped. Request electrical assistance.

7 When directed by the MMF TH06A f:50 SG Tube leak degrades lead evaluator.

8 (In Setup) HPSI A fails to auto start cmCPSI01SIAP02_5 Continued on next page Page 6 of 7 Rev 2

2012 NRC EXAM Scenario 1 Drivers Page 9 (In Setup) Tave fails low mfRX01 f:0 e:RPSCHC If directed align Insert KEY 31 Opens CHB-V327 (key 31) charging pump rfCV28 k:31 f:OPEN (This valve must be open suction to the RWT or you will cause a per Standard charging pump to trip).

Appendix 10 Then for Charging Pump A Aligns Charging Pump A Insert KEY 32 to the RWT by closing rfCV25 k:32 f:OPEN CHA-V316 and opening rfCV36 k:32 f:CLOSE CHA-V755. (Key 32)

Then for Charging Pump B Aligns Charging Pump B Insert KEY 33 to the RWT by opening rfCV26 k:33 f:OPEN CHA-V756 and closing CHA-V319 (Key 33) rfCV35 k:33 f:CLOSE Then for Charging Pump E Aligns Charging Pump E Insert KEY 34 to the RWT by opening rfCV27 k:34 f:OPEN CHA-V757 and closing rfCV24 k:34 f:CLOSE CHA-V322 (Key 34).

Page 7 of 7 Rev 2

Scenario 2 Overview Event 1 CO shift Turbine Cooling Water Pumps from A running to B running.

Event 2 Low failure of the Volume Control Tank level transmitter CHN-LT-227. This causes the charging pump suction to automatically shift from the Volume Control Tank to the Refueling Water Tank (resulting in boration of the RCS). The operator is directed by the alarm response to hold open the VCT outlet valve and hold closed the valve from the Refueling Water Tank while an auxiliary operator opens the breakers to the valves.

The crew may also reduce turbine load depending on how long the boration goes before the valves are repositioned.

Event 3 RU-29 (Control Room intake ventilation radiation monitor) fails high causing a Control Room Essential Filtration Actuation Signal (CREFAS). The crew should determine the rad monitor has failed high (confirmed by the Effluent Technician) and bypass RU-29 on the BOP-ESFAS panel behind the control boards.

Event 4 EW A pump fails to auto start on the previous CREFAS signal. The CRS should address Tech Specs and declare EW A inoperable as well as various other cascading Tech Specs.

Event 5 Steam Generator #1 Tube leak. The CRS should respond by entering Abnormal operating procedure 40AO-9ZZ02 and addressing Tech Specs. The crew should address charging pumps and letdown. The RO will perform a leakrate determination and the CO will minimize the release to environment.

Event 6 Loss of PKC-M43 (125 VDC Motor Control Center). The CRS should respond by entering Abnormal operating procedure 40AO-9ZZ13. The CO should place CEDMCS in standby and place CEAC 2 inop codes in the Core Protection Calculators.

Event 7 SG Tube leak degrades. The CRS should direct starting all available charging pumps, isolating letdown and tripping the reactor since pressurizer level continues to decrease.

The crew performs the Standard Post Trip Actions. After the SPTAs are complete, the CRS should enter 40EP-9EO04, SGTR and initiate and cooldown and depressurization of the RCS. Once below 540 °F, the crew should isolate the affected SG.

Event 8 When the Safety Injection Actuation Signal actuates, the Train A High Pressure Safety Injection pump will fail to auto start. The RO should recognize this and manually start the pump.

Event 9 After the trip, the Tave from the Reactor Reg System will fail low. This will require action by the CO to establish feed to the Steam Generators.

Page 1 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __1__

Event

Description:

______Shift of the Turbine Cooling Water pumps____________________

Time Position Applicants Actions or Behavior T=0 CRS Directs the CO to shift Turbine Cooling Water Pumps.

CO Informs the Auxiliary Operator (AO) in the Turbine Building that he will be shifting TC Pumps.

Starts the standby pump (TCN-P01B) by placing handswitch, TCN-HS-22, in the "START" position (B07).

Directs the AO to close the casing vent valve for TCN-P01B (TCN-HCV-531).

Directs the AO to close the discharge valve for TCN-P01A (TCN-HCV-25).

When the AO reports the discharge valve for TCN-P01A is closed, the CO stops the TC A pump using TCN-HS-21 (B07).

Directs the AO to open the discharge valve for TCN-P01A (TCN-HCV-25).

Directs the AO to visually inspect TC pump A to ensure no rotation then Open the casing vent valve (TCN-528).

Informs the AO in the Turbine Building that the pump shifting operation is complete.

Page 2 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __2__

Event

Description:

____Volume Control Tank level transmitter CHN-LT-227 fails low______

Time Position Applicants Actions or Behavior T=7 Crew The crew receives alarms on B03 (Windows 9A and 8B).

RO Address the alarm response procedure (40AL-9RK3A).

Examiner Note: CHN-LT-227 is not indicated on the control boards but can be seen on the plant computer.

RO Addresses the alarm response procedure (40AL-9RK3A).

Verifies that the auto actions have occurred (B03):

Boric acid makeup to charging pumps valve, CHN-UV-514 opens. (Loss of power to CHN-UV-514 will open CHE-HV-536).

Volume Control Tank Outlet valve, CHN-UV-501 closes.

Boric acid makeup pump recirc valve, CHN-UV-510 closes.

One Boric acid makeup pump, CHN-P02A or CHN-P02B starts.

Checks the VCT level Lo-Lo alarm by reading level indicator CHN-LI-226 (B03).

If the CRS directs, the RO goes to single charging pump operation per 40OP-9CH01, CVCS Normal Operations. This would entail the following:

Manually lowering letdown flow to 20 to 30 gpm using RCN-LIC-110, Level Setpoint Controller (B04).

Place the normally running charging pump (CH B) in the Pull-to-Lock position (B03).

Restore one of the following:

o Restore Pzr level control to AUTO o Balance charging and letdown flow to stabilize level in the VCT.

(Continued on next page)

Page 3 of 15

IF level indicator CHN-LI-226 indicates normal VCT level (i.e.,

greater than 15% level), THEN perform the following to maintain charging pump suction aligned to the VCT:

Examiner Note: The RO may hand off the Alarm Response Procedure to the CO to read as he holds the valves.

RO

Holds open CHN-UV-501, Volume Control Tank Outlet (Continued) valve (B03).

Examiner Note: IF the operators hand slips and CHN-UV-501 starts going closed, the operator should release the handswitch for CHN-UV-514 or a low suction pressure trip will occur on the charging pumps.

RO

Holds closed CHN-UV-514, Boric Acid Makeup to Charging (Continued) Pumps Valve (B03).

(IF at any time, CHN-UV-501 begins to stroke closed or indicates intermediate position. THEN release CHN-HS-514 and check that CHN-UV-514 opens.)

Directs an AO to open the following breakers (in the following order):

o CHE-HV-536 breaker, NHN-M7209 o CHN-UV-501 breaker, NHN-M7208 o CHN-UV-514 breaker, NHN-M1528

Stations an operator(s) in the vicinity of the MCCs to close the following breakers when directed by the Control Room Operator Page 4 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __3 and 4__

Event

Description:

(3)_Control Room Radiation Monitor (RU-29) fails high causing a CREFAS

______ _________(4)_Essential Cooling Water Pump A fails to auto tart________________

Time Position Applicants Actions or Behavior T = 23 Crew The crew receives alarms on B05A (Windows 4A, 4B, and 4C) and on the RMS panel for RU-29.

CO The CO addresses the alarm response procedures (41AL-1RK5A and 74RM-9EF41).

74RM-9EF41 Response:

High alarm initiates a CREFAS.

Notify RP.

Notify Radiation Monitoring Technician (Effluent Tech).

Monitor RU-29 or RU-30 for increasing trends.

Monitor RU-143 and RU-145 readings and trends.

41AL-1RK5A Response:

Checks the auto actions for a CREFAS (SP pump, EW pump, Essential Chiller and Control Room Essential Ventilation should all start).

RO Addresses the alarm response for the blue SEAS light (B02) and determines the EW A pump did not auto start.

Addresses the alarm response (41AL-1ES2A) for the SESS panel and starts the EW A pump (B02).

41AL-1RK5A Response:

If a CREFAS occurs and no SIAS and no LOP, then within 30 minutes stop the Control Bldg Normal Sply Fan A01 and ESF Swgr Room Norm Sply Fan A03 (B02).

Page 5 of 15

Crew When called the Effluent Tech states that RU-29 has failed high due to a sudden increase in the output and requests that the control room place RU-29 in bypass.

CRS Addresses Tech Specs and determines the EW A pump is inoperable and enters LCO 3.7.7 condition a. This will cause numerous other LCOs to be entered due to cascading Tech Specs.

Addresses Tech Spec (LCO 3.3.9) for RU-29 failing and determines only one Control Room Radiation monitor is required.

Directs the CO to bypass RU-29 on the BOP-ESFAS panel per 40OP-9SA01.

May elect to quarantine rather than start EW pump A.

CO Bypass RU-29 (CREFAS A) on the BOP-ESFAS Cabinet (back of control panels) per 40OP-9SA01.

Page 6 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __5__

Event

Description:

__________ ____Steam Generator #1 Tube Leak ______________

Time Position Applicants Actions or Behavior T = 34 Crew The crew receives alarms on RU-142, Main Steam Line N16 Monitors.

CO The CO addresses the Alarm Response procedure for RMS 74RM-9EF41.

The CO determines that RU-142, channels 1 and 2 have the highest readings therefore SG #1 is affected.

Monitors RU-4, RU-139, RU-141, and RU-143 for increases.

Reports the leak rate and rate of change when requested by the CRS.

CRS Enters 40AO-9ZZ02, Excessive RCS Leakrate (Section 5.0) and performs the following:

Enter AOP Entry Time and Date.

If pressurizer level is lowering and additional makeup is required, then ensure all available charging pumps are running.

If all available charging pumps are running and pressurizer level is lowering, then isolate letdown.

Examiner Note: The leak rate should be ~ 1 gpm so additional makeup or isolation of letdown is not required at this time.

CRS

Ensure compliance with LCO 3.4.14 and 3.4.18 (enters (continued) condition b of LCO 3.4.14 and condition a of LCO 3.4.18).

Directs Chemistry to perform the Abnormal Occurrence checklist for a SGTL.

Notifies RP that an RCS leak exists.

(Continued on next page)

Page 7 of 15

CRS

Obtains the leakrate and rate of change of leakrate from (continued) RMS.

Refers to Appendix F, Steam Generator Tube Leak Guidelines to determine operator actions and determines a shutdown is required.

Directs the RO to perform Appendix B, ERFDADS Leak Rate Determination.

Commences performance of 40OP-9ZZ05, Power Operations to perform a plant shutdown.

Examiner Note: Since there is no time requirement for the shutdown, there is no need to wait for a down power prior to going to the next event.

CRS

Directs the CO to perform Appendix C, Minimize Release to (continued) the environment.

RO Performs Appendix B ERFDADS Leak Rate determination.

Checks that TC is constant (+1°F).

Checks that pressurizer pressure is stable between 2235 and 2265 psia.

Ensures Chemistry is not drawing samples.

Ensures Letdown is aligned to the VCT or isolated.

Ensures Charging pump suction is aligned to the VCT.

(The following actions occur on B03):

Places 210X, Reactor Makeup Water to VCT controller, in MANUAL with a zero output.

Places 210Y, Boric Acid Makeup to VCT controller, in MANUAL with a zero output.

Places CHN-HS-527, Makeup to Charging Pumps Valve in CLOSED.

WHEN CHN-UV-527 indicates closed, THEN places CHN-HS-210, Makeup Mode Select Switch, in MANUAL.

Monitors the leakrate on ERFDADs and allows the trend to run for 15 minutes or until VCT level has lowered to 15%.

Page 8 of 15

CO CO performs Appendix C to minimize Release to the environment:

Ensures ARN-HS-19, Post Filter Mode Select Switch is in the THRU FILTER MODE (B07).

Selects OFF on the switches for Steam bypass valves SGN-PV-1007 and 1008 (B06).

Directs an operator to perform Attachment C-1, Condensate Cross-Tie Isolation.

Throttles CDN-HV-275, Demineralizer Water Feed to Condensate Service Header Valve to maintain 50-100 psig on CDN-PI-201 (B05).

Directs an operator to close CDN-V099 CONDENSATE SERVICE HDR SUPPLY REG VALVE CDN-PV-200 OUTLET ISOL VALVE.

Ensures that both of the Condensate Pump Overboard Valves (CDN-HV 29 and 30) are closed (B05).

Page 9 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __6__

Event

Description:

_______ _Loss of Channel C 125 VDC power (PKC-M43 )___________

Time Position Applicants Actions or Behavior T= 56 Crew Receives numerous alarms on Panels B04 and B05. Also receive alarms on B01.

Identifies a loss of PKC-M43 by indications on B05 (loss of instrument and lights on B05 and/or ADV permissive lights on B06).

CRS Enters 40AO-9ZZ14, Loss of Class Instrument or Control Power AOP Section 7.0 and performs the following:

Checks that PNC-D27 is energized. Goes to contingency step and performs Section 8.0.

Enters LCO 3.0.3 due to failure to meet Tech Spec LCO 3.1.5 Condition B.

Directs an operator to place CEDMCS in STANDBY.

Directs an operator to perform 72ST-9RX03, DNBR/LHR/AZTILT/ASI With COLSS out Of Service within 15 minutes.

Directs an operator to set the CEAC 2 INOP code in ALL operable CPCs.

Determines the effect of the de-energized buses using Appendix E.

Directs an operator to place PPS Channel C bistables in bypass.

Ensures compliance with Tech Specs (LCO 3.0.3 will be the most limiting).

CO Places CEDMCS in Standby when directed (B04).

Performs 72ST-9RX03 when directed.

Sets CEAC 2 INOP codes in A, B, and D CPCs (B05).

Bypasses all parameters on Channel C PPS (behind control boards).

Page 10 of 15

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __1__ Event No.: __7, 8, and 9_

Event

Description:

______Steam Generator Tube leak degrades (Trip Initiator)___________

Time Position Applicants Actions or Behavior T = 70 Crew Notices Pzr Level and RCS pressure are lowering.

CRS Directs RO to start additional charging pumps and isolate letdown.

Due to pressurizer level continuing to lower, directs a manual reactor trip and possibly a SIAS/CIAS based on trend.

Directs the crew to perform the Standard Post Trip Actions.

Standard Post Trip Actions CO Trips the reactor and possibly initiates a SIAS/CIAS when directed (may be done by the RO) (B04).

Reports the Reactivity Control Safety Function (CEAs inserted, power dropping, negative startup rate).

Examiner Note: Due to the loss of PKC-M43, 2 of the 3 CEA position indications are not available so the crew should borate the RCS.

CO Reports the Main Turbine is tripped and the generator output (Continued) breakers are open.

Reports SG levels and trends and method of feed.

Examiner Note: Due to the low failure of Tave, the CO will have to either take manual control of the downcomer valves or use Auxiliary Feedwater to feed the SGs.(B02)

CO (Continued) Reports the status of the Electric Plant (all buses energized and DGs running with SP pump IF SIAS/CIAS initiated).

Reports Tcold and trend.

(Continued on next page)

Page 11 of 15

CO Reports SG pressures and trends.

(Continued)

Reports Containment pressure and status of the Radiation Monitors (may be done by the RO).

Reports Containment temperature and pressure (may be done by the RO).

RO Borates the RCS using Standard Appendix 103 (B03).

May direct the Aux Operator to restore power to CHN-UV-514 and CHE-HV-536.

The following reports may be performed by the CO while a boration is being established.

Reports status of pressurizer level and trend (lowering unless post trip heat is still occurring).

Reports RCS Subcooling (lowering).

Reports status of seal injection and Nuclear Cooling Water to the RCPs (in service).

Reports status of RCS pressure (lowering).

Reports status of RCPs, Loop T, and RCS Subcooling.

When SIAS occurs recognizes that HPSI A did not start and starts HPSI A (B02).

SGTR Procedure CRS Diagnoses a SGTR and goes to 40EP-9EO04, SGTR and performs the following:

Directs the CO to ensure the Steam Generator Sample Valves are open.

Directs Chemistry to perform the Abnormal Occurrence Checklist.

Directs the SM to classify the event.

(Continued on next page)

Page 12 of 15

CRS

Checks a SIAS is actuated if pressurizer pressure drops to (continued) the SIAS setpoint.

If SIAS has actuated, directs RO to check that HPSI and LPSI pumps have started and that safety injection flow is adequate.

Examiner Note: If RO has not started the HPSI A pump, the CRS should direct him to start the pump at this time.

CRS

May direct the RO to shift charging pump suction to the (continued) RWT per Standard Appendix 10.

Directs the RO to stop one RCP in each loop if pressurizer pressure remains below the SIAS setpoint (this may have been done in the SPTAs).

Directs the RO to perform Appendix 16, RCP Trip Criteria.

Directs the CO to commence a cooldown to a T-hot of less than 540°F using the SBCS.

Directs the CO or RO to perform Appendix 5, RCS and Pressurizer Cooldown Log.

Directs the RO to depressurize the RCS to less than 1135 psia, approximately equal to the SG with the tube leak and within the P/T limits.

Directs the RO or CO to reset the MSIS setpoints.

CRITICAL TASK: Reset the MSIS during the cooldown to prevent an unmonitored release to the public.

CRS

Determines the most affected SG is SG#1.

(continued)

When T-hot is less than 540°F, directs the CO to isolate SG#1 using Appendix 113, Steam Generator 1 Isolation.

RO Starts the HPSI A pump if not done during the SPTAs (B02).

Shifts Charging pump suction to the RWT using Appendix 10 as follows:

Ensures CHB-HV-530 is open (B02).

Places the appropriate Charging Pump in Pull-to-Lock (B03).

Directs an Auxiliary Operator to perform Attachment 10-A for the appropriate charging pump.

(Continued on next page)

Page 13 of 15

RO Depressurizes the RCS using Main Spray (B04) or Aux Spray (continued) (B03).

Resets the MSIS setpoints as the SGs depressurize (may be done by CO or combination of both operators).

CO Opens SG sample valves as directed (B07).

Commences a cooldown to a T-hot of less than 540°F using the SBCS (B06).

Resets the MSIS setpoints as the SGs depressurize (may be done by RO combination of both operators).

When T-hot is less than 540°F performs Appendix 113 to isolate SG#1 as follows:

Checks both ADVs closed on SG#1 (B06):

o ADV-184 o ADV-178

Closes both SG 1MSIVs using the fast close pushbuttons (B06):

o SGE-UV-170 o SGE-UV-180

Ensure SGE-UV-169, SG1 MSIV Bypass Valve is closed(B06):

Closes both SG 1 Economizer FWIVs using the fast close pushbuttons (B06):

o SGA-UV-174 o SGB-UV-132

Closes both SG 1Downcomer Isolation Valves (B06):

o SGA-UV-172 o SGB-UV-130

Closes both SG 1Blowdown Containment Isolation Valves (B07):

o SGA-UV-500P o SGB-UV-500Q

Closes BOTH of the following steam trap isolation valves (B06):

o SGA-UV-1133 o SGB-UV-1135A/1135B (Continued on next page)

Page 14 of 15

CO

Checks the SG Safety Valves on closed (B06).

(continued)

Ensures BOTH Aux Feed Pump A Steam Supply Valves are closed (B06):

o SGA-UV-134 SG 1 Steam Supply to Aux Feed Pump A o SGA-UV-134A SG1 Steam Supply to Aux Feed Pump A Bypass

Ensures BOTH Auxiliary Feedwater Isolation Valves are closed (B06):

o AFB-UV-34 Aux Feedwater to SG1 Downstream Valve o AFC-UV-36 Aux Feedwater to SG 1 Downstream Valve.

CRITICAL TASK: Isolate the ruptured SG within 70 minutes of initiation of the SGTR.

Scenario termination: The scenario may be terminated when the ruptured SG is isolated.

Page 15 of 15

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __2 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event No. Malf. No. Event Type* Event Description 1 None N Shift from Hydraulic Fluid Pump B to Pump A per section 4.7 of CO/SRO 40OP-9C001, Electro-Hydraulic Control System.

2 mfNI02C f:0 I Control Channel 2 fails low (50% Power indicated). Crew selects CO/SRO channel 1 at the RRS system panel.

40AO-9ZZ16, RRS Malfunctions 3 mfTH01A f:0.01 C Small RCS leak. Crew takes action per section 3 of ~16 gpm RO/SRO 40AO-9ZZ02, Excessive RCS Leakrate (TS) 4 mfAN_1A03D1 C LOP relay failure. Crew responds using 41AL-1RK1A (1A03D) doeED_ZLS037271DS_W1 CO/SRO Crew determines that a LOP should not have occurred and takes action to bypass the appropriate relays per 40OP-9SA01 doRP_ZLSAAC02ALOP1_ (TS)

W1 5 IOR dims_ZDSGEUV170 R -RO An MSIV goes closed. Crew responds per 40AL-9RK6A and begins a down power to less than 65% power.

C - CO/SRO 6 cmCPTP01CENP01B_6 C Stator Cooling Pump B trips with standby pump failing to auto CO/SRO start.

7 mfTH01A f:3 M LOCA RCS leak degrades requiring a reactor trip.

ALL 40EP-9EO03, Loss of Coolant Accident 8 Scenario file noSI/CI C SIAS/CIAS/MSIS fail to automatically initiate.

RO/SRO CRITICAL TASK - Initiate SI flow when the SIAS setpoint has been exceeded.

9 cmCPRH05SIBP03_6 C CS pump B trips on an 86 lockout RO/SRO CRITICAL TASK -Initiate CS flow when the CSAS setpoint has been exceeded.

40EP-9EO09, Functional Recovery Procedure End Scenario may be ended once point SIAS and CSAS flow have been established using LPSI.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 1

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 2

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2 Revision 1

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing.

CS A is tagged out for scheduled maintenance.

Planned shift activities:

The crew needs to shift EHC pumps from B to A to support vibration readings. The vibration tech is standing by.

Revision 1

2012 NRC EXAM Scenario 2 Setup Instructions

1. _____ Reset to IC-20

2. _____ Run scenario 2012 NRC Scenario 2 under Scenario scenario files from NRC exam thumb drive

3. _____ Stage radios for operators

4. _____ Alarm Silence to OFF

5. _____ Ensure CVCS and DFWCS alarms are reset

6. _____ Place the simulator in freeze until the crew enters the simulator.

7. _____ Hang Train B protected sign.

8. _____Hang Protected Equipment plaques near the handswitches for AF B and AF N.

9. _____Hang Protected Equipment plaques near the handswitch for CS B.

10. _____Verify RCS leakrate has stabilized at ~ 0 gpm.

11. _____ Review procedures listed on the next page for marks and missing pages:

Page 1 of 5 Rev 2

2012 NRC EXAM Scenario 2 Procedures to be checked:

40OP-9CO01, ELECTRO-HYDRAULIC 40AL-9RK4A (Window 10B)

CONTROL SYSTEM (Section 6.7) 40AL-9RK6A (Window 6A [Reactor 40AO-9ZZ16, RRS Malfunctions (Section 5)

Power deviation - 8%] and 7A) 40AO-9ZZ02, Excessive RCS Leakrate 41AL-1RK1A (Window 3D)

(Section 3) 40OP-9SA01, BOP ESFAS Module 40AL-9RK6B (Windows 7A, 7B and 7C))

Operations (Section 4.6) 74RM-9EF41, RMS Alarm Response 40OP-9ZZ05, Power Operations (Section 6.0)

(RU-1) 40OP-9CH01, CVCS Normal Operations 40EP-9EO01, SPTAs (Section 7.0) 40EP-9EO03, LOCA 40EP-9EO09, FRP (CTPC-2)

Tech Specs (3.3.7, 3.7.2 and 3.4.14) 40OP-9SF08, RRS Operations (section 6.0)

Page 2 of 5 Rev 2

2012 NRC EXAM Scenario 2 Driver Station Menu should look like this:

SCENARIOS TRIGGERS MALFS COMP REMOTES COMP I/O ALARM MALFS REMOTES OVERRIDES OVRDS 0 0 2:0 11:9 3 8 3:0* 1:0

May be 5:2 if MSIV bypasses are tagged out.

Complete list of malfunctions.

Malfs mfNI02C k:2 f:0 SEN-NG-008 CONT CH 2 SUB CH 1 DET FAIL mfTH01A f:0.01 k:3 LOOP 1A LOCA - COLD LEG Comp Malfs cmBSRP01BSCNTPRHIAT_1 BISTABLE FAILS ASIS: HI CNT PRESS CHANNEL A TRIP cmBSRP01BSCNTPRHIBT_1 BISTABLE FAILS ASIS: HI CNT PRESS CHANNEL B TRIP cmBSRP01BSCNTPRHICT_1 BISTABLE FAILS ASIS: HI CNT PRESS CHANNEL C TRIP cmBSRP01BSCNTPRHIDT_1 BISTABLE FAILS ASIS: HI CNT PRESS CHANNEL D TRIP cmBSRP01BSPZRPRLOAT_1 BISTABLE FAILS ASIS: LO PZR PRESS CHANNEL A TRIP cmBSRP01BSPZRPRLOBT_1 BISTABLE FAILS ASIS: LO PZR PRESS CHANNEL B TRIP cmBSRP01BSPZRPRLOCT_1 BISTABLE FAILS ASIS: LO PZR PRESS CHANNEL C TRIP cmBSRP01BSPZRPRLODT_1 BISTABLE FAILS ASIS: LO PZR PRESS CHANNEL D TRIP cmCPTP01CENP01A_5 FAIL TO AUTO-START: STATOR COOLING PUMP A cmCPTP01CENP01B_6 k:6 SPURIOUS 86 LOCKOUT RELAY TRIP: STATOR COOLING PUMP B cmCPRH05SIBP03_6 k:9 SPURIOUS 86 LOCKOUT RELAY TRIP: CONTAINMENT SPRAY PUMP B Remotes rfFW57 OPR AUX FPT MAIN STM SPLY VLV rfFW59 MAN ACT OVSP TRIP OF AFA-P01 rfFW60B CONTROL POWER TO AFA-HV54 Comp Remotes crB2RH02SIAP03_2 f:RACK_OUT RACK IN/OUT: CONTAINMENT SPRAY PUMP A crB4FW08AFAHV32_1 f:OPEN BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 crB4FW08AFAUV37_1 f:OPEN BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE crB4MS13SGAUV134_1 f:OPEN BKR OPEN/CLOSE: SG 1 TO AUX FWP A STM SUPPLY VLV Page 3 of 5 Rev 2

2012 NRC EXAM Scenario 2 crB4MS13SGAUV138_1 f:OPEN BKR OPEN/CLOSE: SG 2 TO AUX FWP A STM SUPPLY VLV Continued on next page crB4RH02SIAUV664_1 f:OPEN BKR OPEN/CLOSE: CTMT SPRAY PUMPS TO RWT ISO VALVE crB5FW08AFCHV33_1 f:OPEN BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-2 crB5FW08AFCUV36_1 f:OPEN BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE I/O Overrides doED_ZLS037271DS_W1 f:OFF 4.16KV BUS 1-E-PBA-S03 BUS POTENIAL IND LTS k:4 doRP_ZLSAAC02ALOP1_W1 U/V-1 / TST / BYP, LOP/LS f:ON k:4 diMS_ZDSGEUV170 f:OFF k:5 DI (Switch for module power to MSIV-170)

Alarm Ovrds mfAN_1A03D1 f:ALARM_ON UNDERVOLTAGE-1 CHANNEL A TRIP k:4 Page 4 of 5 Rev 2

2012 NRC EXAM Scenario 2 Drivers page EVENT TIME SYNTAX DESCRIPTION MISC.

1 Crew shifts Control Oil If requested to inspect the A Control oil pump after the pumps from B to A. control room shifts pumps, report no abnormalities.

Discharge pressure is 1600 psig.

2 When directed by the lead Key 2 Control channel 2 fails If contacted as I&C maintenance or work control report evaluator. mfNI02C f:0 low (one detector so you will write a PVAR and investigate when Work indicated power is ~50%) Mech is generated.

3 When directed by the lead Key 3 RCS leak of ~16 gpm If called as Chemistry, report you are not sampling evaluator. mfTH01A f:0.01 RCS.

If directed by CR Key 31 Simulates closing SCN- Wait 5 minutes then report that SCN-V11 and 12 have CmAVWD07SCNPV4A_2 V11/12 been closed.

4 When directed by the lead Key 4 Fails PBA-S03 If called as electrical, PR&C, or work control report you evaluator. mfAN_1A03D1 f:ALARM_ON Undervoltage relay UV-1 will write a PVAR and investigate when Work Mech is doeED_ZLS037271DS_W1 f:OFF generated.

doRP_ZLSAAC02ALOP1_W1 f:ON 5 When directed by the lead Key 5 Fails power to MSIV 170 If called as electrical or work control report you will evaluator. IOR dims_ZDSGEUV170 causing it to close. write a PVAR and investigate when Work Mech is generated.

6 When directed by the lead Key 6 Trips the B stator cooling If directed as an area operator to inspect the pump, evaluator. cmCPTP01CENP01B_6 pump report no abnormal indications at pump but there is an 86 lockout indicated at the breaker.

7 When directed by the lead Mmf TH01A ramp:8 minutes and final Modifies the leakrate to a evaluator. severity 3 final severity of 3 over an 8 minute period.

8 (In Setup) No SIAS, CIAS, MSIS Scenario file noSI/CI 9 When directed by the lead Key 9 Trip of the B Containment If sent as area operator to check out the breaker, report it evaluator and after the crew cmCPRH05SIBP03_6 Spray Pump has an 86 Lockout and ground fault flag tripped.

enters the LOCA procedure.

Page 5 of 5 Rev 2

Scenario 2 Overview Event 1 The CO shifts the Electro Hydraulic Control (CO) pumps from B running to A running.

Event 2 One detector on Control Channel #2 fails low (resulting in an indication of 50%

power). The CRS should enter 40AO-9ZZ16 to address the failure. The CO will select the unaffected channel on the Reactor Reg Test Panel behind the control boards.

The CO will also address the alarm on the Digital Feedwater Control System (DFWCS) and place Control channel #2 in maintenance and remove the A-TUN lockout on the DFWCS.

Event 3 A small RCS leak (~ 16 gpm) occurs. The CRS should enter 40AO-9ZZ02 to address the leak. The RO will perform a leakrate calculation.

Event 4 A Loss of Power (LOP) undervoltage relay fails on the class Train A 4160 kV bus.

The crew addresses the alarm response procedure and Tech Specs. The CO should place the LOP/LS relay in bypass on the BOP-ESFAS panel behind the control boards.

Event 5 A Main Steam Isolation Valve fails closed. The CO addresses the alarm response procedure which directs a down power to 65%. The RO will borate and the CO will reduce turbine load.

Event 6 Stator Cooling Water Pump B trips with a failure of the A pump to auto start. The CO should address the alarm response and start the A pump within 70 seconds or a turbine trip will occur.

Event 7 The RCS leak degrades causing a LOCA. The crew performs the Standard Post Trip Actions (SPTAs).

Event 8 After the LOCA, a failure of PPS to initiate a Safety Injection Actuation Signal, Containment Isolation Actuation Signal and Main Steam Isolation Signal occurs. The crew should recognize the signals did not occur and manually initiate these actuations.

Event 9 After the crew enters the LOCA procedure, Containment Spray B will trip (CS A is tagged out). This will cause a loss of safety function CTPC. The CRS should transition the Functional Recovery Procedure and align a LPSI pump to supply Containment Spray.

Page 1 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2_ Event No.: __1__

Event

Description:

Shift from Hydraulic Fluid (EHC) Pump B to A running Time Position Applicants Actions or Behavior T=0 CRS Directs the CO to shift from Hydraulic Fluid Pump B to Pump A.

CO Informs the Auxiliary Operator in the Turbine Building that he will be shifting Hydraulic Fluid (EHC) pumps.

Starts Hydraulic Fluid Pump A by momentarily placing handswitch CON-HS-4, HYDRAULIC FLUID PUMP A P01A, to START (B06).

Checks ALL the following for Hydraulic Fluid Pump A:

The red START light at handswitch CON-HS-4, HYDRAULIC FLUID PUMP A P01A, is on

Motor amps are less than 219 amps

Pump discharge pressure is between 1500 psig and 1750 psig, indicated locally on CON-PI-007, A CO Pump Local Disch Press Indic Performs the following for Hydraulic Fluid Pump B

Stops Hydraulic Fluid Pump B by momentarily placing handswitch CON-HS-5, HYDRAULIC FLUID PUMP B P01B, to STOP.

Checks the green STOP light is on at handswitch CON-HS-5, HYDRAULIC FLUID PUMP B P01B.

Page 2 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2_ Event No.: __2__

Event

Description:

Control Channel 2 fails low (50% power indicated)

Time Position Applicants Actions or Behavior T= 8 Crew The crew receives alarms on B03 and B05. (Windows 3A10B and 6A6A )

RO/CO Address the alarm response procedure (40AL-9RK4A).

Verifies a mismatch in Control Power readings (channel 2 reads 50%)

Verifies that the Reactor Regulating system is not in test.

With CRS concurrence switches CEDMCS out of Auto Sequential (AS)

Verifies pressurizer level is stable.

CRS Enters 40AO-9ZZ16, RRS Malfunctions (section 5).

Ensures that CEDMCS in NOT in Auto Sequential.

Directs the CO to determine the failed channel.

Refers to Appendix B to determine the impact of the failure.

o AMI on 5% deviation o DFWCS uses a canned value of 60% power

Directs the CO to select the unaffected instrument at the RRS Test Panel.

Verifies that Tavg/Tref mismatch is 3°F or less.

Directs the CO to place CEDMCS back in AS.

CO

Determines that Control Channel 2 is reading 50% indicating a failed detector.

Selects channel 1 at the RRS Test Panel

Verifies that the Tavg/Tref mismatch is 3°F or less.

Places CEDMCS in the desired mode of operation as directed.

Addresses alarm response procedure (40AL-9RK6A) window 6A due to Reactor Power 8% deviation.

Page 3 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _2__ Event No.: __3__

Event

Description:

Small RCS leak (~16 gpm)

Time Position Applicants Actions or Behavior T= 14 Crew Crew observes a slight lowering of trends on pressurizer level and pressure.

Crew receives alarms on RU-1, Containment Monitor.

CO The CO addresses the Alarm Response procedure for RMS 74RM-9EF41.

Notifies RP of the alarm.

Notifies Radiation Monitoring Technician (Effluent Tech).

CRS Enters 40AO-9ZZ02, Excessive RCS Leakrate (Section 3.0) and performs the following:

Enter AOP Entry Time and Date.

If pressurizer level is lowering and additional makeup is required, then ensure all available charging pumps are running.

If all available charging pumps are running and pressurizer level is lowering, then isolate letdown.

Examiner Note: The leak rate is ~ 16 gpm so no additional makeup or isolation of letdown is required at this time.

CRS

Ensure compliance with LCO 3.4.14 condition b.

(continued)

Directs Chemistry to perform the Abnormal Occurrence checklist for a RCS leak.

Notifies RP that an RCS leak exists.

Directs the RO to perform Appendix B, ERFDADS Leak Rate Determination.

Directs an operator to walkdown charging and letdown piping.

Page 4 of 14

RO Performs Appendix B ERFDADS Leak Rate determination.

Checks that TC is constant (+1°F).

Checks that pressurizer pressure is stable between 2235 and 2265 psia.

Ensures Chemistry is not drawing samples.

Ensures Letdown is aligned to the VCT or isolated.

Ensures Charging pump suction is aligned to the VCT.

(The following actions occur on B03):

Places 210X, Reactor Makeup Water to VCT controller, in MANUAL with a zero output.

Places 210Y, Boric Acid Makeup to VCT controller, in MANUAL with a zero output.

Places CHN-HS-527, Makeup to Charging Pumps Valve in CLOSED.

WHEN CHN-UV-527 indicates closed, THEN places CHN-HS-210, Makeup Mode Select Switch, in MANUAL.

Monitors the leakrate on ERFDADs and allows the trend to run for 15 minutes or until VCT level has lowered to 15%.

Page 5 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _2__ Event No.: __4__

Event

Description:

LOP relay failure____________________________________________

Time Position Applicants Actions or Behavior T= 22 Crew The crew receives alarms on B01A. (Window 3D)

RO Address the alarm response procedure (40AL-9RK1A).

Verifies normal PBA-S03 bus voltage using PBA-EI-S03L.

CO Places UV-1 in bypass per 40OP-9SA01, BOP ESFAS Modules Operation.

Verifies that the Sequencer is not in Auto Test.

Performs a lamp test on BOP ESFAS cabinet A.

Places Bypass Key in slot for UV-1

Turns the key clockwise ~ 1/4 turn or until the bypass light comes on.

CRS

Ensures compliance with LCO 3.3.7 condition a.

Directs the CO to place UV-1 in bypass per section 4.6 of 40OP-9SA01, BOP ESFAS Modules Operation.

Page 6 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2_ Event No.: __5__

Event

Description:

MSIV 170 inadvertently goes closed___

Time Position Applicants Actions or Behavior T= 32 Crew The crew receives alarms on B06 (A), window 7A.

CO Address the alarm response procedure (40AL-9RK6A).

Checks MSIV handswitches (B06) and determines that MSIV-170 is closed as indicated by SGA-HS-170A & SGB-HS-170B.

Informs CRS that the ARP directs a downpower to 65%

per 40OP-9ZZ05, Power Operations.

Examiner Note: An MSIV may be considered operable if it is closed and its opening capability is disabled.

CRS Refers to 40OP-9ZZ05, Power Operations (section 8).

Informs Rx Engineering, ECC and Water Rec. Facility of power reduction.

Refers to the Maneuvering Box Tools for downpower strategies.

Holds a reactivity brief.

Directs Chemistry to monitor secondary chemistry during power reduction.

Ensures that RCN-LIC-110 (B03), Pressurizer Level Control is in Remote Auto.

Directs an operator to close SCN-V011 & SCN-V012, isolation valves for Blowdown Flash Tank controller.

Directs the performance of appendix U if CEAs are moved.

Directs the RO to borate per the established game plan

(~1800 gallons).

Continued on next page Page 7 of 14

RO Borates the RCS at the desired rate using 40OP-9CH01, CVCS Normal Operations.

(The following actions occur on B03):

On CHN-FIC-210Y, Boric Acid Makeup flow control module (Foxboro), depresses the Sel pushbutton until the blue dot is at the top of the Auto Setpoint bar graph - the left bar graph.

Depress the up or down arrows to vary the auto setpoint.

WHEN the auto setpoint is at the desired value, ensures that A is illuminated on the A/M indicating light.

IF the makeup flow control module is not in automatic as indicated by an A illuminated on the A/M indicating light, THEN depress the A/M pushbutton.

o Check that A illuminates on the A/M indicating light.

Selects the Target makeup flow on the boric acid totalizer/counter module (Micro-Motion), CHN-FQIS-210Y.

Places CHN-HS-210 in borate.

Depresses the reset pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).

Depresses the start pushbutton - the left pushbutton on the totalizer/counter module (Micro-Motion).

o Actual system flow is displayed on the Process Flow bar graph - the middle bar graph on the selected makeup flow control module.

o Actual flow may be read on recorder CHN-FR 210Y, green pen.

CO

Adjust feed pump bias (B06) as directed by CRS

Adjust p between the FWP discharge pressure and SG pressure to maintain sufficient feedwater flow.

Inserts CEAs per the power reduction plan.

Unloads the turbine by slowly lowering the Load Limit Potentiometer to maintain Tavg within +/- 3° of Tref.

Page 8 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2_ Event No.: __6 __

Event

Description:

Stator Cooling Pump B trips, standby pump A fails to auto start ___

Time Position Applicants Actions or Behavior T= 40 Crew Crew receives alarms on B06 (B) windows 7A, 7B and 7C.

CO

Refers to 40AL-9RK6B (Window 7B)

Starts standby Stator Cooling Water pump CEN-P01A by going to start on handswitch, CEN-HS-30.

Examiner Note: Generator trip circuit has a 70-second delay. If condition persists, generator will trip.

CRS

Directs CO to start Stator Cooling Water pump CEN-P01A.

Page 9 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _2__ Event No.: _7&8_

Event

Description:

(7) RCS leak degrades to a LOCA, requiring a reactor trip.___________

________________(8) No SIAS, CIAS, and MSIS________________________________

Time Position Applicants Actions or Behavior T= 44 Crew Observes Pzr level and RCS pressure lowering.

CRS

Directs RO to start additional charging pumps and isolate letdown.

Due to pressurizer level continuing to lower, directs a manual reactor trip and possibly a SIAS/CIAS/MSIS based on trend.

Directs the crew to perform 40EP-9EO01, Standard Post Trip Actions Standard Post Trip Actions CO

Trips the reactor and possibly initiates a SIAS/CIAS/MSIS when directed (may be done by the RO) (B04).

Reports the Reactivity Control Safety Function (CEAs inserted, power dropping, negative startup rate).

Reports main turbine tripped and output breakers open.

Reports Tcold and trend.

Reports SG pressures and trends.

Reports Containment pressure and status of the Radiation Monitors (may be done by the RO).

Reports Containment temperature and pressure (may be done by the RO)

Page 10 of 14

RO

Reports the status of the Electric Plant (all buses energized and DGs running with SP pumps IF SIAS/CIAS initiated).

Reports status of pressurizer level and trend (lowering).

Reports RCS Subcooling (lowering).

Reports status of seal injection and Nuclear Cooling Water to the RCPs (in service).

Reports status of RCS pressure (lowering).

Reports status of RCPs, Loop T, and RCS Subcooling.

Stops 2 RCPs and 1837 psia, stops all 4 RCPs on the Loss of Subcooling (< 24°).

LOCA Procedure CRS Diagnoses a LOCA (40EP-9EO03) and performs the following:

Confirms the diagnosis by directing the performance of the Safety Function Status Check.

Directs the CO to ensure the Steam Generator Sample Valves are open.

Directs Chemistry to perform the Abnormal Occurrence Checklist.

Directs the SM to classify the event.

Checks a SIAS is actuated if pressurizer pressure drops to the SIAS setpoint.

Examiner Note: If the crew has not yet initiated SIAS/CIAS/MSIS, the CRS should direct manual ESFAS actuations at this time.

CRITICAL TASK: Initiate Safety Injection flow when the SIAS setpoint has been exceeded.

CRS

If SIAS has actuated, directs RO to check that HPSI and continued LPSI pumps have started and that safety injection flow is adequate.

May direct the RO to shift charging pump suction to the RWT per Standard Appendix 10.

Directs the RO to stop one RCP in each loop if pressurizer pressure remains below the SIAS setpoint (this may have been done in the SPTAs).

(Continued on next page)

Page 11 of 14

CRS

Directs the RO to perform Appendix 16, RCP Trip Criteria.

continued

Directs the RO to verify that Letdown is isolated.

Directs the CO to verify that the RCS sample lines are isolated.

Directs the RO to place the Hydrogen Analyzers in service.

Verifies that CIAS is actuated.

Directs the RO to verify that an isolation valve is closed for each containment penetration.

If containment pressure is 8.5 psig or more, then check CSAS is actuated.

If CSAS has actuated, then perform the following:

a. Ensure at least one Containment Spray header flow is greater than 4350 gpm.

b. Ensure all RCPs are off.

c. Ensure RCP controlled bleedoff flow is isolated.

d. PERFORM Appendix 19, Containment Hydrogen Control to align the Hydrogen recombiners.

Page 12 of 14

Op-Test No.: _____ Scenario No.: _2__ Event No.: _7&8_

Event

Description:

Trip of Containment Spray Pump B____________________________

Time Position Applicants Actions or Behavior Examiner Note: Direct the driver to activate Key 9 causing CS pump B (SIB-P03) to trip on an 86 lockout.

Functional Recovery Procedure T= 57 CRS Diagnoses a lost Safety Function and goes to 40EP-9EO09, FRP and performs the following:

Directs the SM to classify the event.

Identify the success path(s) to be used to satisfy each safety function. REFER TO BOTH of the following:

o Section 4.0, Safety Function Tracking.

o Section 6.0, Resource Assessment Trees.

PERFORM Section 5.0, Safety Function Status Check for those success paths in use.

Identifies CTPC-2 as Jeopardized.

If CSAS actuated, then check at least one CS header is delivering 4350 gpm or more.

o Implements contingency actions to establish CS flow.

If it is desired to use LPSI Pump A to supply CS A train, and LPSI Pump A is not needed to support any RC, IC, or HR success path, then perform the following (B02):

a. Ensure that LPSI Pump A is running.

b. Ensure (closes) that SIA-HV-306, LPSI Shutdown Cooling Heat Exchanger A Bypass Valve, is closed.

c. Ensure that SIA-HV-687, LPSI Containment Spray from Shutdown Heat Exchanger a Cross-Tie Valve, is open.

(Continued on next page)

Page 13 of 14

Examiner Notes:

1. There is no indication of CS flow when using a LPSI pump for CS flow.

2. The CRS may either direct the following steps or give them to the RO to perform.

CRS d. Ensure that SIA-UV-672, Containment Spray a Discharge to continued Spray Header 1 Valve, is open.

e. Ensure (opens) SIA-HV-685, LPSI-Containment Spray to Shutdown Heat Exchanger a Cross-Tie Valve, is open.

f. Check that the LPSI pump is running at less than 60 amps.

If it is desired to use LPSI Pump B to supply CS B train, and LPSI Pump B is not needed to support any RC, IC, or HR success path, then perform the following (B02):

a. Ensure that LPSI Pump B is running.

b. Ensure (closes) that SIB-HV-307, LPSI Shutdown Cooling Heat Exchanger B Bypass Valve, is closed.

c. Ensure that SIB-HV-695, LPSI Containment Spray from Shutdown Heat Exchanger B Cross-Tie Valve, is open.

d. Ensure that SIB-UV-671, Containment Spray B Discharge to Spray Header 2 Valve, is open.

e. Ensure (opens) SIB-HV-694, LPSI-Containment Spray to Shutdown Heat Exchanger a Cross-Tie Valve, is open.

f. Check that the LPSI pump is running at less than 60 amps.

CRITICAL TASK: Initiate CS flow when the CSAS setpoint has been exceeded.

Scenario termination: The scenario may be ended once CSAS flow has been established using a LPSI pump.

Page 14 of 14

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __3 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (2% power, MOC).

Turnover: Unit 1 is at 2% power (200 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event Malf. No. Event Type* Event Description No.

1 None N Shift the MFP Lube oil pumps per 4.9 of 40OP-9FT02, Feedwater Pump Turbine B.

CO/SRO 2 cmAVRC03RCEPV100F_1 C Pressurizer spray valve fails open.

RO/SRO 3 mfRP06L1 C Inadvertent AFAS, B train AFW pumps and valves align to initiate AFW flow to the SGs. Crew takes actions to terminate mfRP06L2 CO/SRO flow and resulting power increase.

(TS) 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations 4 cmCNCV04CHNFIC243_2 I A seal injection controller will fail closed in automatic f:100 requiring the crew to take manual control of the controller RO/SRO 5 mfED10B C NBN-X04 faults and the DG breaker does not close causing a LOP of class 4160 bus, PBB-S04 cmBKEG03PBBS04B_3 RO/SRO 40AO-9ZZ12, Degraded Electrical.

(TS) 6 mfRD10B M Continuous CEA withdrawal. Crew places CEDMCS in ALL STANDBY then trips the reactor per:

40AO-9ZZ11, CEA Malfunctions 7 mfRD03G C Multiple CEAs stick out on the reactor trip.

mfRD03L RO/SRO CRITICAL TASK - Crew establishes > 44 gpm boration.

40EP-9EO02, Reactor Trip mfRD03M 8 cmAVMC01CDNHV45A_1 C Loss of Main Condenser Vacuum.

CO/SRO 9 mfFW21A C Trip of AFN-P01 RO/CO/SRO CRITICAL TASK - Implement the FRP to restore power to PBB-S04 and establish AFW flow to the SGs.

40EP-9EO09, Functional Recovery Procedure End Crew has restored AFW flow to point the SGs

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 3

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2 NUREG-1021, Revision 9 2 of 3

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 2% power.

The plant has been at 2% power for 2 days awaiting repair of AFA-P01.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

CEDMCS is in Manual Sequential Steam Bypass Master Controller SGN-PIC-1010 is in Local Setpoint with SBCV 1004 and 1006 in manual Pressurizer is in Boron Equalization AFN-P01 is in service feeding the SGs thru the Feedwater Isolation bypasses (SGN-HS-1143/1145)

Maintenance on the breaker was completed on Main Lube Oil pump LON-P07B at the end of last shift and it is ready to be tested.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and c were entered. Expected to return to service in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Planned shift activities:

Shift the running and standby lube oil pumps on Main Feedpump B.

NUREG-1021, Revision 9 3 of 3

2012 NRC EXAM Scenario 3 Setup Instructions

1. _____ Reset to IC-10

2. _____ Go to trigger file and find

PZR Spray selector

In the link command space type in dmf cmAVRC03RCEPV100F_1

Then run scenario 2012 NRC Scenario 3 under Scenario scenario files from the NRC exam thumb drive

3. _____ Stage radios for operators

4. _____ Alarm Silence to OFF

5. _____ Ensure CVCS and DFWCS alarms are reset

6. _____ Place the simulator in freeze until the crew enters the simulator.

7. _____ Hang Train B protected sign.

8. _____Hang Protected Equipment plaques near the handswitches for AF B and AF N.

9. _____Hang Protected Equipment plaques near the handswitch for CS B.

10. _____Check COLSS Constants are correct for the present blowdown lineup.

11. _____Review procedures listed below for marks and missing pages:

Page 1 of 6

2012 NRC EXAM Scenario 3 Procedures to be checked:

40OP-9FT02, Feedwater Pump Turbine 40AL-9RK4A (Windows 1A, 1B, and 8A)

(Section 4.9) 40AL-9RK5B (Window 7B) 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations (Section 3.0) 40AL-9RK3A (Window 11A and 11B) 41AL-1RK1C (Windows 16A and 10B) 40AO-9ZZ12, Degraded Electrical: 40AO-9ZZ11, CEA Malfunctions

Sections 3 and 54

Appendices O and N 40AO-9ZZ05, Loss of Letdown 40EP-9EO01, SPTAs (possible) 40EP-9EO10, Standard Appendices 40EP-9EO02, Reactor Trip (Appendix 16 and 103) 41ST-1ZZ02, Inoperable Power Sources 40ST-9EC03, Essential Chilled Water &

Action Statement available Ventilation System Inoperable Action Surveillance available 40EP-9EO09, FRP (MVAC-1) Tech Specs (LCO 3.3.6, 3.7.5, 3.8.1, 3.8.4 and 3.8.9)

Page 2 of 6

2012 NRC EXAM Scenario 3 Driver Station Menu should look like this:

SCENARIOS TRIGGERS MALFS COMP REMOTES COMP I/O ALARM MALFS REMOTES OVERRIDES OVRDS 0 2 8:3 4:1 3 8 0:0 0:0 Complete list of malfunctions.

Triggers RPSCHC Reactor trip breakers open Pzr Spray Selector PZR Spray Selector shift to 100-E Malfs mfED10B k:5 NBN-X04 ESSEN SERVICE XFORMER PH-PH FAULT mfFW21A k:9 AFN-P01 MTR DRIVEN AUX FEED PP TRIP mfRD03G CEA 43 STUCK CEA mfRD03L CEA 38 STUCK CEA mfRD03M CEA 07 STUCK CEA mfRD10B k:6 ALL MODES UNCONTROLLED ROD WITHDRAW mfRP06L1 k:3 AFAS-1 TR B LG 1 ESFAS ACT CKT FUS FL mfRP06L2 k:3 AFAS-1 TR B LG 2 ESFAS ACT CKT FUS FL Comp Malfs cmAVMC01CDNHV45A_1 POSITIONER OPEN FAILURE: CONDENSER SHELL 'A' VACUUM e:RPSCHC BREAKER cmAVRC03RCEPV100F_1 POSITIONER OPEN FAILURE: PZR SPRAY CONTROL VALVE k:2 cmBKEG03PBBS04B_3 MECHANICAL SEIZURE OF BREAKER: DG B 4.16KV BKR cmCNCV04CHNFIC243_2 OUTPUT FAILURE - AUTO MODE: SEAL INJECTION FLOW TO RCP f:100 k:4 2A Remotes rfEG21 f:STOP k:21 B" DSL EMER STOP rfFW57 OPR AUX FPT MAIN STM SPLY VLV rfFW59 MAN ACT OVSP TRIP OF AFA-P01 rfFW60B CONTROL POWER TO AFA-HV54 Continued on next page Page 3 of 6

2012 NRC EXAM Scenario 3 Comp Remotes crB2RH02SIAP03_2 RACK IN/OUT: CONTAINMENT SPRAY PUMP A f:RACK_OUT crB4FW08AFAHV32_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4FW08AFAUV37_1 BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE f:OPEN crB4MS13SGAUV134_1 BKR OPEN/CLOSE: SG 1 TO AUX FWP A STM SUPPLY VLV f:OPEN crB4MS13SGAUV138_1 BKR OPEN/CLOSE: SG 2 TO AUX FWP A STM SUPPLY VLV f:OPEN crB4RH02SIAUV664_1 BKR OPEN/CLOSE: CTMT SPRAY PUMPS TO RWT ISO VALVE f:OPEN crB5FW08AFCHV33_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-2 f:OPEN crB5FW08AFCUV36_1 BKR OPEN/CLOSE: AUX FEEDWATER ISOLATION VALVE f:OPEN Page 4 of 6

2012 NRC EXAM Scenario 3 Drivers page EVENT TIME SYNTAX DESCRIPTION MISC.

1 Crew shifts MFP B lube oil pumps 2 When directed by Key 2 Fails Spray valve 100F open It takes ~ 6 minutes for the low pressure alarm to annunciate.

the lead evaluator. cmAVRC03RCEPV100F_1 3 When directed by Key 3 Inadvertent Train B AFAS If called as Work Control or I&C, report you will write a the lead evaluator. mfRP06L1 PVAR and get a work order ready to troubleshoot the circuit.

mfRP06L2 4 When directed by Key 4 Fails the Seal Injection

If called as Work Control or I&C, report you will write a the lead evaluator. cmCNCV04CHNFIC243_2 f:100 Controller to 100 in AUTO PVAR and get a work order ready to troubleshoot the controller.

If directed to check Seal Injection filters wait 5 minutes then report that CHN-PDIS-244 indicates 12 psid.

5 When directed by Key 5 Faults NBN-X04 transformer If asked as an area operator to check PBB-S04, wait 3 minutes the lead evaluator. mfED10B and the DG output will fail to and report the only flags are Under-voltage flags.

cmBKEG03PBBS04B_3(in setup) close.

When directed to Key 21 Emergency stops the B DG

If at the DG wait 30 seconds then Emergency Stop the B emergency stop the rfEG21 f:STOP DG, if not already at the DG wait 2 minutes.

B DG

If requested report that PC cooling pump A is in service.

6 When directed by Key 6 Continuous CEA withdrawal the lead evaluator. mfRD10B (all modes).

7 (In setup) Multiple CEAs stick out on mfRD03G the trip.

mfRD03L mfRD03M Continued on next page Page 5 of 6

2012 NRC EXAM Scenario 3 Drivers page 8 (On RPSCHC trigger) Vacuum breaker opens cmAVMC01CDNHV45A_1 causing a loss of vacuum 9 When directed by Key 9 Trip of AFN-P01 If sent as area operator to check breaker, wait 4 minutes and the lead evaluator. mfFW21A report 86 lockout with a ground fault flag.

Page 6 of 6

Scenario 3 Overview This is a 2% power scenario.

Event 1 The CO will shift the Main Feed Pump B lube oil pumps.

Event 2 A pressurizer spray valve will fail open. The RO should address the alarm response procedure and take the selector switch for spray valves from both to the E spray valve position.

Event 3 Inadvertent Train B AFAS. This will require the CRS to enter 40AO-9ZZ17. The CO should override and close the Auxiliary Feedwater Valves to the SG. This will also require the CRS to address Tech Specs for the second Aux Feed pump tagged out.

The crew may have to reduce turbine load to clear the Core Operating Limit Supervisory System alarm due to a small power increase.

Event 4 Seal Injection flow controller for RCP 2A fails closed. The RO should address the alarm response procedure and place the controller in manual.

Event 5 A Loss of Power (LOP) to PBB-S04 (Train B class 4.16 kV bus) occurs. The DG starts but the output breaker will not close. The CRS enters 40AO-9ZZ12 and the crew emergency stops the B DG. A loss of letdown will probably occur. The CRS will address Tech Specs.

Event 6 CEAs will commence withdrawing. The crew should recognize there is no demand for the CEAs to withdraw. The CRS should enter 40AO-9ZZ11. The crew should place CEDMCS in standby and recognize that the CEAs are still withdrawing. The CRS should direct a reactor trip.

Event 7 On the trip, multiple CEAs will not insert, requiring the RO to borate per Standard Appendix 103.

Event 8 A loss of vacuum occurs. This will cause a loss of the SBCS and remove any availability of the Main Feedwater Pumps.

Event 9 After the crew enters the Rx Trip procedure, a trip of AFN-P01 will occur requiring the CRS to enter the Functional Recovery Procedure and energize PBB-S04 to recover Aux Feedwater Pump B.

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3_ Event No.: __1__

Event

Description:

_________Shift the MFP B Lube Oil Pumps________________________

Time Position Applicants Actions or Behavior T=0 CRS Directs the CO to shift the Main Feed Pump B lube oil pumps per 40OP-9FT02.

CO CO goes to section 4.9 of 40OP-9FT02 and performs the following:

Presses LON-HS-186A, FWPT Oil Pump Test Switch for FWPT B (B06).

Ensures the Auto Oil Pump (P07B) starts.

Releases the test switch.

Places the oil pump whose handswitch is in the AUTO position to the STOP position (LON-HS-126).

Places the handswitch for the oil pump that is in the STOP position to the START position (LON-HS-126).

When 15 seconds has elapsed since the pump in Auto was started, stops the oil pump that was originally running (LON-HS-124).

Places the handswitch for the oil pump that was originally running in the AUTO position (LON-HS-124).

Checks auto amber light is illuminated for BOTH oil pumps.

o Main Lube Oil Pump LON-P06B o Main Lube Oil Pump LON-P07B.

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __2__

Event

Description:

_________Pressurizer Spray Valve 100F Fails Open__ ____________

Time Position Applicants Actions or Behavior T= 8 Crew Notices RCS pressure lowering or receives an alarm on B03 (Window 1B) at 2160 psia.

Examiner Note: It will take ~ 6 minutes for the low pressure alarm to annunciate.

CRS Directs the RO to select the unaffected spray valve.

RO Addresses the alarm response procedure 40AL-9RK4A (window 1B) and performs the following:

Checks pressurizer pressure by observing indications on B04.

Determines that controlling channel has not failed.

Determines controller has not failed.

If only one main spray valve is a problem, selects the unaffected main spray valve (RCN-PV-100E) using RCN-HS-100-10 (B04).

Determines spray valve 100F has closed.

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3_ Event No.: __3__

Event

Description:

________Inadvertent Train B AFAS_______________________ _____

Time Position Applicants Actions or Behavior T = 14 Crew Receives alarms on B05B (Window 7B) and on RKN-UA-2B on B05.

CRS Enters 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations and performs the following:

Directs the CO to override and operate Auxiliary Feedwater Valves as needed to control steam generator level.

Informs chemistry that blow down is isolated.

Directs the CO or RO to enter the appropriate COLSS constants. (The CRS may elect not to perform this step because the secondary plant calculation is not being used at this power level).

Directs the CO or RO to perform Appendix C to check equipment actuated as expected.

Ensures compliance with Tech Specs for components that failed or were overridden. The CRS should enter LCO 3.7.5 condition c due to two AF pumps being inoperable.

CO Overrides and closes at least one B Train Aux Feed valve to secure feed SG 1 (B06).

AFB-HS-34A

AFB-HS-30A Enters zero for blowdown flow constants in both CPC and PC COLSS if directed.

Performs Appendix C-2 to check actuated equipment. (May be performed by RO).

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __4__

Event

Description:

______Seal Injection Flow Controller Fails__ _____________________

Time Position Applicants Actions or Behavior T = 24 Crew Receives alarms on B03 (Windows 11A and 11B).

CRS Directs the RO to take manual control of the RCP 2A seal injection flow controller.

RO Addresses the alarm response procedure 40AL-9RK3A and performs the following:

Determines which of the four seal injection valves has the LO flow (by indication on B03 or the alarm CRT). CHN-FIC-243 has full output.

Takes manual control of the 2A RCP flow controller, CHN-FIC-243, (B03) and adjusts seal injection flow to the normal value of 6.0 to 7.5 gpm (6.6 nominal) (B03).

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3_ Event No.: __5__

Event

Description:

_NBN-X04 fault causing a LOP on PBB-S04 (DG breaker fails to close)_

Time Position Applicants Actions or Behavior T = 30 Crew Receives alarms on B01 and other panels due to the loss of power to PBB-S04.

RO or CO Investigates power indications and determines PBB-S04 has lost power due to a fault on NBN-X04 and that DG B output breaker did not close.

CRS Enters 40AO-9ZZ12 Degraded Electrical and performs the following:

Goes to section 54.0.

Goes to Appendix N due to DG B running with the output breaker open.

Directs the operator to check DG B frequency and voltage.

Directs the operator to ensure PBB-S04K and PBB-S04L are open (normal and alternate supply breakers to PBB-S04)

Directs the operator to check that the 86 relays are not actuated for PBB-S04K and PBB-S04L.

Directs the operator to check that the 86 relay is not actuated for breaker PBB-S04B (DG B output breaker).

Directs the operator to place the synch switch on and close PBB-S04B, DG B output breaker.

Once it is determined the DG output breaker will not close, directs the operator to have an Auxiliary Operator emergency stop DG B.

Directs an operator to check NNN-D12 and D16 are energized (both are energized).

Directs an operator to ensure PNB-D26 and PND-D28 are energized (both are energized).

If additional charging pumps are needed, then direct the RO to start an additional charging pump.

Continued on next page Revision 1

Examiner Note: If the additional charging pump is not started in time, a loss of letdown will occur. PVNGS standards do allow the crew to take action per the expected alarm response on trend then verify actions in accordance with the ARP (B0310A). The CRS may hand of the Loss of Letdown AOP (40AO-9ZZZ05) to the Reactor Operator.

CRS

Directs an operator to ensure adequate CTMT Normal (continued) cooling.

Directs an operator to ensure adequate CEDM cooling.

Directs an operator to check which Spent Fuel Pool Cooling Pump was running.

Directs an operator to ensure In-plant communications are aligned to its normal source.

Directs an operator to ensure SA UPS Cabinet QFN-NO2 is aligned to its alternate source.

Directs an operator to perform 41ST-1ZZ02, Inoperable Power Sources Action Statement and 40ST-9EC03, Essential Chilled Water & Ventilation System Inoperable Action Surveillance.

Refers to PBB-S04 Loads table.

Directs an operator to bypass all parameters on Channel B or D PPS panels within 90 minutes.

Goes to Section 3.0 step 4.0 and addresses MCC and LC loads.

Addresses Tech Specs. CRS should enter numerous LCO associated with Section 3.8 (LCO 3.8.1 conditions a and b, 3.8.5 condition c).

RO Goes to B01 and performs the following:

Checks DG B frequency and voltage.

Ensures PBB-S04K and PBB-S04L are open (normal and alternate supply breakers to PBB-S04).

Checks that the 86 relays are not actuated for PBB-S04K and PBB-S04L.

Checks that the 86 relay is not actuated for breaker PBB-S04B (DG B output breaker).

Places the synch switch, PEB-SS-S04B, (B01) to ON.

Attempts to close PBB-S04B, DG B output breaker.

Determines that the PBB-S04B will not close and informs the CRS.

Directs the Auxiliary Operator to emergency stop DG B.

Revision 1

RO Addresses charging pumps and starts the E charging pump or a loss of letdown will occur.

If a loss of letdown occurs, the RO may get 40AO-9ZZ05, Loss of Letdown from the CRS and performs the following:

Places RCN-LIC-110, PLCS Master Control in MAN and closes the selected Letdown Control Valve (B04).

Checks that letdown backpressure is less than setpoint (B03).

Ensures no more than one charging pump running (B03).

Informs the CRS to enter LCO 3.4.9 condition a when pressurizer level is 56% or greater.

Goes to Appendix A to restore letdown.

Ensures at least one of the letdown isolation valves (CHB-UV-515, CHA-UV-516, or CHB-UV-523) are closed (B03).

Ensures the selected Letdown Control Valves are closed.

Ensures alarms are set on ERFDADS for Regin HX outlet temperature and Letdown backpressure.

Places CHN-PIC-201, Letdown Backpressure Controller in MAN and opens the backpressure control valves to 60%

output.

When the selected Letdown Control Valve is closed, ensures all of the following isolation valves are open (CHB-UV-515, CHA-UV-516, and CHB-UV-523) (B03).

Slowly adjust the Letdown Control Valve and Backpressure Control Valve to establish letdown flow.

Starts the second charging pump.

When level is at the setpoint, places controllers in auto.

Revision 1

CO

Checks NNN-D12 and D16 are energized (both are energized) (Various indication can be used to verify this).

Checks PNB-D26 and PND-D28 are energized (both are energized) (Various indications can be used to verify this).

Ensures adequate CTMT Normal cooling (B07).

Ensures adequate CEDM cooling (B07).

Directs an operator to check which Spent Fuel Pool Cooling Pump was running.

Directs an operator to ensure In-plant communications are aligned to its normal source.

Directs an operator to ensure SA UPS Cabinet QFN-NO2 is aligned to its alternate source.

Performs 41ST-1ZZ02, Inoperable Power Sources Action Statement and 40ST-9EC03, Essential Chilled Water &

Ventilation System Inoperable Action Surveillance.

Bypasses all parameters on Channel B or D (as directed by the CRS) PPS panels within 90 minutes.

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __6 __

Event

Description:

________Continuous CEA Withdrawal___________________________

Time Position Applicants Actions or Behavior T = 45 Crew Notices CEAs inserting or receives CEDMCS TRBL alarm on B04 (Window 8A) for continuous CEA Motion.

CRS Enters 40AO-9ZZ11, CEA Malfunctions and performs the following:

Directs an operator to place CEDMCS to Standby (B04).

Examiner Note: The CRS may direct placing CEDMCS in Standby prior to actually entering the Abnormal Operating procedure.

CRS

When it is determined that CEA motion is still continuing, (Continued) directs an operator to trip the reactor.

CO or RO Trips the reactor when directed by the CRS.

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __7 and 8__

Event

Description:

(7)_Multiple CEAs stuck out_________________________________

________________(8) Loss of vacuum ______________________________ _________

Time Position Applicants Actions or Behavior Standard Post Trip Actions T = 46 CRS Directs the crew to perform Standard Post Trip Actions.

When report received of CEAs not inserted, directs RO to borate the RCS using Standard Appendix 103.

When asked by CO, directs CO to use SBCS valves 1007/1008 or Atmospheric Dump Valves (ADVs) to control SG pressure.

Diagnoses a reactor trip and enters 40EP-9EO01, Reactor Trip.

RO Borates the RCS using Standard Appendix 103 by performing the following (assumes Attachment 103-A used):

(All actions performed on BO3)

Sets the boric acid makeup flow rate on CHN-FIC-210Y (Boric Acid Makeup to VCT Flow Controller) to 40 gpm or less.

Sets the Target makeup on CHN-FQIS-210Y (Boric Acid Makeup Totalized Flow Control) to a minimum of 5000 gallons.

Places CHN-HS-210 (Makeup Mode Select Switch) to BORATE.

Checks on Boric Acid Makeup pump is running.

Ensure CHN-UV-527, Makeup to CHRG PMPS is open.

Presses the START button on CHN-FQIS-210Y.

Adjusts flow to greater than or equal to 44 gpm.

continued on next page CRITICAL TASK: Crew establishes > 44 gpm boration prior to the completion of the SPTAs.

Revision 1

RO Reports the status of the Electric Plant (all buses energized with the exception of PBB-S04).

Reports status of pressurizer level and trend (trending to 33%).

Reports RCS Subcooling.

Reports status of seal injection and Nuclear Cooling Water to the RCPs (in service).

Reports status of RCS pressure (recovering to 2250).

Reports status of RCPs, Loop T, and RCS Subcooling.

Examiner Note: Some of these reports may be performed by the CO while the RO is establishing the Boration.

CO Verifies the Rx Control Safety Function and reports that more than one Full Strength CEA is not inserted.

Reports SG level and method of feed.

Reports Tcold and trend.

Uses SBCS valves 1007/1008 or ADVs to control SG pressure since vacuum has been lost.

Reports Containment pressure and status of the Radiation Monitors (may be done by the RO).

Reports Containment temperature and pressure (may be done by the RO)

Examiner Note: After the CRS has entered the Reactor Trip EOP, direct the driver to activate Key-9 causing a trip of auxiliary feed pump (AFN-P01).

Revision 1

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __9, __

Event

Description:

__Trip of AFN-P01__________________________________________

Time Position Applicants Actions or Behavior T = 57 Crew Determines AFN-P01 has tripped due to either SESS alarm (B02) or loss of flow indication/brighter than green light on handswitch for AFN-P01 (B06).

Functional Recovery Procedure CRS Determines that a loss of all feed water has occurred due to loss of MVAC.

Enters the Functional Recovery Procedure (40EP-9EO09) and performs the following:

Ensures the event is being classified.

Directs the RO to perform Appendix 16 for any running RCPs.

Directs the CO to ensure SG sample valves are open.

Direct Chemistry to perform their Abnormal Occurrence Checklist for the FRP.

Directs the RO to place the Train A Hydrogen Analyzer in service.

Identifies the success paths to be used to satisfy each safety function. MVAC-1 and HR-1 should be jeopardized.

Maintenance of Vital Auxiliaries (MVAC-1)

IF one vital 4.16 kV AC bus is energized from offsite power, AND the equipment needed to maintain Safety Functions is NOT available on the energized bus, THEN perform the following to cross-tie offsite power to the de-energized bus:

a. IF PBB-S04 is to be energized, THEN GO TO step 10 and perform the following:

continued on next page Revision 1

CRS Directs the RO to:

1. Place synchronizing switch PBB-SS-S04L, 4.16 KV Bus S04 Alternate Supply, to ON.

2. Close breaker PBB-S04L, 4.16 KV Bus S04 Alternate Supply.

3. Place synchronizing switch PBB-SS-S04L to OFF.

Directs the CO to start AFB-P01 and establish feedwater flow to the SGs.

Examiner Note: AFB-P01 will auto start and commence feeding SG#1 due to the inadvertent Train B AFAS earlier in the scenario.

RO Places synchronizing switch PBB-SS-S04L, 4.16 KV Bus S04 Alternate Supply, to ON. (B01)

Closes breaker PBB-S04L, 4.16 KV Bus S04 Alternate Supply.

(B01)

Places synchronizing switch PBB-SS-S04L to OFF.

CO Starts AFB-P01 by placing AFB-HS-16 to START (B06).

Establishes feedwater flow to the SGs by opening:

AFB-HS-35A

AFB-HS-31A

AFB-HS-34A

AFB-HS-30A CRITICAL TASK: Implement the FRP to restore power to PBB-S04 to establish AFW flow to the SGs prior to lifting the primary safeties.

Scenario termination: The scenario may be terminated when AFB-P01 is feeding a SG.

Revision 1

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __4 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event No. Malf. No. Event Type* Event Description 1 None N Shift Steam Bypass Master Controller, SGN-PIC-1010 from manual to automatic mode of operation.

CO/SRO 2 mfTRRX11SGCPT1013C_4 I Channel C SG 1 pressure transmitter fails low requiring multiple parameters to be placed in bypass. (SGC-PI-1013C)

CO/SRO (TS) 3 cmTRCV19RCALT110X_4 I Pressurizer level transmitter X fails low. Crew selects channel Y on pressurizer heater and level control selectors.

RO/SRO (TS) 4 mfCH01B C Loss of Control Element Drive Mechanism cooling. HCN-A02A and A02C fans fail to auto-start mfCH01D CO/SRO 40AO-9ZZ20, Loss of HVAC 5 mfMC01A R -RO Loss of condenser vacuum requiring the crew to downpower.

N - CO/SRO 40AO-9ZZ07, Loss of Condenser Vacuum 6 mfCV11A f:100 C RCP 1A seal failure. Crew evaluates the status of the affected SRO/RO RCP.

40AO-9ZZ04, Reactor Coolant Pump Emergencies 7 cmCPRC02RCEP01A_6 M RCP 1A trips but PPS fails to initiate a reactor trip. RO opens mfRP04A ALL L03B2 and L10B2 breakers on B01.

mfRP04C CRITICAL TASK - Trip the Reactor prior to completion of mfRD12A SPTAs 8 mfED02 M After the Reactivity Safety Function is addressed a Loss of mfEG06B ALL Offsite Power will occur. DG B will trip when it starts.

40EP-9EO07, Loss of Offsite Power/Loss of Forced Circulation 9 cmCPCC08SPAP01_5 C Spray Pond pump A fails to auto start.

RO/SRO CRITICAL TASK - Starts SPA-P01 prior to DG A running > 3 minutes with no cooling water.

CRITICAL TASK - Establish feed to at least one SG using AFN-P01.

40EP-9EO09, FRP (MVAC-3)

End Once the crew has verified point that Natural Circulation flow has been established

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 1 of 3

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Total malfunctions (5-8) 5

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 3

4. Major transients (1-2) 2

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 2 of 3

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

I&C have completed testing on the SBCS master controller SGN-PIC-1010 and it can be returned to automatic operation.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and b have been entered. Expected to return to service in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Planned shift activities:

Shift SGN-PIC-1010 from local/auto to remote/auto mode of operation.

3 of 3

2012 NRC EXAM Scenario 4 Setup Instructions

1. _____ Reset to IC-20

2. _____ Shift the CEDM fans to B and D running with A and C in standby.

3. ______Then Run scenario 2012 NRC Scenario 4 under Scenario scenario files from NRC exam thumb drive.

4. _____ Stage radios for operators.

5. _____ Alarm Silence to OFF.

6. _____ Ensure CVCS and DFWCS alarms are reset.

7. _____ Place the simulator in freeze until the crew enters the simulator.

8. _____ Hang Train B protected sign.

9. _____Hang Protected Equipment plaques near the handswitches for AF B and AF N.

10. _____Hang Protected Equipment plaques near the handswitch for CS B.

11. _____Place the SBCS Master Controller (SGN-PIC-1010) in AUTO and LOCAL.

12. _____ Review procedures listed on the next page for marks and missing pages:

Page 1 of 6 Rev 2

2012 NRC EXAM Scenario 4 40OP-9SF05, Operation of the Steam 40AL-9RK3A (Window 11B)

Bypass Control System (Section 4.4) 41AL-1RK5A (Windows 7C and 7D) 40AL-9RK5B (Windows 8C, 2D, 4D,8D, and 14A) 40AL-9RK4A (Windows 1A, 2A, 8A, 40AL-9RK7A (Windows 1A and 9B (Group 2B and 6B) E))

40AO-9ZZ07, Loss of Vacuum, 40AO-9ZZ04, RCP Emergencies (Section Section 4.0) 4.0) 40AO-9ZZ20, Loss of HVAC (Section 41AL-1ES2B (Window 6D - SEAS 21B) 10) 40EP-9EO01, SPTAs 40EP-9EO07, LOFC/LOOP 40ST-9ZZ10 available 40ST-9ZZ22 available Tech Specs (3.3.1, 3.3.5, 3.3.10 and 40EP-9EO09, FRP (MVAC-3) (possible) 3.3.11)

Page 2 of 6 Rev 2

2012 NRC EXAM Scenario 4 Driver Station Menu should look like this:

SCENARIOS TRIGGERS MALFS COMP REMOTES COMP I/O ALARM MALFS REMOTES OVERRIDES OVRDS 0 0 9:3 10:3 3 8 0:0 1:0 Complete list of malfunctions.

Malfs mfCH01B k:4 HCN-A02-B CEDM NOR ACU FAN MTR TRIP mfCH01D k:4 HCN-A02-D CEDM NOR ACU FAN MTR TRIP mfCV11A f:100 k:6 RCP-1A RCP #1 SEAL FAILURE mfED02 k:8 LOSS OF GRID mfEG06B k:8 d:15 DG-B DG DIFFERENTIAL RELAY TRIP mfMC01A k:5 f:8 SHELL A CONDENSER AIR INLEAKAGE mfRD12A BYPASS TRIP MG SET #1 OUTPUT CONTACTOR mfRP04A TCB-1 RTSG FAILS AS IS mfRP04C TCB-3 RTSG FAILS AS IS Comp Malfs cmBSEG02DGAPSL3_2 k:31 BISTABLE FAILS TO OPPOSITE STATE: DG A LUBE OIL PRESSURE SW LOW cmBSEG02DGAPSL5_2 k:31 BISTABLE FAILS TO OPPOSITE STATE: DG A LUBE OIL PRESSURE SW LOW cmBSEG02DGAPSL7_2 k:31 BISTABLE FAILS TO OPPOSITE STATE: DG A LUBE OIL PRESSURE SW LOW cmBSEG02DGAPSL9_2 k:31 BISTABLE FAILS TO OPPOSITE STATE: DG A LUBE OIL PRESSURE SW LOW cmCPCH03HCNA02A_5 FAIL TO AUTO-START: CEDM NORM ACU FAN A02A cmCPCH03HCNA02B_5 FAIL TO AUTO-START: CEDM NORM ACU FAN A02B cmCPRC02RCEP01A_6 k:7 SPURIOUS 86 LOCKOUT RELAY TRIP: REACTOR COOLANT PUMP 1A cmCPCC08SPAP01_5 FAIL TO AUTO-START: ESP PUMP A cmTRCV19RCALT110X_4 TRANSMITTER FAILURE BELOW BAD VALUE: XMTR LVL PZR k:3 LVL CONT cmTRRX11SGCPT1013C_4 TRANSMITTER FAILURE BELOW BAD VALUE: TRANSMITTER k:2 PRESSURE SG 1 Continued on next page Page 3 of 6 Rev 2

2012 NRC EXAM Scenario 4 Remotes rfED78 k:37 f:CLOSE SBOG 13.8KV SUPPLY BREAKER CONTROL rfED85 k:36 f:CLOSE SBOG 1 OUTPUT BREAKER STATUS rfFW57 OPR AUX FPT MAIN STM SPLY VLV rfFW59 MAN ACT OVSP TRIP OF AFA-P01 rfFW60B CONTROL POWER TO AFA-HV54 Comp Remotes crB2RH02SIAP03_2 RACK IN/OUT: CONTAINMENT SPRAY PUMP A f:RACK_OUT crB4RH02SIAUV664_1 BKR OPEN/CLOSE: CS PUMP A MINIFLOW VALVE f:OPEN crB4FW08AFAHV32_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4FW08AFAHV37_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4FW08AFAHV33_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4FW08AFAHV36_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4MS13SGAUV134_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN crB4MS13SGAUV138_1 BKR OPEN/CLOSE: AUX FW REG VLV PUMP A TO SG-1 f:OPEN ALARM OVRDS mfAN_1A02D1 k:31 DIESEL GENERATOR A LO PRIORITY TROUBLE f:ALARM_ON Page 4 of 6 Rev 2

2012 NRC EXAM Scenario 4 Drivers page EVENT TIME SYNTAX DESCRIPTION MISC.

1 The crew shifts the SBCS master controller to Remote-Auto.

2 When directed by the Key 2 Channel C SG #1 pressure When called as I&C or work control report that you will write lead evaluator. mfTRRX11SGCPT1013C_4 transmitter fails low a PVAR and start generating a Work Mech.

3 When directed by the Key 3 Pzr level Channel A transmitter When called as I&C or work control report that you will write lead evaluator. cmTRCV19RCALT110X_4 fails low. a PVAR and start generating a Work Mech.

4 When directed by the Key 4 Trip of the B and D CEDM fans. When called as Electrical or work control report that you will lead evaluator. mfCH01B (A and C will not auto start). write a PVAR and start generating a Work Mech.

mfCH01D If directed as the area operator to check the breakers for the B and D CEDM fan (PGB-L32E2 and PGB-L34D3 respectively),

wait 3 minutes and report both have an 86 lockout trip.,

5 When directed by the Key 5 Degrading vacuum in the A If sent as an area operator to check vacuum breakers and dog lead evaluator. mfMC01A f:8 Condenser shell. bone seals, wait 10 minutes and report that you have filled the vacuum breakers and have cut in water to the dog bone seals but have no overflow yet.

When directed to mrf MC01A f:0 When directed to reduce the leakage, report that you have reduce vacuum leak started getting overflow on the dog bone seals.

6 When directed by the Key 6 Failure on the #1 seal on RCP If called as engineering, report that you will be up to look at the lead evaluator. mfCV11A f:100 1A. seal indications as soon as you can.

7 When directed by the Key 7 Trip of the 1A RCP (ATWS will lead evaluator. cmCPRC02RCEP01A_6 occur).

8 After the crew opens Key 8 Loss of offsite power and B DG If asked to check B DG as area operator, wait 5 minutes and L03 and L10 and the mfED02 will trip 15 seconds later. report that you see nothing obvious.

CEAs insert.

mfEG06B d:15 9 (In setup) SP pump A fails to auto start.

cmCPCC08SPAP01_5 Continued on next page Page 5 of 6 Rev 2

2012 NRC EXAM Scenario 4 Drivers page If directed by the lead Key 31 Trips DG A If sent as area operator, report DG A temperature on high and evaluator (due to the cmBSEG02DGAPSL3_2 there is lube oil on the floor.

crew not starting SP cmBSEG02DGAPSL5_2 A pump) cmBSEG02DGAPSL7_2 cmBSEG02DGAPSL9_2 mfAN_1A02D1 f: Alarm_ON If directed to perform Run scenario file EOP Performs attachment 80A. 0 files/attach80a If directed to start a Key 36 Simulates energizing NAN-S07 SBOG and energize rfED85 NAN-S07 If directed to start a None Wait 2 minutes and report NAN-S03AB is closed.

close NAN-S03AB If directed to close Key 37 Simulates closing NAN-S07D NAN-S07D rfED77 Page 6 of 6 Rev 2

Scenario 4 Overview Event 1 The CO shifts the Steam Bypass Master Controller from manual to Remote Automatic.

Event 2 A failure of the Channel C SG #1 pressure transmitter. The CO should address the alarm response procedure. The CRS should address Tech Specs. The CO bypasses the correct parameters on the PPS cabinets.

Event 3 Pressurizer Level Transmitter X fails low. The RO addresses the alarm response procedure and selects the unaffected instrument.

Event 4 Loss of CEDM cooling fans A and C with the failure of the B and D to auto start. The CRS should enter 40AO-9ZZ20 and direct the CO to start the standby fans.

Event 5 Loss of condenser vacuum. The CRS enters 40AO-9ZZ07 and the crew downpowers to maintain vacuum.

Event 6 RCP 1A seal failure. The crew responds to B04 alarms and determines a seal has failed on RCP 1A.

Event 7 RCP 1A trips, but an ATWS occurs. The RO opens breakers on Board 1 to trip the reactor. The crew performs the SPTAs.

Event 8 After the crew addresses reactivity control, a loss of offsite power will occur and the B DG causing a loss of PBB-S04.

Event 9 The A Spray Pond pump will fail to auto start requiring the RO to start it manually.

Revision 1 Page 1 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4_ Event No.: __1__

Event

Description:

Shifting the Steam Bypass Master Controller, SGN-PIC-1010 from the Manual to Automatic mode of operation.________________________________________

Time Position Applicants Actions or Behavior T=0 CRS Directs the CO to shift the Steam Bypass Master controller from Local/Auto to Remote/Auto mode of operation..

CO Depresses the MAN pushbutton on the Steam Bypass Master controller, SGN-PIC-1010 (B06) and verifies that the pushbutton backlight illuminates.

Places the Remote/Local Setpoint Selector switch on the left side of the Master Controller to the R (Remote) position ensuring full movement of switch travel.

Examiner Note: There should be no adjustment of the steam modulation setpoint (black and white pointer)

Verifies that the steam header pressure (red pointer) is less than or equal to the SBCS modulation setpoint program (black and white pointer), THEN depress the AUTO pushbutton on the bottom of the Master Controller and ensure that the pushbutton backlight illuminates.

The Master Controller is now in Remote-Automatic, and its output will be a function of the SBCS modulation setpoint program.

Verifies that the Local-Automatic Setpoint (black pointer) thumbwheel on the right side of the Master Controller to 1170 psia.

Revision 1 Page 2 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4__ Event No.: __2__

Event

Description:

Channel C SG 1 pressure transmitter (SGN-PI-1013C 0 fails low.

Time Position Applicants Actions or Behavior T= 4 Crew Receives alarms on B05A windows 7C and 7D along with B05B windows 8C, 8D and 2D. Addresses alarm response procedure 41AL-1RK5A and 40AL-9RK5B.

CO Addresses the alarm response for window 7C (LO SG 1 PRESS CH Trip) and performs the following:

Determines SGC-PI-1013C has failed low

Verifies SG 1 level on B05 class indicators.

Determines SG 1 total feedwater/main steam flow on DFWCS monitor (B06)

Determines Tave on the Tave/Tref recorder, RCN-TR-100 (B04).

When directed, bypasses parameters 11, 18 and 19 on Channel C PPS cabinet behind B06.

Examiner Note: Although the SG-2 HI delta P bistable is tripped, there is no direction for the crew to bypass the parameter as the bypass is non-functional.

CRS Addresses Tech Specs and enters:

LCO 3.3.1 condition A.

LCO 3.3.5 condition A.

Refers to Tech Spec Bases and determines that in addition to the failed instrument SG 1 & 2 levels (ESF) must be placed in bypass.

Directs the CO to bypass parameters 11, 18 and 19 on Channel C PPS.

Revision 1 Page 3 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4__ Event No.: __3__

Event

Description:

Pressurizer level transmitter RCA-LT-110X fails low.______________ _

Time Position Applicants Actions or Behavior T= 14 Crew Receives alarms on B04 windows 1A (PZR TRBL) and 2B (PZR LVL HI-LO) and addresses alarm response procedure 40AL-9RK4A.

RO Diagnoses and reports that instrument RCA-LT-110X has failed low Addresses the Alarm Response procedure and performs the following:

Determines RCA-LI-110X has failed low

Places the following handswitches on B04 in Channel Y o RCN-HS-110, Level Control Selector Channel X/Y o RCN-HS-100-3, Heater Control Selector Level Trip Channel X/Y

Resets and energizing the proportional heaters by taking the following Pzr heater control handswitches on B04 to ON:

o RCN-HS-100-1 o RCN-HS-100-2 CRS Consults Tech Specs and enters:

LCO 3.3.10 Condition a

LCO 3.3.11 Condition a Revision 1 Page 4 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4__ Event No.: __4__

Event

Description:

Loss of Control Element Drive Mechanism cooling. HCN-A02B and A02D fail to auto-start.______ _______________________________

Time Position Applicants Actions or Behavior T= 26 Crew Receives alarms on B07 window 7A9B (CEDM ACU COOL SYS TRBL) and addresses the alarm response procedure 40AL-9RK7A.

CO Determines that no CEDM fans are running and uses the ARP or direction from the CRS to start the A and C fans using handswitch HCA-HS-49 (B07).

Directs the auxiliary operator to check breakers locally (PGBL32E2 and PGB-L34D3.

Examiner Note:

The crew may elect to wait for an auto-start of HCN-A02A/C.

The standby fans are designed to auto-start after a two minute time delay, however the auto-start has been blocked for this scenario.

RO Responds to alarms on SESS panel (Window 6D). Addresses the alarm response procedure.

CRS Directs the CO to start CEDM cooling fans HCNA02A AND A02C per either:

Loss of HVAC procedure, 40AO-9ZZ20 (Section 10).

Alarm response procedure, 40AL-9RK7A.

May performs brief to address the failure and contingencies.

Revision 1 Page 5 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4_ Event No.: __5__

Event

Description:

Loss of Condenser Vacuum requiring the crew to downpower._______

Time Position Applicants Actions or Behavior T= 32 Crew Receives alarms on B05 window 14A (CNDS SYS TRBL) and address the alarm response procedure 40AL-9RK5B.

CO Determines a loss of Vacuum is occurring in the A Condenser shell.

CRS Enters Loss of Condenser Vacuum, 40AO-9ZZ07 and performs the following:

Performs the diagnostic flow chart and goes to Section 4.0, Strategy/Power Reduction

Directs an auxiliary operator to:

o Place seal water on the condenser expansion joints (Dog-bone seals), vacuum breakers, and steam packing exhauster Condenser drain o Check for air in leakage at the condenser shells, operation of the gland seal regulators, etc.

Directs the CO to ensure ALL available air removal pumps are in operation CO Starts the D Air Removal pump using handswitch ARN-HS-28 (B07).

As directed, opens all Air Removal pump D suction valves using handswitches ARN-HS-14, 15 and 16 (B07).

Revision 1 Page 6 of 14

Examiner Note: A power reduction to improve condenser vacuum will only be effective for plant conditions impacting heat removal from the main condenser. A loss of vacuum due to air in-leakage can only be temporarily improved with a power reduction.

CRS Determines BOTH of the following:

Magnitude of the power reduction

The rate to reduce power Calculates the reactivity needed using ANY of the following:

Total gallons of boric acid and addition rate (53 gal/percent)

CEA insertion Directs the RO to commence a boration to reduce power if the CRS uses boration or may allow CEAs to insert in Automatic.

Directs the CO to lower turbine load and maintain Tavg/Tref mismatch 5°F or less.

Examiner Note: CRS may choose to use CEAs in Auto Sequential or Manual Sequential for the power reduction.

RO Commences a boration using 40OP-9CH01 at a rate and amount directed by the CRS by performing the following:

1. Sets the desired makeup flow rate on the Foxboro Controller, CHN-FIC-210Y on B03

2. If the makeup rate is greater than 40 gpm, set the makeup flow to not more than 40 gpm initially.

3. Select the Target makeup volume (gallons) on the Boric Acid Flow Totalizer CHN-FQIS-210Y on B03

4. Start the boration by:

a. Placing CHN-HS-210 on B03 to BORATE

b. Depress the RESET pushbutton on the Totalizer

c. Depress the START pushbutton on the Totalizer

5. Checks a boric acid pump started

6. Checks no flow on RMW flow indicator CHN-FIC-210X on B03 Revision 1 Page 7 of 14

RO 7. Ensures CHN-UV-527 opened by red lights lit on CHN-HS-(continued) 527

8. Checks flow increases on CHN-FIC-210Y on B03

9. If desired flow is > 40 gpm, raise the flow setpoint on CHN-FIC-210Y to the desired flow rate

10. Informs the CRS that the boration is started.

CO Lowers turbine load using the Load Limit Set potentiometer on B06 to maintain Tave within 5°f of Tref.

CRS When the vacuum leak is fixed, the CRS may direct the crew to stop the downpower.

RO Restores CVCS to a normal lineup when boration is stopped Examiner Note: After the crew has reduced power ~ 5% direct the driver to delete the Loss of Vacuum malfunction.

If the crew trips on this event, have the driver insert Event 6.

Revision 1 Page 8 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4__ Event No.: __6 __

Event

Description:

RCP 1A seal failure. Crew evaluates the status of the affected RCP._

Time Position Applicants Actions or Behavior T= Crew Receives alarms on B04 window 2A (RCP 1A TRBL) and address the alarm response procedure 40AL-9RK4A.

RO Monitors RCP 1A seal 2 inlet pressure at RCN-PI-152 (B04).

Observes a high pressure condition and determines that the first seal on RCP 1A has failed.

Verifies that RCN-HS-430, Controlled Bleed-Off valve, indicates open (B03)

CRS Enters Reactor Coolant Pump Motor Emergencies, 40AO-9ZZ04 and implements section 4, Abnormal Seal Parameters.

Directs the RO to verify Seal Injection flow is 6.0 to 7.5 gpm.

Verifies adequate Seal Injection and Nuclear Cooling water flow.

Determines that no RCP trip setpoints have been exceeded.

Contacts engineering to evaluate RCP parameters.

Revision 1 Page 9 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4_ Event No.: _7 _

Event

Description:

RCP 1A trips but PPS fails to initiate a reactor trip. RO opens L03B2 and L10B2 breakers on B01.______________________________________________________

Time Position Applicants Actions or Behavior T= Crew Recognizes that RCP 1A has tripped by alarms (B04 and B05).

Recognizes that a Reactor Trip should have occurred by all 4 channels of bistable trip indication on PPS parameter indications on B05 and/or first out annunciator indication on B04.

Attempts to trip the reactor using the RTSG pushbuttons, then opens the B2 breakers for L03 and L10 on B01 to trip the reactor using handswitches

NGN-HS-L03B2

NGN-HS-L10B2 CRITICAL TASK - Trip the Reactor prior to completion of SPTAs CRS Directs the crew to perform 40EP-9EO01, Standard Post Trip Actions Standard Post Trip Actions CO Reports the Reactivity Control Safety Function (CEAs inserted, power dropping, negative startup rate).

Examiner Note: Instruct the driver to insert the LOOP and DG B faults after the reactivity report is completed and all CEAs have fully inserted.

Report Main Turbine tripped and output breakers open.

Reports Tcold and trend.

Reports SG pressures and trends.

Reports Containment pressure and status of the Radiation Monitors (may be done by the RO).

Reports Containment temperature and pressure (may be done by the RO).

Revision 1 Page 10 of 14

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __4__ Event No.: __8 & 9 Event

Description:

_ (8) Loss of Offsite power and failure of DG B________________

_________________(9) Failure of SPA-P01 (SP-A) to auto start.___________________

Time Position Applicants Actions or Behavior Standard Post Trip Actions (continued)

T= Crew Observes a LOP on PBB-S04 due to a Loss of Offsite power and subsequent non-recoverable failure of DG B to start and load.

RO Reports the status of the Electric Plant:

Only AC bus energized is PBA-S03 being supplied by DG A with SP pump running following manual start.

All class and non-class DC buses are energized Examiner Note: Electric Plant report may be performed by the CO.

Reports status of pressurizer level and trend Reports RCS Subcooling.

Reports status of seal injection and Nuclear Cooling Water to the RCPs (in service).

Reports status of RCS pressure. (May need to use aux. spray as natural circulation flow develops)..

Reports status of RCPs, Loop T, and RCS Subcooling.

Evaluator Note:

1. If the crew fails to start SPA-P01 within 7.5 minutes then instruct the driver to insert Key 31 causing a trip of DG A (Key-31).

2. The crew will transition to the FRP.

Revision 1 Page 11 of 14

Loss of Offsite Power / Loss of Forced Circulation CRS Diagnoses a LOOP/LOFC (40EP-9EO07) and performs the following:

Confirms the diagnosis by directing the STA to perform the Safety Function Status Check.

Directs Chemistry to perform the Abnormal Occurrence Checklist.

Directs the SM to classify the event.

Verifies that loads have sequenced on at least one 4.16kV AC vital bus (PBA-S03)..

Directs RO to verify that seal injection is in service.

Directs the CO to actuate an MSIS.

Check that Tcold is being maintained less than 570°.

Inform RP that the unit is steaming to atmosphere.

Ensure at least one SG has level being maintained within or being restored to 45 - 60% NR.

CRITICAL TASK: Establish feed to at least one SG using AFN-P01.

Directs CO to verify natural circulation flow in at least one loop by ALL of the following:

Loop T is less than 65°F

Hot and cold leg temperatures are constant or lowering

RCS is 24°F or more subcooled using CET Subcooling

Less than a 30°F T between Th RTDs and the maximum quadrant CET temperature (QSPDS, pages 211 and 213)

Scenario termination: The scenario may be terminated when the AFW flow has been established to the SGs.

Revision 1 Page 12 of 14

Op-Test No.: _____ Scenario No.: __4__ Event No.: _____

Event

Description:

_ High temperature trip of DG A____(If Required)_____________

Time Position Applicants Actions or Behavior Functional Recovery Procedure CRS Determines that a loss of all feed water has occurred due to loss of MVAC.

Enters the Functional Recovery Procedure (40EP-9EO09) and performs the following:

Ensures the event is being classified.

Directs the RO to perform Appendix 16 for any running RCPs.

Directs the CO to ensure SG sample valves are open.

Directs Chemistry to perform their Abnormal Occurrence Checklist for the FRP.

Directs the RO to place the Train A Hydrogen Analyzer in service.

Identifies the success paths to be used to satisfy each safety function. MVAC-3 and HR-1 should be jeopardized.

Maintenance of Vital Auxiliaries (MVAC-3)

Opens the Placekeeper

Informs the Energy Control Center of Blackout

Directs the CO to actuate an MSIS.

NOTE The SBOGs cannot supply Units 2 and 3 simultaneously but can supply Unit 1 and 2 or Unit 1 and 3. All operations involving the SBOGs will be coordinated by Unit 1.

CRS continued Revision 1 Page 13 of 14

CRS

Directs the RO to place all of the charging pump handswitches in PULL TO LOCK.

Directs Appendix 80, Align SBOG to PBA-S03 (BO).

Directs Appendix 53, Align Deenergized Buses.

Once power is restored to PBA-S03, directs the CO to restore feedwater flow to the SGs using AFN-P01.

RO Performs Standard appendices 53 and 80 as directed CO Aligns AFN-P01 to feed SGs as directed.

CRITICAL TASK: Establish feed to at least one SG using AFN-P01.

Scenario termination: The scenario may be terminated when the AFW flow has been established to the SGs.

Revision 1 Page 14 of 14

ML12152A349

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