ML110140218

Initial Exam 2010-301 Draft Administrative JPMs

ML110140218
Person / Time
Site:	Watts Bar
Issue date:	10/19/2010
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/10-301
Download: ML110140218 (61)

Text

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam A.1-IRO&SRO Calculation of values required to raise RWST level.

PAGE 1 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam EVALUATION SHEET Task:

Calculation of values required to raise RWST level.

Alternate Path:

None Facility JPM #:

New Safety Function:

n/a

Title:

Conduct of Operations KIA 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Rating(s):

4.3/4.4 CFR:

41.10/43.5/45.2/45.6 Evaluation Method:

Simulator In-Plant Classroom

References:

SOI-62.02, Boron Concentration Control, Rev. 50 Task Number:

RO-062-SOI-62-018

Title:

Makeup to the RWST using the blender.

Task Standard:

The applicant performs SOI-62.02, Boron Concentration Control, Appendix B, Blending Greater Than 2500 ppm, and calculates:

1.) The amount of primary water to be entered into the PW integrator to be 1637 +/- 5 gallons.

2.) The amount of boric acid solution to be entered into the BA integrator to be 1363 +/- 5 gallons.

Validation Time:

10 minutes Time Critical:

Yes No X

Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam ToolslEguipmentlProcedures Needed:

The latest revision of SOI-62.02, Boron Concentration Control.

Calculator NOTE:

This JPM is designed to be performed in a classroom with procedures available to the applicant.

PACE 3011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1.

RWST level has been reported to be at 371,000 gallons.

2.

RWST boron concentration is currently 3100 ppm.

3. A problem in the makeup control circuit is currently limiting the maximum boric acid flow rate to 30 gpm.

4. You are an extra operator assigned to the shift.

INITIATING CUES:

I. The Unit Supervisor directs you to determine the amount of primary water and the amount of boric acid needed to raise RWST level to 374,000 gallons while maintaining the current boron concentration.

2. You are to notify Unit Supervisor when you have completed your determination of the amount of primary water and the amount of boric acid needed.

4 1W 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam STEPISTANDARD START TIME:

STEP 1: Obtain a copy of the procedure.

SAT STANDARD: A copy of SOl-62.02, Boron Concentration Control, Section UNSAT 8.1 is located by the applicant.

EXAMINERS CUE:After the applicant has demonstrated the method of obtaining the correct instruction, the examiner will provide a copy of the instruction.

NOTE Performance of this Section should be coordinated with performance of 1-TRI-62-3, Boric Acid Flow Paths: Valve Position Verification.

STEP 2:

[1] REFER TO one of the following methods to determine amount SAT of Primary Water (PW) & Boric Acid (BA) needed: (N/A method NOT used)

UNSAT

[1.1] IF blending at less than 2500 ppm, THEN USE TI-59.

[1.2] IF blending at 2500 ppm or greater, THEN USE Appendix B.

STANDARD:

Applicant determines from the INITIAL CONDITIONS that the blended solution is greater than 2500 ppm, and enters an N/A in Step 1.1.

Applicant locates Appendix B to continue the calculation.

COMMENTS:

Page 5 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT NOTE This Appendix should only be used in conjunction with Sections 6.5 or 8.1. Primary water flow must be varied to blend at concentrations greater than 2500 ppm; therefore, blending is only possible when 1-HS-62-140B, VCT MAKEUP MODE is in MANUAL.

STEP 3: From the Table on Page 2 of 2, the applicant locates the row SAT which contains the Desired Blend Concentration of 3100 ppm, and determines Primary Water flow rate to be 48 gpm.

UNSAT STANDARD:

Applicant reads the primary flow rate to be 48 gpm from the row for 3100 ppm.

COMMENTS:

Page 6 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 4: Calculates Required PW flow rate using the formula provided at SAT the bottom of Page 2 of 2 of Appendix B.

UNSAT STANDARD:

Applicant performs the caIcuation at the bottom of Page 2 of 2, and determines that the Required PW Flow Rate to be used with 30 gpm of Boric Acid Flow rate is 36 gpm.

For Boric Acid flow rates other than 40 gpm the following formula may be used:

Actual BA flow rate

=

Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X

PW flow rate from Table

=

Required PV flow rate 40 30 x

48 36gpm 40 COMMENTS:

Page 7 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC_Exam STEPISTANDARD SAT/U NSAT STEP 5: Calculates the amount of primary water to be entered into the PW CRITICAL integrator, by using the ratio of the primary water flow rate to the STEP total flow rate.

SAT STANDARD:

UNSAT Applicant determines the Total Flow rate to be 66 gpm by adding the primary water and boric acid flow rates together.

Applicant determines the total amount of primary water to be added by first calculating the percentage of flow due to primary water by dividing the primary water flow by the total flow, then multiplying the 3000 gallon change by that percentage. This results in 1637 gallons of primary water to be placed in the PW integrator.

Acceptable value: 1637 +/- 5 gallons.

Total Flow Rate

=

36 gpm

+

3D gpm

=

6 gpm 36gprn

=

0.54545 66 gpm 0.54546 X 3000 1 637 ga. PW Could also perform calculation:

3000 gal./66 gpm = 45.45 minutes 36 gpm x 45.45 mm. = 1636 gal. of PW Step is critical since the proper adjustment in primary flow rate is required to ensure proper blended solution is delivered to the RWST.

COMMENTS:

Page 8 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE Al-I RO & SRO 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: Calculates the amount of boric acid to be entered into the BA CRITICAL integrator, by using the ratio of the boric acid rate to the total flow STEP rate.

SAT STANDARD:

UNSAT Applicant determines the total amount of boric acid to be added by first calculating the percentage of flow due to boric acid by dividing the boric acid flow by the total flow, then multiplying the 3000 gallon change by that percentage. This results in 1363 gallons of boric acid to be placed in the BA integrator.

Acceptable values: 1363 +/- 5 gallons.

Total Flow Rate

=

36 gpm

+

30 gpm

=

66 gpm 30 gpm

=

0.45455 66 gpm 0.45455 X 3000 = 1363 gal. BA Could also perform calculation:

3000 gal.166 gpm 45.45 minutes 30 gpm x 45.45 mm. = 1364 gal. of PW Step is critical since the proper adjustment in boric acid flow rate is required to ensure proper blended solution is delivered to the RWST.

COMMENTS:

Page 9 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO & SRO 2010-08 NRC Exam STEP/STANDARD I_SATIUNSAT_I STEP 10:

Notify the Unit Supervisor that the primary water flow rate, SAT amount of boric acid and primary water have been determined.

UNSAT STANDARD:

Applicant informs the Unit Supervisor of the results of the calculations.

COMMENTS:

END OF TASK STOP TIME Page 10 of 11

r WBN Boron Concentration Control SOl-62.02 Unit I Rev. 0050 Page 49 of 62 Appendix B (Page 1 of 2)

Blending Greater Than 2500 ppm NOTE This Appendix should only be used in conjunction with Sections 6.5 or 8.1. Primary water flow must be varied to blend at concentrations greater than 2500 ppm., therefore, blending is only possible when 1-HS-62-140B, VCT MAKEUP MODE is in MANUAL.

(Table is continued on next page)

Desired Blend Boric Acid flow rate 1-FC-62-139 BA to Primary Concentration gpm*

Blender [1-M-6J %

Water Flow ppm.

rate gpm 2500 40 100 69 2550 40 100 67 2600 40 100 65 2650 40 100 63 2700 40 100 61 2750 40 100 59 2800 40 100 57 For Boric Acid flow rates other than 40 gpm the following formula may be used:

Actual BA flow rate

=

Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X

PW flow rate from Table

=

Required PW flow rate 40

WBN Boron Concentration Control 501-62.02 Unit I Rev. 0050 Page 50 of 62 Appendix B (Page2of2)

(Table is continued from previous page)

Desired Blend Boric Acid flow rate 1-FC-62-139 BA to Primary Concentration gpm*

Blender [I-M-6] %

Water Flow ppm.

rate gpm 2850 40 100 56 2900 40 100 54 2950 40 100 52 3000 40 100 51 3050 40 100 49

[

3100 40 100 48

3150 40 100 47 3200 40 100 45 3300 40 100 43 For Boric Acid flow rates other than 40 gpm the following formula may be used:

Actual BA flow rate

=

Required PW flow rate 40 PW flow rate from Table OR Actual BA flow rate X

PW flow rate from Table

=

Required PW flow rate 40 Required PW flow rate = (30/40) X 48 = 36 gpm Total flow rate = 30 gpm ÷ 36 gpm = 66 gpm Primary Water integrator setting

= (36 gpm / 66 gpm) = 0.54545

= 0.54545 x 3000 gallons = 1637 gallons of primary water Acceptable value: 1637 +1-5 gallons.

Boric Acid integrator setting

= (30 gpm / 66 gpm) = 0.45455

= 0.45455 x 3000 gallons = 1364 gallons of boric acid solution Acceptable value: 1364÷/-5 gallons.

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. RWST level has been reported to be at 371,000 gallons.

2. RWST boron concentration is currently 3100 ppm.

3. A problem in the makeup control circuit is currently limiting the maximum boric acid flow rate to 30 gpm.

4. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to determine the amount of primary water and the amount of boric acid needed to raise RWST level to 374,000 gallons while maintaining the current boron concentration.

2. You are to notify Unit Supervisor when you have completed your determination.

A.1-1 RO & SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2010-08 NRC Exam A.1-2 Determine Personal Protective Equipment Requirements and Pre-Job Briefing Requirements.

PAGE 1 OF 6

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 201 0-08 NRC Exam EVALUATION SHEET Task:

Determine Personal Protective Equipment Requirements and Pre-Job Briefing Requirements.

Alternate Path:

n/a Facility JPM #:

New Safety Function:

n/a

Title:

Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

Rating(s):

3.4/3.6 CFR:

41.10/45.12 Evaluation Method:

Simulator In-Plant Classroom

References:

1. Tl-300, Electrical Arc Flash Personal Protective Equipment & Protective Boundary Matrices, Rev. 6.

2. OPDP-1, Conduct of Operations, Rev.1 6.

3. TVA-SPP-1 8.005, Safety Procedure 6, Plan Jobs Safely.

Task Number:

RO-1 19-OPDP-1-008

Title:

Conduct a Pre-Job Brief Task Standard:

The applicant determines:

1.)The personal protective equipment/clothing requirements for the individual performing the breaker swap on the 1A Safety Injection Pump to be: ATPV 31 Flash Suit, ATPV 31 Flash Hood, natural fibers, safety glasses, hard hat.

2.) The pre-job briefing is to be conducted using SPP-18.005, Appendix C, NPG Pre-Job Briefing Checklist.

Validation Time:

15 minutes Time Critical:

Yes No X

Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 6

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 201 0-08 NRC Exam Tools/Equipment/Procedures Needed:

The latest revisions of:

TI-300, Electrical Arc Flash Personal Protective Equipment & Protective Boundary Matrices.

OPDP-1, Conduct of Operations.

Calculator.

NOTE:

This JPM is designed to be performed in a classroom with procedures available to the applicant.

PAGE 3 OF 6

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1.

Unit I is in Mode 3.

2. Electrical Maintenance has requested an AUO to swap the IA-A SI pump breaker with a spare to support surveillance testing to be conducted later in the shift.

INITIATING CUES:

You are to identify:

1. The personal protective equipment/clothing requirements for the AUO performing the breaker swap for the IA Safety Injection Pump.

2. The pre-job briefing requirements for the breaker swap.

PA(F 4 OF Ei

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2010-08 NRC Exam STEP/STANDARD I

SAT/UNSAT START TIME:

STEP 1:

Determine the personal protective equipment requirements CRITICAL for swapping the 1A Safety Injection Pump breaker.

STEP STANDARD:

SAT Using Tl-300, Electrical Arc Flash Personal Protective Equipment &

UNSAT Protective Boundary Matrices, the applicant determines the requirements to be:

ATPV 31 Flash Suit, ATPV 31 Flash Hood, natural fibers, safety glasses, hard hat.

COMMENTS:

STEP 2:

Determine the pre-job briefing requirements for the breaker CRITICAL swap.

STEP SAT STANDARD:

UNSAT Applicant determines from the Pre-Job briefing Guidelines contained in OPDP-1 that a brief using SPP-18.OOlAppendix C,NPG Pre-Job Briefing Checklist, is required for the evolution.

COMMENTS:

END OF JPM STOP TIME PAGE 5 OF 6

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is in Mode 3.

2. Electrical Maintenance has requested an AUO to swap the IA-A SI pump breaker with a spare to support surveillance testing to be conducted by later in the shift.

INITIATING CUES:

You are to identify:

a. The Arc Flash protective clothing requirements for the individual performing the breaker swap for the IA Safety Injection Pump.

b. The pre-job briefing requirements for the breaker swap.

A.1-2 RO & SRO

NPG Standard Conduct of Operations OPDP-1 Department Rev. 0015 Procedure Page 30 of 72 5.2 Operations Role in Effective Work Management (continued)

Shift Managers and Unit Supervisors use discretion when identifying items deemed as emergent work but once identified expect actions, owners and due dates/times for each emergent work item.

Shift Managers and Unit Supervisors hold all station organizations accountable to implement the schedule as published and ensure that plant conditions are established to support approved schedules. For critical systems/components (On-line: tech spec or maintenance rule. Outage: critical or near critical path) notify the work week manager or outage control center when equipment or systems are removed from service.

If not completed according to schedule SM/US expects a recovery plan to ensure timely return to service and sets this as a station priority.

Shift Managers and Operations Management actively participate in T+1 work week and post-outage critiques, identify lessons learned and takes actions to implement improvements.

Operations personnel hold all station organizations accountable for safe, error-free work and compliance with procedures. Unit Supervisors are expected to use Attachment 9, Work Authorization Questions, prior to authorizing work to verify that personnel are adequately prepared.

5.3 Briefings A.

Briefings are used to ensure communications occur, information is exchanged, individuals are properly focused on upcoming evolutions and that behaviors critical to safe, error free performance are reinforced. During a transient a briefing takes advantage of sharing team knowledge to respond to the transient.

1.

Pre-Job Briefs and Post-Job Critiques

• provides guidance in determining Pre-Job Brief requirements.

The forms and format from the referenced procedure should be used. The individual responsible for task performance is expected to prepare for the pre-job briefing and to lead the pre-job briefing. Post-Job Critiques should be performed for infrequently performed tasks or where a near miss or performance issue occurred or where the station could benefit from lessons learned in job efficiency and planning. Document lessons learned from Post-Job Critiques in a PER for further evaluation and disposition.

2.

Exceptions Repetitive activities performed as part of normal daily functions do not require briefings. The following is a listing of examples of activities that would not require a brief (list is not all inclusive):

AUO Round(s) (skill of the craft) Activities Housekeeping Activities Administrative Functions

NPG Standard Conduct of Operations OPDP-1 Department Rev. 0015 Procedure Page 31 of 72 5.3 Briefings (continued)

NOTE WA

- SPP-18.005 states the Post-job critiques are to be performed following any high hazard job, which is defined as a job that has caused or is likely to cause serious injuries / illness or death if not properly carried out. Refer to TVA

- SPP-1 8.005 for the requirements of performing a Post-job critique under these circumstances.

3.

Shift Turnover Brief Shift briefs are conducted at the beginning and middle of each shift. Shift Management directs the briefs. Personnel participation is required. See for Beginning of Shift Brief and Mid-Shift Brief.

If shift activities do not facilitate 100% crew attendance, a crew member knowledgeable of the watchstation status will provide turnover information on that watchstation.

4.

Event Based Brief Event Based Briefs are conducted as determined by the Unit Supervisor utilizing a format similar to that contained in Attachment 4. Event based briefs ensure that key information and strategies are communicated in a concise manner and that crew members are given an opportunity to share critical information.

5.

Crew Updates During many conditions the communication of important information to the crew may not need a scripted brief.

In these cases the Crew Update can be used.

If a crew member has information that should be known by the majority of crew members he/she passes this information in a concise manner by:

Obtaining the crews attention by stating crew update / crew announcement Ensuring crew members are listening through the use of raised hands or crew members stating ready.

Concisely announcing the information and Stating end of update.

NPG Standard Conduct of Operations OPDP-1 Department Rev. 0015 Procedure Page 62 of 72 (Page 1 of 6)

Pre-Job Briefing Guidelines NO NO NO Does the activity meet any of the following criteria?

- Requires interaction between multiple work groups?

- Involves transfer of potentially contaminated water?

- Requires entry into a Technical Specilication, Technical Requirement, ODCM, LCO Action Statement?

- Places Control Systems in MANUAL?

- Involves a potential

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam A.2 RO Perform 1-Sl-O-4, Monthly Surveillances, for the Auxiliary Control Room.

PAGE 1 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam EVALUATION SHEET Task:

Perform 1-SI-0-4, Monthly Surveillances, for the Auxiliary Control Room.

Alternate Path:

N/A Facility JPM #:

New Safety Function:

Title:

12&

2.2.12 Knowledge of surveillance procedures.

Rating(s):

3.7/4.1 CFR:

45.10/45.13 Evaluation Method:

Simulator X

In-Plant Classroom

References:

1-S1-0-4, Monthly Surveillances, Rev. 24.

Task Number:

RO-1 1 3-GEN-004

Title:

Perform surveillance tests.

Task Standard:

A.

Applicant performs data collection for Appendix D, pages 5,6, and 13 of 1-SI-0-4, Monthly Surveillances. and identifies that the following instruments do not meet the acceptable range identified in the instruction:

1.) 1-Ll-68-326C PZR PRESS.

2.) 1-Pl-62-81C LP LETDOWN PRESS.

B. Applicant determines that 1-Fl-62-93C CHARGING FLOW exceeds the 20 gpm limit which requires calibration of the flow instrumentation. Applicant states that a Work Order must be prepared and the number recorded in REMARKS.

Validation Time:

10 minutes Time Critical:

Yes No X

Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. The Unit is in Mode 1, with no LCO entries at this time.

2. Portions of the field data have been entered by NAUOs.

3. You are the Unit Operator responsible to perform and review 1-Sl-0-4, Monthly Surveillances.

INITIATING CUES:

1. You are to complete 1-Sl-O-4, Monthly Surveillances, Appendix D, pages 5, 6, and 13 for 1-L-10. Another Unit Operator will complete the remainder of Appendix D.

2. When you have finished performing the assigned pages of Appendix D, and addressed any deviations, notify the Unit Supervisor that you have completed your task.

PAGE 3011

WATTS BA r NUCLEAR PLANT JOB PERFOr(MANCE MEASURE A.2 RO 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1.

ENSURE NRC Examination Security has been established.

2.

Right click on 315, and then select RESET.

3.

Enter the password.

4.

Select Yes on the INITIAL CONDITION RESET pop-up window.

5.

ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value pi-68-336c 05350 rcs pressurizer press 0

00:00:00 00:00:00 00:00:00 2210 2210 fi-62-93c 28180 chg hdr flow cont 0

00:00:00 00:00:00 00:00:00 79.25 79.244 pi-62-81c 28275 let dwn hx press md 0

00:00:00 00:00:00 00:00:00 380 379.000 6.

Place simulator in RUN and acknowledge any alarms.

7.

Place simulator in FREEZE. This JPM is to be conducted on a dead board.

PAGE 4011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A2 RO 2010-08 NRC Exam STEP/STANDARD I

SAT/UNSAT START TIME:

rEM REFERENCE REQUIRED NOTES DESCRIPTION LCC INST NO READING LCC INST NO READING DATA MCD NO.

NJMBER MODE UNITS 4

SR 3331-25 1.2.3 5) 26 press 164 I_PI_1-2A 1-LID 1-PI-I-IC q

60 5540 SR3,3,4.t-I.e 1.2.3 17)

262 press 1-Fl-s i-L-10 1-FI-l-OC 1-PI.1-20A 1010 SC 3 Press 1-U-4 1-01-1-2DB l-L-10 1-Pl-1-ISC 1-Pl-1-272 1010 SG Press 1-124 1-PI-i-27B 1010 IL-iS 1-PI-l-26C EXAMINERS CUE: Provide a marked-up copy of 1-SI-O-4 to the applicant. All data for the main control room panels is filled in (1-M-1 through 1-M-15, 0-M-27A).

EXAMINERS CUE: 1-SI-0-4, Appendix D, pages 5, 6 and 13 are attached as the key to this JPM. Values which fall outside the MCD are circled on the key.

STEP 1:

PERFORM 1-Sl-0-4, Monthly Surveillances, Appendix D, SAT Item 4, Steam Generator Pressure, data collection and determine if acceptance criteria are met.

UNSAT STANDARD:

Appicant obtains current readings for SG Pressure and records them on the data sheet records values on the data sheet, and determines that the values are within their respective Maximum Channel Deviation (MCD) values.

COMMENTS:

PAGE5OF11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 201 0-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 2.

PERFORM 1-SI-0-4, Monthly Surveillances, Appendix D, SAT Item 6, Pressurizer Level, data collection and determine if acceptance criteria are met.

UNSAT ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING I

LOG INST NO READING DATA MCD NO.

NUMBER MODE I

UNITS 6

SR 3.3.2.1-14 I, 2. 2 NA I-LI-66-339A S

I

-LI-SS-323G SR 33.4.I-3.a P2R LEVEL 144-4 1-U-6E-335A 6C I-L-10 i-LI-ES-326C 60%

I-LI-66-220 se N/A N/A STANDARD:

Applicant obtains current readings for PZR level and records values on the data sheet, and determines that the values are within their respective Maximum Channel Deviation (MCD) values.

COMMENTS:

PAGE6OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4:

PERFORM 1-Sl-0-4, Monthly Surveillances, Appendix D, CRITICAL Item 7, Pressurizer Pressure data collection and STEP determine if acceptance criteria are met.

SAT 7

SR 3.3(1-5 12,3 (8) 1-01-56-3408 2236

SR 3.3.1.1-la 1-01-66-334 223$

I-I-6-33sC 028 PRESS i*t*O p

123 2240*

psig 50 ps 1:pi;22 l--63-337C UNSAT (Si PZR-COLD C.$L I-tA-S

(-01-66-3428 2236 I-L-IS I-°I-3-3-22C PR 0

SS P510 200 950 uS)

LODP 4 HL PRESS 1-PI-66-7S 225$

NA N,A 0)0 3 HI 08055 I-MS

(-p1-05-64 2258 NA (SA NIS LOP I HLPRESS

-P1-68-62 2250 P2,5 NIS O3e05008 InISaIS

-lAS Operators Initials STANDARD:

Applicant enters 2150 psig (ACCEPT 2140 -2160 psig) for 1 -Pl-68-336C.

_____ pp determines that PZR pressure channel 1-Pl-68-336C is NOT within Maximum Channel Deviation (MCD) of 50 psig.

(Critical).

Applicant may report that I -PI-68-336C does not meet MCD limit at this point, or wait until all data is collected.

Step is critical to ensure that the appropriate Tech Spec Actions are entered.

COMMENTS:

PAGE 7 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP/STANDARD SAT/U NSAT STEP 5:

PERFORM 1-SI-0-4, Monthly Surveillances, Appendix D, SAT Item 25 data collection and determine if acceptance criteria are met.

UNSAT 25 5653.3.4.1-3.3 1.23 J

(521 C-i4961N55_O3V J

i-ii-s J

80 j

1-L-55 1-51-62-533 gpn J4005n1]

STANDARD:

Applicant enters 110 gpm (Accept 105 to 115 gpm) for 1 -Fl-62-93A.

Applicant determines that CHARGING FLOW channel 1-Fl-62-93A is within Maximum Channel Deviation (MCD) of 40 gpm, but does not meet the 20 gpm requirement given in Note (32).

From the Table, the applicant determines that requirement of Note (32) is not met, and requests that a Work Order be prepared to initiate calibration of the flow instrumentation.

COMMENTS:

STEP 5:

Perform 1-Sl-0-4, Monthly Surveillances, Appendix D, SAT Items 26 through 28 data collection and determine if acceptance criteria are met.

UNSAT 5

LCU 3.3.4 1,2.3 (32(

1-31-5

(-5-52-324 2370 1-1-10 1-51-02-923 01(5 27 LCO 3.3.4 1, 2.3 321 MER2 608670 1-FI-62-137A 0

i-t-i 1-51-62-1373 gpm 75 gpr SR p3 3 b 1

2 3 I

I LEC NX 1

TI-S 7

92

1. 13 I

I

-uSC F

F STANDARD:

Applicant obtains current readings for charging header pressure, emergency boration flow, letdown heat exchanger outlet temperature and determines that all parameters are within their respective Maximum Channel Deviation (MCD) values.

COMMENTS:

PAGE 8011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6:

Perform 1-Sl-0-4, Monthly Surveillances, Appendix D, CRITICAL Item 29 data collection and determine if acceptance STEP criteria are met.

SAT LCD 3.34 1,2.3 321 LPLTCODN 1-11-5 J

330 1-1-12 1-5162-SiC PlO 3

3P112 UNSAT STANDARD:

Applicant enters 370 psig (Accept 360-380 psig) for 1-Pl-62-81C.

_____ pp determines that LP Letdown Pressure channel 1-Pl 810 is NOT within Maximum Channel Deviation (MCD) of 30 psig.

(Critical).

From the Table, the applicant determines that LCO 3.3.4 must be entered, and may report that 1 -P1-62-810 does not meet MCD limit at this point.

Step is critical to ensure that the appropriate Tech Spec Actions are entered.

COMMENTS:

PAGE9OF 11

STEP/STANDARD Onerators nhrtats 000rators trials SAT/U NSAT SAT UNSAT STANDARD:

Applicant obtains current readings for VCT level and ERCW supply header flows and records them on the data sheet and determines that all parameters are within their respective Maximum Channel Deviation (MCD) values.

COMMENTS:

Applicant reports status of 1-Sl-O-4, Monthly Su rye illances.

Applicant reports that the following instruments do not meet their MCD limits:

1.

1-Pl-68-336C PZR PRESS -fails to meet SR 3.3.3.1-5 and 3.3.4.1-2.a.

2.

1-Pl-62-81C LP LETDOWN PRESS fails to meet LCO 3.3.4.

Applicant reports that 1-Fl-62-93C CHARGING FLOW exceeds the 20 gpm limit which requires calibration of the flow instrumentation. Applicant states that a Work Order must be prepared and the number recorded in REMARKS.

COMMENTS:

STOP TIME WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2010-08 NRC Exam STEP 7:

Perform 1-SI-0-4, Monthly Surveillances, Appendix D, Items 30 and 31 data collection and determines if acceptance criteria are met.

2C LCO 3.3.4 1, 2,3 32 J

CL5V8I iM-S i-LI-52.121,5 20 t-L-tO ILt62-I25C 5%

31 LCO 3 3.4 1.2.3 2

34.1-27A 1-FI-37Sl 1390 tL-tO 1-Fl-7-0lC 9R,.3tP 3-M27A t-Fl-5762 io i-I-hr 1-F-e7-62c 2-M-27A 8000 2-1-13 2-Fl-57-61C 0

O-M27A 2-Fl-i752 5150 2-1-10 2-FI6762C HAD STEP 10:

STANDARD:

SAT UNSAT PAGE 10 OF 11

WBN Monthly Surveillances I -SI-0-4 Unit I Rev. 0024 Page 46 of 74 Appendix D (Page 5 of 15)

Remote Shutdown and PAM Channel Check Data Sheet Data Package: Page of 15 Date Today 1.0 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)

Mode 1

ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA MCD NO.

NUMBER MODE UNITS 4

SR 3.3.3.1-25 1, 2, 3 (5) 1-Pl-1-2A 1000 psig 80 psig SG 1 Press 1-M-4 1-L-10 1-PI-1-1C 1000 SR3.3.4.1-4.c (6) 1-Pl-1-2B SR3.3.4.1-4.e 1, 2,3 (7) 1-PI-1-9A 1010 SG2Press 1-M-4 1-L-10 1-PI-1-8C 1020 1-Pl-1-9B 1-PI-1-20A 1010 SG 3 Press 1-M-4 1-L-10 1-Pl-1-19C 1010 1-Pl-1-20B 1010 1-PI-1-27A 1010 SG4Press 1-M-4

1-L-10 1-PI-1-26C 980 1-Pl-1-27B 1010 5

SR 3.3.3.1-15 1, 2, 3 N/A SG 1 WR LEVEL 1-M-4 1-LI-3-43A SG 2 WR LEVEL 1-M-4 1-Ll-3-56A N/A N/A N/A N/A SG 3 WR LEVEL 1-M-4 1-LI-3-98A SG4WR LEVEL 1-M-4 1-Ll-3-111A Operators Initials Operators Initials 5)

Verification is performed by reading and recording the indication of the SG press indicators for each SG, two on 1-M-4 and one 1-L-10.

(6)

The SG Pressure indicators are dual scale with pressure on the right and Saturation Temperature on the left. Data for this parameter is to be taken on the right side indication.

(7)

SG press indication on 1-L-10 is used as a dual purpose indicator.

It will be used to determine SG Tsat indication as required for SR 3.3.4.1-4e Remarks:

WBN Monthly Surveillances 1-Sl-0-4 Unit I

Rev. 0024 Page 47 of 74 1.0 Appendix D (Page 6 of 15)

Remote Shutdown and PAM Channel Check Data Sheet Mode Ii

\\

xceeds the MCD of 50 psig (8)

Remote Shutdown requires PZR PRESS or RCS WR RANGE PRESS, but both are NOT required to satisfy SR 3.3.4.1-2.a.

(9)

PZR COLD CAL PRESS is to be considered the same as RCS WR RANGE PRESS.

(10)

If 1-PI-68-70 is out-of-tolerance, MIG is to be notified to perform 1-SI-68-88.

6 15 Today Data Package: Page of Date REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)

ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOC INST NO READING LOC INST NO READING DATA MCD NO.

NUMBER MODE UNITS 6

SR3.3.31-14 1,2,3 N/A 1-LI-68-339A 60 1-Ll-68-325C 61 SR 3.3.4.1-3.a PZR LEVEL 1-M-4 1-LI-68-335A 60 1-L-10 1-Ll-68-326C 59 6.0%

1-Ll-68-320 58 N/A N/A 7

SR 3.3.3.1-5 1, 2, 3 (8) 1-Pl-68-340A 2235 1-PI-68-336C SR 3.3.4.1-2.a 1-Pl-68-334 2235_

PZR PRESS 1-M-5 1-L-10 psig 50 psig 1-PI-68-323 2240 I -Pl-68-337C 2240\\

1-PI-68-322 2235 (9)

PZR-COLD CAL 1-M-5 1-PI-68-342A 2235 1-L-10 1-Pl-68-342C 2250 psig 200 psig PRESS (10)

N/A N/A LOOP 4 HL PRESS 1-PI-68-70 2250 N/A N/A LOOP 3 HL PRESS 1-M-6 l-Pl-68-64 2250 N/A N

LOOP I HL PRESS 1-PI-68-63 2250 N/A N/A Operators Initials Operators Initials PI-68-336C

WBN Monthly Surveillances 1-SI-0-4 Unit I Rev. 0024 Page 54 of 74 Appendix D (Page 13 of 15)

Remote Shutdown and PAM Channel Check Data Sheet Date Today 1-Fl-62-93C does not exceed the MCD of 40 gpm, but does require action to initiate a Work Order to calibrate the flow instrumentation per Note (32).

READING,/

UNITS MCR indications are recorded for comparison purposes only. The following requirement is applicable to Item 25 (Charging Flow) ONLY:

If channel deviation is greater than 20 gpm, action shall be initiated to calibrate the flow instrumentation. WO no. shall be recorded in REMARKS.

ll-PI-62-81C exceeds the MCD of 30 psig Descriptions for the Remote Shutdown board instruments:

A. 1-Tl-67-61C, SUP HDR A FLOW.

B. 1-TI-67-62C, SUP HDR B FLOW.

C. 2-TI-67-61C, SUP HDR A FLOW.

D. 2-Tl-67-62C, SUP HDR B FLOW.

1.0 Data Package: Page 13 of 15 REMOTE SHUTDOWN AND PAM CHANNEL CHECKLIST (continued)

ITEM REFERENCE REQUIRED NOTES DESCRIPTION LOG INST NO READING LOC INST NO NO.

NUMBER MODE Mode DATA MCD 24 SR 3.3.3.1-26 1,2, 3 N/A AB PASSIVE 1-M-15 0-LI-77-134 12 N/A N/A/

4.8 N/A in.

SUMP LEVEL O-LI-77-135 12 N/A N/,

in. WC 25 SR p3.3.4.1-3.b 1,2, 3 (32)

CHARGING FLOW 1-M-5 1-Fl-62-93A 80 1-L-10 1-Fl-62-93C gpm 40 gpm 26 LCO 3.3.4 1,2, 3 (32)

CHARGtNG 1-M-5 1-l62-92A 2370 1-L-10 1-Pl-62-92C 2410 psig 150 HDR PRESS psig 27 LCO 3.3.4 1,2, 3 (32)

EMERG BORATE 1-M-5 1-FI-62-137A 0

1-L-10 1-FI-62-137C 0

gpm 7.5 gpm FLOW 28 SRp3.3.4.1-3.b 1,2,3 (32)

LETDOWN HX 1-M-6 1-TI-62-78 92 1-L-10 1-TI-62-80C 92

°F 6°F OUTLET TEMP 29 LCO 3.3.4 1,2, 3 (32)

LP LETDOWN 1-M-6 1-PI-62-81 320 1-L-10 1-Pl-62-81C psig 30 psig PRESS 30 LCO 3.3.4 1,2, 3 (32)

VCT LEVEL 1-M-6 1-Ll-62-129A 28 1-L-10 1-LI-62-1 290 8

6%

31 LCO 3.3.4 1,2,3 (32) 1A ERCWSUP 0-M-27A 1-Fl-67-61 1390 1-L-10 1-Fl-67-61C 1f00 (33)

HDR FLOW 1 B ERCW SUP 1-F 1-67-62 0-M-27A 1430 1-L-10 1-FI-67-62C 1

00 HDR FLOW gpm l000gp 2A ERCW SUP 2-Fl-67-61 m

0-M-27A 8000 2-L-10 2-Fl-67-61C HDR FLOW 2B ERCW SUP 2-FI-67-62 0-M-27A 5150 2-L-10 2-FI-67-62C HDR FLOW

(32)

(33)

Remarks:

Operators Initials Operators Initials

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. The Unit is in Mode 1, with no LCO entries at this time.

2. Portions of the field data have been entered by NAUO5.

3. You are the Unit Operator responsible to perform and review 1-SI-O-4, Monthly urye i Ilances.

INITIATING CUES:

1. You are to complete 1-SI-O-4, Monthly Surveillances, Appendix 0, pages 5, 6, and 13 for 1-L-1O. Another Unit Operator will complete the remainder of Appendix D.

2. When you have finished performing the assigned pages of Appendix D, and addressed any deviations, notify the Unit Supervisor that you have completed your task.

A.2 RO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 201 0-08 NRC Exam A.2 SRO Determine a Technical Specification Completion Time Extension Page 1 of 5

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A2 SRO 201 0-08 NRC Exam EVALUATION SHEET Task:

Determine a Technical Specification Completion Time Extension.

Alternate Path:

n/a Facility JPM #:

New Safety Function:

n/a

Title:

Equipment Control KIA 2.2.42 Ability to track Technical Specification limiting conditions for operations.

Rating(s):

3.1/4.6 CFR:

41.10 / 43.2 / 45.13 Evaluation Method:

Simulator In-Plant Classroom

References:

Watts Bar Nuclear Plant Technical Specifications, All Amendments through Amendment 81. 1.3, Completion Times. LCD 3.5.2, ECCS

- Operating.

Task Number:

SRO-1 1 9-SSP-1 2.56-005

Title:

Evaluate status changes for Tech. Spec.

equipment to determine if LCD action statement entry is required.

Task Standard:

The applicant determines the LATEST date and time that Unit must be placed in Mode 4 if the lB-B Safety Injection pump cannot be restored to OPERABLE STATUS to be 1900 on 7/6/2010.

Validation Time:

10 minutes Time Critical:

Yes No X

Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

I NAME SIGNATURE DATE COMMENTS Page2of5

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2010-08 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The unit is at 100% power.

2. Todays date is July 4, 2010. The time is 0700.

3. On July 2, 2010 at 0700, the IA-A Safety Injection pump was declared INOPERABLE.

4.

LCO Action Statement 3.5.2.A, One or more trains inoperable AND at least 100%

of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.

5. The I B-B Safety Injection pump was declared INOPERABLE today at 0700, and LCO 3.0.3 was entered.

6. At 0900 on July 4, 2010, the IA-A Safety Injection pump was declared OPERABLE.

INITIATING CUE:

You are to determine the LATEST date and time that Unit must be placed in Mode 4 if the I B-B Safety Injection pump cannot be restored to OPERABLE STATUS.

Page 3 of 5

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2010-08 NRC Exam STEP/STANDARD I

SATIUNSAT START TIME:

STEP 1:

Application of Technical Specifications 1.3, Completion Times, CRITICAL to the return of the IA-A Safety Injection pump to service at STEP 0900 on July 4, 2010.

SAT Application of Technical Specifications 3.5.2.B, Required Action and Completion Time not met, and determination of UNSAT time to place the Unit in Mode 4.

STANDARD:

Applicant determines that LCO 3.0.3 can be exited at 0900 on 7/4/2010.

Applicant determines from the second INITIATING CUE that the conditions described in Tech Spec Section 1.3,Completion Times have been met.

Applicant determines that the total Completion Time is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> added to the initial entry into LCD 3.5.2 Condition A. Initial entry July 2, 2010 at 0700. Thel B-B SI pump must be restored to OPERABLE status before 0700 on 7/6/2010.

Applicant determines LCD 3.5.2 Condition B cannot be met, and that the Unit must be placed in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, with the time starting at 0700 on 7/6/2010. Therefore, the Unit must be in Mode 4 by 1900 on 7/6/2010.

Step is critical to ensure equipment is returned to service within the times allowed in Technical Specifications.

COMMENTS:

END OF TASK STOP TIME

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The unit is at 100% power.

2. Todays date is July 4, 2010. The time is 0700.

3. On July 2, 2010 at 0700, the IA-A Safety Injection pump was declared INOPERABLE.

4.

LCO Action Statement 3.5.2.A, One or more trains inoperable AND at least 100%

of the ECCS flow equivalent to a single OPERABLE ECCS train available, was entered at that time.

5. The I B-B Safety Injection pump was declared INOPERABLE today at 0700, and LCO 3.0.3 was entered.

6. At 0900 on July 4, 2010, the IA-A Safety Injection pump was declared OPERABLE.

INITIATING CUE:

You to determine the LATEST date and time that Unit must be placed in Mode 4 if the lB-B Safety Injection pump cannot be restored to OPERABLE STATUS.

A.2 SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3R0&SRO 2010-08 NRC Exam A3R0&SRO Calculate Maximum Permissible Stay Time Within Emergency Dose Limits PAGE 1 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam EVALUATION SHEET Task:

Calculate Maximum Permissible Stay Time Within Emergency Dose Limits Alternate Path:

n/a Facility JPM #:

New Safety Function:

n/a

Title:

Radiation Control K/A 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Rating(s):

3.2/3.7 CFR:

41.12/43.4/45.10 Evaluation Method:

Simulator In-Plant Classroom

References:

EPIP-15, Emergency Exposure Guidelines, Rev. 13.

Task Number:

AUO-119-SSP-5.01-001

Title:

Control personnel radiation exposure.

Task Standard:

Applicant calculates the maximum permissible stay time within Emergency Dose Limits to be 50 minutes (+/- 5 minutes).

Validation Time:

10 minutes Time Critical:

Yes No X

Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMMENTS PACE 2 OF A

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 201 0-08 NRC Exam Tools/EciuipmentlProcedures Needed:

EPIP-1 5, EMERGENCY EXPOSURE GUIDELINES.

Calculator.

NOTE:

This JPM is designed to be performed in a classroom with procedures available to the applicant.

PAGE 3 OF R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A loss of coolant accident is in progress.

2.

ECA-1.1, Loss of RHR Sump Recirculation, has been entered.

3. Automatic swap over to the containment sump has failed to occur.

4. The Auxiliary Building AUO has been dispatched to perform the following tasks:

TASK TIME DOSE RATE I

Go to task performance area.

12 minutes 0.5 RIhr 2

Remove cover from enclosure for I-FCV 54 minutes 9 RIhr 72, CNTMT SUMP TO RHR PMP A SUCT.

3 Manually open 1-FCV-63-72, CNTMT SUMP TO 20 RIhr RHRPMPASUCT.

4 Return from task performance area.

0.5 RIhr

5. Authorization to exceed occupational dose limits to restore critical safety functions has been approved by the Shift Manager (SED) for the Auxiliary Building AUO.

NOTE: Assume the time to travel from the task is equal to the time required to arrive at the task location.

INITIATING CUES:

The Auxiliary Building AUO has completed Tasks I and 2 in the time listed. You are to determine:

I. The amount of time the AB AUO has to complete Task 3 without exceeding his Emergency Dose Limit.

2. What restrictions, if any, are imposed on the AB AUO after receipt of the emergency exposure?

PA(F 4 OF R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam STEP/STANDARD SATIUNSAT START TIME:

STEP 1: Applicant reviews EPIP-1 5, Emergency Exposure Guidelines, SAT Appendix A, Watts Bar Emergency Exposure Reference, and determines that the exposure limit to be 25 Rem.

UNSAT STANDARD: A STEP 2:

Determine dose received performing Tasks 1, 2 and 4.

CRITICAL STEP STANDARD:

SAT Applicant calculates dose to complete Task 1 as:

12 mm. /60 min/hrx 0.5 Rem/hr = 0.1 Rem UNSAT Applicant calculates dose to complete Task 2 as:

54 mm. /60 mm/hr. x 9 Rem/hr = 8.1 Rem Applicant calculates dose to complete Task 4 as:

(SAME CALCULATION AND DOSE AS Task 1, or 0.1 Rem.

Total for Tasks 1,2, and 4 is 8.3 Step is critical to ensure that the Emergency Exposure Limit is NOT exceeded.

COMMENTS:

Page 5of8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam STEP/STANDARD SATIUNSAT STEP 3: Determine remaining for the Emergency Exposure Limit.

CRITICAL STEP STANDARD:

SAT Applicant subtracts 8.3 Rem from the emergency exposure limit of 25 Rem.

UNSAT 25 Rem

- 8.3 Rem = 16.7 Rem:

Step is critical to ensure that the Emergency Exposure Limit is NOT exceeded.

COMMENTS:

STEP 4: Determine the time available for the Auxiliary Building AUO to CRITICAL complete Task 3, without exceeding the Emergency Exposure STEP Limit.

SAT STANDARD:

UNSAT Applicant divides the 16.7 Rem by the dose rate of 20 RIhr and calculates that the AUO has a maximum of 0.835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br /> or 50 minutes to complete the task of opening I -FCV-63-8 locally.

Step is critical to ensure that the Emergency Exposure Limit is NOT exceeded.

COMMENTS:

Page 6of8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO & SRO 2010-08 NRC Exam STEPISTANDARD I

SAT/UNSA[j STEP 5: Determine the restrictions, if any, that are imposed on the AB SAT AUO after receipt of the emergency exposure.

UNSAT STANDARD:

From EPIP-15.

3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.

COMMENTS:

END OF TASK STOP TIME Page 7 of 8

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A loss of coolant accident is in progress.

2. ECA-1.1, Loss of RHR Sump Recirculation, has been entered.

3. Automatic swap over to the containment sump has failed to occur.

4. The Auxiliary Building AUO has been dispatched to perform the following tasks:

TASK TIME DOSE RATE I

Go to task performance area.

12 minutes 0.5 RIhr 2

Remove cover from enclosure for 1-FCV 54 minutes 9 RIhr 72, CNTMT SUMP TO RHR PMP A SUCT.

3 Manually open 1-FCV-63-72, CNTMT SUMP TO 20 RIhr RHRPMPASUCT.

4 Return from task performance area.

0.5 RIhr

5. Authorization to exceed occupational dose limits has been approved by the Shift Manager (SED) for the Auxiliary Building AUO.

NOTE: Assume the time to travel from the task is equal to the time required to arrive at the task location.

INITIATING CUES:

The Auxiliary Building AUO has completed Tasks I and 2 in the time listed. You are to determine:

1. The amount of time the AB AUO has to complete Task 3 without exceeding his Emergency Dose Limit.

2. What restrictions, if any, are imposed on the AB AUO after receipt of the emergency exposure?

A.3 RO & SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam A.4-SRO Determine if conditions warrant a Follow-up Report or Upgrade to General Emergency based on changing conditions.

Po 1 of

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam EVALUATION SHEET Task:

Determine if conditions warrant a Follow-up Report or Upgrade to General Emergency based on changing conditions.

Alternate Path:

n/a Facility JPM #:

Modified Safety Function:

n/a

Title:

K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

Rating(s):

2.7/4.5 CFR:

41.10 / 43.5 / 45.11 Evaluation Method:

Simulator In-Plant Classroom

References:

EPIP-1 Emergency Plan Classification Flowpath, Rev. 31.

EPIP-5 GENERAL EMERGENCY, Rev. 37.

Task Number:

SRO-1 1 3-EPIP-001

Title:

Classify emergency events requiring Emergency Plan Implementation.

Task Standard:

The applicant:

1)

Determines that an upgrade from a Site Area Emergency to a General Emergency is required.

2) Prepares forms for emergency notification as indicated on the attached key.

3)

Initiates Protective Action Recommendations, Recommendation 2.

Validation Time:

15 minutes Time Critical:

Yes X

No Applicant:

Time Start:

NAME Docket No.

Time Finish:

Performance Rating:

SAT UNSAT Performance Time Examiner:

/

NAME SIGNATURE DATE COMMENTS Pci 2 of A

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 201 0-08 NRC Exam THIS JPM IS PERFORMED IN A CLASSROOM SETTING.

REQUIRED MATERIALS:

EPIP-1 through EPIP-5 ToolslEguipmentlProcedures Needed:

Copies of the WBN EPIPs for each applicant.

P;a of R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I was at 100% power when a loss of reactor coolant event occurred.

2. A Site Area Emergency has been declared 30 minutes ago for Unit 1, based on a Loss or Potential Loss of any two barriers:

a.

1.1 Fuel Clad Barrier - Loss (1.1.2, Primary Coolant Activity Level, RCS sample activity is Greater Than 300 CiIgm dose equivalent iodine - 131).

b. 1.2 RCS Barrier - Loss (1.2.2, RCS Leakage/LOCA, RCS Leak results in Loss of subcooling (<65°F indicated) [85°F ADV].

3. EPIP-4, SITE AREA EMERGENCY, has been performed through Step 15.

4. The Shift Technical Advisor now reports the following conditions exist on Unit 1:

a.

RVLIS level is 30%, with no RCPs running.

b. RCS subcooling is 15°F.

c. Containment Radiation monitors 1-RE-90-273 and 1-RE-90-274 both indicate 9ORIhr and are slowly trending up.

d. Initial wind direction was from 165 and has now shifted to from 180 degrees.

e. Wind speed has increased from 5 mph to 12 mph.

INITIATING CUES:

1. As the SED, you are to evaluate plant conditions and decide which is warranted:

a. completion of Appendix C, SITE AREA EMERGENCY Follow-up Notification Form OR

b. an upgrade in classification and determination of Protective Action Recommendations.

2. Once the decision is made, fill out the appropriate forms to make notifications to appropriate personnel.

3. This JPM contains time critical elements.

Pici 4 of 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2010-08 NRC Exam START TIME:

STEP 1:

Refers to EPIP-1 to determine level of event.

CRITICAL STEP STANDARD:

Applicant refers to EPIP-1, Section 1, andFission Product Barrier Matrix.

SAT Applicant determines that the following conditions exist:

1.1.2 Loss, RCS sample activity is greater than 300 pCi/gm dose UNSAT equivalent 1131 1.2.2 Loss, RCS Leakage/LOCA, RCS Leak results in Loss of subcooling

(<65°F indicated) [85°F ADV}.

1.3.5 Potential Loss, Significant Radioactivity in Containment, VALID Reading increase of Greater Than 108 RIhr on I -RE-90-271 and 1-RE-90-272 OR 86 RIhr on 1 -RE-90-273 and I -RE-90-274.

Based on Emergency Class Criteria, the applicant determines the need to declare a General Emergency, based on Loss of two barriers and potential loss of the third barrier.

Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes.

NOTE TO EXAMINER:

RECORD time that declaration was made:_________

COMMENTS:

Pici 5 of R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam STEP 2:

Implements EPIP-5, GENERAL EMERGENCY.

SAT STANDARD:

EPIP-5, GENERAL EMERGENCY, is implemented.

COMMENTS:

UNSAT The following steps are from EPIP-5 STEP 3:

[1] IF the onsite emergency centers are not staffed, THEN SAT DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the Technical Support Center (TSC) and Operations Support Center (OSC). Shift Personnel should confirm activation and provide the 20 minute printed UNSAT report to the SM for review.

a. IF the EPS system fails, call the ODS, ringdown or (5-751-1 700) and DIRECT him to activate the EPS.

b. IF the above methods of activating the EPS fail, THEN DIRECT Shift Personnel to use the Watts Bar Nuclear Plant Emergency Response Call-List to staff the TSC and OSC. (This list is located in the EPS Manual near the terminal.)

STANDARD:

Shift Personnel are directed to activate the Emergency Paging System (EPS)

CUE: When directed state Emergency paging has been activated.

COMMENTS:

Pin S of R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 SRO 2010-08 NRC Exam STEP 4:

[2] IF the TSC has not been activated, THEN CRITICAL

a. INITIATE Appendix A and B, Initial Notification Form for STEP GENERAL EMERGENCY and Protective Action Recommendations.

STANDARD:

Applicant completes Appendix A and Appendix B, SAT determines Recommendation 2.

NOTE TO EVALUATOR:

UNSAT Completed copies of Appendix A and B for this JPM are included and marked EXAM MATERIAL - KEY.

COMMENTS:

End of JPM TIME STOP:

Pici 7 of

EPIP-1 Revision 31 Page 9A of 47 Core Cooling Red (FR-Cl)

EXAM MATERAL KEY 11 Fuel Clad Barrier 1.

Critical Safety Function Status LOSS

I 2_ RCS Barrier Potential LOSS 1.

Critical Safety Function Status Core Cooling Orange (FR-C2)

OR Heat Sink Red (FR-H.1)

(RHR Not in Service)

(

/

LOSS Potential LOSS Not Applicable Pressurized Thermal Shock Red (FR-P.1)

OR Heat Sink Red (FR-HI)

(RHR Not in Service)

-OR

2. Sheakagç/LOCA I.

Potential LOSS RCS Leak results in Non Isolatable RCS Leak Loss of subcooling xceeding The Capacity of

(<65°F Indicated),

Qn Charging Pump (CCP) 5°F1 In the Normal Charging RCS Leakage Results In Entry Into E-l

-OR-3.

Steam Generator Tube Rupture Potential_LOSS SGTR that results in a Not Applicable safety injection actuation OR Entry into E-3

-OR-4.

Reactor Vessel Water Level LOSS

-OR

.ZPriTharycoolant Activity Level

• 1 Potential LOSS RCS sample activity is Greater Than 300 )ICi/gm Not applicable dose equivalent iodine-131/

-OR-3.

Incore TCs Hi Quad Average Potential LOSS Greater Than 1200°F Greater Than 727°F

-OR-4.

Reactor Vessel Water Level Potential LOSS Not Applicable VALID RVLIS level <33%

(No RCP running)

-OR-

5. Containment Radiation Monitors Potential_LOSS VALID reading increase Not Applicable 7e 74 R/hr On 1-RE-90-271 and 272 (see instruction note 5)

-OR-6.

Site Emergency Director Judgment LOSS LOSS LOSS Potential LOSS VALID RVLIS level Not Applicable

<33%

(No RCP Running)

-OR-5.

Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the Fuel Clad Barrier Comparable to the Conditions Listed Above.

Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the RCS Barrier Comparable to the Conditions Listed Above.

EXAM MATERAAL KEY 1 3 CNTMT Barrier LOSS Potential LOSS Containment (FR-Z.1)Red OR Actions of FR-C.1 (Red Path) are INEFFECTIVE (i.e.: core TCs trendinci uø)

-OR-

2. Containment Pressure/Hydrogen Potential LOSS Rapid unexplained decrease Containment Hydrogen following initial increase Increases to >4% by volume Containment pressure or Pressure >2.8 PSIG (Phase Sump level Not increasing B) with < One full train of (with LOCA in progress)

Containment spray

-OR-

3. Containment Isolation Status Potential LOSS Not Applicable Containment Isolation is Incomplete (when required)

AND a Release Path to the Environment Exists

-OR-

4. Containment ass Potential LOSS RUPTURED SIG is also Unexplained VALID increase FAULTED outside CNTMT in area or ventilation RAD OR monitors in areas adjacent to Prolonged (>4 Hours)

CNTMT (with LOCA in Secondary Side release progress) outside CNTMT from a SIG with a SGTL > T/S Limits

-OR-

5. Significant Radioactivity in Containment Potential LOSS

---I Not Applicable VAJ..iWRding increasif.,

,efeater Than; 108 R/hron 1-RE-90-271 and

(

1-RE-90-272 6 Rlhron 1-R (see instruc

-OR-

6. Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the CNTMT Barrier Comparable to the Conditions Listed Above.

Modes: 1,2,3,4 EPIP-1 Revision 31 Page 9B of 47 INSTRUCTIONS NOTE: A condition is considered to be METi in the judgment of the Site Emergency Director the condition will be MET imminently (he., within Ito 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in the absence of a viable success oath).

The classification shall be made a soon as this determination is made.

1.

In the matrix to the left, review the INITIATING CONDITIONS in all columns and identify which, if any, INITIATING CONDITIONS are MET.

Circle these CONDITIONS.

2. For each of the three barriers, identify if any LOSS or Potential LOSS INITIATING CONDITIONS have been MET.

3.

If a CSF is listed as an INITIATING CONDITION; the respective status tree criteria will be monitored and used to determine the EVENT classification for the Modes listed on the classification flowchart.

4. Compare the barrier losses and potential losses to the EVENTS below and make the appropriate declaration.

5.

Containment Radiation Monitors are temperature sensitive and can be affected by temperature induced currents. Following a rapid increase or decrease in containment temperature, testing has shown rad monitors to give unreliable indication for up to 2 minutes.

Any LOSS Potential LOSS of RCS barrier

1. Critical Safety Function Status Not Applicable LOSS LOSS F

I S

S I

0 N

P R

0 B

U C

T B

A R

R I

E R

M A

T R

I x

LOSS UNUSUAL EVENT Loss or Potential LOSS of Containment Barrier U

1 EVENTS

ALERT Any LOSS 2! Potential LOSS of Fuel Clad barrier OR SITE AREA EMERGENCY LOSS or Potential LOSS of any two barriers GENERAL EMERGENCY LOSS of any two barriers nd Potential LOSS of third

(

(

(

EXAM MATERAL KEY

(

WBN GENERAL EMERGENCY EPIP-5 APPENDIX A (Page 1 ofl)

TVA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY X This is a Drill D This is an Actual Event

- Repeat

- This is an Actual Event rhis is Aolicants Name Watts Bar has declared a GENERAL EMERGENCY affecting Unit I 1.1.2 LOR 1.1.5 L, 1.2.2 L, 1.3.5 PL EAL Designator(s):

. Brief Description of the Event:

- Loss of Coolant accident with failed fuel, and significant radiation in containment. (or words to this effect) adiological Conditions:

(Check one under both Airborne and Liquid column.)

>S.

Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits 1

Minor releases within federally approved limits 1

D Releases above federally approved limits 1

D Releases above federally approved limits 1

[ Release information not known Xi Release information not known

( 1 Tech Specs)

( 1 Tech Specs) vent Declared:

Time: Applicant ENTRY Date:

Today he Meteorological Conditions are:

(Use 46 meter data from the Met Tower)

Wind Direction is FROM:

180 degrees Wind Speed:

12 m.p.h rovide Protective Action Recommendation:

(Check eithecj2 or 3, and mark wind direction.)

LI Recommendation I R WIND EVACUATE LISTED SECTORS E

(Mark)

E EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind)

C C

(2 mile radius and 5 mile downwind)

=SHELTER remainder of 10 mile EPZ.

=SHELTER remainder of 10 mile EPZ.

=CONSlDER issuance of Potassium Iodide in

=CONSIDER issuance of Potassium accordance with the State Plan.

2 Iodide in accordance with the State Plan.

A-I, B-I, C-I, D-l, 26-68 A-i, B-I, C-i, D-l, C-7, -9, 0-2, -4, -5, -6, -7, -8, -9

C-7, D-2, -4, -5 A-I, B-i, C-i, D-1,69-110 A-I, B-i, C-i, D-i, A-3, -4, D-2, -3, -4, -5, -6, -7, -8, -9

A-3, D-2, -4, -5 A-i, B-l, C-i, D-i, 111-170

A-i, B-l, C-l, D-l, A-2, -3, -4, -5, -6, -7, D-2, -3, -5, -6 A-2, -3, D-2, -5 A-lB-iC-iD-i, 1112t1 B-l, A-2, -3, -5, -6, -7, B-2, -3, -4, -5, C-2

A-I, B-i, C-I, D-i, 231-270

A-i, B-l, C-i, D-i, B-2, -3, -4, -5, C-2, -3, B-2, -4, C-2 A-l, B-i, C-i, D-1,

27i-325

A-i, B-i, C-i, D-I, B-2, -3, C-2, -3, -4, -5, -6, -ii

B-2, C-2, -4, -5, A-l, 8-1, C-i, D-i, 326-25 A-i, B-i, C-i, D-i, C-2, -4, -5, -6, -7, -8, -9, -10, -ii, 0-4, -9

C-2, -4, -5, -7, -8, 0-4 El Recommendation 3 z.SJlELTER all sectors.

=CONSlDER issuance of Potassium Iodide in accordance with the State Plan.

4NIease repeat the information you have received to ensure accuracy.

ime and Date this information was provided.

Time:. Applicant ENTRY Date Today Aon: When notification complete, FAX form as prescribed in this instruction.

PAGE 13 of 17 REVISION 37

EXAM MATERNAL KEY WBN GENERAL EMERGENCY EPIP-5 APPENDIX B (Page 1 of 1)

PROTECTIVE ACTION RECOMMENDATIONS Note 1:

If conditions are unknown utilizing the flowchart, then answer is NO.

Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.

GENERAL EMERGENCY DECLARED SHELTER 10 mile EPZ 1

TABLE I Protective Action Guides (PAG)

TYPE LIMIT Measured 3.9 E-6 micro Ci/cc of Iodine 131 or 1 REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE CONTINUE ASSESSMENT Modify protective actions based on available plant and field monitoring information.

r

/

release whereas near plant areas cannot be YES RECOMMENDATION 3 I

RECOMMENDATION 1 Locate and evaluate localized hot spots.

(RECOMENwIQN2oN2 EVACUATE 2 miles radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ YES EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ PAGE 14 of 17 REVISION 37

APPLICANT HANDOUT SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I was at 100% power when a loss of reactor coolant event occurred.

2. A Site Area Emergency has been declared 30 minutes ago for Unit 1, based on a Loss or Potential Loss of any two barriers:

a.

1.1 Fuel Clad Barrier - Loss (1.1.2, Primary Coolant Activity Level, RCS sample activity is Greater Than 300 jCi/gm dose equivalent iodine -

131).

b. 1.2 RCS Barrier - Loss (1.2.2, RCS LeakageILOCA, RCS Leak results in Loss of subcooling (<65°F indicated) [85°F ADV].

3. EPIP-4, SITE AREA EMERGENCY, has been performed through Step 15.

4. The Shift Technical Advisor now reports the following conditions exist on Unit 1:

a.

RVLIS level is 30%, with no RCPs running.

b. RCS subcooling is 15°F.

c. Containment Radiation monitors 1-RE-90-273 and 1-RE-90-274 both indicate 9ORIhr and are slowly trending up.

d. Wind direction has shifted from 165 to 180 degrees.

e. Wind speed has increased from 5 mph to 12 mph.

INITIATING CUES:

1. As the SED, you are to evaluate plant conditions and decide which is warranted:

a. completion of Appendix C, SITE AREA EMERGENCY Follow-up Notification Form OR

b. an upgrade in classification and determination of Protective Action Recommendations.

2. Once the decision is made, fill out the appropriate forms to make notifications to appropriate personnel.

3. This JPM contains time critical elements.

A.4-SRO