ML102371251

301 Draft Administrative JPMs

ML102371251
Person / Time
Site:	Watts Bar
Issue date:	08/25/2010
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/08-301
Download: ML102371251 (78)

Text

RevO PAGE 1 0F12 Watts Bar Nuclear Plant 3-OT-JPMADA 1-7a Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT

RevO PAGE 2 0F12 Watts Bar Nuclear Plant 3-OT-JPMADA I -7a NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial issue, generated for NRC Initial All D. Hughes License Exam

PAGE 3 0F12 RevO Watts Bar Nuclear Plant 3-OT-JPMADA 1 -7a for Manual Makeup Task: Hand Calculation of Boric Acid and Primary Water Integrator Setting to the VCT Alternate Path: None Facility JPM #: 3-OT-JPMADA 1-7a Rev 0 K/A Rating(s):

SRO 4.6) 2.1.20 Ability to interpret and execute procedure steps. (IMPORTANCE RO 4.6 ted with reactiv ity

2. 1.37 Knowledge of procedures, guidelines, or limitations associa management. (IMPORTANCE RO 4.3 SRO 4.6) changes, I 2.1.43 Ability to use procedures to determine the effects on reactivity of plant etc.

such as reactor coolant system temperature, secondary plant, fuel depletion, (IMPORTANCE RO 4.1 SRO 4.3)

TASK STANDARDS: Correctly perform Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

1-SOl-62.02 Rev 0047 Tl-59 Rev 0006 Task Number: RO-062-SOl-62-01 7, APPLICABLE FOR: RO!SRO IOCFR55.45: 1,5 Validation Time: 15 mm. Time Critical: No Time Start:

Candidate:

NAME SSN/EIN Time Finish:

UNSAT Performance Time Performance Rating: SAT

/

Examiner: DATE NAME SIGNATURE COMMENTS

RevO PAGE 4 0F12 Watts Bar Nuclear Plant 3-OT-JPMADA 1-7a SIMULATOR OPERATOR INSTRUCTIONS:

If JPM conducted in Simulator, reset to any EOL 100% Ic Tools/EguipmentiProcedures Needed:

copy of latest revision of 1-SOI-62.02 and TI-59 calculator Access to controlled copies of plant procedures READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. 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:

• The unit is in Mode 1 at 100% power.

• current cs CB is 222 ppm.

• current inservice BAT cB is 6350 ppm

• current s-io Depletion value is 12 ppm.

• currently the VT is at 23%

• The Desired VOT Level is 40%

• You are an extra operator.

INITIATING CUES:

• Due to a suspected problem with REACTINW, the Unit SRO has directed you to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOI-62.02

• Report the results of the surveillance to the Unit SRO.

PAGE 5 0F14 3-OT-JPMADA 1-7a START TIME:

STEP 1: Obtain the necessary procedure.

_SAT STANDARD: Performer obtains copy of latest revision of 1-SOI-62.02.

and finds section 6.5 Manual Makeup COMMENTS:

U N SAT EXAMINERS NOTE: Provide copy of SOl 62.02 to candidate.

CUE:

6.5 Manual Makeup STEP 2:

SAT

[1] PERFORM Appendix C, Calculation Of Boric Acid And P ri mary STANDARD: Performer turns to SOI 62.02 Appendix C _UNSAT COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 6 0F14 3-OT-JPMADA 1-7a

( 3TEP3:

Appendix C NOTE 1 SAT Use page 1 of this appendix when using VCT MAKEUP CALCULATION program in REACTINW, otherwise use pages 2 and 3 when performing Hand Calculations.

UNSAT STANDARD: Performer refers to iniating cues and realizes that REACTINW is suspect and goes to page 2 of Appendix C COMMENTS:

STEP 4:

2.0 HAND CALCULATION SAT

[1] OBTAIN the following data for use in the HAND CALCULATION:

[1.1] Current RCS Boric Acid Concentration. 222 PPM

[1.2] Current BAT Boric Acid Concentration. 6350 PPM U N SAT

[1.3] B-i 0 Depletion Value from Reactivity Management Briefing Sheet 12 PPM

[1.4] Current VCT Level 23  %

[1.5] Desired VCT Level 40  %

STANDARD Correctly obtains information from iniating cues.

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 7 0F14 3-OT-JPMADA 1-7a 2] CALCULATE BAT Boric Acid Concentration Ratio Critical Step STEP 5*

(BACR):

6820 ppm ÷ Step 1 .0[1 .2] ppm =_________

(ENTER 1.0 for BACR following a reactor shutdown or for a SAT conservative calculation).

STAN DARD: Performer performs the following calculation:

UNSAT 6820 ppm ÷ 6350 ppm = 1.074 COMMENTS:

Critical Step STEP 6 [3] CALCULATE B-10 corrected boron concentration:

PPM STEP 1.0[1.1] STEP 1.0[1.3] B-10 corrected boron SAT STANDARD: Performer performs the following calculation:

222ppm - l2ppm = 2lOppm. UNSAT COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 8 0F14 3-OT-JPMADA 1-7a

[4j CALCULATE total VCT addition volume needed for Critical Step STEP 7*

desired level.

% -  % ] X 19.3 Gals/% =_______ GALS SAT Step 1 .O[1 .5] Step 1 .0[1 .4] Total Volume (Round to nearest whole number)

STANDARD: Performer performs the following calculation:

UN SAT 40  % - 23 % }X 19.3 Gals!% = 328.1 GALS COMMENTS: -

2.0 HAND CALCULATION (continued) Critical Step STEP 8 NOTE Corrected Boric Acid Flow Rate in Step 2.0[5} should be obtained from Tl-59, Appendix C for the B-10 corrected boron value calculated in Step 2.0[3j.

SAT

[5]

GPMX = GPM corrected Boric BACR from [XJ BA to Blender Acid Flow Rate Step 2.O[2]

UNSAT STANDARD: Performer performs the following calculation:

2.2 GPMX 1.074 = 2.36 GPM Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2.O[2]

COMMENTS:

• • lta!icized Cues Are To Be Used Only If JPM Performance ls Being Simulated.

PAGE 9 0F14 3-OT-JPMADA 1-la Critical Step STEP 9: [6]

GPM+ 70GPM GPM Step 2.0[5] [X] PW to Total Flow Rate SAT Blender Flow STAN DARD: Performer performs the following calculation:

2.36 GPM + 70 GPM = 72.36 GPM UNSAT Step 2.0[5] [X] PW to Total Flow Rate Blender Flow COMMENTS: -

[71 Critical Step STEP 10:

GPM GPM = GPM Step 2.0[5] [XI Step 2.0[6] [Yj BA Fraction Total Flow Rate SAT STANDARD: Performer performs the following calculation:

2.36 GPM ÷ 72.36 GPM = 0.0326 GPM Step 2.0[5] [Xl Step 2.0[6] [Yl BA Fraction UNSAT Flow Rate COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 10 0F14 3-OT-JPMADA 1-7a Critical Step

( STEP 11. [8]

X GALS = GALS Step 2.0[7] [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting SAT STANDARD: Performer performs the following calculation:

UNSAT 0.0326 X 328.1 GALS = 10.7 GALS Step 2.0[7] [Y] Step 2.0[41 Boric Acid Batch Total Volume Counter Setting Performer can round BA counter up to 11 GALS COMMENTS:

Critical Step STEP 12:

70 GPM+/- GPM =

Primary H 0

2 Step 2.0[6] [Z] PW Fraction __SAT Total Flow Rate UN SAT STANDARD: Performer performs the following calculation:

70 GPM ÷ 72.36 GPM = 0.967 Primary H 0

2 Step 2.0[6] [Z] PW Fraction Total Flow Rate COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 11 0F14 3-.OT-JPMADA 1-7a Critical Step STEP 13: [10]

X GALS = GALS Step 2.O[9} [Z} Step 2.O[4} Primary Water SAT Total Volume Batch Counter Setting STANDARD: Performer performs the following calculation:

UNSAT 0.967 X 328.1 GALS = 317.27 GALS Step 2.O[9] [Z] Step 2.O[4] Primary Water Batch Total Volume Counter Setting Performer can round PW counter down to 317 GALS COMMENTS:

[11] ENSURE independently verified by SRO.

STEP 14:

SAT STANDARD: Performer reports that the task is completed and gives calculation to the SRO COMMENTS:

UNSAT Examiner Acknowledge report, notify performer that the task is cue: complete. End task TIME STOP:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. 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:

• The unit is in Mode 1 at 100% power.

• Current RCS CB is 222 ppm.

• Current inservice BAT CB is 6350 ppm -

• Current B-10 Depletion value is 12 ppm.

• Currently the VCT is at 23%

• The Desired VCT Level is 40%

• You are an extra operator.

INITIATING CUES:

• Due to a suspected problem with REACTINW, the Unit SRO has directed you to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOI-62.02

• Report the results of the surveillance to the Unit SRO.

RevO PAGE 1 0F13 Watts Bar Nuclear Plant 3-OT-JPMADA 1-7b SRO Verification of Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT

RevO PAGE 2 0F13 Watts Bar Nuclear Plant 3-OT-JPMADA 1-7b NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial issue, generated for NRC Initial All D. Hughes License Exam

RevO PAGE 3 0F13 Watts Bar Nuclear Plant 3-OT-JPMADA I -7b Task: SRO Verification of Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT Alternate Path: None Facility JPM #: 3-OT-JPMADA 1-7b Rev 0 K/A Rating(s):

2.1.20 Ability to interpret and execute procedure steps. (IMPORTANCE RO 4.6 SRO 4.6) 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (IMPORTANCE RO 4.3 SRO 4.6) 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(IMPORTANCE RO 4.1 SRO 4.3) -

TASK STANDARDS: Correctly verify Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT.. SRO finds error.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Perform X Simulate

References:

1-SOl-62.02 Rev 0047 Tl-59 Rev 0006 Task Number: SRO-113-SSP-12-013, APPLICABLE FOR: SRO IOCFR55.45: 1,5 Validation Time: 15 mm. Time Critical: No Candidate: Time Start:

NAME SSN!EIN Time Finish:

UNSAT Performance Time Performance Rating: SAT

/

Examiner:

NAME SIGNATURE DATE COMMENTS

RevO PAGE 4 0F13 Watts Bar Nuclear Plant 3-OT-JPMADA 1-7b SIMULATOR OPERATOR INSTRUCTIONS:

If JPM conducted in Simulator, reset to any EOL 100% IC Tools/EguipmentlProcedures Needed:

Copy of latest revision of 1-SOl-62.02 and Tl-59 Calculator Access to controlled copies of plant procedures READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. 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:

• The unit is in Mode 1 at 100% power.

• Current RCS CB is 222 ppm.

• Current inservice BAT CB is 6350 ppm

• Current B-b Depletion value is 12 ppm.

• Currently the VCT is at 23%

• The Desired VCT Level is 40%

INITIATING CUES:

• Due to a suspected problem with REACTINW, an RO was directed to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOl-62.02.

• The RO has reported the results of the surveillance to you, the Unit SRO.

• You are task with conducting a verification of the calculation.

PAGE 5 OF 14 3-OT-JPMADA 1-7b START TIME:

STEP 1: Obtain the necessary procedure.

Performer obtains copy of latest revision of 1-SOI-62.02. _SAT STANDARD:

COMMENTS:

UNSAT EXAMINERS NOTE: Provide copy of completed SO! 6202 CUE: Appendix C to candidate.

STEP 2:

2.0 HAND CALCULATION SAT

[1] OBTAIN the following data for use in the HAND CALCULATION:

[1.11 Current RCS Boric Acid Concentration. 222 PPM

[1.2] Current BAT Boric Acid Concentration. 6350 PPM UNSAT

[1.3] B-I 0 Depletion Value from Reactivity Management Briefing Sheet 12 PPM

[1.4] Current VCT Level 23  %

[1 .5] Desired VCT Level 40  %

STANDARD SRO Verifies the above information is correct:

COMMENTS:

• • lta!icized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 6 OF 14 3-OT-JPMADA 1 -7b 2] CALCULATE BAT Boric Acid Concentration Ratio Critical Step STEP 3*

(BACR):

6820 ppm ÷ Step 1.0[1.2J ppm =_________

(ENTER 1.0 for BACR following a reactor shutdown or for a SAT conservative calculation).

STANDARD: Performer performed the following calculation:

UNSAT 6820 ppm ÷ 6350 ppm = 1.074 SRO Verifies the above information is correct:

COMMENTS:

Critical Step STEP 4

[3] CALCULATE B-10 corrected boron concentration:

PPM STEP 1.O[1.1] STEP 1.O[1.3] B-1O corrected boron SAT STANDARD: Performer performed the following calculation:

222ppm - l2ppm = 2lOppm. UNSAT SRO Verifies the above information is correct:

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 7 OF 14 3-OT-JPMADA 1-7b

[4] CALCULATE total VCT addition volume needed for Critical Step STEP 5*

(. desired level.

% -  %] X 19.3 GalsI% =_______ GALS SAT Step 1 .O[1 .5] Step 1 .O[1 .4] Total Volume (Round to nearest whole number)

STANDARD: Performer performed the following calculation:

UNSAT 40  % - 23 % ] X 19.3 Gals!% = 328.1 GALS SRO Verifies the above information is correct: -

COMMENTS:

• • Jta!icized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 8 0F14 3-OT-JPMADA 1-7b 2.0 HAND CALCULATION (continued) Critical Step STEP 6

( NOTE Corrected Boric Acid Flow Rate in Step 2.0[5j should be obtained from Tl-59, Appendix C for the B-i 0 corrected boron value calculated in Step 2.O[3j.

SAT

[51 GPMX_______ GPM Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2.O[2}

U N SAT STANDARD: Performer performed the following calculation:

2.2 GPMX 1.074 = 2.36 GPM Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2O[2]

SRO Verifies the above information is correct:

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 9 OF 14 3-OT-JPMADA 1-7b Critical Step STEP 7: [6]

GPM+ 7OGPM GPM Step 2.O[5] [X] PW to Total Flow Rate SAT Blender Flow STAN DARD: Performer performed the following calculation:

2.36 GPM + 70 GPM = 72.36 GPM UNSAT Step 2.O[5] [Xl PW to Total Flow Rate Blender Flow SRO Verifies the above information is correct:

COMMENTS:

[7] Critical Step STEP 8:

GPM+/- GPM = GPM Step 2.O[5] [X] Step 2.O[6] [Y] BA Fraction Total Flow Rate STANDARD: Performer performed the following calculation:

2.36 GPM ÷ 72.36 GPM = 0.0326 GPM Step 2.0[5] [X] Step 2.0[6] [Y] BA Fraction Fkw Rate UNSAT SRO Verifies the above information is correct:

COMMENTS:

• • Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulateth

PAGE 10 0F14 3-OT-JPMADA 1 -7b Critical Step STEP 9: [8]

X GALS = GALS Step 2.0[7} [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting SAT STANDARD: Performer performe the following calculation:

UN SAT 0.0326 x 21 0 GALS = 6.84 GALS Step 2.0[7j [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting SRO determines that the RO incorrectly obtained data from Step 2.0[3] (used 210). Should have used Step 2.0[4] which was 328.1.

SRO calculates the correct value as follows:

0.0326 x 328.1 GALS = 10.7 GALS Step 2.0[7] [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting SRO may round the BA up to 11 gals COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 11 0F14 3-OT-JPMADA 1-7b Critical Step STEP 10:

70 GPM+/- GPM =

Primary H0 2 Step 2.O[6] [Z] PW Fraction SAT Total Flow Rate UNSAT STANDARD: Performer performs the following calculation:

70 GPM ÷ 72.36 GPM = 0.967 Primary H0 2 Step 2.O6] [Z] PW Fraction Total Flow Rate SRO Verifies the above information is correct: -

COMMENTS:

STEP 11* Critical Step

[101 X GALS = GALS Step 2.O[9] [Z] Step 2O[4] Primary Water SAT Total Volume Batch Counter Setting STANDARD: Performer performs the following calculation: UNSAT 0.967 X 328.1 GALS = 317.27 GALS Step 2.O[9] [Z] Step 2.O[4] Primary Water Batch Total Volume Counter Setting SRO Verifies the above information is correct:

SRO may round PWdown to 317 ga/s COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 12 0F14 3-OT-JPMADA 1-7b STEP 12:

[11] ENSURE independently verified by SRO.

SAT STANDARD: Performer gives calculation back to the RO COMMENTS:

UN SAT Examiner Acknowledge report, notify performer that the task is cue: complete. End task TIME STOP:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I wifl explain the initial conditions, and state the administrative task to be performed. 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:

• The unit is in Mode 1 at 100% power.

• Current RCS C 8 is 222 ppm.

• Current inservice BAT 08 is 6350 ppm

• Current B-10 Depletion value is 12 ppm.

• Currently the VCT is at 23%

• The Desired VCT Level is 40%

INITIATING CUES:

• Due to a suspected problem with REACTINW, an RO was directed to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOl-62.02.

• The RO has reported the results of the surveillance to you, the Unit SRO.

• You are task with conducting a verification of the calculation.

RevO PAGE 1 0F8 Watts Bar Nuclear Plant 3-OT-JPMADA 1-8 Evaluate Overtime Guidelines

RevO PAGE 2 0F8 Watts Bar Nuclear Plant 3-OT-JPMADA 1-8 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial issue, generated for NRC Initial 03/21/08 All D. Hughes License Exam

RevO PAGE 3 0F8 Watts Bar Nuclear Plant 3-OT-JPMADA 1-8 Task: Evaluate Overtime Guidelines Alternate Path: None Facility JPM #: 3-OT-JPMADA 1-8 Rev 0 K/A Rating(s):

2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. (IMPORTANCE RO 2.9/ SRO 3.9)

TASK STANDARDS: Determine maximum hours that can be worked per request. Determine that a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift cannot be worked on the day requested.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

SPP 1.5 Rev 0005 Task Number: RO-119-OPDP-10.1-0O1, APPLICABLE FOR: RO/SRO IOCFR55.45: 11 Validation Time: 15 mm. Time Critical: No Candidate: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

RevO PAGE 4 0F8 Watts Bar Nuclear Plant 3-OT-JPMADA 1-8 SPECIAL INSTRUCTIONS TO EVALUATOR:

a. Hand time (cue) sheet to candidate READ TO OPERATOR Directions to Trainee:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. 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 ATC for the 0700-1900 shift has called in sick.

2. You are the only operator currently available, and You have been requested to work 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> tomorrow, 5/15/2008, from 0700-1 900.

INITIATING CUES:

Determine the number of hours you could work, if any, starting at 0700 on 5/15/2008 without violating overtime guidelines. If required

3-OT-JPMADA 1-8 Page 5 of 8 Rev. 0 Job Performance Checklist:

STEP/STANDARD SAT/UNSAT Evaluator If the performer locates a copy of SPPI.5, Overtime Critical Step Note: Restrictions (Regulatory), give the performer a copy.

SAT Determine the number of hours that can be worked STEP 1. starting at 0700 on 5/15/08 without violating any overtime guidelines.

UNSAT May only work 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the 0700 1900 shift on STANDARD: 5/15/208. The Performer identifies that the requirements per SPP-1 .5 of working more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days will be violated if authorization per SPP- 1 .5 is not approved prior to 1300 on 5/15/2008.

Evaluator This step has 2 critical components. Both of which must Note: be satisfied to pass JPM:

• May only work 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of the 0700 1900 shift without violating overtime restrictions.

• The Performer identifies that the requirements per SPP-1.5 of working more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days will be violated if authorization per SPP- 1.5 is not approved prior to 1300 on 5/15/2008.

If the performer only identifies the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> restriction, then acknowledge report, and inform them to complete the appropriate paperwork as if they were to report to work at 0700. Inform them that they are the only person available.

Comments:

3-OT-JPMADA 1-8 Page 6 of 8 Rev. 0 Job Performance Checklist:

STEP/STANDARD SAT/UNSAT STEP 2. Locates SPP-1 .5, Overtime Restrictions, and fills out the following on Page 8 of the report: SAT

• Name

• SSN

• Organization

• Date UNSAT

• #Hours

• Time limit will be exceeded STANDARD: # Hours and Time that the limit will be exceeded (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 1300 the limit will be exceeded)

Evaluator If the performer ask for a copy of SPP=1.5, Overtime Note. Restrictions (Regulatory), give the performer a copy.

Comments:

STEP 3. Specifies Reasons for cause of overtime.

SAT UN SAT STANDARD: Writes a reasonable reason on the form.

Comments:

3-OT-JPMADA 1-8 Page 7 of 8 Rev. 0 Job Performance Checklist:

STEP/STANDARD SAT/UNSAT STEP 4. Specifies requirements for exception and work to be Critical Step performed.

SAT STANDARD: Determines requirements per SPP-1 .5 Page 8 item 2 and checks the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days block on Appendix A.

UNSAT Evaluator This step is the second of the 2 critical components for Note: this JPM ( which may have been performed in step one of this JPM):

The Performer identifies that the requirements per SPP-1.5 of working more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days will be violated if authorization per SPP- 1.5 is not approved prior to 1300 on 5/15/2008.

Evaluator Que: Shift Clerk will complete the remainder of SPP-1.5 Comments:

End of JPM

CANDIDATE COPY TO BE RETURNED TO EXAMINER UPON COMPLETION OF ANSWER Initial Conditions:

You are a Reactor Operator that has worked the following schedule:

Date Hours Status Notes 5/7/08 0700-1715 Normal Day Off Call out to cover 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift (15 minute turnover) 5/8/08 1500-1915 Normal Day Off Call out to cover 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> shift (15 minute turnover) 5/9/08 0700-1700 Normal Day Off Attended Simulator and Classroom JIT Training 5/10/08 0700-1915 Normal Work Day 15 minute turnover 5/11/08 0700-1915 Normal Work Day 15 minute turnover 5/12/08 0700-1915 Normal Work Day 15 minute turnover 5/13/08 0700-1915 Normal Work Day 15 minute turnover 5/14/08 1100-1900 Normal Day Off Attended Simulator and Classroom_JIT_Training The OAC for the 0700-1900 shift has called in sick.

You are the only operator currently available and you have been requested to work 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> tomorrow, 5/15/2008 from 0700-1 900.

INITIATING CUES:

Determine the number of hours you could work, if any, starting at 0700 on 5/15/2008 without violating overtime guidelines.

RevO PAGE 1 OF 19 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Hand Calculation of RCS Inventory Balance

PAGE 2 0F19 RevO Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 NUCLEAR TRAINING REVISION/USAGE LOG Date Pages Affected Reviewed By Rev. # Description of Changes All 0. Hughes 0 Initial issue, generated for NRC Initial License Exam

PAGE 3 0F19 RevO Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Task: Hand Calculation of RCS Inventory Balance.

Alternate Path: None Facility JPM #: 3-OT-JPMADA 2-3 Rev 0 K/A Rating(s):

ANCE RO 3.7 SRO 4.1) 2.2.1.2 Knowledge of surveillance procedures. (IMPORT on of RCS Inventory Balance TASK STANDARDS: Correctly perform Hand Calculati Preferred Evaluation Method:

Preferred Evaluation Location:

Perform X Simulate Simulator X In-Plant

References:

1-SI-68-32 Rev 0012 TI-4 Part II Rev 0012 Task Number: RO-068-SI-68-32-001, APPLICABLE FOR: RO/SRO 10CFR55.45: 11 Validation Time: 35 mm. Time Critical: No Time Start:

Candidate: Time Finish:

NAME SSN!EIN UNSAT Performance Time Performance Rating: SAT

/

Examiner: DATE NAME SIGNATURE COMMENTS

PAGE 4 0F19 RevO Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 SIMULATOR OPERATOR INSTRUCTIONS:

none Tools/Equipment/Procedures Needed:

page for data to put in 1-Sf-68-32)

Marked up copy of of latest revision of 1-Sl-68-32 (see next Copy of Tl-4 Part II.

Steam Tables Calculator Access to controlled copies of plant procedures READ TO OPERATOR DIRECTION TO TRAiNEE:

rative task to be performed. I I will explain the initial conditions, and state the administ directed by you. Ensure will provide initiating cues and reports on other actions when task. To indicate that you have you indicate to me when you understand your assigned t provided you.

completed your assigned task return the handout shee I INITIAL CONDITIONS:

• The unit is in Mode 1 at 100% power.

• The Plant Computer program RCSWIB is unreliable.

4 (2nd Data Set has been taken)

• 1-Sl-68-32 Appendix A has been completed through step

• You are an extra operator.

INITIATING CUES:

has directed you to perform a

• Due to a suspected problem with RCSWIB, the Unit SRO manual calculation of RCS inventory balance.

• Report the results of the surveillance to the Unit SRO.

PAGE 5 0F19 RevO Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Mark-Up instructions for 1-SI-68-32

1. Starting in section 4.1 initial/N/A steps as required.

Fill in the foHowing data at step 6:

age obtained from Chemistry in

[6] RECORD the most recent Steam Generator Leak l SG Leakage (in gpm) as the appropriate column below, and CALCULATE Tota follows: =, 0 gpd postions for all steps in sections 4.2,

2. Continue to initial steps and/or fill in Handswitch/valve are marked N/A, since Appendix 4.3, and 6.0 (up to step 6.18). Ensure steps 6.5 thru 6.18 A will be performed.

3. Appendix A initial steps 1 thru 4.

ining data points):

4. Appendix B fill in the following data,( N/A all rema Panel Initial Data Set 2nd Data Set Parameter N/A 0800 0912 Time LO112A 31.5% 30.2%

VCT LEVEL PO48OA 2235.3 psig 2235.3 psig PRESSURIZER PRESSURE L0482A 60.24% 59.55%

PRESSURIZER LEVEL T0460A 586.3 °F 586.3 °F RCS TEMPERATURE 1-Nl-41 100% 100%

REACTOR POWER L0485A 72.6% 72.6%

PRT LEVEL 1 LI-77-1 23% 23%

RCDT LEVEL

_ 0-PNL-276-L2 Initials DATA SET N/A Initials RECORDED BY

PAGE 6 0F19 3-OT-JPMADA 2-3 START TIME:

EXAMINERS CUE: Provide a marked up copy of 1-SI-68-32 to candidate.

STEP 1:

CALCULATE RCS leakage per Appendix SAT UNSAT STANDARD:

Performer turns to 1-Sl-68-32 Appendix C COMMENTS:

r, fl IIcrI flnfv If JPM Performance Is Being Simulated.

PAGE 7 0F19 3-OT-JPMADA 2-3

- Critical Step STEP 3

[1] CALCULATE elapsed time (AT) as follows:

AT = FINAL TIME INITIAL TIME SAT

= mm U N SAT STANDARD: Performer determines that AT is 72 minutes COMMENTS:

STEP 4: [2] CONVERT INITIAL and FINAL PZR PRESSURE units of measure to psia as follows: SAT PARAMETER [ INITIAL f FINAL psig ÷ 14.7 psig + 14.7 PZR PRESS

= .__psia U N SAT STANDARD Performer correctly calculates Initial PZR Pressure and final PZR Pressure to be 2250 psia COMMENTS:

• • If;Ii(i7pH Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 8 0F19 3-OT-JPMADA 2-3 3] CALCULATE VCT Leakage as foflows: Critical Step STEP 5:

VCT Leakage = (INITIAL VCT LEVEL - FINAL VCT LEVEL) x 19.27 gal/%

tT (Step [lj)

VCT Leakage ( 31.5% - 30.2 %) x 19.27 gaII% SAT 72 mm STANDARD: Performer performs the following calculation: UNSAT VCT Leakage = 0.3479 gpm COMMENTS:

lated.

• • lfiitjzpd Cues Are To Be Used Only If JPM Performance Is Being Simu

PAGE 9 0F19 3-OT-JPMADA 2-3 Critical Step STEP 6:

[4] CALCULATE Pressurizer (PZR) Leakage as follows:

[a] RECORD INITIAL and FINAL PZR PRESSURE in _SAT tablebelow using values calculated in Step [2].

[b] RECORD INITIAL and FINAL PZR LEVEL in table below using values recorded in Appendix 8.

[cj DETERMINE and RECORD INITIAL and FINAL PZR Vf (volume of water) and Vg (volume of steam) at INITIAL and FINAL PZR PRESS (Step [2)) using ASME Steam UNSAT Tables (Table 2, Properties of Saturated Steam and Saturated Water).

STEP PARAM INITIAL FINAL PZR PRESS psia psia

[a)

(b] PZRLEVEL PZR Vf Ibm

/ft 3 /ft 3 lbm

[C]

PZR V Ibm

/ft 3 3lbm

/ft STANDARD: Performer determines that:

PZR V 1 is between 0.026 ft 3 /Ibm 3 !Ibm and 0.027 ft (calculated value 0.02698 ft 3 /Ibm)

PZR Vg is between 0.156 ft /Ibm and 0.158 3 3 Ibm

/ft (calculated value 0.157025 ft 3 /Ibm)

COMMENTS:

• • u...f;,4ir1 (sic .1rp Th Re Used Only if JPM Performance Is Being Simulated

PAGE 10 0F19 3-OT-JPMADA 2-3 Critical Step STEP 7* [4] CALCULATE Pressurizer (PZR) Leakage as follows:4 (Continued)

[d] CALCULATE INITIAL PZR VOLUME as follows:

__SAT INITIAL = (PZR LVL + 100- PZR LVL) x 16.73 ft3l% x 7.4805 gai/ft3 x 0.01605 ft3/ibm PZR Vf Vg VOLUME 60.24 100- 60.24 ) x 2 gal ft3/% ibm UNSAT INITIAL = +

PZR Vf Vg VOLUME STANDARD: Performer performs the following calculation and determines that:

Initial Pzr Volume is 4971 .946 gal COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 11 0F19 3-OT-JPMADA 2-3 Critical Step STEP 8 [4] CALCULATE Pressurizer (PZR) Leakage as follows:4 (Continued)

[e] CALCULATE INITIAL PZR VOLUME as follows:

SAT FINAL = (PZR LVL + 100- PZR LVL)x 16.73 ft3I% x 7.4805 gaI/ft3 x 0.01605 ft3Iibm PZR Vf Vg VOLUME (59.55 ÷ 100-59.55 )x2gal ft3I% ibm UNSAT FINAL =

PZR Vf Vg VOLUME STANDARD: Performer performs the following calculation and determines that:

Initial Pzr Volume is 4929.5856 gal COMMENTS:

Iated

• • ItIit.i7d Cues Are To Be Used Only if JPM Performance Is Being Simu

PAGE 12 OF 19 3-OT-JPMADA 2-3 Critical Step STEP 9 [4] CALCULATE Pressurizer (PZR) Leakage as follows:4 (Continued)

[F] CALCULATE PZR Leakage as follows: SAT (Step [dj) (Step [ej)

PZR Leakage INITIAL - FINAL PZRVOLUME PZRVOLUM E T(Step [1])

UNSAT PZR Leakage =

mm PZR Leakage = gpm STANDARD: 4971.946198 gal - 4929.5856 gal 172 mm Performer determines that the PZR Leakage is 0.588 gpm:

COMMENTS:

STEP 10: [5) IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL 4

THEN SAT STANDARD: Performer determines from data that RCS Temperature did not change therefore step 5 is N/A UN SAT COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 13 0F19 3-OT-JPMADA 2-3 Critical Step STEP 11:

[6] CALCULATE Total RCS Leakage as follows:

(Step [3]) (Step [4]) (Step [5] or 0)

Total RCS Leakage = VCT Leakage + PZR Leakage + Temp Corr Total RCS Leakage = gpm + gpm + gpm SAT Total RCS Leakage = gpm U N SAT STANDARD: Performer performs the following calculation:

.3479 gpm + .588 gpm + 0 gpm = 0.9359 gpm COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 14 0F19 3-OT-JPMADA 2-3 STEP 12: [7] CALCULATE Leakage to Pressurizer Relief Tank (PRT) as follows:

[a] CONVERT INITIAL and FINAL PRT LEVEL from percent (%) to gallons using TI-4Part II, and SAT RECORD the converted PRT LEVELS in Step [b}.

[b) CALCULATE Leakage to PRT using the following equation:

UN SAT Leakage = FINAL PRT LVL INITIAL PRT LVL To PRT zXT (Step [1))

Leakage = ( aI - cal)

ToPRT _min Leakage = gpm To PRT STANDARD: Performer determines that since the PRT level did not change the Leakage to the PRT is 0 gpm.

COMMENTS:

t cized

• • lta i , Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 15 0F19 3-OT-JPMADA 2-3 STEP 13:

[8] CALCULATE Leakage to Reactor Coolant Drain Tank (RCDT) as follows:

[a] CONVERT INITIAL and FINAL RCDT LEVEL from percent (%) to gallons using TI-4, Part II, and SAT RECORD the converted RCDT LEVELS in Step [bJ.

[b] CALCULATE Leakage to RCDT using the following equation:

Leakage = FINAL RCDT LVL INITIAL RCDT LVL UNSAT To RCDT \T (Step [1])

Leakage = ( gal - gal)

To RCDT mm Leakage = gpm To RCDT STANDARD: Performer determines that since the RCDT level did not change the Leakage to the RCDT is 0 gpm.

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 16 0F19 3-OT-JPMADA 2-3 Critical Step STEP 14:

[9) CALCULATE Identified Leakage as follows:

(Section 4.1 (Step [7]) (Step [81) Step [6])

Identified = Leakage ÷ Leakage + Total SG SAT Leakage To PRT to RCDT Leakage Identified = gpm + gpm + gpm Leakage UNSAT Identified = gpm (Acc Crit: 10 gpm)

STANDARD: Performer determines that Identified Leakage is 0 gpm. -

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 17 0F19 3-OT-JPMADA 2-3 Critical Step STEP 15:

[10] CALCULATE Unidentified Leakage as follows:

(Step [6]) (Step [9])

Unidentified = Total RCS Leakage Identified Leakage Leakage SAT Unidentified = gpm - gpm Leakage Unidentified = gpm (Acc Crit: 1 gpm) UNSAT STANDARD: Performer performs the following calculation:

09359 gpm + 0 gpm = 0.9359 gpm COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 18 0F19 3-OT-JPMADA 2-3 STEP 16:

ENSURE independently verified.

SAT STANDARD: Performer reports that the task is completed and gives calculation to the SRO for independent verification.

COMMENTS: UNSAT Examiner Acknowledge report, notify performer that the task is cue: complete. End task TIME STOP:

• • !talicized Cues Are To Be Used Only if JPM Performance Is Being Simulated.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I wiH 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:

• The unit is in Mode 1 at 100% power.

• The Plant Computer program RCSWIB is unreliable.

• 1-Sl-68-32 Appendix A has been completed through step 4 (2nd Data Set has been taken)

• You are an extra operator.

INITIATING CUES:

• Due to a suspected problem with RCSWIB, the Unit SRO has directed you to perform a manual calculation of RCS inventory balance.

• Report the results of the surveillance to the Unit SRO.

Rev. 1 Page 1 of 9 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA3-1 TASK TITLE: DETERMINE IF PERSONNEL WILL EXCEED ADMINISTRATIVE DOSE LIMITS WHILE PERFORMING TASK

Rev.1 Page2of9 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.3-1 NUCLEAR TRAINING REVISION/USAGE LOG Rev # Date Description of changes Pages Affected Reviewed By 0 Initial Issue, NRC JPM exam question. All H.J. Voiles Does not need to be word processed.

1 03/04/08 Added the option for another route to the All D.L.Hughes task area. Corrected K/A references to comply with revision 2 supplement 1 of NUREG 1122

Rev. 1 3-OT-JPMADA.3-1 Page 3 of 9 REGION II INITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: DETERMINE IF PERSONNEL WILL EXCEED ADMINISTRATIVE DOSE LIMITS WHILE PERFORMING TASK Alternate Path: N/A Facility JPM #: 3-OT-JPMADA3-1 K/A Rating(s): 2.3.7 [3.5/3.6]

Task Standard: Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Perform X Simulate

References:

SPP 5.1 Rev 0006 Radiological Controls Task Number:: AUO-1 1 9-SSP-5.01 -001 APLICABLE FOR: AUO/RO/SRO IOCFR55.45: 10 Validation Time: 15 mm. Time Critical: No Applicant: Time Start:

NAME SSN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

Rev. 1 3-OT-JPMADA.3-1 Page 4 of 9 Tools/Equipment/Procedures Needed:

Calculator NOTE TO EVALUATOR: Hand out the Applicant Data Sheet along with the Applicants Cue Sheet.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. 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:

The unit had experienced a valid safety injection signal.

The unit had also experienced a loss of both Unit I shutdown boards and RCP Seal Injection and thermal barrier cooling have been isolated per ECA-O.O Appendix A.

Shutdown Board 1A has been re-energized and control room dispatches you to locally start IA TBBP and throttle open the discharge valve.

A survey map is available for elevation 737 of the auxiliary building, showing dose rates and travel times to reach the TBBP Discharge valve that you will throttle open.

Three NAUOs are available for assignment to perform this task. All 3 NAUOs have a current NRC FORM-4 documenting current year and previous years exposures.

RADCON personnel are currently unavailable to provide assistance.

INITIATING CUES:

You have been directed to determine the NAUO (s) that could perform task without exceeding NORMAL administrative limits (EP1P 15 Emergency Exposure Guidelines is not to be considered):

• NAUO 1 has TEDE of 631 niRem

• NAUO 2 has TEDE of 603 mRem

• NAUO 3 has TEDE of 613 mRem

Rev. 1 3-OT-JPMADA.3-1 Page 5 of 9 START TIME:

NOTE TO EVALUATOR: The following steps may be performed out of order.

STEP 1: Calculate Exposure during pump start and throttle valve Critical Task operation.

SAT STANDARD: (1.2 R/hr)(1000MR!R)(1HR/6OMin)(10 Mm) = 200 MR EVALUATOR QUE: If the operator locates the current revision of SPP 5.1 UNSAT Radiological Controls, a copy may be given to him/her.

COMMENTS: -

STEP 2: Calculate the exposure getting to task area and return.

STANDARD: Dose received for 2 way travel for survey area B : SAT (2.7 R/hr)(1000MR/R)(1HR!6OMin)(4 Mm) = 180 MR Dose received for 2 way travel for survey area C : UNSAT (4.0 R/hr)(I000MR/R)(1HR!6OMin)(3 Mm) = 200 MR Determines that Route B is the route to take.

COMMENTS:

• • ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Rev. 1 3-OT-JPMADA.3-1 Page 6of9 STEP 3: Calculate total dose for job.

Critical Task STANDARD: Dose received for 2 way travel for survey area B are added to dose received in Survey Area A: SAT

1) TwowaySurveyArea B 180 MR

2) Dose in SurveyAreaA= 200 MR

3) Total Dose = 200 MR + 180 MR 380 MR UNSAT COMMENTS:

STEP 5: Determine total dose that would be received for all NAUO.s involved.

SAT STANDARD: Performer Determines dose that would be received by NAUOs.

1) NAUO #1: 631 mrem +/- 380 mrem = 1011 mrem

2) NAUO #2: 603 mrem + 380 mrem = 983 mrem

3) NAUO #3: 613 mrem + 380 mrem = 993 mrem UNSAT COMMENTS:

STEP 5: Determines which NAUC can perform tasks without exceeding Critical Task Administrative limits.

STANDARD: Performer determines NAUOs #2 and #3 are the only NAUOs SAT that could perform task.

COMMENTS:

UNSAT END OF TASK TIME STOP:

• • lta!icizQd Cues Are To Be Used Only If JPM Performance Is Being SimuIated

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. 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:

The unit had experienced a valid safety injection signal.

The unit had also experienced a loss of both Unit 1 shutdown boards and RCP Seal Injection and thermal barrier cooling have been isolated per ECA-O.O Appendix A.

Shutdown Board 1A has been re-energized and control room dispatches you to locally start 1A TBBP and throttle open the discharge valve.

A survey map is available for elevation 737 of the auxiliary building, showing dose rates and travel times to reach the TBBP Discharge valve that you will throttle open.

Three NAUOs are available for assignment to perform this task. All 3 NAUO5 have a current NRC FORM-4 documenting current year and previous years exposures.

RADCON personnel are currently unavailable to provide assistance.

INITIATING CUES:

You have been directed to determne the NAUO (s) that could perform task without exceeding NORMAL admirstrative limits (EPIP 15 Emergency Exposure Guideline is not to be considered):

• NAUO #1 has TEDE of 631 mRem

• NAUO 2 has TEDE of 603 mRem

• NAUO 3 has TEDE of 613 rnRem

APPLICANT DATA SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

SURVEY DATA:

• TBBP control switches and pump discharge FCV are located in Survey area A.

• Estimated time at control switch and discharge valve is 10 minutes.

• ONE-way travel time to Valve & control switches via route B is 2 minutes.

• ONE-way travel time to Valve & control switches via route C is 1 minute 30 seconds.

• General Area Dose rate for Survey Area A is 1 .2 R/hr.

• General Area Dose rate for Survey Area B is 2.7 RIhr.

• General Area Dose rate for Survey Area C is 4.0 RIhr.

• NAUO#1 has TEDE of 631 mRem

• NAUO #2 has TEDE of 603 mRem -

• NAUO #3 has TEDE of 613 mRem RESULTS:

Indicate below by checking yes or no if the respective NAUO can be allowed to perform task without exceeding administrative dose limits.

YES NO NAUO#1 LI Li NAUO#2 Li Li NAUO#3 Li LI

APPLICANT DATA SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

AUXILIARY BLDG ELEV. 737 G/A I. U/2 I leating & Ventilation Room

2. U/2 Vent & Purge Air Room

3. U/2 Gross Failed Fuel Detector Roen

4. Spent Fuel Pool Equipment Area

5. U/i Letdown Heat Exclmnger Ron.::

fl

6. U/2 Letdown Heat Exchanoer Rou::

7. U/I Gross Failed Fuel Detector Ro:n

8. U/I Vent & Purge Air Room

9. U/l Ileating & Ventilation Room i[

1

10. Hot Instrument Shop ii. Component Cooltng Heat Exchai:ees

REV. 0 PAGE 1 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b TASK TITLE: CLASSIFY THE EVENT PER THE REP (LOCA WITH SIGNIFICANT FUEL FAILURE AND POTENTIAL LOSS OF CONTAINMENT)

REV. 0 PAGE 2 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b NUCLEAR TRAINING REVISION/USAGE LOG REV # Date Description of Changes Pages Affected Reviewed By 0 03/05/08 Initial issue, generated for NRC Initial License ALL D.L.Hughes Exam

PAGE 3 0F17 REV. 0 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b EVALUATION SHEET POTENTIAL LOSS Task: Classify The Event Per The REP (LOCA WITH SIGNIFICANT FUEL FAILURE AND OF CONTAINMENT)

Alternate Path: N/A Facility JPM #: 3-OT-JPMSO81b CE RO 3.1 SRO 4.4 K/A Rating(s): 2.4.29 Knowledge of the emergency plan. IMPORTAN Two Barriers Task Standard: The event is classified as an GENERAL EMERGENCY based on Loss Of Any And A Potential Loss Of Third Barrier Notifications are made per EPIP-5 .

Preferred Evaluation Location: Preferred Evaluation Method:

In-Plant Perform X Simulate Simulator X This JPM will be simulated.

RAL

References:

EPIP-1 Emergency Plan Classification Flowpath, Rev. 27; EPIP-5 GENE EMERGENCY, Rev. 34 Task Number: SRO-1 1 3-EPIP-001 APPLICABLE FOR: SRO IOCFR55.45: 10, 11, 12 Validation Time: 20 mm. Time Critical: Yes Time Start:

Applicant:

NAME SSN/EIN Time Finish:

SAT UNSAT Performance Time Performance Rating:

/

Examiner: DATE NAME SIGNATURE COMMENTS

REV. 0 PAGE 4 OF 17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b EVALUATOR INFORMATION SHEET T FUEL FAILURE TASK TITLE: CLASSIFY THE EVENT PER THE REP (LOCA WITH SIGNIFICAN AND POTENTIAL LOSS OF CONTAINMENT)

SIMULATOR SETUP INSTRUCTIONS:

ions.

NONE: THIS JPM IS SIMULATED and the simulator will not be used to reflect the condit REQUIRED MATERIALS:

EPIP-1 and EPIP-5 SAFETY CONSIDERATIONS:

None Tools/Equipment/Procedures Needed:

tions on the Ensure clean copy of EPIP-1 and EPIP-5 in all copies of Emergency Instruc Simulator Floor and in the file drawer of Unit Supervisors desk.

sheets are to be Print out Met Tower Cue Sheets on following 3 pages. The Met Tower cue Integra ted Computer given to the performer when they are obtaining information from the System (ICS).

SIMULATOR OPERATOR INSTRUCTIONS:

er.

1. Obtain copy of EPIP-5 to facilitate role plays for contacts made by the perform

2. Performer must use NRC ring down phone.

EDS METDATA 46M AVG 5O 360/0 10 340 20 WIND DIR & SPEED 330 30 AAH [/R 40 N ET46A1 5 S [LAM PLAN 310 ..

50 MI/HR 300 / 60 [1ET46D15 I

2907 70 DEGREES 1

a flta (FROM)

//

4 - 80 280 / .

a 1II

,i W 270 j -

I 90 E WA I 1 E31R Fl a

L( HAR 260

/ 1U0 pko1Fr1FD ARE: 110 250\

140 150 200 160 190 170 I I Ij ri

i;i j

I

IIJ 1:.. hLKI ii Dr

4 I

I BN PEr

REV. 0 PAGE 8 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b Ensure clean copy of EPIP-1 and EPIP-5 in all copies of Emergency Instructions on the Simulator Floor and in the file drawer of Unit Supervisors desk.

READ TO OPERATOR DIRECTION TO TRAINEE:

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.

THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.

INITIAL CONDITIONS:

- Unit 1 was at 100% RTP when a LOCA occurred.

- An SI occurred due to high containment pressure.

- RCS pressure stabilized at 350 psig saturated conditions.

- The CLAs are injecting.

shortly

- The ONLY ECCS pump in service is the 1 B-B RHR pump, all other ECCS pumps tripped after the SI.

- Containment pressure is 1 .8 psig and stable.

- 1-RM-90-273 & 1-RM-90-274 have risen to 35 rem/hr.

RM-90-271 & 1-RM-90-272 have risen to 60 rem/hr.

Containment Hydrogen concentration is 6% as indicated on the H2 analyzers.

The STA reports a RED path condition exists on core cooling.

You are the SM/SRO INITIATING CUES:

The Unit Supervisor has informed you of the above conditions.

The operators are taking actions per the emergency instructions (currently transitioning from E-1 to FR-C.1).

You are to make the initial classification of the event per the REP EPIPs and make required notifications.

Portions of this JPM are time critical.

REV. 0 PAGE 9 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b START TIME:

STEP 1: Refers to EPIP-1 to determine level of event. CRITICAL STEP STANDARD: Performer refers to EPIP-1 and declares a GENERAL EMERGENCY based on Loss Of Any Two Barriers And A Potential Loss Of Third Barrier (1.1.1 Loss, 1.2.2 Loss, SAT 1.3.2 Potential Loss) This must be completed within 15 minutes of task assignment.

This step is critical to ensure proper activation of TVA UNSAT resources for event in progress.

COMMENTS: RECORD time that declaration was made:________ -

STEP 2: Implements EPIP-5, GENERAL EMERGENCY SAT STANDARD: EPIP-5, GENERAL EMERGENCY, is implemented.

COMMENTS: UNSAT

REV. 0 PAGE 10 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 3: [1] IF the onsite emergency centers are not staffed, THEN CRITICAL DIRECT Shift Personnel to activate the Emergency Paging STEP System (EPS) to staff the Technical Support Center (TSC) and Operations Support Center (OSC). Shift Personnel SAT should confirm activation and provide the 20 minute printed 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. UNSAT 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: The SRO activates the emergency paging system (EPS) to staff the TSC and Operations Support Center (OSC) or EPS is activated in the control room.

This step is critical to ensure proper activation of TVA resources for event in progress.

• • CUE: After the shift personnel are notified, acknowledge the request to activate the Emergency Paging System.

COMMENTS:

REV. 0 PAGE 11 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 4: [2] IF the TSC has not been activated, THEN

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

STANDARD: Appendix A is accurately completed with SAT

1. This is a Drill

2. Their name, Shift Manager (SED) at WBN Plant.

General Emergency declared on UNIT 1

3. EAL Designators: [LOSS 1.1.1 and LOSS 1.2.2, and UNSAT Potential LOSS 1.3.2]

4. Brief description of incident: [RCS LOCA with a Loss of Subcooled Margin, Loss of Core Cooling and High Hydrogen concentration in Containment] (or something similar)

5. Radiological Conditions [Either Release information not known or Minor releases within federally approval limits]

6. Event Declared: [Time and Date]

7. Wind direction at 46 meters, coming from [73] degrees AND wind speed at 46 meters [4.8] mph.

Evaluator Cue (1): The Met Tower cue sheets are to be given to the performer when they are obtaining information from the Integrated Computer System (ICS).

Evaluator Cue (2): When release data addressed, state Release data not available for Appendix B.

NOTE TO EVALUATOR: Items 2, 3, 6, and 7 above are the critical parts.

• Items 2 & 3 are critical due to correct EALs must be used for General Emergency declaration.

• Item 6 is critical and it must be within 15 minutes of the performer stating that they understand their task and the JPM is started.

• Item 7 is criticalto ensure proper protective actions are recommended.

COMMENTS:

REV. 0 PAGE 12 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b Critical Step STEP 5:

Appendix B:

SAT STANDARD: Operator determines from page 15, logic chart in EPIP-5, that appropriate protective action recommendation is RECOMMENDATION 2. This should be identified on the notification form in the next JPM step.

UN SAT COMMENTS Critical Step STEP 6:

Appendix A completion:

SAT STANDARD: Appendix A is accurately completed with:

Item 8:

UN SAT LI Recommendation 2 is checked 69-110 A-lB-iC-iD-i, A-3, D-2, -4, -5 is checked (Both blocks should be checked)

COMMENTS

REV. 0 PAGE 13 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 7: [2.bJ NOTIFY the ODS direct by ODS Ring-down or by CRITICAL USING 5-751-1 700 or 5-751-2495 and STEP

1) PROVIDE the information from Appendix A.

2) FAX Appendix A to the ODS. (# pre-programmed or 5- SAT 751-8620).

STANDARD: The ODS is notified and provided the information on Appendix A. This notification must be made within 10 UNSAT minutes of event declaration. Appendix A is placed in the fax machine and transmission simulated.

EVALUATOR NOTE: DO NOT allow actual call to actual ODS. Ensure call is made to simulator operator

• • CUE: (Booth Operator) Role play as the ODS and repeat back the report.

• • CUE: Do NOT allow fax to be actually transmitted.

COMMENTS: RECORD time that ODS was notified:

REV. 0 PAGE 14 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 8: [2.c] IF the ODS CANNOT be contacted within 10 minutes, THEN

1) NOTIFY Rhea County, Meigs County, McMinn County, and the Tennessee Emergency Management Agency SAT (TEMA) of the Classification USING the contact information in Appendix E.

2) FAX Appendix A to TEMA at 9-1 -61 5-242-9635.

UNSAT STANDARD: Performer N/As step since ODS was previously notified.

COMMENTS:

STEP 9: [2.dJ ANNOUNCE to the crew: A GENERAL EMERGENCY is CRITICAL being declared based on Loss of Two Barriers and STEP Potential Loss Of A Third Barrier. I will be the Site Emergency Director. SAT STANDARD: The above announcement is made to the crew. Wording describing the event may vary.

Step is critical to alert crew to the declaration of the UNSAT GENERAL EMERGENCY and provide for tracking personnel.

• • CUE: After the crew is notified, acknowledge the report.

COMMENTS:

REV. 0 PAGE 15 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 10: [2.e] TRACK dispatched personnel by name, and PERFORM one of the following:

• IFOSCisnotstaffed,THENINFORM SAT Maintenance Shift Supervisor of names for team tracking.

• WHEN OSC is staffed, THEN INFORM OSC manager of names for team tracking. UNSAT STANDARD: Maintenance Shift Supervisor is notified of names for team tracking.

• • CUE: (As Crew Member) If asked, State that Control Bldg AUQ John Doe was dispatched to evaluate lB 6.9 KV Shutdown Board.

• • CUE: (Booth Operator) Role play as the Maintenance Shift Supervisor or OSC manager and repeat back the report.

COMMENTS:

STEP 11: [5] ANNOUNCE to the plant: ATTENTION ALL SITE CRITICAL PERSONNEL. ATTENTION ALL SITE PERSONNEL. A STEP GENERAL EMERGENCY has been declared based on Loss of two barriers and potential loss of a third barrier. SAT Staff the TSC and OSC. (Repeat)

STANDARD: A public address announcement for Plant Emergency Response Personnel to staff the TSC and OSC is made UNSAT over the plant paging system. Wording describing the event may vary.

Step is critical to alert plant to the declaration of the GENERAL EMERGENCY.

COMMENTS:

REV. 0 PAGE 16 0F17 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO8I b STEP 12: [6] INITIATE WBN EPIP-8, Personnel Accountability and Evacuation, Appendix D.

SAT EVALUATOR CUE: When the performer starts to refer to EPIP-8, inform him/her that another SRO will continue on UNSAT from here. Notify performer that the task is complete.

End of task COMMENTS:

TIME STOP:

PERFORMER HANDOUT SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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.

THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.

INITIAL CONDITIONS: -

- Unit 1 was at 100% RTP when a LOCA occurred.

- An SI occurred due to high containment pressure.

- RCS pressure stabilized at 350 psig saturated conditions.

- The CLAs are injecting.

- The ONLY ECCS pump in service is the lB-B RHR pump, all other ECCS pumps tripped shortly after the SI.

- Containment pressure is 1.8 psig and stable.

- 1-RM-90-273 & 1-RM-90-274 have risen to 35 rem/hr.

RM-90-271 & 1-RM-90-272 have risen to 60 rem/hr.

- Containment Hydrogen concentration is 6% as indicated on the H2 analyzers.

- The STA reports a RED path condition exists on core cooling.

- You are the SM/SRO INITIATING CUES:

The Unit Supervisor has informed you of the above conditions.

The operators are taking actions per the emergency instructions (currently transitioning from E-1 to FR-C.1).

You are to make the initial classification of the event per the REP EPIP5 and make required notifications.

Portions of this JPM are time critical.