Latest revision as of 09:06, 12 March 2020

Text

Initial Exam 2009-301 Final Administrative JPMs
	ML092810557
Person / Time
Site:	Watts Bar
Issue date:	10/08/2009
From:	; NRC/RGN-II
To:	;
References
	50-390/09-301, 50-391/09-301
	Download: ML092810557 (107)
	v • d • e

Page 1 of 106 WATTS BAR NUCLEAR PLANT A.1-1 RO A.1-1 RO Calculate Shutdown Margin.

Page 2 of 106 WATTS BAR NUCLEAR PLANT A.1-1 RO EVALUATION SHEET Task: Calculate Shutdown Margin.

Alternate Path: N/A Facility JPM #: 3-OT-JPMADA-1.3 K/A Rating(s): 001A4.11 Ability to manually operate and/or monitor in the control room:

Determination of SDM [3.5/4.1] (CFR: 41.7/45.5 to 45.8).

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

[3.9/4.2] (CFR: 41.10 / 43.5 / 45.12).

Task Standard: Applicant completes a Conservative SDM Hand Calculation per 1-SI-0-10, Shutdown Margin, Section 6.2. Conservative Hand Calculation, and determines present boron concentration is inadequate for cooldown.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

1-SI-0-10, Shutdown Margin, Rev. 21; NUPOP, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2; NOB, Unit 1 Nuclear Operating Book, Sheet A-3, Rev 59.

Task Number: RO-085-SI-0-10-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5, 12 Validation Time: 20 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Page 3 of 106 WATTS BAR NUCLEAR PLANT A.1-1 RO Tools/Equipment/Procedures Needed:

Latest revision of 1-SI-0-10, Shutdown Margin.

NUPOP, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2.

NOB, Unit 1 Nuclear Operating Book, Sheet A-3, Rev 59.

Ruler or straight edge.

Calculator NOTE: START THIS JPM AT A LOCATION WHERE APPLICANT HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide applicant with procedure).

Rev. 0 A.1-1 RO Page 4 of 106 READ TO OPERATOR DIRECTION TO APPLICANT:

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:

1. The Unit has tripped and requires a cooldown to 220°F.

2. ICS Point U7981 indicates core average burnup is 7500 MWD/MTU.

3. All control rods have fully inserted into the core.

4. At least one reactor coolant pump will remain in operation until cooldown is complete. RCP #2 is running and is to remain running for the entire cooldown.

5. RCS boron concentration is 1500 ppm.

6. You are an extra Unit Operator.

INITIATING CUES:

The SM/Unit SRO has directed you to perform 1-SI-0-10 Shutdown Margin, Section 6.2, Conservative SDM Hand Calculation, beginning at Step 3.

Base the calculation on the conditions stated above.

1. Determine the required RCS boron concentration.

2. Determine if Acceptance Criteria are met.

3. Notify SM/Unit SRO of the required RCS boron concentration.

Rev. 0 A.1-1 RO Page 5 of 106 START TIME: _______

STEP 1: Obtain a copy of the instruction.

___ SAT STANDARD: A copy of 1-SI-0-10 Shutdown Margin has been obtained.

EXAMINERS CUE: Provide the applicant a copy of the instruction.

___ UNSAT COMMENTS:

NOTE Due to the amount of conservatism factored into this calculation, this instruction may NOT pass acceptance criteria if performed in MODES 1 or 2. During MODES 1 or 2, perform Sections 6.3 or 6.4.

STEP 2: [3] OBTAIN the NuPOP for the applicable cycle AND RECORD: ___ SAT A. The WCAP number and cycle number:

WCAP - _____________________ Cycle _________

B. The Maximum Stuck Rod Worth.

Table D1, (Mode 2 below nuclear heating through Mode ___ UNSAT 5):

________pcm STANDARD: Applicant records WCAP- 16880-P and Cycle 9. Applicant records 1242 pcm.

COMMENTS:

NOTES

1) It is permissible to use a conservative RCS temperature to bound a potential plant cooldown. Remember that Mode 4 is more limiting than Mode 5.

2) Number of immovable/untrippable rods refers to the actual number of immovable/untrippable rods, NOT the one that is assumed to be untripped from the definition of SDM

Rev. 0 A.1-1 RO Page 6 of 106 STEP 3: [4] DETERMINE the following plant conditions: ___ SAT A. Core average burnup: ________MWD/MTU (ICS computer point U7981) and check the applicable core life below as defined in NuPOP Section 8.3.

Beginning of Life ___ UNSAT Middle of Life End of Life B. Number of immovable/untrippable rods: ________

C. Minimum Tcold for the desired condition: ________°F D. RCS Boron Concentration CB: ________ppm STANDARD: Applicant records the following:

A. Core average burnup: 7500MWD/MTU.

From Section 8.3, Applicant checks Middle of Life box.

B. Number of immovable/untrippable rods: 0 C. Minimum Tcold for the desired condition: 220 °F D. RCS Boron Concentration Cb: 1500 ppm COMMENTS:

Rev. 0 A.1-1 RO Page 7 of 106 STEP 4: [5] IF there are immovable/untrippable rods, THEN ___ SAT A. RECORD the differential Boron Worth using burnup from Step 6.2[4]A and RCS Boron Concentration from Step 6.2[4]D:

Differential Boron Worth: ________pcm/ppm. ___ UNSAT (See NuPOP Figure 6-22) ________

B. CALCULATE the absolute value stuck rod correction

________ x ________ pcm ÷ ________ pcm / ppm (Step 6.2[4]B) (Step 6.2[3]B ) (Step 6.2[5]A)

Stuck rod correction (absolute value) = _________ ppm.

STANDARD: Applicant enters N/A for this step, since the Cue Sheet stated that there were NO UNTRIPPABLE RODS.

NOTE: If the applicant completes the calculation, the value entered will still be ZERO.

____0_____ x __1242__pcm ÷ __-6.5 pcm/ppm (Step [4] B) (Step [3] B) (Step [4] E)

Stuck rod correction = __0 __ ppm.

COMMENTS: Applicant may enter a 0 for the stuck rod correction without looking up data since there are no additional stuck rods, and the step is CONDITIONAL (IF...THEN)

STEP 5: [6] RECORD the (M-P)SDM from NOB Sheet A-3. CRITICAL (M-P)SDM = ________ppm. STEP STANDARD: Applicant obtains the required value by referring to the NOB ___ SAT sheet A-3. records it in the procedure blank.

(M-P)SDM = 90 ppm.

Step is critical, since an incorrect entry will affect the ___ UNSAT calculated value for SDM.

COMMENTS:

Rev. 0 A.1-1 RO Page 8 of 106 STEP 6: [7] CALCULATE required RCS CB. CRITICAL STEP

[a] DETERMINE UNCORRECTED Maximum Required CB, from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:

___ SAT UNCORRECTED Max Required CB = __________ ppm.

STANDARD: Applicant obtains the required value by referring to the NuPOP Table 7-4 for 7500 MWD/MTU and 220°F records value in the ___ UNSAT procedure blank.

UNCORRECTED Max Required CB = 1547 ppm.

Step is critical, since an incorrect entry will affect the calculated value for SDM.

COMMENTS:

STEP 7: [7b] CALCULATE required RCS CB. CRITICAL STEP

[b] CALCULATE the Required CB

__________ + __________ + ____________ ___ SAT (Step [5]) (Step [6]) (Step [7] [a])

Required CB = ______________ ppm.

___ UNSAT STANDARD: Applicant calculates the sums from Step [5], Step [6] and Step 7a, and enters the valve calculated in the Required Cb blank.

__0 ___ + ___90____ + ___1547_____

(Step [5]) (Step [6]) (Step [7] [a])

Required CB = __1637____ ppm Step is critical, since an incorrect entry will affect the calculated value for SDM, and will lead to violating the SDM requirements.

COMMENTS:

Rev. 0 A.1-1 RO Page 9 of 106 STEP 8: [8] VERIFY That RCS CB in Step [4] D is greater than or equal to CRITICAL the Required CB in Step [7}[b] (Acc Crit. A & B). STEP STANDARD: Applicant determines that the acceptance criteria are NOT ___ SAT MET. Value in step [4] D is less than Value in Step [7] [b] and reports to the Unit Supervisor.

EVALUATOR CUE: Role play as SM/Unit supervisor and acknowledge ___ UNSAT report.

COMMENTS:

END OF TASK TIME STOP: ________

Rev. 0 Page 10 of 106 WATTS BAR NUCLEAR PLANT A.1-1SRO 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:

1. The Unit has tripped and will require a Unit Cooldown to 220°F.

2. ICS Point U7981 indicates core average burnup is 7500 MWD/MTU.

3. All control rods have fully inserted into the core.

4. At least one reactor coolant pump will remain in operation until cooldown is complete. #2 RCP is running and is to remain running for the entire cooldown.

5. RCS boron concentration is 1500 ppm.

6. You are an extra Unit Operator.

INITIATING CUES:

The SM/Unit SRO has directed you to perform 1-SI-0-10 Shutdown Margin, Section 6.2, Conservative SDM Hand Calculation, beginning at Step 3.

Base the calculation on the conditions stated above.

1. Determine the required RCS boron concentration.

2. Determine if Acceptance Criteria are met.

3. Notify SM/Unit SRO of the required RCS boron concentration.

Rev. 0 Page 11 of 106 WATTS BAR NUCLEAR PLANT A.1-1SRO A.1-1 SRO Perform Technical Review of Shutdown Margin Calculation.

Rev. 0 Page 12 of 106 WATTS BAR NUCLEAR PLANT A.1-1SRO EVALUATION SHEET Task: Perform Technical Review of Shutdown Margin Calculation.

Alternate Path: N/A Facility JPM #: New K/A Rating(s): 001A4.11 Ability to manually operate and/or monitor in the control room:

Determination of SDM [3.5/4.1] (CFR: 41.7/45.5 to 45.8).

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

[3.9/4.2] (CFR: 41.10 / 43.5 / 45.12).

Task Standard: Applicant completes a Technical Review of Shutdown Margin Calculation Conservative SDM Hand Calculation per 1-SI-0-10, Shutdown Margin, Section 6.2. Determine Required RCS Boron Concentration, determines present boron concentration is inadequate for cooldown due to multiple errors made in transposing data and performing calculations.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

1-SI-0-10, Shutdown Margin, Rev. 21; NUPOP, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2; NOB, Unit 1 Nuclear Operating Book, Sheet A-3, Rev 59.

Task Number: RO-085-SI-0-10-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5, 12 Validation Time: 15 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Rev. 0 Page 13 of 106 WATTS BAR NUCLEAR PLANT A.1-1SRO Tools/Equipment/Procedures Needed:

Latest revision of 1-SI-0-10, Shutdown Margin.

NUPOP, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2.

NOB, Unit 1 Nuclear Operating Book.

Ruler or straight edge.

Calculator NOTE: START THIS JPM AT A LOCATION WHERE APPLICANT HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide Applicant with procedure).

Rev. 0 A.1-1SRO Page 14 of 106 READ TO OPERATOR DIRECTION TO APPLICANT:

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:

7. The Unit has tripped and requires a cooldown to 220°F.

8. ICS Point U7981 indicates core average burnup is 7500 MWD/MTU.

9. All control rods have fully inserted into the core.

10. At least one reactor coolant pump will remain in operation until cooldown is complete. #2 RCP is running and is desired to remain running for the entire cooldown.

11. RCS boron concentration is 1500 ppm.

12. You are the Unit SRO.

INITIATING CUES:

The SM has directed you to perform a technical review of the Conservative SDM Hand Calculation per 1-SI-0-10 Shutdown Margin, Section 6.2 which was calculated based on these conditions.

Rev. 0 A.1-1SRO Page 15 of 106 START TIME: _______

STEP 1: Obtain a copy of the instruction.

___ SAT STANDARD: A copy of 1-SI-0-10, Shutdown Margin has been obtained.

EXAMINERS CUE: Provide the applicant a copy of the completed 1-SI-0-1, Shutdown Margin Section 6.2, Determine ___ UNSAT Required RCS Boron Concentration.

COMMENTS:

NOTE Due to the amount of conservatism factored into this calculation, this instruction may NOT pass acceptance criteria if performed in MODES 1 or 2. During MODES 1 or 2, perform Sections 6.3 or 6.4.

STEP 2: [1] ENSURE precautions and limitations in Section 3.0 have been reviewed. ___ SAT STANDARD: Applicant reviews Section 3.0 Precautions and Limitations.

COMMENTS: ___ UNSAT STEP 3: [2] ENSURE prerequisite actions in Section 4.0 have been met.

___ SAT STANDARD: Applicant determines that Section 4.0 is complete.

COMMENTS: ___ UNSAT

Rev. 0 A.1-1SRO Page 16 of 106 STEP 4: [3] OBTAIN the NuPOP for the applicable cycle AND RECORD: CRITICAL B. The WCAP number, unit, and cycle number (front cover of STEP NuPOP):WCAP-________ Unit ____ Cycle_____

___ SAT C. The Maximum Stuck Rod Worth.

Table D1, (Mode 2 below nuclear heating through Mode 5):

________pcm ___ UNSAT STANDARD: Applicant verifies that the information associated with A is correct. (WCAP- 16880-P Unit 1 and Cycle 9.)

Applicant determines that an incorrect value of 1020 was entered from Table D-1 and notes 1242 pcm is the correct value.

Step is critical since an incorrect data entry was made, which affects the calculation.

COMMENTS:

STEP 5: [4] DETERMINE the following plant conditions: ___ SAT A. Core average burnup: ________MWD/MTU (ICS computer point U7981) and check the applicable core life below as defined in NuPOP Section 8.3.

Beginning of Life ___ UNSAT Middle of Life End of Life B. Number of immovable/untrippable rods: ________

C. Minimum Tcold for the desired condition: ________°F D. RCS Boron Concentration CB: ________ppm STANDARD: Applicant determines the following data was entered correctly:

E. Core average burnup: 7500MWD/MTU.

From Section 8.3, Applicant checks Middle of Life box.

F. Number of immovable/untrippable rods: 0 G. Minimum Tcold for the desired condition: 220 °F H. RCS Boron Concentration Cb: 1500 ppm COMMENTS:

Rev. 0 A.1-1SRO Page 17 of 106 STEP 6: [5] IF there are immovable/untrippable rods, THEN A. RECORD the differential Boron Worth using burnup from ___ SAT Step 6.2[4]A and RCS Boron Concentration from Step 6.2[4]D:

Differential Boron Worth: ________pcm/ppm (See NuPOP Figure 6-22) ________ ___ UNSAT B. CALCULATE the absolute value stuck rod correction

________ x ________ pcm ÷ ________ pcm / ppm (Step 6.2[4]B) (Step 6.2[3]B ) (Step 6.2[5]A)

Stuck rod correction (absolute value) = _________ ppm STANDARD: This step should have an N/A entered, since the Cue Sheet stated that there were NO UNTRIPPABLE RODS.

If the performer had completed the calculation, the value entered is still ZERO.

____0_____ x __1242__pcm ÷ __-6.4 pcm/ppm (Step 6.2[4] B) (Step 6.2[3] B) (Step 6.2[5] A)

Stuck rod correction = __0 __ ppm.

COMMENTS:

Rev. 0 A.1-1SRO Page 18 of 106 STEP 7: [6] RECORD the (M-P)SDM from NOB Sheet A-3. CRITICAL (M-P)SDM = ________ppm. STEP STANDARD: Applicant determines that the value entered is incorrect, in that ___ SAT a negative sign was entered. Applicant obtains the required value by referring to the NOB sheet A-3. records it in the procedure blank.

(M-P)SDM = -90 ppm. ___ UNSAT CORRECT VALUE (M-P)SDM = 90 ppm.

Step is critical since an incorrect data entry was made, which affects the calculation.

COMMENTS:

Rev. 0 A.1-1SRO Page 19 of 106 STEP 8: [7] CALCULATE required RCS CB CRITICAL STEP

[a] DETERMINE UNCORRECTED Maximum Required CB, from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:

___ SAT UNCORRECTED Max Required CB = __________ ppm STANDARD: Applicant determines that the value entered is incorrect, ___ UNSAT Applicant obtains the required value by referring to the NuPOP Table 7-4 for 7500 MWD/MTU and 220°F records value in the procedure blank.

UNCORRECTED Max Required CB = 1556 ppm CORRECT VALUE UNCORRECTED Max Required CB = 1547 ppm Step is critical since an incorrect data entry was made, which affects the calculation.

COMMENTS:

Rev. 0 A.1-1SRO Page 20 of 106 STEP 9: [7b] CALCULATE required RCS CB CRITICAL STEP

[b] CALCULATE the Required CB

__________ + __________ + ____________ ___ SAT (Step [5]) (Step [6]) (Step [7] [a])

Required CB = ______________ ppm

___ UNSAT STANDARD: Applicant determines that the value entered is incorrect.

Applicant calculates the sums from Step [5], Step [6] and Step 7a, and enters the value calculated in the Required CB blank.

__0 ___ + ___-90____ + ___1556_____

(Step [5]) (Step [6]) (Step [7] [a])

Required CB = __1466____ ppm CORRECT VALUE

__0 ___ + ___90____ + ___1547_____

(Step [5]) (Step [6]) (Step [7] [a])

Required CB = __1637____ ppm Step is critical, since an incorrect entry will affect the calculated value for SDM, and will lead to violating the SDM requirements.

COMMENTS:

Rev. 0 A.1-1SRO Page 21 of 106 STEP 10: [8] VERIFY That RCS CB in Step [4] D is greater than or equal to CRITICAL the Required CB in Step [7] [b] (Acc Crit. A & B). STEP STANDARD: Applicant determines that the acceptance criteria is NOT MET, ___ SAT which was not initially reported. Actual corrected value in step

[4] D is less than Value in Step [7] [b].

Informs the SM that multiple errors were made in the calculation and that the Acceptance Criteria which was initially ___ UNSAT indicated as MET was NOT MET based on the corrected calculation.

Step is critical since the applicant must determine that the acceptance criteria have NOT bee met.

COMMENTS:

END OF TASK TIME STOP: ________

Page 22 of 106 WATTS BAR NUCLEAR PLANT A.1-2 RO DIRECTION TO APPLICANT:

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:

1. The Unit has tripped and requires a cooldown to 220°F.

2. ICS Point U7981 indicates core average burnup is 7500 MWD/MTU.

3. All control rods have fully inserted into the core.

4. At least one reactor coolant pump will remain in operation until cooldown is complete. RCP #2 is running and is desired to remain running for the entire cooldown.

5. RCS boron concentration is 1500 ppm.

6. You are the Unit SRO.

INITIATING CUES:

The SM has directed you to perform a technical review of the Conservative SDM Hand Calculation per 1-SI-0-10 Shutdown Margin, Section 6.2 which was calculated based on these conditions.

Page 23 of 106 WATTS BAR NUCLEAR PLANT A.1-2 RO A.1-2 RO Calculate Target Boron Cb for Load Escalation Using Appendix E of SOI-62.02, Boron Concentration Control.

Page 24 of 106 WATTS BAR NUCLEAR PLANT A.1-2 RO EVALUATION SHEET Task: Calculate Target Boron Cb for Load Escalation Using Appendix E of SOI-62.02, Boron Concentration Control.

Alternate Path: N/A Facility JPM #: 3-OT-JPMADA.1-2R K/A Rating(s): 004 Chemical and Volume Control System. A4.04 Ability to manually operate and/or monitor in the control room: Calculation of boron concentration changes [3.2/3.6] (CFR: 41/7 / 45.5 to 45.8)

Task Standard: Applicant completes a calculation for Target Boron Concentration per SOI-62.02, Appendix E Reactivity balance calculation. Target RCS Boron Concentration is determined.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

SOI-62.02, Boron Concentration Control, Rev. 48; NUPOP, WCAP-16880-P, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2.

Task Number: RO-062-SOI-62-016 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5, 12 Validation Time: 20 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Page 25 of 106 WATTS BAR NUCLEAR PLANT A.1-2 RO

A.1-2 RO Page 26 of 106 Tools/Equipment/Procedures Needed:

SOI-62.02, Boron Concentration Control, Rev. 48 NUPOP, WCAP-16880-P, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2 Ruler or straight edge.

Calculator NOTE: START THIS JPM AT A LOCATION WHERE APPLICANT HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide Applicant with procedure).

A.1-2 RO Page 27 of 106 READ TO OPERATOR DIRECTION TO APPLICANT:

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:

1. The Unit is operating at 76% rated thermal power.

2. Core average burnup is 12000 MWD/MTU.

3. Control Bank D rods are at 190 steps.

4. RCS Boron Concentration is 750 ppm.

5. Target Rod Position at 100% RTP will be 220 Steps on Control Bank D.

6. Power will be raised at a rate of 3% per hour.

7. Xenon printout from REACTINW has been performed by an STA.

8. You are an extra Unit Operator.

INITIATING CUES:

Using the information provided, the SM/Unit SRO has directed you to calculate Target Boron Concentration for raising power to 100% per SOI-62.02 Appendix E Reactivity Balance Calculation.

Determine the RCS Target Boron concentration.

Notify SM/Unit SRO of the RCS Target Boron Concentration.

A.1-2 RO Page 28 of 106 START TIME: _______

STEP 1: Obtain a copy of the instruction. ___ SAT STANDARD: A copy of SOI-62.02 Appendix E Reactivity Balance Calculation has been obtained.

___ UNSAT EXAMINERS CUE: Provide the applicant a copy of the instruction.

COMMENTS:

NOTE 1 One calculation is required for each major change. Calculation is an approximation of Final Target Boron CB. Rough interpolation of NuPop figures is acceptable and expected.

NOTE 2 Dilution or Boration value for power change from P1 % to P2 %

power in time period T with rods moving from step position R1 to R2. (Subscript convention: 1 = current point, 2 = target point)

Evaluator Note. JPM Steps 2 through 6 evaluate applicant's completion of the first page of Appendix E.

STEP 2: [1] CALCULATE target boron concentration by performing the following: ___ SAT Obtains: Current RCS Boron CB: __________PPM.

STANDARD: Value provided on task assignment sheet. Applicant may contact Chem Lab for current boron concentration. ___ UNSAT CUE: If CHEM LAB notified, acknowledge request, then report current RCS Boron Concentration is 750 ppm.

COMMENTS:

A.1-2 RO Page 29 of 106 STEP 3: Obtains: Core Burnup: _______MWD/MTU.

___ SAT STANDARD: Applicant determines current core burnup from task assignment sheet. 12000 MWD/MTU. (ICS point display U7981 or other ICS displays that indicate core burnup; i.e.,

Xenon (Core burnup is provided on task assignment sheet). ___ UNSAT COMMENTS:

STEP 4: Obtains:

Current Reactor power = P1: ________ % ___ SAT Target Reactor power = P2: _______ %

Calculates: Total Reactor power change: _______%

STANDARD: Applicant determines current reactor power and target power ___ UNSAT from information provided on assignment sheet. P1 = 76%.

P2 = 100%. Target reactor power was given on task assignment. Applicant determines total power change to be 24%.

COMMENTS:

A.1-2 RO Page 30 of 106 STEP 5: Obtains:

Rate of Reactor power change: ________ %/hr. ___ SAT Number of hours to change power: ________ hr(s).

STANDARD: Applicant determines rate of reactor power change from task assignment to be 3% per hour. Applicant calculates number ___ UNSAT of hours projected to reach target power as 8 hrs.

COMMENTS:

STEP 6: Obtains:

Current Rod Position: _________ steps. ___ SAT Final Rod Position: _________ steps.

STANDARD: Applicant determines final rod position from task assignment as 220 Steps. Applicant determines current rod position from ___ UNSAT ICS or Control Board Step Counters (Value provided on task assignment sheet). Value for current position is 190 steps.

COMMENTS:

A.1-2 RO Page 31 of 106 CAUTION Follow sign conventions explicitly. When using values from Table 7-17, 7-18, or 7-19, they must be corrected as indicated below.

Evaluator Note: JPM Steps 7 through 11 evaluate applicants completion of the second page of Appendix E steps for Reactivity Balance.

STEP 7: Determines Power Defect: CRITICAL From NUPOP, Figure 6-18, 19, or 20 STEP (or from Table 7-17, 7-18, or 7-19 Must multiply value from these tables by (-1) to maintain sign convention. The figures are ___ SAT correct as shown).

STANDARD: Applicant determines the PD1 for current power level is -1594 pcm from Table 7-18, and determines PD2 for target power ___ UNSAT level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Applicant then calculates Power Defect by subtracting algebraically PD2 from PD1. The value determined is 494 pcm.

If Applicant determines the PD1 for current power level using Figure 6-19, accept -1570 to -1600 pcm for the 76% power level and accept -2050 to -2100 pcm for the 100% power level.

Acceptable Range is 450 to 530pcm.

COMMENTS:

A.1-2 RO Page 32 of 106 STEP 8: Determines Xenon: CRITICAL Xenon1: STEP From REACTW (either current conditions or projection to initial condition). _________ pcm XE1.

Xenon2: ___ SAT From REACTW (projected over time period T). _______ pcm XE2.

NOTE: Xenon values must be negative.

Applicant then calculates Xenon by subtracting XE2 from XE1. ___ UNSAT

-2644.7 pcm XE1 - -2508.1 pcm XE2 = -136.6 pcm (current) (Target) Xenon STANDARD: Applicant determines the XE1 for current power level is

-2644.7 pcm from Xenon REACTW printout, and determines XE2 for target power level as -2508.1 pcm from the same printout, and enters the values in appropriate table locations.

Applicant then calculates Xenon by subtracting XE2 from XE1. The value determined is -136.6 pcm.

Acceptable range is 137 +/-1 pcm.

COMMENTS:

A.1-2 RO Page 33 of 106 STEP 9 Determines rods: CRITICAL Rods 1, 2 : From NUPOP, Figure 6-24, or 25. STEP

___________ pcm Rods1 - _________ pcm Rods2 = _______ pcm (current) (Target) Rods

___ SAT STANDARD: Applicant determines the Rods1 for current rod position as 150 pcm (accept 175 - 125) from NUPOP Figure 6-25, and determines Rods2 for target as 0 (accept 0 - 40) pcm from the same figure, and enters the values in appropriate table ___ UNSAT locations. Applicant then calculates Rods by subtracting algebraically Rods2 from Rods1. The value determined is 150 pcm.

Acceptable Range is 85 to 175 pcm.

Applicant may adjust values based on interpretation of NUPOP Figure 6-25. Values entered that are within the stated acceptable range may be used.

COMMENTS:

A.1-2 RO Page 34 of 106 STEP 10: Determines boron1:

Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure CRITICAL 6-21). STEP

______ Boron X ( 1000 ÷ _________pcm/%) = _________pcm (current) BORON1

___ SAT STANDARD: Applicant enters 750 ppm for current boron concentration.

Applicant determines the inverse boron worth is -159 pcm/%

(accept -158 to -160) from NUPOP Figure 6-21 for the current boron concentration, and enters the values in appropriate table ___ UNSAT location. Applicant then calculates BORON1 by multiplying RCS boron concentration by the product of 1000 pcm divided by current inverse boron worth boron worth determined from figure 6-21 for the current RCS boron concentration.

BORON 1 value is calculated is - 4717 pcm.

Acceptable Range is - 4725 to - 4650 pcm.

Applicant must adjust value based on interpretation of NUPOP Figure 6-21. Values entered that are within the stated acceptable range may be used.

COMMENTS:

A.1-2 RO Page 35 of 106 STEP 11: Determines boron2:

Calculates BORON2 by CRITICAL STEP

______ Power Defect + _____ pcm Xenon - ____ pcm +

____________ pcm ( BORON1) = _____________ pcm BORON2 ___ SAT STANDARD: Applicant calculates boron2 by algebraically adding/subtracting the change in power defect, change in ___ UNSAT Xenon reactivity, change in reactivity due to rods and current worth of RCS boron. The result of the calculation in reactivity required by boron at the target power level. The values previously calculated are entered into the table observing proper signs.

+ 494 pcm ( Power Defect )

+ -136.6pcm ( Xenon)

- 150 pcm ( Rods)

+ -4717 pcm ( BORON1) = -4510 pcm BORON2

+ 450 pcm ( Power Defect )

+ -136pcm ( Xenon)

- 175 pcm ( Rods)

+ -4725 pcm ( BORON1) = -4586 pcm BORON2

+ 530 pcm ( Power Defect )

+ -138 pcm ( Xenon)

- 85 pcm ( Rods)

+ -4650 pcm ( BORON1) = -4343 pcm BORON2 Acceptable Range is - 4586 to - 4343 pcm.

The new calculated value must be within the stated acceptable range.

COMMENTS:

A.1-2 RO Page 36 of 106 Evaluator Note. JPM Step 12 evaluates applicant's completion of the second page of Appendix E steps for Target PPM.

STEP 12: (-4510) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ CRITICAL 1000 pcm/%) = 717 ppm STEP

(-4586) pcm BORON2 X (-160_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 724 ppm

___ SAT

(-4343) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 694 ppm STANDARD: Applicant determines Target Boron Concentration by taking ___ UNSAT BORON2 times boron worth and conversion factor. The target boron concentration is calculated to be 717 ppm.

Acceptable Range is 725 to 690 pcm.

COMMENTS:

A.1-2 RO Page 37 of 106 STEP 13: NOTIFY SM/Unit SRO of RCS Target Boron Concentration calculated.

EVALUATOR CUE: Role play as SM/Unit supervisor and acknowledge ___ SAT report. Acknowledge request for independent verification. State that this Admin JPM has been completed. We will stop here.

___ UNSAT STANDARD: Applicant informs the SM/Unit Supervisor of the Target RCS boron concentration that was calculated.

COMMENTS:

END OF TASK TIME STOP: ________

Rev. 1 Page 38 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO DIRECTION TO APPLICANT:

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:

1. The Unit is operating at 76% rated thermal Power.

2. Core average burnup is 12000 MWD/MTU.

3. Control Bank D rods are at 190 steps.

4. RCS Boron Concentration is 750 ppm.

5. Target Rod Position at 100% RTP will be 220 Steps on Control Bank D.

6. Power will be raised at a rate of 3% per hour.

7. Xenon printout from REACTINW has been performed by an STA.

8. You are an extra Unit Operator.

INITIATING CUES:

Using the information provided, the SM/Unit SRO has directed you to calculate Target Boron Concentration for raising power to 100% per SOI-62.02 Appendix E Reactivity Balance Calculation

Determine the RCS Target Boron concentration.

Notify SM/Unit SRO of the RCS Target Boron Concentration.

Rev. 1 Page 39 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO

[REACTW - VERS WB3.3]

XENON CALCULATION WATTS BAR UNIT 1 CYCLE 9 MOL NIX XENON DATA XE DEL XE TIME POWER XE I WORTH WORTH (HRS) (%) (% EQ) (% EQ) (PCM) (PCM)

.0 76.0 91.2 76.0 -2644.7 .0 1.0 79.0 90.8 76.3 -2634.6 10.1 2.0 82.0 90.2 76.9 -2618.1 16.5 3.0 85.0 89.6 77.7 -2598.2 19.9 4.0 88.0 88.8 78.7 -2577.1 21.1 5.0 91.0 88.1 79.9 -2556.5 20.6 6.0 94.0 87.5 81.3 -2537.7 18.8 7.0 97.0 86.9 82.9 -2521.3 16.4 8.0 100.0 86.5 84.6 -2508.1 13.2

Rev. 1 Page 40 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO A.1-2 SRO Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.

Rev. 1 Page 41 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO

Rev. 1 Page 42 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO EVALUATION SHEET Task: Perform Independent Verification of Target Boron Concentration for Load Escalation Calculation.

Alternate Path: N/A Facility JPM #: 3-OT-JPMADA.1-5 K/A Rating(s): 004 A4.04 Ability to manually operate and/or monitor in the control room:

Calculation of boron concentration changes [3.2/3.6] (CFR: 41/7 / 45.5 to 45.8)

Task Standard: Applicant completes an independent verification of the SOI-62.02, Appendix E Reactivity balance calculation. Target RCS Boron Concentration is corrected based upon errors found. Applicant notifies SM of the results.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

SOI-62.02, Boron Concentration Control, Rev. 47; NUPOP, WCAP-16880-P, Nuclear Parameters and Operating Package for Watts Bar Unit 1, Cycle 9, Rev 2; Nuclear Operating Book for WBN Unit 1 Task Number: RO-062-SOI-62-016 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5, 12 Validation Time: 20 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Rev. 1 Page 43 of 106 WATTS BAR NUCLEAR PLANT A.1-2 SRO

A.1-2 SRO Page 44 of 106 Tools/Equipment/Procedures Needed:

Latest revision of SOI-62.02, Boron Concentration Control.

WCAP-16880-P Nuclear Parameters and Operating Package for Watts Bar Unit 1, for WBN Unit 1 Cycle 9 Nuclear Operating Book for WBN Unit 1 Ruler or straight edge.

Calculator NOTE: START THIS JPM AT A LOCATION WHERE APPLICANT HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide Applicant with procedure).

A.1-2 SRO Page 45 of 106 READ TO APPLICANT DIRECTION TO APPLICANT:

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:

9. The Unit is operating at 76% rated thermal Power.

10. Core average burnup is 12000 MWD/MTU.

11. Control Bank D rods are at 190 steps.

12. RCS Boron Concentration is 750 ppm.

13. Target Rod Position at 100% RTP will be 220 Steps on Control Bank D.

14. Power will be raised at a rate of 3% per hour.

15. Xenon printout from REACTINW has been performed by an STA.

16. The Unit Operator has just completed SOI-62.02 Appendix E Reactivity Balance Calculation for this power change.

INITIATING CUES:

The SM/Unit SRO has directed you to perform an independent verification of SOI-62.02 Appendix E Reactivity Balance Calculation performed by the Unit Operator.

A.1-2 SRO Page 46 of 106 START TIME: _______

STEP 1: Obtain a copy of the completed instruction.

___ SAT STANDARD: A copy of SOI-62.02 Appendix E Reactivity Balance Calculation has been obtained.

EXAMINERS CUE: Provide the Applicant a copy of the completed ___ UNSAT instruction.

COMMENTS:

NOTE 1 One calculation is required for each major change. Calculation is an approximation of Final Target Boron CB. Rough interpolation of NuPop figures is acceptable and expected.

NOTE 2 Dilution or Boration value for power change from P1 % to P2 %

power in the time period T with rods moving from step position R1 to R2. (Subscript convention: 1 = current point, 2 = target point)

Evaluator Note. JPM Steps 2 through 6 evaluate Applicants completion of the first page of Appendix E.

STEP 2: [1] CALCULATE target boron concentration by performing the following:

Obtains: Current RCS Boron CB: __________PPM.

___ SAT STANDARD: Applicant ensures correct RCS Boron Concentration is entered in the Table associated with Step 1.

___ UNSAT COMMENTS:

A.1-2 SRO Page 47 of 106 STEP 3: Obtains: Core Burnup: _______MWD/MTU STANDARD: Applicant ensures correct current core burnup from task ___ SAT assignment sheet. 12000 MWD/MTU.

COMMENTS: ___ UNSAT STEP 4: Obtains:

Current Reactor power = P1: ________ %

Target Reactor power = P2: _______ %

Calculates: Total Reactor power change: _______% ___ SAT STANDARD: Applicant ensures correct current reactor power and target power from information provided on assignment sheet. P1 = ___ UNSAT 76%. P2 = 100 % Target reactor power was given on task assignment. Applicant ensures correct total power change to be 24%.

COMMENTS:

A.1-2 SRO Page 48 of 106 STEP 5: Obtains:

Rate of Reactor Power change: ________ %/hr ___ SAT Number of hours to change power: ________ hr(s)

STANDARD: Applicant ensures correct rate of reactor power change from ___ UNSAT task assignment to be 3 % per hour. Applicant ensures correct number of hours projected to reach target power as 8 hrs.

COMMENTS:

STEP 6: Obtains:

Current Rod Position: _________ steps ___ SAT Final Rod Position: _________ steps STANDARD: Applicant ensures correct final rod position from task ___ UNSAT assignment as 220 Steps. Applicant ensures correct current rod position from ICS or Control Board Step Counters (Value provided on task assignment sheet). Value for current position is 190 steps.

COMMENTS:

A.1-2 SRO Page 49 of 106 CAUTION Follow sign conventions explicitly.

Evaluator Note. JPM Steps 7 through 11 evaluate Applicants completion of the second page of Appendix E steps for Reactivity Balance.

STEP 7: Determines Power Defect: CRITICAL From NUPOP, Figure 6-18, 19, or 20 STEP (or from Table 7-17, 7-18, or 7-19 Must multiply value from these tables by (-1) to maintain sign convention. The figures are ___ SAT correct as shown).

STANDARD: Applicant determines the PD1 for current power level is -1594 pcm from Table 7-18, and determines PD2 for target power ___ UNSAT level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Applicant then calculates Power Defect by subtracting algebraically PD2 from PD1. The value determined is 494 pcm.

If Applicant determines the PD1 for current power level using Figure 6-19, accept -1570 to -1600 pcm for the 76% power level and accept -2050 to -2100 pcm for the 100% power level.

Acceptable Range is 450 to 530 pcm.

COMMENTS:

A.1-2 SRO Page 50 of 106 STEP 8: Determines Xenon: CRITICAL Xenon1: From REACTW (either current conditions or projection to STEP initial condition). _________ pcm XE1.

Xenon2: From REACTW (projected over time period T). _______

pcm XE2. ___ SAT NOTE: Xenon values must be negative.

Applicant than calculates Xenon by subtracting algebraically XE2 from XE1.

-2644.7 pcm XE1 - -2508.1 pcm XE2 = -136.6 pcm ___ UNSAT (current) (Target) Xenon STANDARD: Applicant determines the XE1 for current power level is -

2644.7 pcm from Xenon REACTW printout, and determines XE2 for target power level as -2508.1 pcm from the same printout, and enters the values in appropriate table locations.

Applicant then calculates Xenon by subtracting algebraically XE2 from XE1. The value determined is -136.6 pcm.

Acceptable range is 137 +/-1 pcm.

This step is critical since the Applicant must identify the lack of a minus (-) sign applied to the Xenon worth and make a correction.

COMMENTS:

A.1-2 SRO Page 51 of 106 STEP 9 Determines rods: CRITICAL Rods 1, 2 : From NUPOP, Figure 6-24, or 25. STEP

___________ pcm Rods1 - _________ pcm Rods2 = _______ pcm (current) (Target) Rods

___ SAT STANDARD: Applicant determines the Rods1 for current rod position as 150 pcm (accept 175 - 125) from NUPOP Figure 6-25, and determines Rods2 for target as 0 (accept 0 - 40) pcm from the same figure, and enters the values in appropriate table ___ UNSAT locations. Applicant then calculates Rods by subtracting algebraically Rods2 from Rods1. The value determined is 150 pcm.

Acceptable Range is 85 to 175 pcm.

Applicant may adjust values based on interpretation of NUPOP Figure 6-25. Values entered that are within the stated acceptable range may be used.

COMMENTS:

A.1-2 SRO Page 52 of 106 STEP 10: Determines boron1: CRITICAL Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure STEP 6-21).

______ Boron X ( 1000 ÷ _________pcm/%) = _________pcm (current) BORON1 ___ SAT STANDARD: Applicant enters 750 ppm for current boron concentration.

Applicant determines the inverse boron worth is -159 pcm/%

(accept -158 to -160) from NUPOP Figure 6-21 for the current ___ UNSAT boron concentration, and enters the values in appropriate table location. Applicant then calculates BORON1 by multiplying RCS boron concentration by the product of 1000 pcm divided by current inverse boron worth boron worth determined from figure 6-21 for the current RCS boron concentration. boron 1 value is calculated is - 4717 pcm.

Acceptable Range is - 4725 to - 4650 pcm.

Applicant must adjust value based on interpretation of NUPOP Figure 6-21. Values entered that are within the stated acceptable range may be used.

COMMENTS:

A.1-2 SRO Page 53 of 106 STEP 11: Determines boron2: CRITICAL Calculates boron2 by STEP

______ Power Defect + _____ pcm Xenon - ____ pcm +

____________ pcm ( BORON1) = _____________ pcm ___ SAT BORON2 STANDARD: Applicant calculates boron2 by algebraically ___ UNSAT adding/subtracting the change in power defect, change in Xenon reactivity, change in reactivity due to rods and current worth of RCS boron. The result of the calculation in reactivity required by boron at the target power level. The values previously calculated are entered into the table observing proper signs.

+ 494 pcm ( Power Defect )

+ -136.6pcm ( Xenon)

- 150 pcm ( Rods)

+ -4717 pcm ( BORON1) = -4510 pcm BORON2

+ 450 pcm ( Power Defect )

+ -136pcm ( Xenon)

- 175 pcm ( Rods)

+ -4725 pcm ( BORON1) = -4586 pcm BORON2

+ 530 pcm ( Power Defect )

+ -138 pcm ( Xenon)

- 85 pcm ( Rods)

+ -4650 pcm ( BORON1) = -4343 pcm BORON2 Acceptable Range is - 4586 to - 4343 pcm.

Applicant must adjust value based on errors previously identified. The new calculated value must be within the stated acceptable range.

COMMENTS:

A.1-2 SRO Page 54 of 106 Evaluator Note. JPM Steps 12 evaluate Applicants completion of the second page of Appendix E steps for Target PPM.

STEP 12: (-4510) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ CRITICAL 1000 pcm/%) = 717 ppm STEP

(-4586) pcm BORON2 X (-160_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 724 ppm

___ SAT

(-4343) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 694 ppm STANDARD: Applicant determines Target Boron Concentration by taking ___ UNSAT BORON2 times born worth and conversion factor. The target boron concentration is calculated to be 725 ppm +/-12 ppm.

Acceptable Range is 725 to 690 pcm.

COMMENTS:

STEP 13: NOTIFY SM/Unit SRO of RCS Target Boron Concentration independently verified. .

EVALUATOR CUE: Role play as SM/Unit supervisor and acknowledge ___ SAT report. Acknowledge request for independent verification, State that this Admin JPM has been completed. We will stop here.

___ UNSAT STANDARD: Applicant informs the SM/Unit Supervisor of the Target RCS boron concentration that was calculated and of the errors discovered during the independent verification process.

COMMENTS:

END OF TASK TIME STOP: ________

Page 55 of 106 WATTS BAR NUCLEAR PLANT A.2-RO DIRECTION TO APPLICANT:

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:

1. The Unit is operating at 76% rated thermal Power.

2. Core average burnup is 12000 MWD/MTU.

3. Control Bank D rods are at 190 steps.

4. RCS Boron Concentration is 750 ppm.

5. Target Rod Position at 100% RTP will be 220 Steps on Control Bank D.

6. Power will be raised at a rate of 3% per hour.

7. Xenon printout from REACTINW has been performed by an STA.

8. The Unit Operator has just completed SOI-62.02 Appendix E Reactivity Balance Calculation for this power change.

INITIATING CUES:

The SM/Unit SRO has directed you to perform an independent verification of SOI-62.02 Appendix E Reactivity Balance Calculation performed by the Unit Operator.

Page 56 of 106 WATTS BAR NUCLEAR PLANT A.2-RO

[REACTW - VERS WB3.3]

XENON CALCULATION WATTS BAR UNIT 1 CYCLE 9 MOL NIX XENON DATA XE DEL XE TIME POWER XE I WORTH WORTH (HRS) (%) (% EQ) (% EQ) (PCM) (PCM)

.0 76.0 91.2 76.0 -2644.7 .0 1.0 79.0 90.8 76.3 -2634.6 10.1 2.0 82.0 90.2 76.9 -2618.1 16.5 3.0 85.0 89.6 77.7 -2598.2 19.9 4.0 88.0 88.8 78.7 -2577.1 21.1 5.0 91.0 88.1 79.9 -2556.5 20.6 6.0 94.0 87.5 81.3 -2537.7 18.8 7.0 97.0 86.9 82.9 -2521.3 16.4 8.0 100.0 86.5 84.6 -2508.1 13.2

Page 57 of 106 WATTS BAR NUCLEAR PLANT A.2-RO A.2-RO Calculate QPTR using 1-SI-0-21 Excore QPTR &

Axial Flux Difference.

A.2 - RO Page 58 of 106 EVALUATION SHEET Task: Calculate QPTR Using 1-SI-0-21 Excore QPTR & Axial Flux Difference Alternate Path: N/A Facility JPM #: 3-OT-JPMADA.2-1 K/A Rating(s): 015 A1.04 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including:

Quadrant power tilt ratio. 3.5 / 3.7 (CFR: 41.5, 45.5) 2.2.40 Ability to apply Technical Specifications for a system. 3.4 / 3.7 (CFR: 41.10 /

43.2 / 43.5 / 45.3)

Task Standard: Quadrant Power Tilt Ratio has been determined per 1-SI-0-21 Excore QPTR &

Axial Flux Difference Section 6.1 and Attachment 1. Acceptance criteria are determined to be not met due for N-42 Upper Detector, N-44 Upper Detector and N-42 Lower Detector.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

1-SI-0-21 Excore QPTR & Axial Flux Difference, Rev. 15; Nuclear Operating Book (NOB) A-2 Sheet 1 Rev. 89, Sheet 2 Rev. 88, Sheet 3 Rev. 89, Sheet 4 Rev 87.

Task Number: RO-092-SI-2-001 APLICABLE FOR: RO/SRO 10CFR55.45:

Validation Time: 13 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

A.2 - RO Page 59 of 106 Tools/Equipment/Procedures Needed:

Applicant Data Sheet.

Latest revision of 1-SI-0-21 Excore QPTR & Axial Flux Difference.

Attached NOB Sheets A-2 (all four PR detector channels).

Calculator.

NOTE: START THIS JPM AT A LOCATION WHERE APPLICANT HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC, etc.).

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

A.2 - RO Page 60 of 106 READ TO APPLICANT DIRECTION TO APPLICANT:

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:

1. The unit is operating at 100% power.

2. AFD Monitor Alarm and QPTR alarms are out of service due to a card problem in the annunciator system.

3. 1-SI-0-21 Excore QPTR & Axial Flux Difference is required to be performed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months since both QPTR alarms are inoperable.

4. Plant computer is not available for performing this SI.

5. You are a support CRO.

INITIATING CUES:

1. Given the data that was just obtained from each power range channel upper and lower detector currents, the Unit Supervisor directs you to perform Section 6.1 Excore QPTR Determination of 1-SI-0-21 Excore QPTR & Axial Flux Difference. M&TE will not be utilized for data measurements.

2. Report the results to the Unit Supervisor when 1-SI-0-21 Excore QPTR & Axial Flux Difference, Section 6.1 and Attachment 1 have been completed.

3. Perform all calculations to 3 decimal places.

A.2 - RO Page 61 of 106 START TIME: _______

STEP 1: Obtain a copy of the instruction.

___ SAT STANDARD: A copy of 1-SI-0-21 Excore QPTR & Axial Flux Difference has been obtained.

EXAMINERS CUE: After the applicant has identifies the correct ___ UNSAT instruction, provide a copy of the instruction.

COMMENTS:

NOTE TO EVALUATOR: The following steps are from Section 6.1 of 1-SI-0-21 Excore QPTR & Axial Flux Difference NOTE 1 Obtaining QPTR calculated values from the Process Computer is the preferred method to check that the QPTR is within Technical Specification limits. QPTR values are obtained from Process Computer calculated computer points for upper and lower radial flux tilt. These points are available on the Tilting Factors display. The report may be printed with Turn On code TFREP.

NOTE 2 Up to one inoperable excore channel can be marked N/A if THERMAL POWER is < 75% RTP.

STEP 2: [Step 1] IF performing this instruction during an NIS calibration (when all four channels are NOT complete), THEN REFER to Precautions and Limitations 3.0 E.

___ SAT STANDARD: Step is N/A since the QPTR is NOT being performed during an NIS calibration.

___ UNSAT COMMENTS:

A.2 - RO Page 62 of 106 STEP 3: [Step 2] IF the process Computer is available, THEN PRINT the Tilting Factors Report AND/OR PERFORM the QPTR calculations using Attachment 1.

___ SAT STANDARD: Applicant goes to Attachment 1 and performs applicable steps.

___ UNSAT COMMENTS:

NOTE 1 Determining detector currents by measuring the voltage across the detectors meter test points, using DVM, is the most accurate method for measuring QPTR and for determining the validity of a QPTR alarm.

NOTE 2 Using detector current meter readings is another method to quickly check that QPTR is within limits. These meters are not as accurate as the DVM readings and may produce unacceptable results because: 1) the meters on the B drawer may be scaled too high or (2) the meter may be unstable due to drift or noise. When unacceptable results are obtained DVM readings should be obtained, otherwise, Step [1] and [2] may be marked N/A if DVM not used.

NOTE 3 Up to one inoperable excore channel can be marked N/A if THERMAL POWER is < 75% RTP.

STEP 3: [Step 1] RECORD DVM information:

A. TVA M&TE ID: ________________

B. Cal Due Date: ________________

___ SAT STANDARD: Applicant determines step is N/A based on initial conditions for task performance and proceeds to the next step.

___ UNSAT COMMENTS:

A.2 - RO Page 63 of 106 STEP 4: [Step 2] ENSURE required M&TE is within its current calibration.

___ SAT STANDARD: Applicant determines step is N/A based on initial conditions for task performance and proceeds to the next step.

___ UNSAT COMMENTS:

CAUTION An inadvertent reactor trip may be prevented by ensuring that no power range neutron high flux rate or power range high flux channels are in the tripped condition prior to taking EACH measurement in the NIS Power Range Drawer B.

NOTE The following determination may be made by measuring the voltage across the 1000 ohm precision resistor in NIS power range drawer B. When using this method the Ohms Law conversion from a millivolt measurement to a microamp measurement only requires changing the unit designator (e.g., 280 millivolts converts to 280 microamps).

NOTE Detector A is the TOP or UPPER Detector and Detector B is the BOTTOM or LOWER detector on the NIS drawer B.

A.2 - RO Page 64 of 106 STEP 5: [Step 3] DETERMINE the microamps for each upper and lower excore detector on each NIS power range drawer B, AND RECORD below:

UPPER DETECTOR LOWER DETECTOR NIS Channel It Detector Current Ib Detector Current (microamps) (microamps)

N-41A (369) (384)

N-42A (364) (386)

N-43A (369) (385)

N-44A (371) (386)

STANDARD: Applicant obtains the detector current microamp readings from ___ SAT the handout given during task assignment and enters the appropriate data into Attachment 1 step 3.

NOTE TO EVALUATOR: Values above in ( ) are detector currents from ___ UNSAT handout.

COMMENTS:

A.2 - RO Page 65 of 106 NOTE: Rt and Rb (detector calibration data) changes periodically throughout the cycle.

Current values are on NOB Sheet A-2, NIS Calibration Data.

NOTE TO EVALUATOR: The NOB Sheets attached to this JPM are to be given to the applicant when the applicant refers to the NOB. The data sheets attached are the basis for the calculations in the JPM.

STEP 6: [Step 4] OBTAIN and RECORD current values of Rt and Rb (volts/microamps).

UPPER DETECTOR LOWER DETECTOR NIS Channel Rt (volts/microamps) Rb (volts/microamps)

N-41A (0.03774) (0.03833)

N-42A (0.04439) (0.04492)

N-43A (0.03770) (0.03713)

N-44A (0.04198) (0.03813)

STANDARD: Applicant obtains the detector current values from NOB Sheets ___ SAT A-2 for the respective NIS Power Range Detectors and records them in appropriate blocks on Attachment 1 Step 4.

NOTE TO EVALUATOR: Values above in ( ) are detector currents from ___ UNSAT respective NOB Sheets A-2 which are attached to this JPM.

COMMENTS:

A.2 - RO Page 66 of 106 STEP 7: [Step 5] CALCULATE calibrated output voltages by multiplying the uncalibrated detector output currents by Rt or Rb (as applicable).

A. Vt = It x Rt B. Vb = Ib x Rb UPPER DETECTOR LOWER DETECTOR NIS Channel Vt Calib. Output Vb Calib. Output Voltage Voltage N-41A (369) (0.03774)=13.926 (384) (0.03833)=14.719 N-42A (364) (0.04439)=16.158 (386) (0.04492)=17.339 N-43A (369) (0.03770)=13.911 (385) (0.03713)=14.295 N-44A (371) (0.04198)=15.575 (386) (0.03813)=14.718 STANDARD: Applicant calculates the calibrated output voltages [from Step Critical Step 3] by multiplying the respective detectors current reading times resistance values [from Step 4] and records the results in the ___ SAT appropriate blocks on Attachment 1 Step 5.

COMMENTS: ___ UNSAT STEP 8: [Step 6] CALCULATE average calibrated output voltage for the upper and lower detectors.

UPPER Vt LOWER Vb AVERAGE (13.926+16.158+13.911+ (14.719+17.339+14.295+

15.575)/4 =14.893 14.718)/4 = 15.268 STANDARD: Applicant calculates the average output voltages for the upper Critical Step detector by adding the respective upper detectors calibrated output voltage readings [from Step 5] and dividing the result ___ SAT by the number of channels in service. This process is repeated for the lower detector using the lower detector calibrated voltages. The results recorded in appropriate blocks on Attachment 1 Step 6. ___ UNSAT COMMENTS:

A.2 - RO Page 67 of 106 STEP 9: [Step 7] CALCULATE QPTR values by dividing each detectors (upper or lower) Calibration Output Voltage by the average (upper or lower) Calibrated Output Voltage.

A. QPTRt = Vt ÷ Avg Vt B. QPTRb = Vb ÷ Avg Vb UPPER LOWER DETECTOR DETECTOR NIS Channel QPTRt Value QPTRb Value N-41A (13.926/14.893) = 0.935 (14.719/15.268)= 0.964 N-42A (16.158/14.893) = 1.085 (17.339/15.268)= 1.136 N-43A (13.911/14.893) = 0.934 (14.295/15.268)= 0.936 N-44A (15.575/14.893) = 1.046 (14.718/15.268)= 0.964 STANDARD: Applicant calculates QPTR values by dividing the respective Critical Step Calibrated Output Voltage [from step 5] by the Average Calibrated Output Voltage for each NIS channel detector [from ___ SAT step 6]. The results recorded in appropriate blocks on Attachment 1. Applicant returns to Section 6.1 Step 7.

___ UNSAT COMMENTS:

NOTE TO EVALUATOR The following steps are from Section 6.1 of 1-SI-0-21 Excore QPTR & Axial Flux Difference.

STEP 10: [Step 3] REVIEW the Upper (A) and Lower (B) QPTR values.

STANDARD: Applicant reviews QPTR values from Attachment 1 Step 7. ___ SAT COMMENTS:

___ UNSAT

A.2 - RO Page 68 of 106 STEP 11: [Step 3] CHECK () Acceptance Criteria. Critical Step ACCEPTANCE CRITERIA: All operable excore channels ___ SAT (upper and lower) indicate a QPTR 1.02.

YES NO

___ UNSAT STANDARD: Applicant determines that N-42 Upper Detector, N44 Upper Detector, and N-42A Lower Detectors exceed 1.02 QPTR.

Applicant then checks NO statement.

COMMENTS:

STEP 12: Inform the Unit Supervisor that Attachment 1 and Section 6.1 of 1-SI-0-21 Excore QPTR & Axial Flux Difference have been completed and the results of the QPTR.

___ SAT STANDARD: Applicant informs the Unit Supervisor of the completion of Attachment 1 and Section 6.1 of 1-SI-0-21 Excore QPTR &

Axial Flux Difference and reports that acceptance criteria have ___ UNSAT not been satisfied. QPTR for N-42 Upper Detector is 1.085, N-42 Lower Detector is 1.136, N-44 Upper Detector is 1.046, anyone of which exceeds the QPTR limit of 1.02.

EXAMINERS CUE: Acknowledge report as Unit Supervisor, then state "We will stop here."

COMMENTS:

END OF TASK TIME STOP: ________

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

DIRECTION TO APPLICANT:

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:

1. The unit is operating at 100% power.

2. AFD Monitor Alarm and QPTR alarms are out of service due to a card problem in the annunciator system.

3. 1-SI-0-21 Excore QPTR & Axial Flux Difference is required to be performed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months since both QPTR alarms are inoperable.

4. Plant computer is not available for performing this Surveillance Instruction.

5. You are a support CRO.

INITIATING CUES:

1. Given the data that was just obtained from each power range channel upper and lower detector currents, the Unit Supervisor directs you to perform Section 6.1 Excore QPTR Determination of 1-SI-0-21 Excore QPTR & Axial Flux Difference. M&TE will not be utilized for data measurements.

2. Report the results to the Unit Supervisor when 1-SI-0-21 Excore QPTR & Axial Flux Difference, Section 6.1 and Attachment 1 have been completed.

3. Perform all calculations to 3 decimal places.

Rev. 0 Page 70 of 106 WATTS BAR NUCLEAR PLANT A.2-SRO The following microampere readings were taken from the Power Range NIS detectors:

UPPER DETECTOR LOWER DETECTOR NIS Channel It Detector Current Ib Detector Current (microamps) (microamps)

N-41A 369 384 N-42A 364 386 N-43A 369 385 N-44A 371 386

Rev. 0 Page 71 of 106 WATTS BAR NUCLEAR PLANT A.2-SRO A.2-SRO Review and Approve a Disabled Alarm Checklist, per OPDP-4.

Rev. 0 Page 72 of 106 WATTS BAR NUCLEAR PLANT A.2-SRO EVALUATION SHEET Task: Review and Approve a Disabled Alarm Checklist, per OPDP-4.

Alternate Path: N/A Facility JPM #: New K/A Rating(s): 2.2.43 Knowledge of the process used to track inoperable alarms. [3.0/3.3]

(CFR: 41.10 / 43.5 / 45.13)

Task Standard: Applicant identifies that the OPDP-4-1 Disabled Alarm Checklist is NOT filled out correctly for Annunciator 85-F. Applicant DOES NOT sign package at Step 7 as approved.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ __ In-Plant _____ Perform __X___ Simulate ___ _

References:

. OPDP-4, Annunciator Disablement, Rev. 4.

Task Number: SRO-055-PAI-208-001 APPLICABLE FOR: SRO 10CFR55.45: 13 Validation Time: 15 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Rev. 0 Page 73 of 106 WATTS BAR NUCLEAR PLANT A.2-SRO

Rev. 0 A.2-SRO Page 74 of 106 Tools/Equipment/Procedures Needed:

OPDP-4-1 Attachment 1, Disabled Alarm Checklist.

GO-6, Unit Shutdown from Hot Standby to Cold Shutdown ARI-85-F, RVLIS SYS MALFUNCTION

Rev. 0 A.2-SRO Page 75 of 106 READ TO APPLICANT DIRECTION TO APPLICANT:

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:

17. A plant shutdown is in progress.

18. Mode 3 has just been entered.

19. The Operator-at-the-Controls has informed you that Annunciator 85-F, RVLIS SYS MALFUNCTION has been received on multiple occasions, and that OPDP-4-1 Disabled Alarm Checklist has been filled out to disable the alarm.

20. You are the Unit SRO.

INITIATING CUES:

Review the OPDP-4-1 Disabled Alarm Checklist for approval. Note any and all discrepancies found during your review.

Rev. 0 A.2-SRO Page 76 of 106 START TIME: _______

STEP 1: Obtain a copy of the completed instruction.

___ SAT STANDARD: A copy of OPDP-4-1 Attachment 1, Disabled Alarm Checklist.

EXAMINERS CUE: Provide the Applicant a copy of the completed instruction. ___ UNSAT COMMENTS:

STEP 2: DISABLED ALARM CHECKLIST block reviewed. ___ SAT STANDARD: Applicant determines that the correct Panel Number is entered in the block.

___ UNSAT COMMENTS:

STEP 3: ALARM LOCATION block is reviewed. ___ SAT STANDARD: Applicant determines correct information is entered in the Node/Mux/Pt or SER.

___ UNSAT COMMENTS:

STEP 4: Reviews entry in 1. Description of the alarm that is being ___ SAT defeated.

STANDARD: Applicant determines that an adequate description of the alarm function has been entered. ___ UNSAT COMMENTS:

Rev. 0 A.2-SRO Page 77 of 106 STEP 5: Reviews entry in 2. Describe reason for disabling the alarm Critical Step (include procedure or WO number, if applicable).

___ SAT STANDARD: Error Discovery - Incorrect/inadequate description for disabling alarm.

The data entered should describe that the alarm has been ___ UNSAT deemed a nuisance, and is to be disabled for that reason.

Refering to GO-6 Section 5.4, Step [10.4].

COMMENTS:

STEP 6: Reviews entry in 3. Description of how alarm will be disabled.

___ SAT STANDARD: Applicant determines that the description is adequate.

COMMENTS:

___ UNSAT STEP 7: Reviews entry in 4. Is a 10CFR50.59 Review required prior to Critical Step disabling alarm? (Refer to Appendix A).

___ SAT STANDARD: Error Discovery - Incorrect block checked.

Applicant determines that a 10CFR50.59 review is required, since the alarm is NOT being disabled per GO-6. ___ UNSAT COMMENTS:

STEP 8: Reviews entry in 5. Is a 10CFR50.59 Review required prior to ___ SAT exceeding 90 days.(alarm disabled for maintenance)?

STANDARD: Applicant determines that a 10CFR50.59 review is not required, since the alarm is NOT being removed for a ___ UNSAT maintenance evolution.

COMMENTS:

Rev. 0 A.2-SRO Page 78 of 106 STEP 9: Reviews entry in 6. Is a Technical Evaluation (Form OPDP Critical Step

5) required prior to disabling the alarm? (Refer to Appendix A).

___ SAT STANDARD: Error Discovery - Incorrect block checked.

Applicant determines that a Technical Evaluation (Form OPDP-4-5) is required. ___ UNSAT COMMENTS:

STEP 8: Performs entry in 7, and determines that the form cannot be Critical Step approved as presented.

STANDARD: Applicant states that the package cannot be signed as approved until after the errors have been corrected. ___ SAT COMMENTS:

___ UNSAT END OF TASK TIME STOP: ________

Page 79 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO DIRECTION TO APPLICANT:

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:

1. A plant shutdown is in progress.

2. Mode 3 has just been entered.

3. The APPLICANT-at-the-Controls has informed you that Annunciator 85-F, RVLIS SYS MALFUNCTION has been received on multiple occasions, and that OPDP-4-1 Disabled Alarm Checklist has been filled out to disable the alarm.

4. You are the Unit SRO.

INITIATING CUES:

Review the OPDP-4-1 Disabled Alarm Checklist for approval. Note any and all discrepancies found during your review.

A.3-SRO Authorize a Radioactive Liquid Release.

Page 80 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO

Page 81 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO EVALUATION SHEET Task: Authorize a Radioactive Liquid Release.

Alternate Path: N/A Facility JPM #: New K/A Rating(s): 2.3.6 Ability to approve release permits. [2.0/3.8] (CFR: 41.13 / 43.4 / 45.10)

Task Standard: Applicant identifies that the release permit is for the wrong tank/release point, and the voltage setpoint for 0-RE-90-122 is not within the 0.101VDC limit established in 0-ODI-90-1 Liquid Radwaste Tank Release, Section 6.1, Step 15. Applicant DOES NOT sign package as approved.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ __ In-Plant _____ Perform __X___ Simulate ___ _

References:

. 0-ODI-90-1 Liquid Radwaste Tank Release, Rev. 31 Task Number: SRO-077-SOI-77-001 APPLICABLE FOR: SRO 10CFR55.45: 9 Validation Time: 15 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS

Page 82 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO

Page 83 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO Tools/Equipment/Procedures Needed:

Marked up copy of 0-ODI-90-1 Liquid Radwaste Tank Release, Rev. 31.

Batch Liquid Permit, Dated 3-18-09 Monitor Tank Sample Report DKB600

Page 84 of 106 WATTS BAR NUCLEAR PLANT A.3-SRO READ TO APPLICANT DIRECTION TO APPLICANT:

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:

21. A release of the Monitor Tank is scheduled for this shift.

22. Chemistry has prepared a 0-ODI-90-1, Liquid Radwaste Tank Release Package for the release.

23. You are the Unit SRO.

24. The dates on the documentation are correct.

INITIATING CUES:

1. Review the 0-ODI-90-1 package for release approval. Note any and all discrepancies found during your review.

2. If 0-RM-90-122 WDS Liquid Release Radiation Monitor fails during the batch release, what actions are required to be taken to comply with the Offsite Dose Calculation Manual (ODCM)?

WATTS BAR NUCLEAR PLANT A.3-SRO START TIME: _______

STEP 1: Obtain a copy of the completed instruction.

___ SAT STANDARD: Marked up copy of the Release Package including 0-ODI-90-1 Liquid Radwaste Tank Release is acquired by the applicant.

EXAMINERS CUE: Provide the applicant a copy of the completed ___ UNSAT instruction.

COMMENTS:

STEP 2: Applicant reviews package for correct tank to be released. Critical Step STANDARD: Error - The Batch Liquid Effluent Permit provided is for the ___ SAT wrong tank.

NOTE: According to the INITIAL CONDITIONS, a realease of the MONITOR TANK is to be conducted. The Batch Liquid ___ UNSAT Effluent Permit provided is for a release of the Cask Decon Collector Tank, NOT the Monitor Tank as described in the 0-ODI-90-1 Appendix A Pre-Release Permit Data.

COMMENTS:

STEP 3: Applicant reviews package to verify radioanalysis values are ___ SAT less than the limits provided on the Batch Liquid Effluent Permit.

STANDARD: Applicant determines that all values are less than limits (III. ___ UNSAT RADIOANALYSIS - LIQUID).

COMMENTS:

Page 85 of 106

WATTS BAR NUCLEAR PLANT A.3-SRO STEP 4: Applicant reviews package to verify the EXP. RESPONSE ___ SAT VALUE is less than the 0-RE-90-122 SETPOINT.

STANDARD: Applicant determines the EXP. RESPONSE VALUE is less than the 0-RE-90-122 SETPOINT given in IV. RADIATION ___ UNSAT MONITOR(S) section of the Batch Liquid Effluent Permit.

COMMENTS:

STEP 5: Applicant reviews package to verify the volume, flow, and ___ SAT dilution values are within limits.

STANDARD: Applicant determines the volume, flow, and dilution values are within limits given in V. AUTHORIZATION section of the Batch ___ UNSAT Liquid Effluent Permit.

COMMENTS:

STEP 6: Applicant reviews package to verify the radiation monitor Critical Step voltage is within limits.

___ SAT STANDARD: Error - The voltage setpoint for 0-RE-90-122 is outside allowable limits.

NOTE The 0-RE-90-122 Setpoint voltage of 5.84 Vdc recorded on 0- ___ UNSAT ODI-90-1, Appendix A is more than 0.101 Vdc higher than the setpoint of 5.262 Vdc provided in the Batch Liquid Effluent Permit.

COMMENTS:

STEP 6: Applicant reviews 0-ODI-90-1 package to verify the proper step sign-offs are made. ___ SAT STANDARD: Error - Attachment B, PRE-RELEASE SETPOINT ADJUSTMENT is not included in the 0-ODI-90-1 package.

___ UNSAT COMMENTS:

Page 86 of 106

WATTS BAR NUCLEAR PLANT A.3-SRO STEP 8: Applicant determines that the package cannot be approved as Critical Step written.

STANDARD: Applicant states that the package cannot be signed as approved until after the errors have been corrected. ___ SAT COMMENTS:

___ UNSAT STEP 8: Applicant addresses question If 0-RM-90-122 WDS Liquid Critical Step Realease Radiation Monitor fails during the batch release, what actions are required to be taken to comply with the Offsite Dose Calculation Manual (ODCM)?

___ SAT STANDARD: Applicant refers to ODCM 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, Item 1.a, Liquid Radwaste Effluent Line (RE- ___ UNSAT 90-122).

Determines that ACTION A is applicable during a release, and lists the following as actions to be taken.

ACTION A - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tanks contents obtained by two technically qualified members of the facility staff are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations,

c. At least two technically qualified members of the facility staff independently verify the discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

COMMENTS:

END OF TASK TIME STOP: ________

Page 87 of 106

Page 88 of 8 WATTS BAR NUCLEAR PLANT A.3- RO DIRECTION TO APPLICANT:

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:

1. A release of the Monitor Tank is scheduled for this shift.

2. Chemistry has prepared a 0-ODI-90-1 Liquid Radwaste Tank Release Package for the release.

3. You are the Unit SRO.

4. The dates on the documentation are correct.

INITIATING CUES:

1. Review the 0-ODI-90-1 package for release approval. Note any and all discrepancies found during your review.

2. If 0-RM-90-122, WDS Liquid Release Radiation Monitor, fails during the batch release, what actions are required to be taken to comply with the Offsite Dose Calculation Manual (ODCM)?

Page 88 of 106

Page 89 of 8 WATTS BAR NUCLEAR PLANT A.3- RO A.3-RO Evaluate RADCON Survey Map to determine posting requirements.

Page 89 of 106

Page 90 of 8 WATTS BAR NUCLEAR PLANT A.3- RO EVALUATION SHEET Task: Evaluate RADCON Survey Map to determine posting requirements.

Alternate Path: N/A Facility JPM #: RO ADMIN JPM - Category A.3 K/A Rating(s): 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. [3.4/3.8] (CFR: 41.12 / 43.4

/ 45.10)

Task Standard: Applicant determines appropriate radiological posting requirements associated with the attached RADCON survey map.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References:

Survey Map; SPP-5.1, Radiological Controls, Rev 5; RCI-152, Radiological Postings, Rev. 5.

Task Number:: APLICABLE FOR: RO/SRO 10CFR55.41.12, 43.4, 45.9, 45.10:

Validation Time: 10 min. Time Critical: No

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS Page 90 of 106

Page 91 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Page 91 of 106

Page 92 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Tools/Equipment/Procedures Needed:

RADCON survey map Latest revision of SPP-5.1, Radiological Controls.

Latest revision of RC!-152, Radiological Postings.

NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC, etc.).

NOTE TO EVALUATOR: Hand out the Survey Map along with the Applicants Cue Sheet.

Page 92 of 106

Page 93 of 8 WATTS BAR NUCLEAR PLANT A.3- RO READ TO APPLICANT DIRECTION TO APPLICANT:

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:

Plant is operating normally at power.

You are an NAUO on shift.

INITIATING CUES:

1. Evaluate the provided RADCON survey map and determine the appropriate radiological posting requirements for this area.

2. Report the results to the Unit Supervisor.

3. Answer the following question:

Maintenance is to be performed on the RHR pump using a robot. What will the dose rate to the robots operator be if the operator stands 1.5 meters from the RHR pump?

(Treat the RHR Pump as a point source.)

Page 93 of 106

A.3- RO START TIME: _______

STEP 1: Applicant reviews materials given and may determine references needed. ___ SAT STANDARD: Applicant becomes familiar with materials. May refer to SPP-5.1 Radiological Controls.

___ UNSAT COMMENTS:

STEP 2: Evaluation of Contaminated Area. Critical Step STANDARD: Applicant should determine that the area where smears 1,2 ___ SAT and 3 were taken would be posted as a Contaminated Area. These smears indicated removable contamination >

2 1000 dpm/100 cm .

___ UNSAT COMMENTS:

Page 94 of 8

A.3- RO STEP 3: Evaluation of High Radiation Area. Critical Step STANDARD: Applicant should determine the general area readings near ___ SAT the RHR pump in excess of 100 mrem/hr. The applicant should request the area near the pump to be posted as a High Radiation Area.

___ UNSAT COMMENTS:

STEP 4: Evaluation of Radiation Areas. Critical Step STANDARD: Applicant should determine that the general area readings ___ SAT in the majority of the area inside the Bio-Shield are in excess of 5 mrem/hr. A Radiation Area posting should be located at the Bio-Shield wall.

___ UNSAT COMMENTS:

Page 95 of 8

A.3- RO STEP 5: Evaluation of Room Posting.

STANDARD: Room need not be posted if postings stated above are ___ SAT completed.

COMMENTS: ___ UNSAT STEP 6: Question: Maintenance is to be performed on the RHR pump using a robot. What will the dose rate to the robots operator be if the operator stands 1.5 meters from the RHR pump? (Assume the dose reduction based on a point source)

ANSWER:

I 1( d 1) 2 = I 2( d 2) 2 I 2 = I 1( d 1) 2 /( d 2) 2

=150 mrem/hr (30 cm) 2/ [(1.5 m) (100 cm/m)] 2

= 6 mrem/hr Page 96 of 8

A.3- RO STEP 7: Results of the evaluation are reported to the Unit Supervisor.

___ SAT STANDARD: Applicant reports results of the previous steps.

EXAMINERS CUE: Acknowledge report as Unit Supervisor, then state We will stop here. ___ UNSAT COMMENTS:

END OF TASK TIME STOP: ________

Page 97 of 8

PAGE 98 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO 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:

1. Plant is operating normally at power.

2. You are an NAUO on shift.

INITIATING CUES:

1. Evaluate the provided RADCON survey map and determine the appropriate radiological posting requirements for this area.

2. Report the results to the Unit Supervisor.

3. Answer the following question:

Maintenance is to be performed on the RHR pump using a robot. What will the dose rate to the robots operator be if the operator stands 1.5 meters from the RHR pump? (Treat the RHR pump as a point source.)

Page 98 of 8

PAGE 99 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO A.4-SRO CLASSIFY THE EVENT AND DETERMINE PAR.

Page 99 of 8

PAGE 100 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO EVALUATION SHEET Task: Classify the Event and determine PAR.

Alternate Path: N/A Facility JPM #: 3-OT-JPMS081A K/A Rating(s): 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation

[2.5/3.3] (CFR: 41.10 / 43.5 / 45.11) 2.4.41 Knowledge of the emergency action level thresholds and classifications.

[2.9/4.6] (CFR: 41.10 / 43.5 / 45.11)

Task Standard: The event is classified as a GENERAL EMERGENCY based on Loss of Any Two Barriers and Potential Loss of Third Barrier within 15 minutes of starting the evaluation. Protective Action Recommendation determined is Recommendation 2.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ X ___ In-Plant ______ Perform __ X ____

Simulate ______ This JPM will be simulated.

References:

EPIP-1 Emergency Plan Classification Flowpath, Rev. 30; EPIP-5 GENERAL EMERGENCY, Rev. 37 Task Number: SRO-113-EPIP-001 APPLICABLE FOR: SRO 10CFR55.45: 11, 12 Validation Time: 15 min. Time Critical: Yes

=======================================================================

Applicant: ______________________________ ___________________ Time Start: _________

NAME SSN Time Finish: _________

Performance Rating: SAT ______ UNSAT ______ Performance Time ____

Examiner: __________________________________ __________________________________/________

NAME SIGNATURE DATE

=======================================================================

COMMENTS Page 100 of 8

PAGE 101 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Page 101 of 8

PAGE 102 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO NONE: THIS JPM IS PERFORMED IN A CLASSROOM SETTING.

REQUIRED MATERIALS:

EPIP-1 through EPIP-5 Tools/Equipment/Procedures Needed:

Copies of the WBN EPIPs for each candidate.

Page 102 of 8

PAGE 103 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO 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 handout sheet I provided you.

INITIAL CONDITIONS:

1. The unit was at 90% power when the crew manually initiated a reactor trip and safety injection due to a SGTR on SG #1 of greater than 140 gpm.

2. The crew has entered E-3, Steam Generator Tube Rupture.

3. Subsequently, a Safety Valve on SG #1 OPENED and FAILED to RECLOSE and the crew transitioned to E-2, Faulted Steam Generator.

4. Currently, the Status Trees are GREEN except for FR-H.5, Steam Generator Low Level, which is YELLOW due to level in SG #1 at 50% wide range.

5. Chem Lab reports RCS activity is 340 uCi/gram dose equivalent I-131.

6. Wind is from 90 degrees, at 8 mph.

7. You are the SM/SRO.

INITIATING CUES:

1. You are requested to classify the emergency event and determine any required Protective Action Recommendation.

2. Portions of this JPM are time critical.

Page 103 of 8

PAGE 104 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO 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 Three Barriers (1.1.2 Loss, 1.2.3 Loss, 1.3.4 Loss). This must be completed ___ SAT within 15 minutes of task assignment.

This step is critical to ensure proper activation of TVA resources for event in progress. ___ UNSAT COMMENTS: RECORD time that declaration was made:_________

STEP 2: Implements EPIP-5, GENERAL EMERGENCY.

___ SAT STANDARD: EPIP-5, GENERAL EMERGENCY, is implemented.

COMMENTS: ___ UNSAT Page 104 of 8

PAGE 105 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO STEP 3: [STEP 1] IF the onsite emergency centers are not staffed, ___ SAT THEN 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 ___ UNSAT minute printed report to the SM for review.

a. IF the EPS system fails, call the ODS, ringdown or (5-751-1700) 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: Per the INITIATING CUES, The applicant DOES not need to address this step.

COMMENTS:

STEP 3: [STEP 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: Appendix A is accurately completed with Appendix B ___ SAT RECOMMENDATION 2 SELECTED. Performer notifies the ODS, and then assigns the NLO to FAX Appendix A to the ODS.

___ UNSAT NOTE TO EVALUATOR: Underlined portion is the critical part.

COMMENTS:

TIME STOP: ________

Page 105 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 handout sheet I provided you.

INITIAL CONDITIONS:

1. The unit was at 90% power when the crew manually initiated a reactor trip and safety injection due to a SGTR on SG #1 of greater than 140 gpm.

2. The crew has entered E-3, Steam Generator Tube Rupture.

3. Subsequently, a Safety Valve on SG #1 OPENED and FAILED to RECLOSE and the crew transitioned to E-2, Faulted Steam Generator.

4. Currently, the Status Trees are GREEN except for FR-H.5, Steam Generator Low Level, which is YELLOW due to level in SG #1 at 50% wide range.

5. Chem Lab reports RCS activity is 340 uCi/gram dose equivalent I-131.

6. Wind is from 90 degrees, at 8 mph.

7. You are the SM/SRO.

INITIATING CUES:

1. You are requested to classify the emergency event and determine any required Protective Action Recommendation.

2. Portions of this JPM are time critical.

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