ML092810557
| 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) | |
Text
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 SSNTime 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 Ca lculation," beginning at Step 3. Base the calculation on the conditions stated above.
Rev. 0 A.1-1 RO Page 5 of 106 START TIME: _______
STEP 1: Obtain a copy of the instruction.
STANDARD: A copy of 1-SI-0-10 "Shutdown Margin" has been obtained.
EXAMINER'S CUE: Provide the applicant a copy of the instruction.
COMMENTS:
___ SAT
___ UNSAT 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: A. The WCAP number and cycle number:
WCAP - _____________________ Cycle _________
B. The Maximum Stuck Rod Worth.
Table D1, (Mode 2 below nuclear heating through Mode 5):
________pcm STANDARD: Applicant records WCAP- 16880-P and Cycle
- 9. Applicant records 1242 pcm.
COMMENTS:
___ SAT
___ UNSAT 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 r ods 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: 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
~ 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:
___ SAT
___ UNSAT Rev. 0 A.1-1 RO Page 7 of 106 STEP 4: [5] IF there are immovable/untrippable rods, THEN 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.
(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)
___ SAT
___ UNSAT STEP 5: [6] RECORD the (M-P)SDM from NOB Sheet A-3. (M-P)SDM = ________ppm.
STANDARD: Applicant obtains the required value by referring to the NOB sheet A-3. records it in the procedure blank. (M-P)SDM =
90 ppm. Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT Rev. 0 A.1-1 RO Page 8 of 106 STEP 6: [7] CALCULATE required RCS C B. [a] DETERMINE UNCORRECTED Maximum Required C B , from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:
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 procedure blank. UNCORRECTED Max Required CB =
1547 ppm. Step is critical, since an incorrect entry will affect the calculated value for SDM.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 7: [7b] CALCULATE required RCS C B. [b] CALCULATE the Required C B __________ + __________ + ____________
(Step [5]) (Step [6]) (Step [7] [a])
Required C B = ______________ ppm.
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 C B = __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:
CRITICAL STEP
___ SAT
___ UNSAT Rev. 0 A.1-1 RO Page 9 of 106 STEP 8: [8] VERIFY That RCS C B in Step [4] D is greater than or equal to the Required C B in Step [7}[b] (Acc Crit. A & B).
STANDARD: Applicant determines that the acceptance criteria are NOT 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 report.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT 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 Ca lculation," beginning at Step 3. Base the calculation on the conditions stated above.
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 SSNTime 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 desi red 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.
STANDARD: A copy of 1-SI-0-10, "Shutdown Margin" has been obtained.
EXAMINER'S CUE: Provide the applicant a copy of the completed 1-SI-0-1, "Shutdown Margin" Section 6.2, "Determine
Required RCS Boron Concentration."
COMMENTS:
___ SAT
___ UNSAT 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.
STANDARD: Applicant reviews Section 3.0 Precautions and Limitations.
COMMENTS:
___ SAT
___ UNSAT STEP 3: [2] ENSURE prerequisite actions in Section 4.0 have been met.
STANDARD: Applicant determines that Section 4.0 is complete.
COMMENTS:
___ SAT
___ UNSAT Rev. 0 A.1-1SRO Page 16 of 106 STEP 4: [3] OBTAIN the NuPOP for the applicable cycle AND RECORD: B. The WCAP number, unit, and cycle number (front cover of NuPOP):WCAP-________ Unit ____ Cycle_____
C. The Maximum Stuck Rod Worth.
Table D1, (Mode 2 below nuclear heating through Mode 5):
________pcm
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:
CRITICAL STEP
___ SAT
___ UNSAT STEP 5: [4] DETERMINE the following plant conditions: 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
~ 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:
___ SAT
___ UNSAT 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 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) ________ 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:
___ SAT
___ UNSAT Rev. 0 A.1-1SRO Page 18 of 106 STEP 7: [6] RECORD the (M-P)SDM from NOB Sheet A-3. (M-P)SDM = ________ppm.
STANDARD: Applicant determines that the value entered is incorrect, in that 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. CORRECT VALUE (M-P)SDM =
90 ppm. Step is critical since an incorrect data entry was made, which affects the calculation.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT Rev. 0 A.1-1SRO Page 19 of 106 STEP 8: [7] CALCULATE required RCS C B [a] DETERMINE UNCORRECTED Maximum Required C B , from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:
UNCORRECTED Max Required CB = __________ ppm STANDARD: Applicant determines that the value entered is incorrect, 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:
CRITICAL STEP
___ SAT
___ UNSAT Rev. 0 A.1-1SRO Page 20 of 106 STEP 9: [7b] CALCULATE required RCS C B [b] CALCULATE the Required C B __________ + __________ + ____________
(Step [5]) (Step [6]) (Step [7] [a])
Required C B = ______________ ppm 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 C B blank. __0 ___ + ___-
90____ + ___
1556_____ (Step [5]) (Step [6]) (Step [7] [a])
Required C B = __1466____ ppm CORRECT VALUE
__0 ___ + ___90____ + ___
1547_____ (Step [5]) (Step [6]) (Step [7] [a])
Required C B = __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:
CRITICAL STEP
___ SAT
___ UNSAT Rev. 0 A.1-1SRO Page 21 of 106 STEP 10: [8] VERIFY That RCS C B in Step [4] D is greater than or equal to the Required C B in Step [7] [b] (Acc Crit. A & B).
STANDARD: Applicant determines that the acceptance criteria is NOT MET , 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 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 CRITICAL STEP
___ SAT
___ UNSAT 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 desi red 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 SSNTime 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.
- 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.
- 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".
A.1-2 RO Page 28 of 106 START TIME: _______
STEP 1: Obtain a copy of the instruction.
STANDARD: A copy of SOI-62.02 Appendix E "Reactivity Balance Calculation" has been obtained.
EXAMINER'S CUE: Provide the applicant a copy of the instruction.
COMMENTS:
___ SAT
___ UNSAT NOTE 1 One calculation is required for each major change. Calculation is an approximation of Final Target Boron C B. Rough interpolation of NuPop figures is acceptable and expected. NOTE 2 Dilution or Boration value for power change from P 1 % to P 2 % power in time period T with rods moving from step position R 1 to R 2. (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:
Obtains: Current RCS Boron C B: __________PPM.
STANDARD: Value provided on task assignment sheet. Applicant may contact Chem Lab for current boron concentration.
CUE: If CHEM LAB notified, acknowle dge request, then report current RCS Boron Concentration is 750 ppm.
COMMENTS:
___ SAT
___ UNSAT A.1-2 RO Page 29 of 106 STEP 3: Obtains: Core Burnup: _______MWD/MTU.
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).
COMMENTS:
___ SAT
___ UNSAT
STEP 4: Obtains: Current Reactor power = P1: ________ %
Target Reactor power = P2: _______ % Calculates: Total Reactor power change: _______%
STANDARD: Applicant determines current reactor power and target power 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:
___ SAT
___ UNSAT A.1-2 RO Page 30 of 106 STEP 5: Obtains: Rate of Reactor power change: ________ %/hr.
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 of hours projected to reach target power as 8 hrs.
COMMENTS:
___ SAT
___ UNSAT
STEP 6: Obtains: Current Rod Position: _________ steps.
Final Rod Position: _________ steps.
STANDARD: Applicant determines final rod position from task assignment as 220 Steps. Applicant determines current rod position from ICS or Control Board Step Counters (Value provided on task assignment sheet). Value for current position is 190 steps.
COMMENTS:
___ SAT
___ UNSAT 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 applicant's completion of the second page of Appendix E steps for Reactivity Balance.
STEP 7: Determines Power Defect:
From NUPOP, Figure 6-18, 19, or 20 (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 correct as shown).
STANDARD: Applicant determines the PD 1 for current power level is -
1594 pcm from Table 7-18, and determines PD 2 for target power level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Applicant then calculates Power Defect by subtracting algebraically PD 2 from PD 1. The value determined is 494 pcm.
If Applicant determines the PD 1 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 RO Page 32 of 106 STEP 8: Determines Xenon: Xenon 1: From REACTW (either current conditions or projection to initial condition). _________
pcm XE 1. Xenon 2: From REACTW (projected over time period T). _______
pcm XE 2.
NOTE: Xenon values must be negative. Applicant then calculates Xenon by subtracting XE2 from XE
- 1. -2644.7 pcm XE 1 - -2508.1 pcm XE 2 = -136.6 pcm (current) (Target) Xenon STANDARD: Applicant determines the XE 1 for current power level is
-2644.7 pcm from Xenon REACTW printout, and determines XE 2 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 XE 2 from XE 1. The value determined is -136.6 pcm.
Acceptable range is 137 +/-1 pcm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 RO Page 33 of 106 STEP 9 Determines rods: Rods 1, 2 : From NUPOP, Figure 6-24, or 25. ___________ pcm Rods 1 - _________ pcm Rods 2 = _______ pcm (current) (Target) Rods STANDARD: Applicant determines the Rods 1 for current rod position as 150 pcm (accept 175 - 125) from NUPOP Figure 6-25, and determines Rods 2 for target as 0 (accept 0 - 40) pcm from the same figure, and enters the values in appropriate table locations. Applicant then calculates Rods by subtracting algebraically Rods 2 from Rods
- 1. 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 RO Page 34 of 106 STEP 10: Determines boron 1: Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure 6-21).
______ Boron X ( 1000
÷ _________pcm/%) = _________pcm (current) BORON 1 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 location. Applicant then calculates BORON 1 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:
CRITICAL STEP
___ SAT
___ UNSAT
A.1-2 RO Page 35 of 106 STEP 11: Determines boron 2: Calculates BORON 2 by ______ Power Defect + _____ pcm Xenon - ____ pcm +
____________ pcm ( BORON 1) = _____________ pcm BORON 2 STANDARD: Applicant calculates boron 2 by algebraically 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 ) + -136.6 pcm ( Xenon) - 150 pcm ( Rods) + -4717 pcm ( BORON 1) = -4510 pcm BORON 2 + 450 pcm ( Power Defect ) + -136 pcm ( Xenon) - 175 pcm ( Rods) + -4725 pcm ( BORON 1) = -4586 pcm BORON 2 + 530 pcm ( Power Defect ) + -138 pcm ( Xenon) - 85 pcm ( Rods) + -4650 pcm ( BORON 1) = -4343 pcm BORON 2 Acceptable Range is - 4586 to - 4343 pcm.
The new calculated value must be within the stated acceptable range.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT 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 BORON 2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 717 ppm (-4586) pcm BORON 2 X (-160_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 724 ppm (-4343) pcm BORON 2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 694 ppm STANDARD: Applicant determines Target Boron Concentration by taking BORON 2 times boron worth and conversion factor. The target boron concentration is calculated to be 717 ppm.
Acceptable Range is 725 to 690 pcm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT 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 report. Acknowledge re quest for independent verification. State that this Admin JPM has been completed. We will stop here.
STANDARD: Applicant informs the SM/Unit Supervisor of the Target RCS boron concentration that was calculated.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT 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.
- 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.
- 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"
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 SSNTime 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.
- 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.
- 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.
STANDARD: A copy of SOI-62.02 Appendix E "Reactivity Balance Calculation" has been obtained.
EXAMINER'S CUE: Provide the Applicant a copy of the completed instruction.
COMMENTS:
___ SAT
___ UNSAT NOTE 1 One calculation is required for each major change. Calculation is an approximation of Final Target Boron C B. Rough interpolation of NuPop figures is acceptable and expected. NOTE 2 Dilution or Boration value for power change from P 1 % to P 2 % power in the time period T with rods moving from step position R 1 to R 2. (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 C B: __________PPM.
STANDARD: Applicant ensures correct RCS Boron Concentration is entered in the Table associated with Step 1.
COMMENTS:
___ SAT
___ UNSAT A.1-2 SRO Page 47 of 106 STEP 3: Obtains: Core Burnup: _______MWD/MTU
STANDARD: Applicant ensures correct current core burnup from task assignment sheet. 12000 MWD/MTU
.
COMMENTS:
___ SAT
___ UNSAT
STEP 4: Obtains: Current Reactor power = P1: ________ %
Target Reactor power = P2: _______ % Calculates: Total Reactor power change: _______%
STANDARD: Applicant ensures correct current reactor power and target power from information provided on assignment sheet. P1 =
76%. P2 = 100 % Target reactor power was given on task assignment. Applicant ensures correct total power change to be 24%.
COMMENTS:
___ SAT
___ UNSAT A.1-2 SRO Page 48 of 106 STEP 5: Obtains: Rate of Reactor Power change: ________ %/hr Number of hours to change power: ________ hr(s)
STANDARD: Applicant ensures correct rate of reactor power change from task assignment to be 3 % per hour. Applicant ensures correct number of hours projected to reach target power as 8 hrs.
COMMENTS:
___ SAT
___ UNSAT
STEP 6: Obtains: Current Rod Position: _________ steps Final Rod Position: _________ steps
STANDARD: Applicant ensures correct final rod position from task 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:
___ SAT
___ UNSAT A.1-2 SRO Page 49 of 106 CAUTION Follow sign conventions explicitly.
Evaluator Note. JPM Steps 7 through 11 evaluate Applicant's completion of the second page of Appendix E steps for Reactivity Balance.
STEP 7: Determines Power Defect:
From NUPOP, Figure 6-18, 19, or 20 (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 correct as shown).
STANDARD: Applicant determines the PD 1 for current power level is -
1594 pcm from Table 7-18, and determines PD 2 for target power level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Applicant then calculates Power Defect by subtracting algebraically PD 2 from PD 1. The value determined is 494 pcm.
If Applicant determines the PD 1 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 SRO Page 50 of 106 STEP 8: Determines Xenon: Xenon 1: From REACTW (either current conditions or projection to initial condition). _________
pcm XE 1. Xenon 2: From REACTW (projected over time period T). _______
pcm XE2. NOTE: Xenon values must be negative. Applicant than calculates Xenon by subtracting algebraically XE2 from XE 1. -2644.7 pcm XE 1 - -2508.1 pcm XE 2 = -136.6 pcm (current) (Target) Xenon STANDARD: Applicant determines the XE 1 for current power level is
-2644.7 pcm from Xenon REACTW printout, and determines XE 2 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 XE 2 from XE 1. 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 SRO Page 51 of 106 STEP 9 Determines rods: Rods 1, 2 : From NUPOP, Figure 6-24, or 25. ___________ pcm Rods 1 - _________ pcm Rods 2 = _______ pcm (current) (Target) Rods STANDARD: Applicant determines the Rods 1 for current rod position as 150 pcm (accept 175 - 125) from NUPOP Figure 6-25, and determines Rods 2 for target as 0 (accept 0 - 40) pcm from the same figure, and enters the values in appropriate table locations. Applicant then calculates Rods by subtracting algebraically Rods 2 from Rods
- 1. 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 SRO Page 52 of 106 STEP 10: Determines boron 1: Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure 6-21).
______ Boron X ( 1000
÷ _________pcm/%) = _________pcm (current) BORON 1 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 location. Applicant then calculates BORON 1 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:
CRITICAL STEP
___ SAT
___ UNSAT
A.1-2 SRO Page 53 of 106 STEP 11: Determines boron 2: Calculates boron 2 by ______ Power Defect + _____ pcm Xenon - ____ pcm +
____________ pcm ( BORON 1) = _____________ pcm BORON 2 STANDARD: Applicant calculates boron 2 by algebraically 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 ) + -136.6 pcm ( Xenon) - 150 pcm ( Rods) + -4717 pcm ( BORON 1) = -4510 pcm BORON 2 + 450 pcm ( Power Defect ) + -136 pcm ( Xenon) - 175 pcm ( Rods) + -4725 pcm ( BORON 1) = -4586 pcm BORON 2 + 530 pcm ( Power Defect ) + -138 pcm ( Xenon) - 85 pcm ( Rods) + -4650 pcm ( BORON 1) = -4343 pcm BORON 2 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:
CRITICAL STEP
___ SAT
___ UNSAT A.1-2 SRO Page 54 of 106 Evaluator Note. JPM Steps 12 evaluate Applicant's completion of the second page of Appendix E steps for Target PPM.
STEP 12: (-4510) pcm BORON 2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 717 ppm (-4586) pcm BORON 2 X (-160_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 724 ppm (-4343) pcm BORON 2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 694 ppm STANDARD: Applicant determines Target Boron Concentration by taking BORON 2 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:
CRITICAL STEP
___ SAT
___ UNSAT STEP 13: NOTIFY SM/Unit SRO of RCS Target Boron Concentration independently verified. .
EVALUATOR CUE: Role play as SM/Unit supervisor and acknowledge report. Acknowledge re quest for independent verification, State that this Admin JPM has been completed. We will stop here.
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
___ SAT
___ UNSAT 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.
- 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.
- 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 SSNTime 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 Applicant's 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 require d to be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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.
STANDARD: A copy of 1-SI-0-21 "Excore QPTR & Axial Flux Difference" has been obtained.
EXAMINER'S CUE: After the applicant has identifies the correct instruction, provide a copy of the instruction.
COMMENTS:
___ SAT
___ UNSAT 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 co mputer 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.
STANDARD: Step is N/A since the QPTR is NOT being performed during an NIS calibration.
COMMENTS:
___ SAT
___ UNSAT 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.
STANDARD: Applicant goes to Attachment 1 and performs applicable steps.
COMMENTS:
___ SAT
___ UNSAT NOTE 1 Determining detector currents by measuring the voltage across the detector's 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 mete r 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: ________________
STANDARD: Applicant determines step is N/A based on initial conditions for task performance and proceeds to the next step.
COMMENTS:
___ SAT
___ UNSAT A.2 - RO Page 63 of 106 STEP 4: [Step 2] ENSURE required M&TE is within its current calibration.
STANDARD: Applicant determines step is N/A based on initial conditions for task performance and proceeds to the next step.
COMMENTS:
___ SAT
___ UNSAT 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 Ohm's 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 I t Detector Current (microamps)
I b Detector Current (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 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 handout.
COMMENTS:
___ SAT
___ UNSAT A.2 - RO Page 65 of 106 NOTE: R t and R b (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 R t and R b (volts/microamps).
UPPER DETECTOR LOWER DETECTOR NIS Channel R t (volts/microamps) R b (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 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 respective NOB Sheets A-2 which are attached to this JPM.
COMMENTS:
___ SAT
___ UNSAT
A.2 - RO Page 66 of 106 STEP 7: [Step 5] CALCULATE calibrated output voltages by multiplying the uncalibrated detector output currents by R t or R b (as applicable). A. V t = I t x R t B. V b = I b x R b UPPER DETECTOR LOWER DETECTOR NIS Channel V t Calib. Output Voltage V b Calib. Output 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 3] by multiplying the respective detector's current reading times resistance values [from Step 4] and records the results in the appropriate blocks on Attachment 1 Step 5.
COMMENTS:
Critical Step
___ SAT
___ UNSAT STEP 8: [Step 6] CALCULATE average calibrated output voltage for the upper and lower detectors.
UPPER V t LOWER V b AVERAGE (13.926+16.158+13.911+ 15.575)/4 =14.893 (14.719+17.339+14.295+ 14.718)/4 = 15.268 STANDARD: Applicant calculates the average output voltages for the upper detector by adding the respective upper detector's calibrated output voltage readings [from Step 5] and dividing the result 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 Step 6.
COMMENTS:
Critical Step
___ SAT
___ UNSAT
A.2 - RO Page 67 of 106 STEP 9: [Step 7] CALCULATE QPTR values by dividing each detector's (upper or lower) Calibration Output Voltage by the average (upper or lower) Calibrated Output Voltage. A. QPTR t = V t ÷ Avg V t B. QPTR b = V b ÷ Avg V b UPPER DETECTOR LOWER DETECTOR NIS Channel QPTR t Value QPTR b 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 Calibrated Output Voltage [from step 5] by the Average Calibrated Output Voltage for each NIS channel detector
[from step 6]. The results recorded in appropriate blocks on Attachment 1. Applicant returns to Section 6.1 Step 7.
COMMENTS:
Critical Step
___ SAT
___ UNSAT 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.
COMMENTS:
___ SAT
___ UNSAT
A.2 - RO Page 68 of 106 STEP 11: [Step 3] CHECK () Acceptance Criteria.
ACCEPTANCE CRITERIA: All operable excore channels (upper and lower) indicate a QPTR 1.02. YES NO 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:
Critical Step
___ SAT
___ UNSAT
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.
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
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.
EXAMINER'S CUE: Acknowledge report as Unit Supervisor, then state "We will stop here."
COMMENTS:
END OF TASK
___ SAT
___ UNSAT 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 require d to be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 DETECTORLOWER DETECTOR NIS Channel I t Detector Current (microamps)
I b Detector Current (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 SSNTime 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 mult iple 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.
STANDARD: A copy of OPDP-4-1 Attachment 1, Disabled Alarm Checklist.
EXAMINER'S CUE: Provide the Applicant a copy of the completed instruction.
COMMENTS:
___ SAT
___ UNSAT
STEP 2: DISABLED ALARM CHECKLIST block reviewed.
STANDARD: Applicant determines that the correct Panel Number is entered in the block.
COMMENTS:
___ SAT
___ UNSAT
STEP 3: ALARM LOCATION block is reviewed.
STANDARD: Applicant determines correct information is entered in the Node/Mux/Pt or SER.
COMMENTS:
___ SAT
___ UNSAT
STEP 4: Reviews entry in 1. Description of the alarm that is being defeated.
STANDARD: Applicant determines that an adequate description of the alarm function has been entered.
COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.2-SRO Page 77 of 106 STEP 5: Reviews entry in 2. Describe reason for disabling the alarm (include procedure or WO number, if applicable).
STANDARD: Error Discovery - Incorrect/inadequate description for disabling alarm.
The data entere d should describe that the alarm has been deemed a nuisance, and is to be disabled for that reason.
Refering to GO-6 Section 5.4, Step [10.4].
COMMENTS:
Critical Step
___ SAT
___ UNSAT
STEP 6: Reviews entry in 3. Description of how alarm will be disabled.
STANDARD: Applicant determines that the description is adequate.
COMMENTS:
___ SAT
___ UNSAT
STEP 7: Reviews entry in 4. Is a 10CFR50.59 Review required prior to disabling alarm? (Refer to Appendix A).
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.
COMMENTS:
Critical Step
___ SAT
___ UNSAT
STEP 8: Reviews entry in 5. Is a 10CFR50.59 Review required prior to 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 maintenance evolution.
COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.2-SRO Page 78 of 106 STEP 9: Reviews entry in 6. Is a Technical Evaluation (Form OPDP-4-5) required prior to disabling the alarm? (Refer to Appendix A).
STANDARD: Error Discovery - Incorrect block checked.
Applicant determines that a Technical Evaluation (Form OPDP-4-5) is required.
COMMENTS:
Critical Step
___ SAT
___ UNSAT
STEP 8: Performs entry in 7, and determines that the form cannot be approved as presented.
STANDARD: Applicant states that the package cannot be signed as approved until after the errors have been corrected.
COMMENTS:
END OF TASK Critical Step
___ SAT
___ UNSAT 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 mu ltiple 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 SSNTime 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 Pa ge 85of 106 START TIME: _______
STEP 1: Obtain a copy of the completed instruction.
STANDARD: Marked up copy of the Release Package including 0-ODI-90-1 "Liquid Radwaste Tank Release" is acquired by the applicant.
EXAMINER'S CUE: Provide the applicant a copy of the completed instruction.
COMMENTS:
___ SAT
___ UNSAT
STEP 2: Applicant reviews package for correct tank to be released.
STANDARD: Error - The Batch Liquid Effluent Permit provided is for the wrong tank. NOTE: According to the INITIAL CONDITIONS, a realease of the MONITOR TANK is to be conducted. The Batch Liquid 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:
Critical Step
___ SAT
___ UNSAT
STEP 3: Applicant reviews package to verify radioanalysis values are less than the limits provided on the Batch Liquid Effluent Permit.
STANDARD: Applicant determines that all values are less than limits (III. RADIOANALYSIS - LIQUID).
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT A.3-SRO Pa ge 86of 106 STEP 4: Applicant reviews package to verify the EXP. RESPONSE 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 MONITOR(S) section of the Batch Liquid Effluent Permit.
COMMENTS:
___ SAT
___ UNSAT
STEP 5: Applicant reviews package to verify the volume, flow, and 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 Liquid Effluent Permit.
COMMENTS:
___ SAT
___ UNSAT
STEP 6: Applicant reviews package to verify the radiation monitor voltage is within limits.
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-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:
Critical Step
___ SAT
___ UNSAT STEP 6: Applicant reviews 0-ODI-90-1 package to verify the proper step sign-offs are made.
STANDARD: Error - Attachment B, PRE-RELEASE SETPOINT ADJUSTMENT is not included in the 0-ODI-90-1 package.
COMMENTS: ___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT A.3-SRO Pa ge 87of 106 STEP 8: Applicant determines that the package cannot be approved as written. STANDARD: Applicant states that the package cannot be signed as approved until after the errors have been corrected.
COMMENTS:
Critical Step
___ SAT
___ UNSAT STEP 8: Applicant addresses question "If 0-RM-90-122 WDS Liquid Realease Radiation Monitor fails during the batch release, what actions are required to be taken to comply with the Offsite Dose Calculation Manual (ODCM)?"
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-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 tank's 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 Critical Step
___ SAT
___ UNSAT TIME STOP: ________
Page 88 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Page 88 of 106 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 89 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Page 89 of 106
A.3-RO Evaluate RADCON Survey Map to determine posting requirements.
Page 90 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Page 90 of 106 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 SSNTime Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________ NAME SIGNATURE DATE
===============================================================
COMMENTS 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 Page 92 of 106 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 Applicant's Cue Sheet.
Page 93 of 8 WATTS BAR NUCLEAR PLANT A.3- RO Page 93 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:
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 robot's operator be if the operator stands 1.5 meters from the RHR pump?
(Treat the RHR Pump as a point source.)
A.3- RO Pa ge 94of 8 START TIME: _______
STEP 1: Applicant reviews materials given and may determine references needed.
STANDARD: Applicant becomes familiar with materials. May refer to SPP-5.1 "Radiological Controls".
COMMENTS:
___ SAT
___ UNSAT
STEP 2: Evaluation of Contaminated Area.
STANDARD: Applicant should determine that the area where smears 1,2 and 3 were taken would be posted as a Contaminated Area. These smears indicated removable contamination >
1000 dpm/100 cm
- 2.
COMMENTS:
Critical Step
___ SAT
___ UNSAT A.3- RO Pa ge 95of 8 STEP 3: Evaluation of High Radiation Area.
STANDARD: Applicant should determine the general area readings near 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.
COMMENTS:
Critical Step
___ SAT
___ UNSAT
STEP 4: Evaluation of Radiation Areas.
STANDARD: Applicant should determine that the general area readings 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.
COMMENTS:
Critical Step
___ SAT
___ UNSAT
A.3- RO Pa ge 96of 8 STEP 5: Evaluation of Room Posting.
STANDARD: Room need not be posted if postings stated above are completed.
COMMENTS:
___ SAT
___ UNSAT STEP 6: Question: Maintenance is to be performed on the RHR pump using a robot. What will the dose rate to the robot's 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
A.3- RO Pa ge 97of 8 STEP 7: Results of the evaluation are reported to the Unit Supervisor.
STANDARD: Applicant reports results of the previous steps.
EXAMINER'S CUE: Acknowledge report as Unit Supervisor, then state We will stop here.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT TIME STOP: ________
PAGE 98 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Page 98 of 8
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 robot's operator be if the operator stands 1.5 meters from the RHR pump? (Treat the RHR pump as a point source.)
PAGE 99 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Page 99 of 8
A.4-SRO CLASSIFY THE EVENT AND DETERMINE PAR.
PAGE 100 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Page 100 of 8 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 SSNTime Finish: _________
Performance Rating: SAT ______ UNSAT ______
Performance Time ____
Examiner: __________________________________
__________________________________/________ NAME SIGNATURE DATE
=======================================================================
COMMENTS 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 Page 102 of 8 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 103 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Page 103 of 8 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.
- 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 104 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Pa ge 104of 8 START TIME: _______
STEP 1: Refers to EPIP-1 to determine level of event.
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 within 15 minutes of task assignment.
This step is critical to ensure proper activation of TVA resources for event in progress.
COMMENTS: RECORD time that declaration was made:_________
CRITICAL STEP ___ SAT
___ UNSAT
STEP 2: Implements EPIP-5, GENERAL EMERGENCY.
STANDARD: EPIP-5, GENERAL EMERGENCY, is implemented.
COMMENTS:
___ SAT
___ UNSAT
PAGE 105 0F 106 WATTS BAR NUCLEAR PLANT A.4 - SRO Pa ge 105of 8 STEP 3: [STEP 1] IF the onsite emergency centers are not staffed, 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 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:
___ SAT
___ UNSAT
STEP 3: [STEP 2] IF the TSC has not been activated , THEN a. INITIATE Appendix A and B, Initial Notification Form for GENERAL EMERGENCY and Protective Action Recommendations.
STANDARD: Appendix A is accurately completed with Appendix B RECOMMENDATION 2 SELECTED. Performer notifies the ODS, and then assigns the NLO to FAX Appendix A to the ODS.
NOTE TO EVALUATOR: Underlined portion is the critical part.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
TIME STOP: ________
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.
- 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.