ML092810538
| ML092810538 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/08/2009 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML092810538 (144) | |
Text
Page 1 of 11 WATTS BAR NUCLEAR PLANT A.1-1 RO A.1-1 RO Calculate Shutdown Margin
Page 2 of 11 WATTS BAR NUCLEAR PLANT A.1-1 RO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Calculate Shutdown Margin Alternate Path: N/A Facility JPM #:
3-OT-JPMADA-1.3 K/A Rating(s):
001A4.11 [3.5/4.1]
2.1.7 [3.7/4.4]
2.1.25 [2.8/3.1]
Task Standard:
Performer completes a Conservative SDM Hand Calculation per 1-SI-0-10 Section 6.2. Determines Required RCS Boron Concentration, 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
===============================================================
Performer:
Time Start: ________
NAME SSN Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS Tools/Equipment/Procedures Needed:
Rev. 0 A.1-1R Page 3 of 11 Latest revision of 1-SI-0-10 NUPOP for WBN Unit 1 Cycle 9 NOB for WBN Unit 1 Ruler or straight edge.
Calculator NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide performer with procedure).
Rev. 0 A.1-1R Page 4 of 11 READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit has tripped and requires a cooldown to 160 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.
- 6. You are an extra Unit Operator.
INITIATING CUES:
The SM/Unit SRO has directed you to perform a Conservative SDM Hand Calculation per 1-SI-0-10 Shutdown Margin, Section 6.2 based on the conditions stated above.
- 2. Determine if acceptance criteria are met.
Rev. 0 A.1-1R Page 5 of 11 START TIME: _______
STEP 1:
Obtain a copy of the instruction.
STANDARD: A copy of 1-SI-0-10 has been obtained.
EXAMINERS CUE: Provide the Performer 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: [1]
ENSURE precautions and limitations in Section 3.0 have been reviewed.
STANDARD: Performer reviews Section 3.0 Precautions and Limitations.
COMMENTS:
___ SAT
___ UNSAT STEP 3: [2]
ENSURE prerequisite actions in Section 4.0 have been met.
EVALUATOR CUE: State that Section 4.0 actions have been met.
STANDARD: Performer proceeds to the next step COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.1-1R Page 6 of 11 STEP 4: [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: Performer records WCAP-16880-P and Cycle 9. Performer records 1242 pcm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1R Page 7 of 11 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 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: Performer records the following:
A. Core average burnup: 7500MWD/MTU.
From Section 8.3, Performer checks Middle of Life box.
B. Number of immovable/untrippable rods: 0 C. Minimum Tcold for the desired condition: 160 F D. RCS Boron Concentration Cb: 1500 ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1R Page 8 of 11 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: Performer enters N/A for this step, since the Cue Sheet stated that there were NO UNTRIPPABLE RODS.
If the Performer 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: Performer 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 7: [6]
RECORD the (M-P)SDM from NOB Sheet A-3.
(M-P)SDM = ________ppm.
STANDARD: Performer obtains the required value by referring to the NOB sheet A-3. records it in the procedure blank.
(M-P)SDM = 90 ppm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1R Page 9 of 11 STEP 8: [7]
CALCULATE required RCS CB
[a] DETERMINE UNCORRECTED Maximum Required CB, from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:
UNCORRECTED Max Required CB = __________ ppm STANDARD: Performer obtains the required value by referring to the NuPOP Table 7-4 for 2500 MWD/MTU and 160 °F records value in the procedure blank.
UNCORRECTED Max Required CB = 1563 ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 9: [7b] CALCULATE required RCS CB
[b] CALCULATE the Required CB
__________ + __________ + ____________
(Step [5]) (Step [6]) (Step [7] [a])
Required CB = ______________ ppm STANDARD: Performer calculates the sums from Step [5], Step [6] and Step 7a, and enters the valve calculated in the Required Cb blank.
__0 ___ + ___90____ + ___1563_____
(Step [5]) (Step [6]) (Step [7] [a])
Required CB = __1653____ ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1R Page 10 of 11 STEP 10: [8] VERIFY That RCS CB in Step [4] D is greater than or equal to the Required CB in Step [7}[b] (Acc Crit. A & B).
STANDARD: Performer 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: ________
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit has tripped and will require a Unit Cooldown to 160 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 desired to remain running for the entire cooldown.
- 6. You are an extra Unit Operator.
INITIATING CUES:
The SM/Unit SRO has directed you to perform a Conservative SDM Hand Calculation per 1-SI-0-10 Shutdown Margin, Section 6.2 based on the conditions stated above.
- 2. Determine if acceptance criteria are met.
Rev. 0 Page 1 of 17 WATTS BAR NUCLEAR PLANT A.1-1SRO A.1-1SRO Perform Technical Review of Shutdown Margin Calculation
Rev. 0 Page 2 of 17 WATTS BAR NUCLEAR PLANT A.1-1SRO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Perform Technical Review of Shutdown Margin Calculation Alternate Path: N/A Facility JPM #: New K/A Rating(s): 001A4.11 [3.5/4.1]
2.1.7 [3.7/4.4]
2.1.25 [2.8/3.1]
Task Standard: Performer completes a Technical Review of Shutdown Margin Calculation Conservative SDM Hand Calculation per 1-SI-0-10 Section 6.2. Determines 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
===============================================================
Performer:
Time Start: ________
NAME SSN Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
Rev. 0 A.1-1SRO Page 3 of 17 Tools/Equipment/Procedures Needed:
Latest revision of 1-SI-0-10 NUPOP for WBN Unit 1 Cycle 9 NOB for WBN Unit 1 Ruler or straight edge.
Calculator NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide performer with procedure).
Rev. 0 A.1-1SRO Page 4 of 17 READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit has tripped and requires a cooldown to 160 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 desired to remain running for the entire cooldown.
- 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.
Rev. 0 A.1-1SRO Page 5 of 17 START TIME: _______
STEP 1:
Obtain a copy of the instruction.
STANDARD: A copy of 1-SI-0-10 has been obtained.
EXAMINERS CUE: Provide the Performer a copy of the completed 1-SI-0-1, Section 6.2.
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: Performer reviews Section 3.0 Precautions and Limitations.
COMMENTS:
___ SAT
___ UNSAT STEP 3: [2] ENSURE prerequisite actions in Section 4.0 have been met.
STANDARD: Performer determines that Section 4.0 is complete.
COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 6 of 17 STEP 4: [3] OBTAIN the NuPOP for the applicable cycle AND RECORD:
A. The WCAP number, unit, and cycle number (front cover of NuPOP):WCAP-________ Unit ____ Cycle_____
B. The Maximum Stuck Rod Worth.
Table D1, (Mode 2 below nuclear heating through Mode 5):
________pcm STANDARD: Performer verifies that the information associated with A is correct. (WCAP-16880-P Unit 1 and Cycle 9.)
Performer determines that an incorrect value of 1020 was entered from Table D-1 and notes 1242 pcm is the correct value.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 7 of 17 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 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: Performer determines the following data was entered correctly:
A. Core average burnup: 7500MWD/MTU.
From Section 8.3, Performer checks Middle of Life box.
B. Number of immovable/untrippable rods: 0 C. Minimum Tcold for the desired condition: 160 F D. RCS Boron Concentration Cb: 1500 ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 8 of 17 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 completes the calculation, the value entered will still be ZERO.
____0_____ x __1242__pcm __-6.5 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 9 of 17 STEP 7: [6] RECORD the (M-P)SDM from NOB Sheet A-3.
(M-P)SDM = ________ppm.
STANDARD: Performer determines that the value entered is incorrect, in that a negative sign was entered. Performer 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.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 10 of 17 STEP 8: [7] CALCULATE required RCS CB
[a] DETERMINE UNCORRECTED Maximum Required CB, from NuPOP Table 7-4 using burnup of Step [4] A and temperature of Step [4] C:
UNCORRECTED Max Required CB = __________ ppm STANDARD: Performer determines that the value entered is incorrect, Performer obtains the required value by referring to the NuPOP Table 7-4 for 7500 MWD/MTU and 160 °F records value in the procedure blank.
UNCORRECTED Max Required CB = 1558 ppm CORRECT VALUE UNCORRECTED Max Required CB = 1563 ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 11 of 17 STEP 9: [7b] CALCULATE required RCS CB
[b] CALCULATE the Required CB
__________ + __________ + ____________
(Step [5]) (Step [6]) (Step [7] [a])
Required CB = ______________ ppm STANDARD: Performer determines that the value entered is incorrect.
Performer calculates the sums from Step [5], Step [6] and Step 7a, and enters the value calculated in the Required CB blank.
__0 ___ + ___-90____ + ___1558_____
(Step [5]) (Step [6]) (Step [7] [a])
Required CB = __1468____ ppm NOTE TO EVALUATOR: CORRECT VALUE
__0 ___ + ___90____ + ___1563_____
(Step [5]) (Step [6]) (Step [7] [a])
Required CB = __1653____ ppm COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
Rev. 0 A.1-1SRO Page 12 of 17 STEP 10: [8] VERIFY That RCS CB in Step [4] D is greater than or equal to the Required CB in Step [7][b] (Acc Crit. A & B).
STANDARD: Performer 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.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT TIME STOP: ________
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit has tripped and requires a cooldown to 160 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.
- 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.
6.2 WBN Shutdown Margin Unit 1 Data Package: Page _,_ of ---+/-.
Conservative SOM Hand Calculation NOTE 1-51-0-10 Rev. 0021 Paae 16 of 47 Due to the amount of conservatism factored into this calculation, this instruction may NOT pass acceptance criteria if pertormed in MODES 1 or 2. During MODES 1 or 2, perform Sections 6.3 or 6.4.
ENSURE Precautions and limitations in Section 3.0 have been reviewed.
ENSURE Prerequisite Actions in Section 4.0 have been met.
OBTAIN the NuPOP for the applicable fuel cycle AND RECORD:
The WCAP number. unit, and cycle number (front cover of NuPOP) :
WCAP-I~So-P Unit _I _ Cycle~
B.
The Maximum Stuck Rod Worth.
Appendix D Table D-1, (Mode 2 below nuclear heating through Mode 5):
10ZO pcm NOTES
- 1)
It is permissible to use a conservative ReS 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 immovablefuntrippable rods, NOT the one that is assumed to be untripped from the definition of SOM
~TERMINE the following plant conditions:
~
Core average burnup:
'7st?O MWD/MTU (ICS computer point U7981) and check the applicable core life below as defined in NuPOP Section 8.3.
o Beginning of Life
..r Middle of Life o End of Life
~
Number of immovable/untrippable rods: ->1-¢"-----
WBN Shutdown Margin 1-51-0-10 Unit 1 Rev. 0021 Paae 17 of 47 Data Package: Page...!:.- of -+/--
6.2 Conservative SOM Hand Calculation (continued)
Minimum T cold for the desired condition:
I ~O of RCS Boron Concentration Ca: ISOD ppm IF there are immovable/untrippable rods. THEN l\\1i RECORD the differential Boron Worth using burnup from
':l( Step 6.2(4)A and RCS Boron Concentration from Step 6.2(4)0:
Differential Boron Worth: -". '\\-
pcm/ppm (See NuPOP Figure 6-22)
CALCULATE the absolute value stuck rod correction
!)
x lOW pcm +
(Step 6.2(4)B) (Step 6.2(3)B )
I -~. 4 pem / ppml (Step 6.2(5)A)
Stuck rod correction (absolute value) = _-.;¢~ __ ppm Date~
6.2 WBN Shutdown Margin 1-51-0-10 Unit 1 Rev. 0021 Pace 18 of 47 Da 7PaCkage: Page~of....1....
Date Co servative SOM Hand Calculation (continued)
RECORD the (M-P)soM from NOB Sheet A-3.
(M-P)sOM - _---"9"'0'-_
ppm
~
CALCULATE required RCS CB
& DETERMINE UNCORRECTED Maximum Required CB, from NuPOP Table 7-4 using burnup of Step 6.2[4JA and temperature of Step 6.2[4JC:
UNCORRECTED Max Required CB ;
IS'O> ppm C5z CALCULATE the Required C B:
¢
+
-90
+
1SS"'a (Step 6.2[5J9 )
(Step 6.2[6])
(Step 6.2[7JA)
Required CB::;
ppm VERIFY that RCS CB in Step 6.2[4JD is greater than or equal to the Required CB in Step 6.2[7J9 (Acc Crit. A & B).
CAUTION sL'e>/,,'1 I
It is the responsibility of Operations to ensure that dilution protection is adequate for plant conditions. Dilution protection is assured by either 1) the perfonnance of 1-5/-62-1, Uncontrolled Boron Dilution, 2) Stopping ALL Primary Water pumps and issuing a HOLD ORDER as administrative controls, or 3) performing the calculations within this procedure and verifying that the ReS boron concentration is adequate to allow the operator time to recognize the presence of a dilution.
NOTE Dilution protection calculations are NOT needed when RHR is NOT in service or when one or more Rep's will be maintained in operation along with RHR or when dilution protection will be accomplished via valve alignment or primary water pump hold order.
IF dilution protection is needed via boron analysis, THEN PERFORM Appendix A.
Page 1 of 16 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
Page 2 of 16 WATTS BAR NUCLEAR PLANT A.1-2 RO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Calculate Target Boron Cb for Load Escalation Using Appendix E of SOI-62.02 Alternate Path:
N/A Facility JPM #: 3-OT-JPMADA.1-2R K/A Rating(s): G2.1.25 [2.8/3.1]
Task Standard: Performer 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. 47; 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
===============================================================
Performer:
Time Start: ________
NAME SSN Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
A1-2R Page 3 of 16 Tools/Equipment/Procedures Needed:
Latest revision of SOI-62.02 NUPOP for WBN Unit 1 Cycle 9 NOB for WBN Unit 1 Ruler or straight edge.
Calculator NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide performer with procedure).
A1-2R Page 4 of 16 READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit is operating at 75% 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 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 Determine the RCS Target Boron concentration.
Notify SM/Unit SRO of the RCS Target Boron Concentration.
A1-2R Page 5 of 16 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.
EXAMINERS CUE: Provide the Performer 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 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 performers 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.
CUE: When CHEM LAB notified, acknowledge request, then report current RCS Boron Concentrations is 750 ppm.
STANDARD: Performer contacts Chem Lab for current boron concentration (Value provided on task assignment sheet.)
COMMENTS:
___ SAT
___ UNSAT
A1-2R Page 6 of 16 STEP 3:
Obtains: Core Burnup: _______MWD/MTU STANDARD: Performer 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: Performer 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.
Performer determines total power change to be 24%.
COMMENTS:
___ SAT
___ UNSAT
A1-2R Page 7 of 16 STEP 5:
Obtains:
Rate of Reactor Power change: ________ %/hr Number of hours to change power: ________ hr(s)
STANDARD: Performer determines rate of reactor power change from task assignment to be 3% per hour. Performer 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: Performer determines final rod position from task assignment as 220 Steps. Performer 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
A1-2R Page 8 of 16 CAUTION Follow sign conventions explicitly.
Evaluator Note. JPM Steps 7 through 11 evaluate performers 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: Performer determines the PD1 for current power level is -1594 pcm from Table 7-18, and determines PD2 for target power level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Performer then calculates Power Defect by subtracting algebraically PD2 from PD1. The value determined is 494 pcm.
If using Performer determines the PD1 for current power level is 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
A1-2R Page 9 of 16 STEP 8: Determines Xenon:
Xenon1: From REACTW (either current conditions or projection to initial condition). _________ pcm XE1.
Xenon2: From REACTW (projected over time period T). _______
pcm XE2.
NOTE: Xenon Values must be negative.
Performer than calculates Xenon by subtracting algebraically XE2 from XE1.
-2644.7 pcm XE1 - -2508.1 pcm XE2 = -136.6 pcm (current)
(Target)
Xenon STANDARD: Performer 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.
Performer then calculates Xenon by subtracting algebraically XE2 from XE1. The value determined is -136.6 pcm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
A1-2R Page 10 of 16 STEP 9 Determines rods:
Rods 1, 2 : From NUPOP, Figure 6-24, or 25.
___________ pcm Rods1 - _________ pcm Rods2 = _______ pcm (current)
(Target)
Rods STANDARD: Performer 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 locations. Performer then calculates Rods by subtracting algebraically Rods2 from Rods1. The value determined is 150 pcm. Acceptable Range is 85 to 175 pcm.
Performer 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
A1-2R Page 11 of 16 STEP 10: Determines boron1:
Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure 6-21).
______ Boron X ( 1000 ÷ _________pcm/%) = _________pcm (current)
BORON1 STANDARD: Performer enters 750 ppm for current boron concentration.
Performer 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. Performer 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 minus -
4717 pcm.
Performer 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
A1-2R Page 12 of 16 STEP 11: Determines boron2:
Calculates boron2 by
______ Power Defect + _____ pcm Xenon - ____ pcm +
____________ pcm ( BORON1) = _____________ pcm BORON2 STANDARD: Performer calculates boron2 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 )
+ -136.6pcm ( Xenon)
- 150 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4510 pcm BORON2
+ 450 pcm ( Power Defect )
+ -136.6pcm ( Xenon)
- 85 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4635 pcm BORON2
+ 530 pcm ( Power Defect )
+ -136.6pcm ( Xenon)
- 175 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4498 pcm BORON2 Performer must adjust value based on errors previously identified. The new calculated value must be within the stated acceptable range.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT Evaluator Note. JPM Steps 12 evaluate performers completion of the second page of Appendix E steps for Target PPM.
A1-2R Page 13 of 16 STEP 12: (-4510) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 717 ppm
(-4635) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 736 ppm
(-4498) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 715 ppm STANDARD: Performer determines Target Boron Concentration by taking BORON2 times born worth and conversion factor. The target boron concentration is calculated to be 725 ppm +/-12 ppm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
A1-2R Page 14 of 16 STEP 13:
NOTIFY SM/Unit SRO of RCS Target Boron Concentration calculated.
EVALUATOR CUE: Role play as SM/Unit supervisor and acknowledge report. Acknowledge request for independent verification, State that this Admin JPM has been completed. We will stop here.
STANDARD: Performer informs the SM/Unit Supervisor of the Target RCS boron concentration that was calculated.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT TIME STOP: ________
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 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 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 Determine the RCS Target Boron concentration.
Notify SM/Unit SRO of the RCS Target Boron Concentration
[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 1 of 19 WATTS BAR NUCLEAR PLANT A.1-2 SRO A.1-2 SRO Perform Independent Verification of Appendix E of SOI-62.02, REACTIVITY BALANCE CALCULATION
Rev. 1 Page 2 of 19 WATTS BAR NUCLEAR PLANT A.1-2 SRO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Perform Independent Verification of Appendix E of SOI-62.02, REACTIVITY BALANCE CALCULATION Alternate Path:
N/A Facility JPM #: 3-OT-JPMADA.1-5 K/A Rating(s): G2.1.25 [2.8/3.1]
Task Standard: Performer completes an independent verification of the SOI-62.02, Appendix E Reactivity balance calculation. Target RCS Boron Concentration is corrected based upon errors found. Performer 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.
Task Number: RO-062-SOI-62-016 APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5, 12 Validation Time: 20 min.
Time Critical: No
===============================================================
Performer:
Time Start: ________
NAME SSN Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
A.1-2 SRO Page 3 of 19 Tools/Equipment/Procedures Needed:
Latest revision of SOI-62.02 NUPOP for WBN Unit 1 Cycle 9 NOB for WBN Unit 1 Ruler or straight edge.
Calculator NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide performer with procedure).
A.1-2 SRO Page 4 of 19 READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit is operating at 75% 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 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
A.1-2 SRO Page 5 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
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.
EXAMINERS CUE: Provide the Performer 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 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 performers 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.
CUE: If the CHEM LAB notified to confirm value that was entered is correct, acknowledge request, then report current RCS Boron Concentrations is 750 ppm.
STANDARD: Performer ensures correct RCS Boron Concentration is entered in the Table associated with Step 1.
COMMENTS:
___ SAT
___ UNSAT
A.1-2 SRO Page 6 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 3:
Obtains: Core Burnup: _______MWD/MTU STANDARD: Performer 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: Performer 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. Performer ensures correct total power change to be 24%.
COMMENTS:
___ SAT
___ UNSAT
A.1-2 SRO Page 7 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 5:
Obtains:
Rate of Reactor Power change: ________ %/hr Number of hours to change power: ________ hr(s)
STANDARD: Performer ensures correct rate of reactor power change from task assignment to be 3 % per hour. Performer 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: Performer ensures correct final rod position from task assignment as 220 Steps. Performer 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 8 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
CAUTION Follow sign conventions explicitly.
Evaluator Note. JPM Steps 7 through 11 evaluate performers 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: Performer determines the PD1 for current power level is -1594 pcm from Table 7-18, and determines PD2 for target power level as -2088 pcm from Table 7-18, and enters the values in appropriate table locations. Performer then calculates Power Defect by subtracting algebraically PD2 from PD1. The value determined is 494 pcm.
If using Performer determines the PD1 for current power level is 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 SRO Page 9 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 8: Determines Xenon:
Xenon1: From REACTW (either current conditions or projection to initial condition). _________ pcm XE1.
Xenon2: From REACTW (projected over time period T). _______
pcm XE2.
NOTE: Xenon Values must be negative.
Performer than calculates Xenon by subtracting algebraically XE2 from XE1.
-2644.7 pcm XE1 - -2508.1 pcm XE2 = -136.6 pcm (current)
(Target)
Xenon STANDARD: Performer 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.
Performer then calculates Xenon by subtracting algebraically XE2 from XE1. The value determined is -136.6 pcm.
Performer identifies the lack of a minus sign applied to the Xenon worth and makes correction.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
A.1-2 SRO Page 10 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 9 Determines rods:
Rods 1, 2 : From NUPOP, Figure 6-24, or 25.
___________ pcm Rods1 - _________ pcm Rods2 = _______ pcm (current)
(Target)
Rods STANDARD: Performer 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 locations. Performer then calculates Rods by subtracting algebraically Rods2 from Rods1. The value determined is 150 pcm. Acceptable Range is 85 to 175 pcm.
Performer 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 11 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 10: Determines boron1:
Current RCS Boron X 1000 ÷ Inverse Boron Worth NUPOP, Figure 6-21).
______ Boron X ( 1000 ÷ _________pcm/%) = _________pcm (current)
BORON1 STANDARD: Performer enters 750 ppm for current boron concentration.
Performer determines the inverse boron worth is -159 pcm/% (accept 158 -160) from NUPOP Figure 6-21 for the current boron concentration, and enters the values in appropriate table location. Performer 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 minus -
4717 pcm.
Performer 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 12 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 11: Determines boron2:
Calculates boron2 by
______ Power Defect + _____ pcm Xenon - ____ pcm +
____________ pcm ( BORON1) = _____________ pcm BORON2 STANDARD: Performer calculates boron2 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 )
+ -136.6pcm ( Xenon)
- 150 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4510 pcm BORON2
+ 450 pcm ( Power Defect )
+ -136.6pcm ( Xenon)
- 85 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4635 pcm BORON2
+ 530 pcm ( Power Defect )
+ -136.6pcm ( Xenon)
- 175 pcm ( Rods)
+ -4717 pcm ( BORON1) = -4498 pcm BORON2 Performer must adjust value based on errors previously identified. The new calculated value must be within the stated acceptable range.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT Evaluator Note. JPM Steps 12 evaluate performers completion of the second page of Appendix E steps for Target PPM.
A.1-2 SRO Page 13 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
STEP 12: (-4510) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 717 ppm
(-4635) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 736 ppm
(-4498) pcm BORON2 X (-159_ppm/% Inverse Boron Worth ÷ 1000 pcm/%) = 715 ppm STANDARD: Performer determines Target Boron Concentration by taking BORON2 times born worth and conversion factor. The target boron concentration is calculated to be 725 ppm +/-12 ppm.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
A.1-2 SRO Page 14 of 19
- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.
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 request for independent verification, State that this Admin JPM has been completed. We will stop here.
STANDARD: Performer 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: ________
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit is operating at 75% 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 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
[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
WBN Unit 1 Boron Concentration Control Appendix E (page 1 of 3) 501-62.02 Rev. 0047 Page 55 of 62 REACTIVITY BALANCE CALCULATION 1.0 REACTIVITY BALANCE CALCULATION NOTES i
- 1)
One calculation IS reqUIred for each major change Calculation IS an approxlmalton of Final Target Boron C, Rough Interpolalton of NuPop figures IS acceptable and expected
- 2)
Dilullon or Boratton value for power change from P, % to P, % power In t,me penod T With rods moving from slep posllton R, to R, (Subscnpt convention. 1 = current p~nt, 2 = target poinl)
~
CALCULATE target boron concentrallon by performing the following:
~
Initials
.. t:l1 DATA REQUIRED DATA Where To Get Current RCS Boron C,
~
.ppm Chem Lab Core Burnup 12 MWDIMTU ICS U7ge1 Current Reactor power = P, 110 NIS Target Reactor power = P, I III ri As required for plant conditions Total Reactor Power change Z q.
6%
6 Current and final Reactor power Rate of Reactor power chanQe 3
%lhr As required for plant condibons Number of hours to chanQe power B
hr(s)
As required for plant condibons Current Rod Position l'lO steps ICS or MCR Board Final Rod Position ao steps Estimate number of rod steps reqUired to control 61 and rod withdrawal requiremenls for power chanQe
WBN Unit 1 Boron Concentration Control Appendix E (Page 2 of 3) 1.0 REACTIVIT' BALANCE CALCULATION (continued)
CAUTION 501-62.02 Rev. 0047 Paae 56 of 62 Follow sign convenhO'ls exphclily. When uSing values from Table 7*17. 7*18. or 7-19. they must be correcled as Indlcaled In below REACTIVIT' BALANCE REACTMTV BALANCE Parameter Where To Get Cakulation Value _
6f' POWER PowerOefect 12 FromNUPOP, FtgureS*18, 19.or20 DEFECT (or from Table 7*17, 7-18, or 7.19
-1S'~4 pcm PO, - -l088 pcm PD, -
4'14 pcm Must muHlply value from these tables by (-' ) to (current)
(Target)
,lp POWER maintain sign convenbOrl The figures are DEFECT correct as shown)
'1' XENON Xenol\\ From REACTW (either current coodltlons or prOjectIon NOTE Xenon values must be neg8~ve to Inill" condition).
- z1044.1 oem XE, - -2508.1 oem XE,-
Xenollj From REACM (prOjettJon over time period T).
1~1D.1o pcm NOTE Xenon values must be negative (current)
(Target) 6f' XENON
.. w RODS
-RodS12 From NUPo"P: --Figure 6..24 or 11~
t~
114 from Figure 6-25 oem Rods t -
oem Rods2
- pcm (current)
(Target) c~l RODS I' BORON Curren ReS Boron X (1000 + Inverse Boton Worth NUPOP,
~
Boron X (1000 +.:!!!L.PPmI%,lp)-
-4('S~ pcm Flgure6-21)
(curroOt)
I p BORON 4~4 pcm.lpPOWERDEFECT + 13~. " pcm.\\jlXENON -
11.0 oem \\jl RODS + - 41058 pcm (I' BORON,)-
-1: I~] pcm I" BORON contmued on next page
1.0 WBN Unil1 Oale, __ _
Boron Concentration Control Appendix E (Page 3 of 3)
REACTIVITY BALANCE CALCULATION (conlinued)
TARGET PPM 501-62.02 Rev. 0047 Page 57 of 62 INITIALS to 41\\? 7 oem p Boron,l X t -I ~ \\
ppm'%;p Inverse Boron WO<1h
- 1000 pcm'%tlpl =
I (.74 ppm
________ -"IN"U"-P"'O'-P.'-F,,'g"'ur"-e,,6-:0.21,,1__
. Target Boron C, NOTE IV IS NOT requlled 'f append,x 's pertormed by an SRO 10 venfy dala prov,ded by Rx Eng
~!~ ENSURE,ndependenlly verified by SRO IV J
WATTS BAR NUCLEAR PLANT A.2-RO A.2-RO CALCULATE QPTR USING 1-SI-0-21 Page 1 of 18
EVALUATION SHEET A.2-RO Page 2 of 18 Task: CALCULATE QPTR USING 1-SI-0-21 Alternate Path:
N/A Facility JPM #:
3-0T-J PMADA. 2-1 KIA Rating(s):
2.1.12
[2.9/4.0]
Task Standard:
Quadrant Power Tilt Ratio has been determined per 1-SI-0-21 Section 6.1 and. 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
Tools/Equipment/Procedures Needed:
Applicant Data Sheet Latest revision of 1-51-0-21 Attached NOB Sheets A-2(all four PR detector channels)
Calculator A.2-RO Page 3 of 18 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 Applicant Data Sheet along with the Applicant's Cue Sheet.
READ TO OPERATOR A.2-RO Page 4 of 18 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 is operating at 100% power
- 2. AFD Monitor Alarm and QPTR alarms are out of service due to card problem in the annunciator system.
- 3. 1-SI-0-21 "Excore QPTR & Axial Flux Difference SI is required 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.
e 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. M&TE will not be utilized for data measurements.
- 2. Report the results to the Unit Supervisor when 1-SI-0-21, Section 6.1 and have been completed~
A.2-RO Page 5 of 18 START TIME: __
STEP 1:
Obtain a copy of the instruction.
STANDARD:
A copy of 1-51-0-21 has been obtained.
EXAMINER'S CUE: After the performer identified correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
NOTE TO EVALUATOR: The following steps are from Section 6.1 of 1-SI-0-21 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.
STAN DARD:
Performer goes to attachment 1 and commences performance of attachment 1.
COMMENTS:
SAT UNSAT
_SAT
_UNSAT
STEP 3: [Step 2] IF the process Computer is available, THEN PRINT the Tilting Factors Report ANDIOR PERFORM the QPTR calculations using Attachment 1.
STANDARD:
Performer goes to attachment 1 and commences performance of attachment 1.
COMMENTS:
A.2-RO e 6 of 18 SAT UNSAT
A.2-RO Page 7 of 18
.NOTE TO EVALUATOR: The following steps are from Attachment 1 of 1*
SI-0-21 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 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 '8' 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.
B.
Cal Due Date:
SAT STANDARD: Performer determine step in N/A based on initial conditions for task performance and proceeds to the next step.
UNSAT COMMENTS:
STEP 4: [Step 2] ENSURE require M& TE is within its current calibration.
SAT STANDARD: Performer determines step is N/A based on initial conditions for task performance and proceeds to the next step.
UNSAT COMMENTS:
A.2-RO Page 8 of 18 An inadvertent reactor trip may be prevented by ensuring that no power 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.
STEP 4: [Step 3] DETERMINE the microamps for each upper and lower excore detector on each NIS power range drawer B, AND RECORD below:
NIS Channel STANDARD: Performer obtains the detector current microamp readings from the handout given during task assignment and enters the appropriate data into Attachment 1 step 3.
SAT NOTE TO EVALUATOR: Values above in ( ) are detector currents from handout.
COMMENTS:
UNSAT
A.2-RO Page 9 of 18 NOTE: Rt and Rb (detector calibration data) changes periodically throughout the cycle.
Current values are on NOB Sheet NIS Calibration Data.
TO EVALUATOR: The NOB Sheets attached to this JPM are are to be given to the Performer when the Performer refers to the NOB. The data sheets attached are the basis for the calculations in the JPM>
STEP 5: [Step 4] OBTAIN and RECORD current values of Rt and Rb (volts/microamps ).
NIS Channel STANDARD: Performer 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.
SAT UNSAT
[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 NIS Channel Vt Calib. Output Vb Calib. Output A.2-RO Page 10 of 18 STANDARD: Performer calculates the calibrated output voltages [Step 3] by SAT multiplying the respective detector's current reading times resistance values [step 4] and records the results in appropriate blocks on Attachment 1 Step 5.
COMMENTS:
STEP 7: [Step 6] CALCULATE average calibrated output voltage for the upper and lower detectors.
UPPER LOWER AVERAGE (13.926+16.158+13.911 +
(14.719+17.339+14.295+
15.57
=14.893 14.71
= 15.268 STANDARD: Performer 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:
UNSAT SAT UNSAT
A.2-RO Page 11 of 18 STEP 8: [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.
NIS Channel N-41A N-42A N-43A N-44A A. QPTRt = Vt + Avg Vt
- 8. QPTRb = Vb x Avg Vb UPPER DETECTOR UI-" I Ht Value (13.926/14.893)= 0.935 (16.158/14.893) 1.085 (13.911/14.893) 0.934 (15.575/14.893) 1.046 LOWER DETECTOR QPTRb Value (14.719/15.268)= 0.964 (17.339/15.268)= 1.136 (14.295/15.268)= 0.936 (14.718/15.268)= 0.964 STANDARD: Performer 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. Performer returns to Section 6.1 Step 7.
IMMENTS' NOTE TO EVALUATOR The following steps are from Section 6.1 of 1-51-0-21..
STEP 9: [Step 2] REVIEW the Upper (A) and Lower (8) QPTR values.
STANDARD: Performer reviews QPTR values from Attachment 1 Step 7.
COMMENTS:
A.2-RO 12 of 18 STEP 10: [Step 3] CHECK (~) Acceptance Criteria.
ACCEPTANCE CRITERIA: All operable excore channels (upper and lower) indicate a QPTR ~ 1.02.
SAT YES NO STANDARD: Performer determines that N-42 Upper Detector, N44 Upper Detector, and N-42A Lower Detectors exceed 1.02 QPTR.
Performer then checks NO statement.
COMMENTS:
STEP 11:
Inform the Unit Supervisor that Attachment 1 and Section 6.1 of 1-SI-0-21 has been completed and the results of the QPTR.
STANDARD: Performer informs the Unit Supervisor of the completion of and Section 6.1 of 1-SI-0-21 and reports that acceptance criteria have not been satisfied. QPTR for N-42 Upper Detector is 1.114, N-44 Upper detector is 1.037 and N-42 Lower Detector is 1.131, ALL exceeding the QPTR limit of 1.02.
EXAMINER'S CUE: Acknowledge report as Unit Supervisor, then state We will stop here.
COMMENTS:
TIME STOP: __
UNSAT SAT UNSAT
APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. The unit is operating at 100% power
- 2. AFD Monitor Alarm and QPTR alarms are out of service due to 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 <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. M&TE will not be utilized for data measurements.
- 2. Report the results to the Unit Supervisor when 1-SI-0-21, Section 6.1 and have been completed.
APPLICANT DATA SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
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
~;
(rJBN 1
N-41 POWER QREF = 100%
PRESTP,RTU P ALIGNM. []
NUCLEAR OPERATING BOOK (NOB)
NIS CALIBRATION DATA NOB Sheet A-2 Revision 90 Page 1 of 5 RANGE DETECTOR CALIBRATION DATA RTP 1-S1-92-3
/
3/3/09 Date INCORE-EXCORE X Cf:iL.
- SINGLE POINT ALIGN1>1.
r-i L-l NC305 LOW POWER TRIP NC306 HIGH POWER TRIP 0 -
20% FULL POWER 0 -
10 Vde 0 - 120 FULL POWER
('-cJ -
]0 Vde 2 c "
..J,<"
TRIP 2.083 Vdc 105 TRIP 8.750 Vde 231>
HESET 1.917 Vdc 1031';
RESET
- 8. :)f3 3 Vdc TOP (A) DETECTOR BOTTOM (B) DETECTOR N== 17.503
!VOLT R, ""
0.03774 V/f.lA RB ""
0.03833 V/f.lp.,
b r zz
-1.433 f.lAI ~D.+
btl ""
-1.57
~1}\\.1 \\\\ D. 4>
f'== 1.8 c:r
- Ilt, 220.79
~(A H
217.43
=
T. p =
~l}:l.
NI301 DWR B TOP (A) DETECTOR NI302 DWR B BOTTOM (B) DETECTOR F'(JLL POVIER Desired Desired FULL POWER Desired Desired (mVdc)
( I--li\\)
(mVde)
(pAl 0
0 0
0 0
0 30%
66.24 66.24 30'6 65.23 6~). 23 60%
132.47 132.47 60 130.46 130.46 90%
1.98.71 198.71 90'l!
195.69 195.69 120%
264.95 264.9:,
120
~~60. 92 260.92 DESIRED D. FLUX TOP (A)
DESIRED 6 Fl,UX BOTTOM (B)
I-NI-41C DETECTOR I-NI-He DETECTOR (mVde)
(mVdc)
+30.0 263.78
+30.0 170.33 0.0 220.79 0.0 21~ n
-30,0 177,80
-30.0 264
- c. './
- J....;
NOTE:
N
=:.:
Plant Comouter AFD Calibration Factor :::: K0554 R
==
NIS Calibration (i. e. Conversion ) Factors b
=:;
Slopes of Current versus !.\\<jl 1#
Full Power Calibration Currents-at L\\<jl = o. 0 ~\\
I'
\\ 1., e. Intercepts)
G Eagle-21 Seal Flux Calib
'1; ItmN 1
N-42 POWER QREF= 100%
PRESTARTUP ALIGNM. 0 NUCLEAR OPERATING BOOK (NOB)
NIS CALIBRATION DATA NOB Sheet A-2 Revision 89 Page 2 of 5 RANGE DETECTOR CALIBRATION DATA RTP 1-S1-92-3 I
3/3/09 Date TNCORE-EXCORE X CAlJ..
- SINGLE POINT P,LIGNivl
- I..J NC305 LOW POWER TRIP NC306 HIGH POWER TRIP 0 - 120 'b FULL POWER 0 - 10 Vdc 0 -
1201; FULL POWE:R 0 -
lO Vdc 25'1; TRIP 2.083 Vdc 105 TEIP 8.750 Vdc 23%
RESET 1.917 Vdc 103%
RESET 8.583 Vdc TOP (A) DETECTOR BOTTOM (B) DETECTOR N = :6.957
!VOLT
£.\\1' 0.04439 V /~tA Re 0.04492 V/~A b~
+1.333
~AI %L\\~
bE!,
-1.309
~IA/t,6$
G 1.8 I",:, =
187.72
~A Tn
=
185.52
~IA
- 1. 3 NI301 DltlR B TOP (A) DETECTOR NI302 DWR B BOTTOM (B) DETECTOR 2"ULL POltlER Desired Desired FOLL ?Oi'iER Desired Desired (mVdc)
(~)
(mVdc)
(
~l.n. )
0'5 0
0 0
0 0
30%
56.32 56.32 30"1; 55.66
- )5.66 60~,
112.63 112.63 60'6 111*31 111.31 90%
168.95 168.95 90 166.97 166.97 120%
225.26 225.26 120'~
222.62 222.62 DESIRED 6-FLUX TOP (A)
DESIRED
~ FLUX BOTTOM (B) 1-NI-42C DETECTOR I-NI-42C DETECTOR (mVdc)
(mVdc) 130.0 227.71 130.0 14 6.25 0.0 187.72 0.0 185. :)2
-30.0 147.73
-30.0 224. -)9 NOTE:
N
=
Plant Computer AFD Calibration Factor = K0552 R
=
NIS Calibration (i.e. Conversion ) Factors b
Slopes of Current versus L\\<jJ 1#
==
Full Power Calibration Currents at L\\<jJ '" 0.0%
(i.e. Intercepts)
/~
u
=:
Eagle-21 Seal Flux Ca1ib
vmN NUCLEAR OPEPATING NOB Sheet A-2 1
BOOK Revision 90 (NOB)
Page 3 of 5 NIS CALIBRATION DATA N-43 POWER RANGE DETECTOR CALIBRATION DATA QREF= 100% RTP 1-SI-92-3
/
3/3/09 Date E'RESTJ\\RTUP ALIGNM. 0 INCORE-E:XCORE X G\\L.
- SINGLE POINT ALIGNM. 0 NC305 LOW POWER TRIP NC306 HIGH POWER TRIP 0 -
120% FULL POWER 0 -
10 Vdc 0 -
120% FULL POWER 0 - 10 Vdc
- 251, TRIP 2.083 Vde 105%
TRIP 8.750 Vdc 23%
RESET 1.917 Vdc 103 RESET 8.583 Vdc TOP (A) DETECTOR BOTTOM (B) DETECTOR N '" 16.968
/VOLT Rr ""
0.03770 VillA REJ
=
0.03713 V/pA b, =
+1.539 J.l}I./%tlq, btl --
-1.613 J.lA/%tlljl G== 1.8 I~T.'"
221.06 pA In
=
224.46 J.lA B
NIJOl DWR B TOP (A) DETECTOR NI302 DWR B BOTTOM (B) DETECTOR FULL POWEB.
Desired Desired
~ FULL POWER Desired Desired (mVdc)
(flA)
(mVdc)
( ~tA) 09-c' 0
0 0
0 r\\
\\J 30%
66.32 66.32 30%
67.34 67.34 60~;
132.64 132.64 60~)
134.68 134.68 90'i; 198.95 198.95 90%
202.01 202.01
- 1209, 265.27 265.27 120'1\\
269.35 269.35 DESIRED tl FLUX TOP (A)
DESIRED 9, c Ll FLUX BOTTOM (B)
I-NI-43C DETECTOR I-NI-43C DETECTOR (rnVdc)
(mVdc)
+30.0 267.23 uO.O 17 6.07 0.0 221. 06 (1. 0 224.46
-30.0 174.89
-30.0 272.8:)
NOTE:
N Plant Computer AFD Calibration Factor== 1<.0551 R
NIS Calibration (i.e. Conversion ) Factors b
~-
Slopes of Current versus L\\<j>
1#
=
Full Power Calibration Currents at ~<j> = 0.0%
(i. e. Intercepts)
G
=
Eagle-2l Scal Flux Calib
vJBN 1
NUCLEAR OPERATING BOOK (NOB)
NIS CALIBRATION DATA NOB Sheet A-2 Revision 88 Page 4 of 5 N-44 POWER RANGE DETECTOR CALIBRATION DATA QREi' = 100% RTP 1-51-92-3
/
3/3/09 Date PRESTARTUP ALIGNM. 0 INCORE-EXCORE X CAL.*
SINGLE POINT ALIGNM. 0 NC305 LOW POWER TRIP NC306 HIGH POWER TRIP o -
120% FULL POWER o -
10 Vde o -
120% FULL POWER o - 10 Vde TRIP 2.083 Vde 105%
TRIP
- 8. 7 SO VClc 23%
RESET 1.917 Vde 103%
RESET
- 8. ::;83 Vde TOP (A) DETECTOR BOTTOM (B) DETECTOR N "" 17.54
!VOLT Rr = 0.04198 VillA RB =
0.03813 V / Illl.
br
=
+ 1. 347 j.tA/ %L\\cl>
DB =
-1.:)07
~lP../ :~Llcl>
1\\, =
218.57
~ll>.
G = 1 ~ 8 1\\,=
198.53 IlA NIJOI Dvm B TOP CA) DETECTOR NI302 DvJR B BOTTOM (B) DETECTOR (8
FULL POWER Desired Desired FULL pm'JER Desired Desired 0 0 l5 30%
60%
90%
120'1; (mVdc) a 59.56 119.12 178.68 238.24
( !lA) o 59.56 119.12 178.68 238.24
{rnVdc)
(pAl o
o CJ 30'1; 65.57
- 65. '57 l31.14 131.14 90'/;
196.71 196.71 120%
262.28 262.28 DESIHEO
'1; Ll F.LOX 1..,NI-44C TOP (A)
DETECTOR (mVde)
DESIRED
,,\\ fLUX I-NI-44C BOTTOM (B)
DETECTOR (mVde)
+30.0t30.0 73.36 238.94
.r-----------~~--------~~--------~~----------------------~------,----~
0.0 19fL53 0.0 2.,tl.S-;
NOTE:
N R
b 1#
G
-30.0 1~)8.12
-30.0 263.78
=
Plant Computer AFD Calibration Factor = K0553 NIS Calibration (i.e. Conversion) Factors Slopes of Current versus A.
Full Power Calibration Currents at~.
0.0%
(i.e. Intercepts)
Eagle-2l Scal Flux Calib
Rev. 0 Page 1 of 12 WATTS BAR NUCLEAR PLANT A.2-SRO A.2-SRO Review and Approve a Disable Alarm Checklist, per OPDP-4
Rev. 0 Page 2 of 12 WATTS BAR NUCLEAR PLANT A.2-SRO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Review and Approve a Disable Alarm Checklist, per OPDP-4 Alternate Path:
N/A Facility JPM #: New K/A Rating(s): G2.2.43 [3.0/3.3]
Task Standard: Performer identifies that the OPDP-4-1 Disabled Alarm Checklist is NOT filled out correctly for Annunciator 85-F. Performer 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
===============================================================
Performer:
Time Start: ________
NAME SSN Time Finish: ________
Performance Rating: SAT ____ UNSAT ____
Performance Time ___
Examiner: _____________________________
_____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS
Rev. 0 A.2-SRO Page 3 of 12 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 4 of 12 READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. A plant shutdown is in progress.
- 2. Mode 3 has just been entered.
- 3. 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.
- 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.
Rev. 0 A.2-SRO Page 5 of 12 START TIME: _______
STEP 1:
Obtain a copy of the completed instruction.
STANDARD: A copy of OPDP-4-1 Attachment 1, Disabled Alarm Checklist.
EXAMINERS CUE: Provide the Performer a copy of the completed instruction.
COMMENTS:
___ SAT
___ UNSAT STEP 2:
DISABLED ALARM CHECKLIST block reviewed STANDARD: Performer determines that the incorrect Panel Number is entered in the block.
COMMENTS:
___ SAT
___ UNSAT STEP 3:
ALARM LOCATION block is reviewed.
STANDARD: Performer determines incorrect information is entered in the Node/Mux/Pt or SER COMMENTS:
___ SAT
___ UNSAT STEP 4:
Reviews entry into 1. Description of the alarm that is being defeated.
STANDARD:.Performer determines that an adequate description of the alarm function has been entered.
COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.2-SRO Page 6 of 12 STEP 4:
Reviews entry into 2. Reason for disabling the alarm that is being defeated.
STANDARD:.Performer determines that an inaccurate description of the reason for disabling the alarm is entered. The data entered should describe that the alarm has been deemed a nuisance.
COMMENTS:
___ SAT
___ UNSAT STEP 6:
Reviews entry into 3. Description of how alarm will be disabled.
STANDARD: Performer determines that the description is adequate.
COMMENTS:
___ SAT
___ UNSAT STEP 7:
Reviews to 4. Determine if a 10CFR50.59 Review is required.
STANDARD: Performer 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 to 5. Determine if a 10CFR50.59 Review is required prior to exceeding 90 days.
STANDARD: Performer determines that a 10CFR50.59 review is not required, since the alarm is NOT being for a maintenance evolution.
COMMENTS:
___ SAT
___ UNSAT
Rev. 0 A.2-SRO Page 7 of 12 STEP 9:
Reviews to 6. Determine if a Technical Evaluation (Form OPDP-4-5) is required.
STANDARD: Performer determines that a 10CFR50.59 review is a Technical Evaluation (Form OPDP-4-5) is required.
COMMENTS:
Critical Step
___ SAT
___ UNSAT STEP 8:
Performs Step 7, and determines that the form cannot be approved as presented.
STANDARD: Performer 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: ________
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. A plant shutdown is in progress.
- 2. Mode 3 has just been entered.
- 3. 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.
- 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.
NPG Standard Department Procedure Annunciator Disablement (Page 1 of 2)
OPDP-4 Rev. 0004 Page 15 of 21 OPDP-4 Disabled Alann Checklist DISABLED AlARM CHECKLIST DISABLED AlARM CHECKLIST ALARM LOCATION "e
W&~
UM 1
BS-F WIndow Numbef
.1-Y.d 4 1>
1"1\\G.t"'C'~'56Or T'2AI'" - A Panel Number
eiMuxlPt or SERlSensor 1
Describe the function of this alarm (II! 9 proVide indication of 6bnomlal optIrahon equlPlTIent failure indication Of? automatic tnp. Indlcatl~lof loss 01ntfl.),IJ r ' d<~'
ion"
'4.,H<- of +I.
m
{c..s.sor 2
Describe reason for dlS4bllng alarmlinput (Ind ude procedure or WO number, I' appNcable)
~ot r""i,cc.c!.1 fl:r 60-4>.
3 Des~
thiS alarm/alann Input will be disabled t>
aA-4'tv, 03;\\'-'" ~(1)u...ss.,.,... [ f1'£
){::JQ Q~ - £"",51:1 -000 Y6 No 4
Is a 10CFRSO 59 Review reqUIred pnor to disabling alarm? (ReIer to Appendix A)
U l!l 5,
Is 8 10CFRSO 59 Review required pnor to exceedlflg 90 days (alarm disabled for 0
~
maintenance)?
6 Is a T echnic:al Evaluation (Form OPDP-4-5) required prior to disabling alarm? (Refer to 0
)!!I.
Appendix A) J-t,.
l:<<k.~
Prepared By 6-!/~
--- ~ ~
7 Aprr"".. 1 fN.. nn" n n mnr n;c.. hI....... nt Yes No NlA If reqUired, IS 10CFRSO S9 Review attached?
0 0
0 If reqUired, IS TechnICal Evaluabon ( Form OPDP-4-5) attaChed?
0 0
0 If a Technical evaluation was pelfonned, IS CompenS61ory MonotOIl" 9 leqUlfed and acceptable?
0 0
0 Ase steps to enable the alarm prOVided In tt1e controDmg WQfk document?
0 0
0 Signature (SM/US)
Prmt Name Date ThiS alarm must be returned to service by N/A if nOl: an lCO Date Time TVA 40745102 2009]
Page 1 0/2 OPDP-+I 102 02 20091
WATTS BAR NUCLEAR PLANT A.3-SRO Page 1 of 20 A.3-SRO Authorize a Radioactive Liquid Release
Page 2 of 20 WATTS BAR NUCLEAR PLANT A.3-SRO ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Authorize a Radioactive Liquid Release Alternate Path:
N/A Facility JPM #: New KIA Rating(s): G2.3.6
[2.0/3.8]
Task Standard: Performer 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 0.101 VOC limit established in 0-001-90-1, Section 6.1, Step 15. Performer DOES NOT sign package as approved.
Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator __ In-Plant __
Perform X
Simulate __
References:
. 0-001-90-1 Liquid Radwaste Tank Release, Rev. 31 Task Number: SRO-077-S01-77-001 APPLICABLE FOR: SRO 10CFR55.45: 9 Validation Time: 15 min.
Time Critical: No Performer:
Time Start:
NAME SSN Time Finish: ---
Performance Rating: SAT UNSAT Performance Time Examiner: ------------ ------____
--~/------
NAME SIGNATURE DATE COMMENTS
Tools/Equipment/Procedures Needed:
A.3-SRO Page 3 of 20 Marked up copy of 0-001-90-1 Liquid Radwaste Tank Release, Rev. 31.
Batch Liquid Permit, Dated 3-18-09 Monitor Tank Sample Report DKB600
READ TO OPERATOR DIRECTION TO TRAINEE:
A.3-SRO Page 4 of 20 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 0-001-90-1 Liquid Radwaste Tank Release Package for the release.
- 3. You are the Unit SRO.
- 4. The DATES on the documentation are CORRECT.
INITIATING CUES:
e Review the 0-001-90-1 package for release approval. Note any and all discrepancies found during your review.
START TIME: __
STEP 1:
Obtain a copy of the completed instruction.
STANDARD:
Marked up copy of the Release Package including 0-001-90-1 "Liquid Radwaste Tank Release" is acquired by the performer.
EXAMINER'S CUE: Provide the Performer a copy of the completed instruction.
COMMENTS:
STEP 2:
Performer reviews package for correct tank to be released.
STANDARD: Error - The Batch Liquid Effluent Permit is for the Cask Decon Collector Tank, NOT the Monitor Tank as described in the 0-001-90-1 Appendix A Pre-Release Permit Data COMMENTS:
STEP 3:
Performer reviews package to verify radioanalysis values are less than the limits provided on the Batch Liquid Effluent Permit.
STANDARD: Performer determines that all values are less than limits (III.
RADIOANAL YSIS - LIQUID).
COMMENTS:
A.3-SRO Page 5 of 20 SAT UNSAT Critical Ste~
A.3-SRO Page 6 of 20 STEP 4:
Performer reviews package to verify the EXP. RESPONSE SAT VALUE is less than the O-RE-90-122 SETPOINT.
STANDARD:
Performer 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:
Performer reviews package to verify the volume, flow, and SAT dilution values are within limits.
STANDARD: Performer determines the volume, flow, and dilution values are within limits given in V. AUTHORIZATION section of the Batch UNSAT Liquid Effluent Permit.
COMMENTS:
Critical Ste~
STEP 6:
Performer reviews package verify the radiation monitor voltage is within limits.
SAT STANDARD: Error - 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 UNSAT Liquid Effluent Permit.
COMMENTS:
STEP 7:
COMMENTS:
STEP 8:
Performer reviews 0-001-90-1 for correct step sign-off.
Error - The O-RE-90-122 Setpoint voltage of 5.84 Vdc recorded on 0-001-90-1, Appendix A is more than 0.101 Vdc higher than the setpoint of 5.262 Vdc provided in the Batch Liquid Effluent Permit. Step 15 of Section 6.1 should have been Nt A, and Steps 16 and 17 should have been performed.
Performer determines that the package cannot be approved as written EVALUATOR CUE: When the two errors have been identified and the performer addresses the fact that the package cannot be approved with these errors state "We will stop here".
STANDARD: Performer states that the package cannot be signed as approved until after the errors have been corrected.
TIME STOP: __
A.3-SRO e 7 of 20 SAT UNSAT Critical Step SAT UNSAT
PERFORMER CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. A release of the Monitor Tank is scheduled for this shift.
- 2. Chemistry has prepared a 0-001-90-1 Liquid Radwaste Tank Release Package for the release.
- 3. You are the Unit SRO.
INITIATING CUES:
Review the 0-001-90-1 package for release approval. Note any and all discrepancies found during your review.
SURVEILLANCE TASK SHEET (STS)
Work Order NIA Page ___ of ---
SIKey N/A Procedure No.
0*001*90-1 Title LRW Release Perf. Section ChemistryfCEM)
NIA NlA NIA Test Reason Conditional Performance Aulhorization to Begin: SRO Dale Time Data Sheets NlA Due NlA
~l'~(\\(1 C'~!C:.c_~
Extension NlA Max. Extension NlA SIs Dale Time Frequency Conditional EQ NIA ASMEXI NIA APP Mode 1234567 Completion Date Time Performance Mode 1234567 Operational N/A Condition Dry Cask Storage UYes xNo Subsequent NIA Reviews Instruction Conditional Performance Test Performer's Was this a complete or partial Name
~
~'-ture Initial SectiOn performance?
~~' \\1 "T~ 11.,<' "!oJ V
.L
.s-.
iA\\
c..}.k'"
(Explain "Partial" In Remarks)
Complete 0 Partial 0
~
Were aU Tech Spe<iTech ReqJ ISFSI CoC/ODCMlFire Protecllon Req, acceptance criteria Yes No NIA 0 satisfied?
0 0
Were all other acceptance - - - - - - - - - - - - - - - - - - - - - - - -
criteria satisfied?
Yes No N/A 0
~----_Q_---------
If all Tech Spec/fech Req./ISFSI Coc/ODCM/Fire Protection Req.
were not satisfied, was an LCOI TRIODCMlOR aellon required?
(Explain in Remarks)
Yes No NIA 0
'Aiert -Scheduilng-Requlrec:f - - - - - -~s- - - -g ----NIA n-
____.. _________________ ~ ____ JJ_.. _______
Test Director/Lead Performer Date Acceptance Criteria Review: SRO Dale Time (ASME XI Sis require review within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />)
Independenl Reviewer Dale ANU (If required)
Date Copy of STS sent 10 Scheduling I
Remark:
Inillals Date Section No.
Our.
Men Hrs
Tennessee Valley Authority Watts Bar Nuclear Plant I. REQUEST X NORMAL UNPLANNED BATCH LIQUID EFFLUENT PERMIT RELEASE POINT CASK DECON COLLECTOR TANK 90034.010.00?L Unit #
1 Allocation 100.%
ESTIMATED START:
18-mar-2009 16:00:00 RELEASE VOLUME (ESTIM.)
ESTIMATED STOP:
1.5190E+04 GAL lS-mar-2009 17:48:30 DILUTION FLOW AVAIL.
DISCHARGE POINT 2.0000E+04 GPM COOLING TOWER BLOWDOWN II. SAMPLE IDENTIFICATION NUMBER COLLECTION DATE/TIME ANALYSIS DATE/TIME 71 06-mar-2009 02:3S:00 06-mar-2009 02:51:23 CONFIGURATION FILE NAME: CAS_SAM:090306_0434_C.CNF III. RADlOANALYSIS -
LIQUID ECL FRACTION SUM 0.67
< 10.00 DIS. GAS SUM O.OOE+OOuCi/ml < 2.0E-04 IV. RADIATION MONITOR(S)
CUM. TOT-BODY DOSE(Q) 3.S8E-03 mrem <
1.50 CUM. TOT-BODY DOSE (A) 3.88E-03 mrem <
3.00 CUM. ORGAN DOSE (Q) 3.89E-03 mrem <
5.00 CUM. ORGAN DOSE (A) 3.89E-03 mrem < 10.00 NUMBER 0-RE-90-122 SETPOINT 1.43E+04 CPM O.OOE+OO CPM EFFECTIVE GAIN 2.27E-09 uCi/ml/CPM O.OOE+OO uCi/ml/CPM EXP. RESPONSE 7.1?E+03 CPM O.OOE+OO CPM V. AUTHORIZATION MAX. VOLUME 1.5190E+04 GAL MAX. WASTE FLOW
?6896E+02 GPM MIN. DILUTION FLOW 2.0000E+04 GPM analyzed and is in compliance with is authorized for the volume and Review and Approval (Unit SRO) 7 Date Time The voltage for radiation monitor 0-RE-90-122 should be set to:
5.262 (Volts)
Tennessee Valley Authority Watts Bar Nuclear Plant Liquid Radioactive Waste Release Permit Pre-Release Supplementary Data PART I: PRE-RELEASE DATA RELEASE POINT DISCHARGE POINT Dilution Stream 10): CASK DECON COLLECTOR TANK 1): COOLING TOWER BLOWDOWN 1): ERCW Permit Issued: 17-mar-2009 09:59:10 Waste Tank Volume:
1.5190E+04 GAL Recirc. Start:
Sample After:
RadMonitor: (1
) 0-RE-90-122 Rad Monitor Bckgrnd:
6.2100E+03 CPM Release Type: Batch Recirc. Rate:
Min Recirc Time:
Agitator Used:
page 1 of 2
90034.010.007.L O.OOOOE+OO GPM o MIN Estim. Dilution Flow:
2.0000E+04 GPM Estim. Waste Flow: 1.4000E+02 GPM Estim. Dilution Vol.:
2.1700E+06 GAL Estim. Waste Vol.: 1.5190E+04 GAL Dilution Factor (Act): 1.4386E+02 Estim. Duration:
108.50 MIN Estim. Release Start:
18-mar-2009 16:00:00 Estim. Release End:
18-mar-2009 17:48:30 PART II: PRE-RELEASE CALCULATIONS Sample Entry # :
71 Sample time: 06-mar-2009 02:38:00 Sampled by: DJH Configuration File Name: CAS_SAM:090306_0434_C.CNF Total Waste Activity:
5.5036E+00 Curies Total Waste Cone:
9.5715E-02 uCi/ml Total Waste Cone/ECL:
9.6033E+01 Total Monit Cone:
2.1851E-06 uCi/ml Dilution Allocation:
7.0000E-Ol Concurrent Releases:
1 Min Dilution Flow:
3.6413E+03 GPM Max Waste Flow:
7.6896E+02 GPM Dilution Strm Sample:
0 Dilution Cone/ECL: 6.6756E-Ol Max.Monitor Setpoint:
4.3702E-06 uCi/ml Flag:
1.4343E+04 CPM Rqrd Dilution Fet: 1.9207E+01 Flags: C-Release CUries> Loeal Limit R-Expeeted Response > Max Setpoint A-Setpoint Adjustment Factor < 1.0 F-Waste Flow > Max Allowable F-Dilution Flow < Min Allowable
Tennessee valley Authority Watts Bar Nuclear Plant Liquid Radioactive Waste Release Permit Pre-Release supplementary Data ISOTOPIC IDENTIFICATION - Unit 1
Pre-Dilut.: Pre-Dilut.: Pre-Dilut.:
Post
- Measured
- Measured
- Measured
- Dilution Isotope uCi/ml
- Cone/ECL
- Cone/Total:
uCi/ml CO-60 P:
7.31E-07 2.44E-Ol 7.64E-06 S.OSE-09 FE-55 0:
2.27E-06 2.27E-02 2.37E-05 I.SBE-OS H-3' 0:
9.S7E-02 9.57E+Ol 1.00E+OO 6.6SE-04 SB-12S P:
1.45E-06 4.SSE-02
- 1. 52E-OS I.OIE-OS SR-B9 0:
6.23E-OB 7.79E-03 6.51E-07 4.33E-IO page 2 of 2
90034.010.007.L Post
- Dilution
- Cone/ECL 1.69E-03 1.5BE-04 6.6SE-Ol 3.37E-04 5.41E-OS Estimated Curies Released 4.20E-OS 1.31E-04 5.S0E+OO 8.36E-OS 3.SSE-06 Totals:
9.S7E-02:
9.60E+OI:
6.6SE-04:
6.6SE-OI:
5.50E+OO
17-MAR-2009 09:56:40.68 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT 0-ODI-90-1 MONITOR TANK SAMPLE TITLE FILE IDENT DKB600: [TVA.SAMPLE.CHEM.NEW] 090306 0434_C.CNFi1 SAMPLE ID SAMPLE TIME SAMPLE TYPE 090306 0434 C 6-MAR-2009 02:38:
- 1L LIQ. MARIN.
- OPERATOR
- SAMPLE GEOMETRY
- SHELF HEIGHT
- EFFICIENCY FILE
- SAMPLE QUANTITY DJHUTCHISON LM1K o
LM1KO 1.00000E+03 ML ACQ DATE & TIME PRESET LIVE TIME ELASPED REAL TIME ELAPSED LIVE TIME 6-MAR-2009 02:51:
o 00:15:00 o 00:15:00 o 00:15:00
- DEADTIME (%)
- SENSITIVITY
- GAUSS IAN SEN
- NBR ITERATIONS 0.0%
4.00000 10.00000 10 DETECTOR EFFIC CAL DATE DCAL DATE & TIME KEV/CHAN OFFSET Q COEFFICIENT PEAK START CHAN DET #4, GSS-3850 14-APR-2003 08:32 5-MAR-2009 20:47:
5.00794E-01
-1.48231E-01 keV
-3.28672E-07 140
- LIBRARY
- EFFIC CERT DATE
- ENERGY TOLER
- HALF LIFE RATIO
- ABUNDANCE LIMIT
- CORRECTION FACTOR
- PEAK END CHAN LIQUID 14-APR-2003 08:32 1.25 8.00000 80.0%
1.00000E+00 4096 ANALYSES: PEAK V16.9 NID V3.3 MINACT V2.8 WTMEAN/KEY Vl.8 COUNTED ON COLLECTED BY COUNTED BY REVIEWED BY COMMENTS Post-NID Peak Search Report It Energy Area Bkgnd FWHM Channel Left Pw %Err Fit Nuclides 0
81.53 30 59 1.00 163.11 158 9 48.9 XE-133 0
176.59 90 105 1.04 353.00 348 11 24.4 SB-125 0
381.29 19 26 0.67 762.05 757 9 54.1 SB-125 0
428.01 205 63
- 1. 35 855.44 847 16 11.2 SB-125 0
463.48 78 22
- 1. 34 926.35 920 11 16.2 SB-125 0
510.59 74 20 3.35 1020.54 1013 16 17.9 ANNIL 0
600.56 110 18 1.81 1200.45 1192 13 12.3 SB-125 0
636.07 70 7
1.46 1271.49 1265 14 14.4 SB-125 0
810.82 180 22
- 1. 79 1621. 08 1613 14 9.2 CO-58 0
1173.03 147 3
2.01 2346.25 2338 14 8.7 CO-60 0
1332.19 114 2
2.22 2665.12 2659 11 9.8 CO-60
Nuclide Line Activity Report Sample ID : 090306 0434 C Acquisition date Page:
- 2 6-MAR-:2009 02:51:23 Nuclide Type: AP Uncorrected Decay Corr I-Sigma Nuclide Energy tAbn
%Eff uCi/ML uCi/ML
%:Error Status CO-58 810.76 99.40*
8.330E-01 6.521E-07 6.522E-07 9.23 OK 863.94 0.74 7.882E-Ol Line Not Found Absent 1674.00 0.54 4.519E-01 Line Not Found Absent Final Mean for 1 Valid Peaks =
6.522E-07+/- 6.021E-08 (
9.23%:)
CO-60 1173.22 100.00*
6.044E-01 7.310E-07 7.310E-07 8.66 OK 1332.49 100.00 5.426E-01 6.285E-07 6.285E-07 9.79 OK Final Mean for 2 Valid Peaks 7.310E-07+/- 6.329E-08 (
8.66%:)
Nuclide Type: FP Uncorrected Decay Corr I-Sigma Nuclide Energy
%Abn
%Eff uCi/ML uCi/ML
%:Error Status SB-125 176.33 6.89 2.679E+00 1.465E-06 1.465E-06 24.39 OK 380.43
- 1. 50 1.591E+00 2.390E-06 2.390E-06 54.12 OK 427.89 29.33*
1.443E+00
- 1. 454E-06 1.454E-06 11.17 OK 463.38 10.35 1.349E+00
- 1. 678E-06 1.678E-06 16.24 OK 600.56 17.80 1.080E+00 1.714E-06
- 1. 714E-06 12.25 OK 606.64 5.02 1.071E+00 Line Not Found Absent 635.89 11.32 1.028E+00 1.806E-06
- 1. 806E-06 14.39 OK 671. 41
- 1. 81 9.812E-01 Line Not Found Absent Final Mean for 6 Valid Peaks 1.454E-06+/- 1. 625E-07 ( 11.17%)
Nuclide Type: FG Uncorrected Decay Corr I-Sigma Nuclide Energy
%Abn
%Eff uCi/ML uCi/ML
%Error Status XE-133 81.00 37.32*
1.793E+00 1.364E-07 1.366E-07 48.89 OK Final Mean for 1 Valid Peaks 1.366E-07+/- 6.680E-08 ( 48.89%:)
Nuclide Type: OTHER Uncorrected Decay Corr I-Sigma Nuclide Energy
%Abn
%:Eff uCi/ML uCi/ML
%:Error Status ANNIL 511.00 0.00*
1.241E+00 O.OOOE+OO O.OOOE+OO 0.00 OK Final Mean for 1 Valid Peaks = O.OOOE+oo+l-O.OOOE+OO
(
0.00%)
Flag: "*" = Keyline
Unidentified Energy Lines S~ple ID : 090306_0434_C None Flags: "T" = Tentatively associated ACquisition date Page:
3 6-MAR-2009 02:51:23
Rejected Report Page :
4 Sample ID : 090306 0434 C Acquisition date : 6-MAR-2009 02:51:23 Half-Life Activity 1-Sigma Nuclide Half-life Ratio Energy %Abund (uCi/ML)
%Error Rejected by I-131 8.04D 0.00 80.18 2.62 Not Found Abun.
284.29 6.05 --- Not Found -- -
364.48* 81.20 --- Not Found -- -
636.97 7.26 2.823E-06 14.39 722.89 1.08 --- Not Found
% Abundances Found =
7.39 I-l32 2.30H 0.15 262.70 1.44 Not Found Abun.
505.90 5.03 Not Found 522.65 16.10 Not Found 630.20 13.70 Not Found 650.60 2.66 Not Found 667.69* 98.70 Not Found 671. 60 5.23 Not Found 727.00 5.33 Not Found 772.61 76.. 20 Not Found 809.80 5.63
- 1. 278E-05 9.23 954.55 18.10 Not Found 1l36.00 2.96 Not Found 1295.30
- 1. 97 --- Not Found l372.10 2.47 --- Not Found l398.60 7.11 -- - Not Found
% Abundances Found =
2.14 (Abn. Limit = 75.00%)
TE-134 41.80M 0.50 180.89 18.00 Not Found Abun.
201.24 8.70 Not Found 210.47 21.90 Not Found 277.95 21.30 Not Found 435.06 18.60 Not Found 460.99 10.80 Not Found 464.64 5.10 4.814E-06 16.24 565.99 18.90 --- Not Found ---
636.26
- 1. 71
- 1. 687E-05 14.39 665.85 1.20 Not Found 712.97 4.20 Not Found 742.59 14.70 Not Found 767.20* 30.00 Not Found 844.06 1.20 Not Found 925.55
- 1. 65 Not Found
% Abundances Found =
3.83 CS-136 13.16D 0.00 86.29 6.30 Not Found Abun.
153.22 7.46 Not Found 163.89 4.61 Not Found 176.55 13.56 7.453E-07 24.39 273.65 12.66 Not Found 340.57 48.50 Not Found 818.50* 99.70 Not Found 1048.07 79.60 Not Found 1235.34 19.70 Not Found
% Abundances Found =
4.64
Rejected Report (continued)
Sample ID : 090306_0434_C Nuclide CS-138 PM-148M RA-228 Half-Life Half-life Ratio 32.20M 0.65
% Abundances 41.30D 0.00
% Abundances 5.75Y 0.00
% Abundances Flag: "*" = Keyline Energy 138.10 227.76 408.98 462.79 546.94 871. 80 1009.78 1147.22 1343.59 1435.86*
Found =
98.48 189.63 288.11 311. 63 414.07 432.78 501.26 550.27*
599.74 611. 26 629.97 725.70 915.33 1013.81 Found =
99.45 129.08 209.28 270.23 327.64 409.51 463.00 755.18 772.17 794.70 835.50 911. 07*
969.11 1459.30 1495.80 1588.00 1630.40 Found =
Page:
5 Acquisition date: 6-MAR-2009 02:51:23
%Abund 1.49 1.51 4.66 30.70 10.80 5.11 29.80 1.24 1.14 76.30 18.86 2.47 1.10 12.56 3.92 18.66 5.35 6.75 94.90 12.54 5.48 89.00 32.80 17.17 20.30 3.88 1.30 2.80 4.40 3.60 3.20 2.13 4.40 1.05 1.55 4.60
- 1. 75 27.70 16.60 1.00 1.00 3.50 1.86 5.34 Activity 1-Sigma (uCi/ML)
%Error
--- Not Found ---
--- Not Found ---
--- Not Found ---
8.822E-07 16.24 Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found 2.430E-06 12.25 Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found 3.944E-06 16.24 Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found Not Found*
Not Found Rejected by Abun.
Abun.
Abun.
Interference Report Sample ID : 090306_0434_C No interference correction performed Acquisition date Page:
6 6-MAR-2009 02:51:23
summary of Nuclide Activity Sample ID : 090306_0434_C Acquisition date Page:
7 6-MAR-2009 02:51:23 Total number of lines in spectrum 11 Number of unidentified lines 0
Number of lines tentatively identified by NID 11 Nuclide Type : AP Nuclide CO-58 CO-60 Hlife 70.80D 5.27Y Decay
- 1. 00
- 1. 00 Wtd Mean Uncorrected uCi/ML 6.S21E-07 7.310E-07 Total Activity Nuclide Type : FP 1.383E-06 Nuclide SB-125 Hlife 2.77Y wtd Mean Uncorrected Decay uCi/ML
- 1. 00
- 1. 454E-06 Total Activity
- 1. 454E-06 Nuclide Type : FG Nuclide XE-133 Hlife 5.24D Wtd Mean Uncorrected Decay uCi/ML 1.00 1.364E-07 Total Activity 1.364E-07 Nuclide Type : OTHER Nuclide ANNIL Hlife 100. DOD Wtd Mean Uncorrected Decay uCi/ML
- 1. 00 O. OOOE+OO Total Activity O.OOOE+OO Orand Total Activity:
2.974E-06 Wtd Mean Decay Corr uCi/ML 6.522E-07
?310E-07 1.383E-06 Wtd Mean Decay Corr uCi/ML 1.454E-06 1.454E-06 Wtd Mean Decay Corr uCi/ML 1.366E-07
- 1. 366E-07 Wtd Mean Decay Corr uCi/ML O.OOOE+OO O.OOOE+OO 2.974E-06 100.00%
Decay Corr 1-Sigma Error 0.602E-07 0.633E-07 Decay Corr 1-Sigma Error 0.162E-06 Decay Corr 1-Sigma Error 0.668E-07 Decay Corr 1-sigma "Error O.OOOE+OO "M" = Manually accepted 1-Sigma
%Error 9.23 8.66 Flags 1-Sigma
'tError Flags 11.17 1-Sigma
'tError Flags 48.89 1-Sigma
%Error Flags 0.00 Flags: "K" = Keyline not found "En = Manually edited "An = Nuclide specific abn. limit
1aximum Permissible concentration Report jample ID : 090306 0434 C Acquisition date Activity l-Sigma MPC Fractional Nuclide (uCi/ML)
% Error (uCi/ML)
M.PC CO-58 6.522E-07 9.2 9E-05 7.247E-03 CO-60 7.310E-07 8.7 3E-05 2.437E-02 SB-125 1.4S4E-06 11.2 1E-04 1.4S4E-02 XE-133
- 1. 366E-07 48.9 ANNIL O.OOOE+OO 0.0 ------------------------------------------
Totals:
2.974E-06 4.61SE-02 Page:
8 6-MAR-2009 02:51:23
Page 1 of 12 WATTS BAR NUCLEAR PLANT A.4-RO A.4-RO Respond To Medical Emergency
Page 2 of 12 WATTS BAR NUCLEAR PLANT A.4-RO EVALUATION SHEET Task:
Respond To a Medical Emergency Alternate Path:
N/A Facility JPM #: 3-0T-JPMADA.4-1 K/A Rating(s): 2.4.39
[3.3/3.1]
Task Standard: Performer performs actions of Appendix A of EPIP-10, Medical Emergency Response.
Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator __X__ In-Plant _____
Perform __X___ Simulate ___ _
References:
EPIP-10, Medical Emergency Response, Rev. 20.
Task Number: RO-100-SOI-100-011 APPLICABLE FOR: RO/SRO 10CFR55.45: 11 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 3 of 12 WATTS BAR NUCLEAR PLANT A.4-RO SIMULATOR OPERATOR INSTRUCTIONS:
This JPM may be performed either on the simulator or in another location. If performed on the simulator refer to the following.
- 1. Initialize to any IC.
- 2. Acknowledge all alarms.
- 3. Freeze simulator for duration of task performance.
- 5. NOTE: This JPM may be performed using a console booth instructor who acts as personnel outside the main control room. Cues may be made by him as indicated by the JPM.
SIMULATOR OPERATOR INSTRUCTIONS:
When directed by the evaluator, place phone call to the Horseshoe to initiate the medical emergency:
Call the Horseshoe and state the following:
I want to report a medical emergency.
Page 4 of 12 WATTS BAR NUCLEAR PLANT A.4-RO Tools/Equipment/Procedures Needed:
Latest revision of EPIP-10 NOTE: START THIS JPM AT A LOCATION WHERE PERFORMER HAS ACCESS TO PROCEDURES (Simulator, Main Control Room, TIC or provide performer with procedure).
Page 5 of 12 WATTS BAR NUCLEAR PLANT A.4-RO READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
You are the Control Room Operator (CRO) on shift.
You have received a telephone call reporting an onsite medical emergency.
INITIATING CUES:
Respond to the medical emergency in accordance with EPIP-10.
A.4 RO Page 6 of 12 START TIME: _______
STEP 1:
Obtain a copy of the instruction.
STANDARD: A copy of EPIP-10 has been obtained.
EXAMINERS CUE: After the performer locates and obtains correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
___ SAT
___ UNSAT NOTE TO EVALUATOR: The following steps are from EPIP-10, Appendix A STEP 2: [Step A]
Obtain NAME of caller.
STANDARD: CRO requests name of caller and records on Appendix A.
CUE:
State to the performer that your name is John Doe.
COMMENTS:
___ SAT
___ UNSAT STEP 3: [Step B]
LOCATION of caller.
STANDARD: Performer requests the location of the caller and records on Appendix A.
CUE:
State to the performer that you are just south of the station air compressors on elevation 708 in the Turbine Building.
COMMENTS:
___ SAT
___ UNSAT
A.4 RO Page 7 of 12 STEP 4: [Step C]
Type of Medical Emergency.
STANDARD: Performer requests the type of Medical Emergency and records on Appendix A.
CUE:
State to the performer that you found a male victim lying on the floor unconscious. The victim has a heartbeat and is breathing.
COMMENTS:
___ SAT
___ UNSAT STEP 5: [Step D]
Number of personnel Involved.
STANDARD: Performer requests how many people involved and records on Appendix A.
CUE:
State to the performer: No other individuals are involved.
COMMENTS:
___ SAT
___ UNSAT STEP 6: [Step E]
Immediate Area Hazards (Radiological, Safety).
STANDARD: Requests if immediate hazards exist and records on Appendix A.
CUE:
State to the performer: No hazards exist in the area.
COMMENTS:
___ SAT
___ UNSAT
A.4 RO Page 8 of 12 STEP 7: [Step F] Telephone number of the caller.
STANDARD: Request the telephone number of the caller and records on Appendix A.
CUE:
State to the performer that the phone number of the phone you are calling from is 5555.
COMMENTS:
___ SAT
___ UNSAT NOTE TO EVALUATOR: The sequence of actions to initiate the Fire Alarm is taken from AOI-30.1, Step 1. These steps appear as un-numbered steps.
STEP 8: INITIATE the fire alarm.
STANDARD: Performer describes how to initiate the Fire Alarm.
EXAMINERS CUE:
COMMENTS:
STEP 9: RESET the fire alarm.
STANDARD:
EXAMINERS CUE:
COMMENTS:
A.4 RO Page 9 of 12 STEP 10: [Step G] ALERT and DISPATCH MERT PERSONNEL STANDARD: Performer alerts and dispatches MERT personnel using a plant radio set to Channel 3.
CUE:
As MERT personnel, acknowledge performers communication.
COMMENTS:
___ SAT
___ UNSAT STEP 11: [Step H] Make the following plant announcement with public address:
ATTENTION ALL SITE PERSONNEL.
ATTENTION ALL SITE PERSONNEL.
A MEDICAL emergency has been reported. The MERT is to ACTIVATE and RESPOND to the following LOCATION:
STANDARD: Performer makes public address announcement and has MERT respond to Turbine Building elevation 708, just south of the station air compressors.
EXAMINERS CUE: DO NOT allow performer to actually perform this announcement. Ensure it is simulated.
COMMENTS:
A.4 RO Page 10 of 12 STEP 12: INITIATE the fire alarm.
STANDARD:
EXAMINERS CUE:
COMMENTS:
STEP 13: [Step I] CONFIRM that the Shift Manager (SM) has been notified.
STANDARD: Performer ensures the SM has been notified. (may make phone call or announce to the control crew that a medical emergency is in progress)
- CUE:
Acknowledge report as Shift Manager.
COMMENTS:
A.4 RO Page 11 of 12 STEP 11: [Step J] CONFIRM that the Fire Protection Section Duty Shift Supervisor (Fire Brigade Leader) was notified by:
Radio or Telephone (extension 3311 or 3355) or Pocket Pager 40566 STANDARD: Performer ensures the Fire Protection Section Duty Shift Supervisor was notified by radio, telephone, or pocket pager.
EXAMINERS CUE: Do NOT allow performer to actually perform this notification. Ensure it is simulated.
CUE:
Acknowledge report as Fire Protection Section Duty Shift Supervisor.
COMMENTS:
___ SAT
___ UNSAT STEP 12: [Step K] CONFIRM/COORDINATE MERT response (via radio or phone) until Incident Commander assumes control.
STANDARD: Performer confirms/coordinate the MERT response until the Incident Commander assumes control.
CUE:
As Incident Commander, notify the performer that you have assumed control of the emergency. We will stop here.
COMMENTS:
END OF TASK TIME STOP: ________
APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
You are the Control Room Operator (CRO) on shift.
You have received a telephone call reporting an onsite medical emergency.
INITIATING CUES:
Respond to the medical emergency in accordance with EPIP-10.
PAGE 1 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO D.1-SRO CLASSIFY THE EVENT PER THE REP (HIGH RCS ACTIVITY, SGTR AND FAULTED SG)
PAGE 2 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO EVALUATION SHEET Task: Classify the Event per the REP (HIGH RCS ACTIVITY, SGTR AND FAULTED SG)
Alternate Path:
N/A Facility JPM #:
3-OT-JPMS081A K/A Rating(s):
2.1.14 [2.5/3.3]
2.4.30 [2.2/3.6]
2.4.38 [2.2/4.0 035A2.01 [4.5/4.6 Task Standard:
The event is classified as a GENERAL EMERGENCY based on Loss of Any Two Barriers and Potential Loss of Third Barrier Notifications are made per EPIP-5.
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: 26 min.
Time Critical: Yes
=======================================================================
Applicant:
Time Start: _________
NAME SSN Time Finish: _________
Performance Rating: SAT ______ UNSAT ______
Performance Time ____
Examiner: __________________________________
__________________________________/_______
NAME SIGNATURE DATE
=======================================================================
COMMENTS
PAGE 3 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO EVALUATOR INFORMATION SHEET SIMULATOR SETUP INSTRUCTIONS:
NONE: THIS JPM IS SIMULATED and the simulator will not be used to reflect the conditions.
REQUIRED MATERIALS:
EPIP-1 and EPIP-5 SPECIALCONSIDERATIONS:
TO PRESERVE EXAM SECURITY:
DO NOT allow actual call to ODS. If a call is made, ensure call is to simulator instructor UNDER NO CIRCUMSTANCES IS THE PERFORMER TO OPERATE THE FAX IN THE ODS or ODS DRILL MODES.
Tools/Equipment/Procedures Needed:
Ensure clean copy of EPIP-5 in all copies of Emergency Instructions on the Simulator Floor and in the file drawer of Unit Supervisors desk.
SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Obtain copy of EPIP-5 to facilitate role plays for contacts made by the performer.
- 2. Performer must use NRC ring down phone.
PAGE 4 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO READ TO OPERATOR DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.
INITIAL CONDITIONS:
- 1. The unit was at 90% RTP 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. The Unit Supervisor has informed you of the above conditions.
- 2. The operators are taking actions per the emergency instructions (currently in E-3 and transitioning from E-2 and will be transitioning to ES-3.1).
- 3. You are to make the initial classification of the event per the REP EPIPs and make required initial notifications.
- 4. Portions of this JPM are time critical.
PAGE 5 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO 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 6 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO NOTE 1 Steps not required to be performed may be marked N/A.
NOTE 2 Steps with in the margin may be performed by Non-Licensed Operator phone talker.
STEP 3:
[STEP 1] Upon determining that existing conditions are classified as a GENERAL EMERGENCY according to EPIP-1 (independent evaluations by crew members may be beneficial), the SED, or designee, will:
STANDARD:
- CUE:
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT NOTE 1 IF ongoing onsite Security events may present risk to the emergency responders, THEN CONSULT with Security to determine if site access is dangerous to the life and health of emergency responders.
NOTE 2 IF ongoing events makes activating EPS and site access dangerous to the life and health of emergency responders, THEN the STAGING AREA button on the EPS terminal should be used INSTEAD of the EMERGENCY button.
This will direct off-site personnel to Training Center Classroom 19 (LNC).
Responders within the Protected Area will monitor Plant Announcements and report to the TSC or OSC as conditions permit.
NOTE 3 The Emergency Paging System (EPS) provides a printed report every 10 minutes during the 90 minutes duration after activation. Printouts are available in the TSC, OSC and the MCR NOTE 4 When initiating Appendix A or C ensure that only the applicable EAL(s) for which the classification is declared are documented. Example: When using the fission product barrier matrix, document three digits including P or L(1.1.1 P, 1.2.2 L, & 1.3.2 L) When initiating Appendix D only the additional EAL(s) need to be listed.
PAGE 7 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 4:
[STEP 1] IF the onsite emergency centers are not staffed, THEN DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the 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 have him activate the EPS.
B IF the above methods of activating the EPS fail, Shift Personnel must use the Radiological Emergency Response Call Lists to staff the TSC and OSC. This list is located in the EPS Manual near the terminal.
STANDARD: Performer directs the NLO to perform Step 1 to activate the emergency paging system (EPS) to staff the TSC and Operations Support Center (OSC) or EPS is activated in the control room.
This step is critical to ensure proper activation of TVA resources for event in progress.
- CUE:
After the NLO is notified, acknowledge the request to activate the Emergency Paging System.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 8 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 5:
[STEP 2] IF the TSC has not been activated, THEN
- a. INITIATE Appendix A and B, Initial Notification Information 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 NOTE ODS should be notified within 5 minutes after declaration of the event.
PAGE 9 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 6:
- b. NOTIFY the ODS direct by ODS Ringdown or 5-751-1700 or 5-751-2495
- 1) PROVIDE the information from Appendices A and B.
STANDARD: Appendix A is accurately completed with Appendix B RECOMMENDATION 2 SELECTED.
The ODS is notified and provided the information on Appendix A. This notification must be made within 5 minutes of event declaration.
Performer notifies the ODS, and then assigns the NLO to FAX Appendix A to the ODS.
EVALUATOR NOTE:
TO PRESERVE EXAM SECURITY, DO NOT allow actual call to ODS. If a call is made, ensure call is to simulator instructor NOTE TO EVALUATOR: TO PRESERVE EXAM SECURITY, UNDER NO CIRCUMSTANCES IS THE PERFORMER TO OPERATE THE FAX IN THE ODS or ODS DRILL MODES.
- CUE:
EVALUATOR (or Booth Operator) Role play as the ODS and repeat back the report.
COMMENTS: RECORD time that ODS was notified:_________
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 10 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 7:
- c. IF the ODS cannot be contacted within 10 minutes, then NOTIFY Rhea County, Meigs County, McMinn County, and the Tennessee Emergency Management Agency (TEMA) of the classification USING the contact information in Appendix E.
STANDARD: The ODS is notified and provided the information on Appendix A. This notification must be made within 5 minutes of event declaration. The conditions of this step are not met, so the step is N/A.
COMMENTS:
___ SAT
___ UNSAT
PAGE 11 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 8:
d ANNOUNCE to the crew: A GENERAL EMERGENCY is being declared based on Primary Coolant Activity Level, SGTR on SG #1/Faulted SG #1 Outside Containment. I will be the Site Emergency Director.
STANDARD: The above announcement is made to the crew. Wording describing the event may vary.
Step is critical to alert crew to the declaration of the GENERAL EMERGENCY and provide for tracking personnel.
- CUE:
After the crew is notified, acknowledge the report.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 9:
- e. TRACK dispatched personnel by name, and PERFORM one of the following.
IF OSC is not staffed, THEN INFORM Rotating Maintenance Organization Supervisor of names for team tracking.
WHEN OSC is staffed, THEN INFORM OSC manager of names for team tracking.
STANDARD: Performer addresses the fact that the OSC has not been staffed and that until it is, dispatched personnel will be provided to the RMOS for team tracking.
- CUE:
If the Rotating Maintenance Organization Supervisor is contacted, acknowledge the report.
COMMENTS:
___ SAT
___ UNSAT
PAGE 12 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 10:
- f. GO TO Step 5.
STANDARD: Performer advances to Step 5.
COMMENTS:
___ SAT
___ UNSAT STEP 10:
[Step 5] ANNOUNCE to the plant: "ATTENTION ALL SITE PERSONNEL. ATTENTION ALL SITE PERSONNEL. A GENERAL EMERGENCY has been declared based on
_____________________." (Repeat)
STANDARD: Performer provides NLO with the following information in order to make the Plant announcement :
"ATTENTION ALL SITE PERSONNEL. ATTENTION ALL SITE PERSONNEL. A GENERAL EMERGENCY has been declared based on Primary Coolant Activity Level, SGTR on SG #1/Faulted SG #1 Outside Containment." (Repeat)
COMMENTS:
___ SAT
___ UNSAT
PAGE 13 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO CAUTION If there is any possibility of a radiological release, A severe weather condition (such as a Tornado) or security adversary attack, HOLD assembly and accountability actions until these conditions have been resolved. Do not send personnel into areas of unknown radiological conditions or security risk without first contacting Radiological Control (RADCON) or Security.
NOTE 1 The following action is N/A if assembly and accountability actions have already been initiated.
NOTE 2 EPIP-8, Personnel Accountability and Evacuation, Appendix D initiates Site Security actions and Radiation Protection actions (as necessary).
STEP 11 :
[STEP 6] INITIATE EPIP-8, Personnel Accountability and Evacuation STANDARD: The performer determines that assembly and accountability should be performed and assigns Steps 6 to the NLO for completion.
This step is critical in that specific guidance is given with regard to assembly & accountability.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 14 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 12:
[STEP 7] CONTACT Radiation Protection (x7865), and PROVIDE the following:
- a. ANNOUNCE "We are in a GENERAL EMERGENCY.
(Repeat)
- b. DIRECT Radiation Protection to IMPLEMENT EPIP-14, Radiological Control Response, and CECC EPIP-9, Emergency Environmental Radiological Monitoring Procedures.
- c. EVALUATE the need to implement EPIP-13, Initial Dose Assessment for Radiological Emergencies, for a dose projection if radioactivity is being released through normal plant release paths.
STANDARD: The performer assigns completion of this step to the NLO.
This step is critical to ensure Radiation Protection implements the proper procedures in response to the GENERAL EMERGENCY.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 15 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 13:
[STEP 8] IF there are personnel injuries, IMPLEMENT WBN EPIP-10, Medical Emergency Response.
STANDARD: Performer determines that it is NOT necessary to implement EPIP-10.
- CUE:
Inform the performer that there are NO personnel injuries.
COMMENTS:
___ SAT
___ UNSAT STEP 14:
[STEP 9] CONTACT Site Security (x8464 or x8495), and REQUEST Security to IMPLEMENT EPIP-11, Security and Access Control.
STANDARD: The performer assigns completion of this step to the NLO.
This step is critical to ensure Radiation Protection implements the proper procedures in response to the GENERAL EMERGENCY.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 16 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 15:
[STEP 10] INFORM TVA Management by PERFORMING the following:
NOTIFY Duty Plant Manager in accordance with SPP-3.5.
PROVIDE Duty Plant Manager GENERAL EMERGENCY information from one of the following (as applicable).
The information recorded on Appendix A, Initial Notification form for GENERAL EMERGENCY, or The information recorded on Appendix C, Initial Classification form for GENERAL EMERGENCY.
STANDARD: Duty Plant Manager is provided the Appendix A information.
This step is critical as it alerts plant management to REP activation.
- CUE:
(Booth Operator) Role play as the Duty Plant Manager and acknowledge the report.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT NOTE: The following step is not applicable if the state was contacted directly.
STEP 16:
[STEP 11] CONFIRM with the ODS or CECC that the State of Tennessee has been notified.
STANDARD: ODS is contacted to confirm that the State of Tennessee has been notified of REP activation.
- CUE:
(Booth Operator) Role play as the ODS and report that the State of Tennessee has been Notified of REP Activation at Watt Bar Nuclear Plant.
COMMENTS:
___ SAT
___ UNSAT NOTE: NRC notification should be made as soon as practicable but within one hour of GENERAL EMERGENCY declaration. Whenever NRC requests, a qualified person must be provided for a continuous update to NRC Operations Center.
PAGE 17 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO EVALUATOR NOTE: DO NOT allow actual call to NRC. Ensure call is to simulator instructor.
STEP 22:
[STEP 12] NOTIFY the NRC, using designated NRC phone (ENS), of plan activation. The following commercial numbers are for the NRC Operations Center.
9-1-301-816-5100 (MAIN) 9-1-301-951-0550 (BACKUP) 9-1-301-816-5151 (FAX)
STANDARD: The performer assigns completion of this step to the NLO.
This step is critical as it alerts NRC to REP activation.
EVALUATOR NOTE: DO NOT allow actual call to NRC. Ensure call is to simulator instructor.
- CUE:
(Booth Operator) Role play the NRC and acknowledge the report.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
PAGE 18 0F 19 WATTS BAR NUCLEAR PLANT D.1 - SRO STEP 23:
[STEP 13] NOTIFY the NRC Resident Inspector (x1776) and PROVIDE one of the following (as applicable).
The information recorded on Appendix A, or The information recorded on Appendix C.
STANDARD: The NRC Resident Inspector is provided Appendix A information.
This step is critical as it alerts NRC to REP activation.
EVALUATOR NOTE:
DO NOT allow actual call to NRC Resident.
Ensure call is to simulator instructor.
- CUE:
(Booth Operator) Role play the NRC Resident and acknowledge the report.
EVALUATOR NOTE: Give the following cue to performer when the performer completes the call to the NRC Resident Inspector:
- CUE:
Role play and report that the TSC is staffed, and that the SED will be coming to the control room for a turnover of SED duties. We will stop here.
COMMENTS:
END OF TASK CRITICAL STEP
___ SAT
___ UNSAT TIME STOP: ________
PERFORMER HANDOUT SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.
INITIAL CONDITIONS:
- 1. The unit was at 90% RTP 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:
The Unit Supervisor has informed you of the above conditions.
The operators are taking actions per the emergency instructions (currently in E-3 and transitioning from E-2 and will be transitioning to ES-3.1).
You are to make the initial classification of the event per the REP EPIPs and make required initial notifications.
Portions of this JPM are time critical.