ML120720077
| ML120720077 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/21/2012 |
| From: | NRC/RGN-II |
| To: | |
| Gerald Laska | |
| References | |
| Download: ML120720077 (119) | |
Text
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SEQUOYAH NUCLEAR PLANT SRO ADMIN A.ia
1201 NRC ROADMINA.1.a Page 2 of 8 SRO JOB PERFORMANCE MEASURE Task:
Review Completed Refueling Checklist and Implement Technical Specification Requirements.
Task#:
0001430302 Task Standard:
Examinee reviews the completed Refueling Checklist Log Appendices and discovers two embedded errors, than applies LCO 3.9.10 to stop fuel movement and LCO 3.9.8.2 action a to immediately commence corrective action to return the required RHR loops to OPERABLE status as soon as possible.
Time Critical Task:
YES:
NO:
X KIA ReferencelRatings:
2.1.40 (3.9)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
I Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
12 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC RO ADMIN A.1.a Page 3 of 8 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
1.
In progress copy of 0-SI-OPS-000-065.S, Refueling Surveillance Log 2.
Technical Specifications, Unit 1 3.
Chronological Test Log
References:
Reference Title Rev No.
1.
O-Sl-OPS-000-065.S Refueling Surveillance Log Rev 17 2.
Unit 1 Technical Specifications Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1.
Unit 1 is in MODE 6 on day shift.
2.
Fuel movement is in progress using FHI-3 MOVEMENT OF FUEL, 35 fuel bundles have been loaded into the core.
3.
The loading of the 36th bundle was in progress when data was obtained.
4.
0-SI-OPS-000-065.S, Refueling Surveillance Log has been completed INITIATING CUES:
1.
You have been directed to review the completed copy of 0-SI-OPS-000-065.S, Refueling Surveillance Log.
2.
When you have completed your review, identify all deviations (if any) on the Chronological Test Log and take all required action.
3.
Inform the evaluator when you are complete.
1201 NRC ROADMINA.1.a Page 4 of 8 Start Time Obtain a copy of 0-Sl-OPS-000-065.S, Refueling Surveillance Log STEP 1
SAT UNSAT Standard:
Copy of 0-SI-OPS-000-065.S, Refueling Surveillance Log is obtained Cue Provide an in progress copy of 0-SI-OPS-000-065.S, Refueling
Surveillance Log Comment
1201 NRC RO ADMIN A.1.a Page 5 of 8 I
67 I
Refueling Canal Ladde;in 1 STEP 2
Level I
reactor vessel contairrmer6 sic 734 ladder Reactor Vessel SR 49O 6
I 23 feel above I equipment pit Iinde rungs SAT i
flange j
aørevWs O1-OP-OOO-Q65.S, afue1ing Sun UNSAT Ape9dix A for ReactorVessefLeveI.
Critical Step Standard:
inen ReactorVeseft,ve1 of 9 rungs qn the ladder 1risinsafIetent REACTOR CAVITY LEVEL INDICATOR (RefuelIng Canal Ladder)
RUNG NO.
EL 733-9 112 (TOP of CURB>
zzz EL 72510 112 NORMAL TECH SPEC WATER
MIN. LEVEL LEVEL 725-l 112 726-l 112 ziz
- EL 717-lO 112 20
-EL713-lO 112 Examiner Note:
32
- EL 701-lO 112 REACTOR VESSEL FLANGE 702-l 112 42
- F[ R1-1fl 112 REFUELING CANAL FLOOR 690-lO 112 REFUELING CANAL (EQUIPMENT PIT) LADDER 42 RUNGS SPACED AT 1-O Notes
- 7) Minimum TECH SPEC level is 725 ft and 1 1/2, If water level is at 8 rungs from the top of the Refueling Canal ladder, the level will be at elevation_725_ft_and_10_1/2.
Comment
1201 NRC ROADMINA.1.a Page 6 of 8 RHR loop LCO 3.9.82 8
STEP 3
operabilby SAT operable 8-B RHR Pump E*nfr r1eS-ØP-OOO-O66, Refeh uRobJ UNSAT APfl 9
A for RHR Loop ojrability.
Critical Step Standard Exán,inee determines two loops are required operable if ReactorVessel levelis less than23 ft above the Reactor Vessel flange.
Comment Notes Examiner Note:
- 8) Two loops are required operable if Reactor Vessel level is less than 23 ft above the Reactor Vessel flange.
STEP 4
LIMrnNGCONDITIONSFOROPERA.11ONS SAT
. 39 10 At least 23 feet of water shall be maintained over the top of the reactor pcessure vessel flange.
UNSAT APPIJCABILITY:
Dunng nento rai ted Critical Step ACON:
With the requirements of the above specification not satisfied, immediately suspend operations iiwoMr movement of ilTadiated fuel assemblies withei containment.
- r
-:g-!: -q
-C--
P-Standard Exarninee enters the LCO3 91.0 action and suspendsofnovnt%
irradiafed fuel assemblies within containment.
. W. -
Comment
1201 NRC RO ADMIN A.1.a Page 7 of 8 LIMITiNG CONDITiON FOR OPERATION STEP 5:
SAT 3.9.8.2 Two independent Residual Heat Removal (RHR) loops shall be OPERABLE.
APPliCABILITY: MODE 6 wtien the water level above the top of the reactor pressure vessel flange s U NSAT less than 23 feet.
Critical Step ACTION:
f a.
With less than the required RHR loops OPERABLE, immediately halate conective action to return the required RHR loops to OPERABLE status as soon as possible.
b.
The provisions of Spedfication 3.0.3 are not applicable.
r Standard:
Examinee enters LCO 3.9.82 action a.
Comment Terminating The JPM is complete when the Examinee returns the JPM ue.
briefing sheet to the Examiner.
Stop Time
1201 NRC ROADMINA.1.a Page 8 of 8 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
1.
Unit I is in MODE 6 on day shift.
2.
Fuel movement is in progress, 35 fuel bundles have been loaded into the core.
3.
The loading of the 36th bundle was in progress when data was obtained.
4.
0-SI-OPS-000-065.S, Refueling Surveillance Log has been completed INITIATING CUES:
1.
You have been directed to review the completed copy of 0-SI-OPS-000-065.S, Refueling Surveillance Log.
2.
When you have completed your review, identify all deviations (if any) on the Chronological Test Log and take all required action.
3.
Inform the evaluator when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC SRO ADMIN SRO A.1.b
1201 SRO ADMIN JPM A.1.b Page 2 of 12 SRO JOB PERFORMANCE MEASURE Task:
Perform Technical Review of Shutdown Margin Calculation.
Task#:
0010040101 Task Standard:
Examinee completes a review of a completed 0-SI-NUC-000-038.0 Shutdown Margin, finds two embedded errors and ultimately enters the LCO 3.1.1 ACTION to immediately initiate a boration of> 35 gpm.
Time Critical Task:
YES:
NO:
X KIA ReferencelRatings:
2.1.37 (4.3/4.6)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
I Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
25 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 SRO ADMIN JPM A.1.b Page 3 of 12 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
1.
Unit 2 Cycle 18 NDR 2.
Unit 2 Tech Specs 3.
0-SI-NUC-000-038.0 Shutdown Margin In Progress copy 4.
0-Sl-NUC-000-038.0 Att 2 Unit 2 Cycle Specific SDM Data 5.
0-SI-NUC-000-038.0 Att 3, Correction To Boron Concentration (M-P) 6.
TI-33 Xenon Worth Calculation 7.
Chronological Test Log 8.
Calculator
References:
Reference Title Rev No.
1.
Unit2Cyclel8NDR 2
Unit 2 Tech Specs 3.
O-SI-NUC-000-038.O Shutdown Margin 59 4.
O-Sl-NUC-000-038.O Att 2 Unit 2 Cycle Specific SDM Data 5.
0-Sl-NUC-000-038.O Att 3 Correction To Boron Concentration (M-P) 6 Tl-33 Xenon Worth Calculation 27 Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1.
Unit 2 is in MODE 3, 350 deg F.
2.
Core Average Burnup is 6000 MWD/MTU.
3.
The present RCS Boron concentration is 1299 ppm.
4.
Unit 2 tripped from full power hours 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> ago ago.
5.
Unit 2 had been at 100% power for 2 weeks prior to the trip.
6.
0-SI-NUC-000-038.0, Shutdown Margin, Data Sheet 1 has been completed.
7.
REACTF is unavailable 8.
ICS is unavailable INITIATING CUES:
1.
You have been directed to review the completed copy of 0-Sl-NUC-000-038.0, Shutdown Margin data Sheet 1.
2.
When you have completed your review, identify all deviations (if any) on the Chronological Test Log and take all required action.
3.
Inform the evaluator when you are complete.
1201 SROADMIN JPMA.1.b Page 4 of 12 Start Time Obtain a copy of the following:
STEP 1
SAT Unit2Cyclel8NDR U NSAT 0-Sl-NUC-000-038.0 Shutdown Margin In Progress copy 0-Sl-NUC-000-038.0 Aft 2 Unit 2 Cycle Specific SDM Data 0-SI-NUC-000-038.0 Att 3 Correction To Boron Concentration (M-P)
Unit 2 Tech Specs Tl-33 Xenon Worth Calculation.
Copies of the following are obtained.
Unit 2 Cycle 18 NDR 0-Sl-NUC-000-038.0 Shutdown Margin In Progress copy Standard:
0-Sl-NUC-000-038.0 Aft 2 Unit 2 Cycle Specific SDM Data 0-Sl-NUC-000-038.0 Att 3 Correction To Boron Concentration (M-P)
Unit 2 Tech Specs Tl-33 Xenon Worth Calculation.
Provide copies of:
Unit2Cyclel8NDR 0-Sl-NUC-000-038.0 Shutdown Margin In Progress copy 0Sl-NUC-000-038.0 Aft 2 Unit 2 Cycle Specific SDM Data 0-Sl-NUC000-038.0 Aft 3 Correction To Boron Concentration (M-P)
Unit 2 Tech Specs Tl-33 Xenon Worth Calculation.
Comment
1201 SROADMIN JPMA.1.b Page 5 of 12 Data Sheet I STEP 2
(Page 1 of 4)
SAT SHUTDOWN MARGIN CALCULATION IN MODES 3,4, OR 5 1.0 Minimum Boron Concentration (C 5)
UNSAT
[11 A.
Date/time unit was shutdown Date Time B.
Current date/time Date Time C.
Mode SDM calculation is performed for:
MODE_____________
D.
Minimum expected core average temperature for surveillance interval E.
Time since plant shutdown F.
Steady-state core power level before plant shutdown G.
Core average burnup H.
Currentlprojected RCS C5 and associated date/time (N/A date and time for projected RCS boron concentration)
Date Time I.
Surveillance interval The examinee reviews Data Sheet 1 secfion 1.0 step 1 and notes no Standard:
errors.
Comment
1201 SRQADMIN JPMA.1.b Page 6 of 12 SSSSSt SS
.5555 5/
5.
,e 5/s,s// /f/
5/.
STEP 3
SAT S
SHUTDOWN MARGIN CALCULATION IN MODES 3,4, OR 5 1.0 Minimum Boron Concentration (CB)
UNSAT
/
S
.5/S
.. Z.,,.
V,,.
Critical Step
[2]
Minimum C8 I
WsS/ 7
/
7
/t 7 /SSS 5/
555/
r 5
4/SS55S 5/
the exmine reviews Data Set.t section tO step 2 and iscci,rthe Standard:
errorfor mininiurnoron óonqtration for SDM from Table 64 o$tide andiçintifle tije correct value of I 320 ppm
ø Examiner The number entered on the Data Sheet 1 section 1.0 step 2 was 1231 Note ppm which applies to 450 deg F, whereas the correct answer is 1320 ppm which applies to 350 deg F.
Comment Data Sheet 1 (Page 1 of 4)
SHUTDOWN MARGIN CALCULATION IN MODES 3,4, OR 5 Minimum Boron Concentration (CB) pp 1.0
[3]
Correction to Minimum CB (M-P) 5557 5*5555
/55/
/55/5555/55555 S55555///
- /55SS55*/SsS/
/5/5 SAT UNSAT Critical Step The number entered on the Data Sheet 1 section 1.0 step 3 was zero which applies to Unit 1 whereas the correct answer is 40 which applies to Unit 2.
Data Sheet 1 (Page 1 ot4)
SHUTDOWN MARGIN CALCULATION IN MODES 3,4, OR 5 1.0 Minimum Boron Concentration (Ce) 1201 SROADMIN JPMA.1.b Page 7 of 12 Standard:
[5]
Was the minimum boron concentration provided by the Reactor Engineering memorandum used in Step 1.0[2]?
Yes C
No U
If yes, proceed to Section 6.0 and NJA (or discard) intermediate steps.
STEP 5
Data Sheet I (Page lof 4)
SHUTDOWN MARGIN CALCULATION IN MODES 3,4, OR 5 Minimum Boron Concentration (CB) 1.0 4]
Adj. Mm. Boron Conc. = Step 1.0[2] + Step 1.O[3]
p Standard:
SAT UNSAT Critical Step Adjusted Minimum C8 =
+
Examiner Note:
Comment The number entered on the Data Sheet I section 1.0 step 4 was 1231 ppm whereas the correct answer is 1360 ppm.
STEP 6
SAT UNSAT The examinee reviews Data Sheet 1 section 1.0 step 5 identifies the answer to step 5 was No and proceeds to review step 6.
Comment
1201 SRO ADMIN JPM A.1.b Page 8 of 12 STEP 7
Data Sheet 1 SAT (Page 2 of 4)
UNSAT 1.0 Mnlmum Boron Concentration (CB) (continued)
[6]
Are corrections to the adjusted minimum 08 recorded in tO[4] desired?
Yes D
No C
If No, proceed to Section 6.0 and NIA (or discard) intermediate steps.
Standard The examinee reviews Data Sheet 1 section 1.0 step 6 identifies the answer to step 6 was Yes and proceeds to review section 2.
Comment NOTE Xenon worths shall be entered as negative values.
STEP 8
Data Sheet 1 SAT (Page 2 of 4)
UNSAT 2.0 Xe Worth 11]
Xe Worth Standard:
The examinee reviews Data Sheet I section 2.0 step 1 and verifies the value of Xe Worth of -99 pcm from Table 6-40 of the Unit 2 NDR.
Comment
1201 SROADMIN JPMA.1.b Page 9 of 12 STEP 9
Data Sheet 1 SAT (Page2of4) 3.0 Correction for Reduced 5DM Requirement in Mode 5 UNSAT
[1]
Mode 5 SDM correction (negative value if other than zero) pcm Standard The examinee reviews Data Sheet 1 section 3.0 step I and verifies the Correction for Reduced SDM Requirement in Mode 5 is zero pcm.
Comment STEP 10 Data Sheet 1 SAT (Page 2 of 4) 4.0 CorrectIon for Immovable or Untrippable Rods UNSAT
[1]
No. immovable/untrippable rods
[2]
A.) Maximum double stuck rod worth B.) Maximum stuck rod worth
[3]
Stuck rod worth = Step 4.O[2)A - Step 4.O[2]B
=
[4]
Correction for immovable/untrippable rods = Step 4.O[1] x Step 4.O[3]
=
x Standard The examinee reviews Data Sheet 1 section 4.0 step 1 and verifies the Correction for Immovable or Untrippable Rods is zero pcm.
Comment
1201 SRO ADMIN JPM A.1.b Page 10 of 12 Data Sheet (Page 3 of 4)
Minimum Boron Concentration Calculation
[1]
Correction to Mm. Boron Conc. = 2.0(1] + 3.0th
+ 4.0(4]
Correction to Mm. Boron Conc. =
+
+
[3]
UNSAT Critical Step Correction to Mm. Boron Conc. = Step 5.0[1] Istep 5.0[2]j
[4]
I I
Correction to Mm. SDM Boron Conc. = Step 1.0(41 + Step 5.0[3]
+
Data Sheet I
<Page 3 of 4) 6.0 Acceptance Criteria Verification
[1]
Required Boron Concentration for Shutdown Margin
[2]
CHECK appropriate box and sign to indicate whether the following acceptance criteria was satisfied.
Acceptance Criteria:
The RCS boron concentration 1.0[1]H is greater than the required boron concentration of 6.0th].
SAT U NSAT Critical Step Yes D
No D
1201 SROADMIN JPMA.1.b Page 11 of 12 Data Sheet 1 (Page 4 of 4) 6.0 Acceptance Criteria Verification (continued)
[3]
IF acceptance criteria from Step 6.012] was NOT satisfied, THEN IMMEDIATELY NOTIFY the US that acceptance criteria has NOT been satisfied and borate per action requirement of LCO 3.11.1 or LCD 3.1 1.2.
Test Director Signature Date 14]
Was boron concentration provided by Reactor Engineering memorandum used in Step 1.0[2]?
Yes D
No D
IF yes, proceed to Section 8.0 and N!A (or discard) Section 7.0.
Standard The examinee reviews Data Sheet I section 6.0 step 3 and transitions to Unit2LCO3.1.1.
Comment LIMI1]NG CONDITION FOR OPERATION STEP 14 SAT 3.1.11 The SHU1DOWN MARGIN shall be greater than or equal to 1.6% delta ki1. for4 loop oation.
NSAT APPlICABILITY: MODES 1,2,3, and 4.
Critical Step ACTION:
With the SHUTDOWN MARGIN less than 1.6% delta kflç immediately initiate and continue beration at greater than or equal to 35 gpm of a souion containing greater than or equal to 6120 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.
L bnwh Standard:
an Op orequ equir 0
i est Comment Terminating The JPM is complete when the Examinee returns the JPM STOP Cue:
briefing sheet to the Examiner.
STEP 13 SAT UNSAT Stop Time
1201 SROADMIN JPMA.1.b Page 12 of 12 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
1.
Unit 2 is in MODE 3, 350 deg F.
2.
Core Average Burnup is 6000 MWD/MTU.
3.
The present RCS Boron concentration is 1299 ppm.
4.
Unit 2 tripped from full power hours 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> ago ago.
5.
Unit 2 had been at 100% power for 2 weeks prior to the trip.
6.
0-Sl-NUC-000-038.0, Shutdown Margin, Data Sheet I has been completed.
7.
REACTF is unavailable 8.
ICS is unavailable INITIATING CUES:
1.
You have been directed to review the completed copy of 0-Sl-NUC-000-038.0, Shutdown Margin data Sheet 1.
2.
When you have completed your review, identify all deviations (if any) on the Chronological Test Log and take all required action.
3.
Inform the evaluator when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
tQL t%ç cii SHUTDOWN MARGIN 0-SI-NUC-000-038.0 ReV. 0059 IN MODES 3,4, OR 5 A.
Date/time unit was shutdown Date Time B.
Current date/time Date Time C.
Mode SDM calculation is performed for:
MODE______________
D.
Minimum expected core average temperature for surveillance interval
°F E.
Time since plant shutdown F.
Steady-state core power level before plant shutdown G.
Core average burnup H.
Current/projected RCS CB and associated date/time (N/A date and time for projected RCS boron concentration)
Date Time I.
Surveillance interval
[2]
Minimum CB
[3]
Correction to Minimum CB
[4]
Adj. Mm. Boron Conc. = Step 1.0[21 + Step 1.0j3J Adjusted Minimum CB = t 3
+ I L/ 0 i /3 (O ippm
[5]
Was the minimum boron concentration provided by the Reactor Engineering memorandum used in Step 1.0[2]?
Yes U
No U
If yes, proceed to Section 6.0 and NIA (or discard) intermediate steps.
SQN Unit 0 1.0 Data Sheet I (Page 1 of 4)
SHUTDOWN MARGIN CALCULATION Minimum Boron Concentration (Ce)
[1]
r SQN SHUTDOWN MARGIN 0-SI-NUC-000-038.0 UnitO Rev. 0059 L
Page 58 of 72 Data Sheet I (Page 2 of 4) 1.0 Minimum Boron Concentration (C
- 8) (continued)
[6]
Are corrections to the adjusted minimum CB recorded in 1.0[4] desired?
Yes E1 No 0
If No, proceed to Section 6.0 and N/A (or discard) intermediate steps.
2.0 Xe Worth r
NOTE Xenon worths shall be entered as negative values.
[1]
Xe Worth p
3.0 Correction for Reduced SDM Requirement in Mode 5
[1]
Mode 5 SDM correction (negative value if other than zero) pcm 4.0 Correction for Immovable or Untrippable Rods 1]
No. immovable/untrippable rods
[2]
A.) Maximum double stuck rod worth p
B.) Maximum stuck rod worth p
[3]
Stuck rod worth = Step 4.0[2]A
- Step 4.0[2jB p
SQN SHUTDOWN MARGIN 0-SI-NUC-000-038.0 Unit 0 Rev. 0059 Page 59 of 72 Data Sheet I (Page 3 of 4) 4.0 Correction for Immovable or Untrippable Rods (continued)
[4j Correction for immovable/untrippable rods = Step 4.O[1j x Step 4.O[3]
=
x 5.0 Minimum Boron Concentration Calculation
[1)
Correction to Mm. Boron Conc.
2.O[l] + 3.O[1] + 4.O[4]
Correction to Mm. Boron Conc.
+
+
[2]
Inverse Boron Worth
[3]
Correction to Mm. Boron Conc. = Step 5.O[1]
- IStep 5.O[211
- 1 I
ppm
[4]
çrection to Mm. 3DM Boron Conc. = Step 1.O[4j + Step 1
I3o+
11 fl 3
l 3
ppm 6.0 Acceptance Criteria Verification
[1]
Required Boron Concentration for Shutdown Margin pm
[2]
CHECK appropriate box and sign to indicate whether the foflowing acceptance criteria was satisfied.
Acceptance Criteria:
The RCS boron concentration 1.O[1]H is greater than the required boron concentration of 6.O[1].
Yes U
No Test Director Signature Date
SQN SHUTDOWN MARGIN 0-SI-NUC-000-038.0 Unit 0 Rev. 0059 Page 60 of 72 Data Sheet I (Page 4 of 4) 6.0 Acceptance Criteria Verification (continued)
[3]
IF acceptance criteria from Step 6.O[2] was NOT satisfied, THEN IMMEDIATELY NOTIFY the US that acceptance criteria has NOT been satisfied and borate per action requirement of LCO 3.1.1.1 or LCO 3.1.1.2.
Test Director Signature Date
[4]
Was boron concentration provided by Reactor Engineering memorandum used in Step 1.O{2]?
Yes D
No D
IF yes, proceed to Section 8.0 and NIA (or discard) Section 7.0.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC SRO ADMIN A2
1201 NRC SRO Admin JPM A.2 Page 2 of 17 SRO JOB PERFORMANCE MEASURE Task:
Perform RCS Leakage Calculation (0-SI-OPS-068-1 37.0) and Take All required Actions Task#:
0020010201 Task Standard:
The examinee performs a manual RCS Leakrate calculation using 0-Sl-OPS-068-1 37.0 Appendix D obtains a result of 1.07 gpm, and discovers the acceptance criteria are not met.
The Examinee will then enter LCO 3.4.6.2 Action a and identify a Site Event Notification is required.
Time Critical Task:
YES:
NO:
X KIA ReferencelRatings:
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
/
Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
20 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC SRO Admin JPM A.2 Page 3 of 17 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
Tools/EquipmentlProcedures Needed:
1.
0-SI-OPS-068-1 37.0 Reactor Coolant System Water Inventory 2.
NPG-SPP-03.5 Regulatory Reporting Requirements 3.
Unit 2 tech Specs 4.
Chronological Test Log 5.
Calculator
References:
Reference Title Rev No.
1.
0-SI-OPS-068-1 37.0 Reactor Coolant System Water Inventory 26 2.
NPG-SPP-03.5 Regulatory Reporting Requirements 3
3.
Unit 2 Tech Specs Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
1201 NRC SRO Admin JPM A.2 Page 4 of 17 INITIAL CONDITIONS:
1.
Unit-2 is in MODEl.
2.
The perFormance of 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory is due.
3.
ICS is not available.
4.
Data for the 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix C is as follows:
5.
Parameter Final Initial VCT Level 42.9 50.1 Pressurizer level 58 58 RCS Temperature 578 578 PRT Level 12358 12349 RCDT Level 172.2 171.8 CLA#1 Level 7692 7692 CLA #2 Level 7677 7677 CLA#3 Level 7672 7672 CLA#4 Level 7680 7680 Appendix D is complete through section 1.4 SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd 6.
0-SI-CEM-000-050.2 and 2-Sl-CEM-068-1 37.5 were completed last night at 2300.
7.
CCPIT/HUT leakage and other leakage is 0 gpm.
8.
Data collected for performance of this leak rate is documented in Appendix C and was collected over 120 minutes 9.
The Shift manager is unavailable.
INITIATING CUES:
1.
You are the Unit 2 Unit Supervisor and have been directed to complete a manual RCS Leakage calculation using 0-Sl-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix D 2.
All calculations should be carried out to two decimal places.
3.
Record your answers on the Appendix D.
4.
Identify the following on the Chronological Test Log:
Deviations (if any).
Required actions (if any).
Internal or External Notification requirements (if any).
5.
Notify the Examiner when you are complete.
1201 NRC SRO Admin JPM A.2 Page 5 of 17 Start Time Obtain a copy of 0-SI-OPS-068-1 37.0 Reactor Coolant System Water STEP I
Inventory.
SAT UNSAT Standard Copy of 0-Sl-OPS-068-1 37.0 Reactor Coolant System Water Inventory, is obtained.
Cue Provide a marked up copy of copy of 0-SI-OPS-068-1 37.0 Reactor
Coolant System Water Inventory.
Comment RCS LEAKAGE CALCULATIONS NOTE I All calculations must be performed manually. Veritication may be performed using the computer.
NOTE 2 All calculations should be carried out to tiio places after the decimal.
Signs must be carried through all calculations.
NOTE 3 Calculations in this Appendix may need to be performed more than
- once, If multiple calculations are required, copies of this Appendix may he used.
STEP 2
1.0 TOTAL RCS LEAKAGE SAT 1.1 Volume Control Tank (VCT)
UNSAT
[(
%)(
%)]x1927gal1%
VCT Leakage
=
Initial Level Final Level mm. )
Time VCT Leakage =
Standard:
The Examinee determines VCT Leakage is 1.16 gpm.
Comment
1201 NRC SRO Admin JPM A.2 Page 6 of 17 NOTE I Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
STEP 3
10 TOTAL RCS LEAKAGE SAT 1.2 Pressurizer (Pzr) UNIT 2 only UNSAT
[1]
CALCULATE initial PZR volume by using the following equation:
Initial PZR Vol = I PZRLeveI + 100% PZRLeveI gil *ft 3
/
j i7
/ lb olevel Initial PZR Vol =
+.?._.;.
2.02l/
- %vel
,ib 4b I
/
i in
/
mi Initial P7R Vol =
Performed By Reviewed By Standard:
The Examinee determines Initial Pressurizer Volume is 4857.55 gallons Comment
1201 NRC SRO Admin JPM A.2 Page 7 of 17 NOTE I V (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
STEP 4
1.0 TOTAL RCS LEAKAGE SAT 1.2 Pressurizer (Pzr) UNIT 2 only UNSAT
[2] CALCULATE Final PZR volume by using the following equation:
1 Vf lb
/elevel e
o 3/
Final PZR Vol=
÷/ k202 if3 /
/ lb olevel 7th
/ lb
/
m
/
in Final PZR Vol =
al Performed By Reviewed By Standard:
The Examinee determines Fina Pressurizer Volume is 4857.55 gallons Comment STEP 5
1.0 TOTALRCSLEAKAGE SAT 1.2 Pressurizer (Pzr) UNIT 2 only UNSAT (3] CALCULATE PZR leakage rate by using the following equation:
Initial PZR Volume Final PZR Volume PZR Leakage =
time PZR Leakage =
mm PZR Leakage =
epm Performed By Reviewed By Standard:
The Examinee determines Pressurizer Leakage is 0 gpm.
Comment
1201 NRC SRO Admin JPM A.2 Page 8 of 17 NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
STEP 6
1.0 TOTAL RCS LEAKAGE NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
1.0 TOTAL RCS LEAKAGE 1.4 RCS Temperature Correction[C.1]
A.
Initial Conditions:
RCS pressure
+ 14] =
psia RCS temperature =
Specific volume (U) =
ft 3
/lbm Density 1/v 1
Ibm/ft 3
8.
Final Conditions:
RCS pressure =
+ 14.7 =
RCS temperature Specific volume (v) =
ft 3
llbm Density 1/v =
Ibm/ft 3
C. Temperature Correction:
psia
[(
Ibm/ft 3 )
(
Ibmlft 3 )]
- 1298.19 gal*ft 3
/ Ib Temp Corr. =
inftial Density Final Density Temperature Correction =.
time GPM Standard:
The Examinee determines RCS Temperature Correction is 0 gpm.
Comment 1.3 Pressurizer (Pzr) UNIT I only Standard:
The Examinee addresses the step as not applicable.
SAT UNSAT Comment STEP 7
SAT UNSAT
Performed By Reviewed By 64 NOTE Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tanks pressure.
If negative leakage is calculated under these conditions, that tanks leakage must be set equal to zero.
STEP 9
2.0 IDENTIFIED LEAKAGE SAT 2.1 Pressurizer Relief Tank (PRT)
UNSAT 2.1 Pressurizer Relief Tank (PRT)
Critical Step
[(
aal)-(
gal)]
PRT Leakage =
Final Volume Initial Volume
(
mm)
Time PRT Leakage =
GPM
- ?
g Thamit*e detej!rnfneskssu er Relief Tan1 (PRT)1eak is O Qtanuaru.
gpm.
Comment STEP 8
1201 NRC SRO Admin JPM A.2 Page 9 of 17 1.0 TOTAL RCS LEAKAGE 1.5 Total RCS Leakage Total RCS Leakage =
+ (
) +
VCT PZR Temp Corr SAT UNSAT Critical Step Total RCS Leakage =
1201 NRC SRO Admin JPM A.2 Page 10 of 17 NOTE RCDT Level (2.2) may be marked N/A if conditions do NOT permit obtaining RCDT level.
STEP 10 2.0 IDENTIFIED LEAKAGE SAT 2.2 Reactor Coolant Drain Tank (RCDT)
UNSAT
[(
qal)(
gal)]
RCDT Leakage =
Final Volume Initial Volume
(
mm)
Time RCDT Leakage Performed By Reviewed By Standar&
The Examinee determines Reactor Coolant Drain Tank (RCDT) is zero gpm.
Comment NOTE 1 SG leak rates are obtained by 1, 2SICEM068137.5.
0SlCEM--000050.2 is performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and looks at activity levels which will determine if those leak rates from the last performance of 1, 2Sl--CEM068--137.5 have risen.
NOTE 2 Individual steam generator leakage may be NIAd if activity is too low to be separately identified.
STEP 11 Standard:
Comment 2.0 IDENTIFIED LEAKAGE 2.3 Steam Generator (SG)
A. iLeakage=
C B. SG2Leakage=
GPO C. SG3Leakage=________ GPD
- 0. SG4Leakage=
GPD SAT Total SG leakage U NSAT Critical Step cPn
=
1440 minlday
1201 NRC SRO Admin JPM A.2 Page 11 of 17 STEP 12 20 IDENTIFIED LEAKAGE SAT 2.3 Steam Generator (SG)
UNSAT Date/Time OSI--CEM000050.2 performed:
/
Date Time Date/Time 1, 2SICEM0681 37.5 performed:
/
Date Time Recorded by Standard The examinee obtains the date and time of the steam generator leakage surveillance from the initiating cue.
Comment
1201 NRC SRO Admin JPM A.2 Page 12 of 17 NOTE CLA leakage calculations may be marked NIA if RCS pressure is greater than 683 psig and quantification of CLA leakage is fl required STEP 13 2.0 IDENTIFIED LEAKAGE SAT 2.4 Cold Leg Accumulators (CLA)
UNSAT A. C 1 Leakage j(Final Volume) - (Initial Volume 9a1)]
(
tTime mm)
CLA 1 Leakage =
B. CLA 2 Leakage
= mna1 Volume gai) -
Volume g)]
I mm
\\
Time CLA2Leakage=
GPM C. CLA 3 Leakage = [(Final Volume gaij
- (ll Volume gal))
I mm Time CLA3Leakage=
- 0. CLA 4 Leakage
[(Final Volume gaij
- (Initial Volume gal)]
I mm Time CLA 4 Leakage =
Total CLA leakage =
GPM Performed By Reviewed By Standard:
The Examinee determines the Cold Leg Accumulators (CLA) is zero.
Comment
1201 NRC SRO Admin JPM A.2 Page 13 of 17 NOTE The following value may be marked NIA if no additional identified leakage sources (i.e., Appendix A) are to be included.
STEP 14 2.0 IDENTIFIED LEAKAGE SAT 2.5 Other Identified Leakage UNSAT Other ideniffied leakage (Appendix A) =
GPM Standard:
The Examinee determines the Other Identified Leakage is zero.
Comment NOTE If NO CCPIT de-pressurization 1 pressurization activity has occurred during the stabilization period, CCPIT/HUT leakage may be marked N/A STEP 15 2.0 iDENTIFIED LEAKAGE 2.6 Total Identified Leakage Total ed leaiage
=
SAT UNSAT
+/-__________ +
Critical Step PRT RCDT SG Total identified leakage =
+
+_____
Total CLA CCPIT/HUT Other Standard:
Comment
1201 NRC SRO Admin JPM A.2 Page 14 of 17
- 1. The primarytosecondary leakage must be less than or equal to 150 GPD through any one steam generator.
- 2. The total identified RCS leakage must be less than or equal to 10 GPM.
- 3. The total unidentified leakage must be less than or equal to 1 GPM.
Examiner The Examinee will now transition to the Unit 2 Tech Specs or NPG Note:
SPP-3.5, Regulatory Reporting Requirements.
Standard:
Comment STEP 17 W?
en 5.0 ACCEPTANCE CRITERIA A. The Technical Specification acceptance criteria is as follows:
UNSAT Critical Step SAT B.
If any of the Technical Specification criteria are NOT satisfied, the SM must be notified and action requirement (b) of LCO 3.4.6.2 satisfied.
Examiner The following two JPM steps may be performed in any order, the only Note:
critical step is for the Examinee to identify the LCO 3.4.6.2 action a entry and identify the internal notification requirement.
1201 NRC SRO Admin JPM A.2 Page 15 of 17 U)M11NG CONDON FOR OPERATION 3A.&2 Reactcjr Coolant Systn leakage sh be Iimit to:
a.
No PRESSURE 8O4JNDARY LEAKAGE I GPM UNIDT1FO LEAKAGE, c
150 gallons per day of pdina ecadary Iaaage tvougti any one stern generator, ci.
10 6PM )ENT1FI2) LEAKAGE from the Reaotor Cotarrt Sysm.
APPLICABIUTY: MODES 1,2, 3and4 9
ACTION:
- b. W any ReaotorCodant System Iea)age eater than any one of the tho,e limits.
ezoludinq PRESSURE BOUNDARY LEAKAGE or primary-to-secondary leakage, reduce I
the leakagerateto within linitswithin4 hours orbe in astHOTSTANDBYwithinthenext 8 hcers arid in COLD SKUTCOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
F STEP 18 SAT U NSAT Critical Step NPG-SPP-3.5, Regulatory Reporting Requirements STEP 19 SAT 3.2 Event or Condition Reporting A
The specift event or condtion reporting requirements aop icable to different licenses U NSAT or permits ThA possesses are identified in the following Appendices:
4.
Appendix D. Site Event Notification Matrix contains the internal management notification requirements for plant events If designated TVA Manager is unavailable For notification due to temporary assignment, (e.g., INPO, loanee) notification should be made to designee or next higher manager. The Operations Shift Manager is responsible for notifying Site Operations management and the Duty Plant Manager. The Duty Plant Manager is responsible for making the remaining internal management notifications.
d d*
The Examinee addresses the procedure step and transitions to Appendix tanar.
D.
Comment
1201 NRC SRO Admin JPM A.2 Terminating The JPM is complete when the Examinee returns the JPM briefing STOP Cue:
sheet to the Examiner.
Stop Time
1201 NRC SRO Admin JPM A.2 Page 17 of 17 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
1.
Unit 2 is in MODEl.
2.
The performance of 0-Sl-OPS-068-1 37.0, Reactor Coolant System Water Inventory is due.
3.
ICS is not available.
4.
Data for the 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix C is as follows:
5.
Parameter Final Initial VCT Level 42.9 50.1 Pressurizer level 58 58 RCS Temperature 578 578 PRT Level 12358 12349 RCDT Level 172.2 171.8 CLA#1 Level 7692 7692 CLA #2 Level 7677 7677 CLA #3 Level 7672 7672 CLA#4 Level 7680 7680 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix D is complete through section 1.4 SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd 6.
0-SI-CEM-000-050.2 and 2-Sl-CEM-068-1 37.5 were completed last night at 2300.
7.
CCPIT/HUT leakage and other leakage is 0 gpm.
8.
Data collected for performance of this leak rate is documented in Appendix C and was collected over 120 minutes.
9.
The Shift manager is unavailable.
INITIATING CUES:
1.
You are the Unit 2 Unit Supervisor and have been directed to complete a manual RCS Leakage calculation using 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix D 2.
All calculations should be carried out to two decimal places.
3.
Record your answers on the Appendix D.
4.
Identify the following on the Chronological Test Log:
Deviations (if any).
Required actions (if any).
Internal or External Notification requirements (if any).
5.
Notify the Examiner when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC SRO ADMIN A3
1201 NRC SRO ADMIN A.3 Page 2 of 10 SRO JOB PERFORMANCE MEASURE Task:
Screen Workers for Emergency Exposure.
Task#:
3430290302 Task Standard:
Given five different workers during a life saving emergency, the Examinee will choose two (Roberts and Crabtree) of the five for the authorization to exceed the TVA Administrative Dose Levels, determines authorization from the Site Emergency Director is required and the maximum TEDE exposure limit for the conditions given is 25 Rem.
Time Critical Task:
YES:
NO:
X KIA ReferencelRatings:
2.3.13 (3.8)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
I Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
14 mm Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC SRQ ADMIN A.3 Page 3 of 10 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
2.
EPIP-15, Emergency Exposure Guidelines 3.
Calculator
References:
Reference Title Rev No.
1.
EPIP-15 Emergency Exposure Guidelines 9
Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
1201 NRC SRO ADMIN A.3 Page 4 of 10 INITIAL CONDITIONS:
1.
UnitlisinMODE3 2.
An event is in progress involving due to failed fuel.
3.
The TSC is not operational.
4.
An RP Technician reports that an operator working with him in the Unit 1 690 Penetration Room has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
5.
RP has been contacted and estimates it will take at least 30 minutes to retrieve the victim.
Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
6.
Dose rates at the area needing access are greater than 9.8 Rem/Hr.
7.
There are five people that are available to perform the rescue operation.
Worker Name Age Sex Volunteer YTD TEDE Dose Shearer 23 years old Male Yes 137 mrem Roberts 26 years old Male Yes 132 mrem Ferry 27 years old Female not declared pregnant Yes 121 mrem Crabtree 57 years old Female Yes 125 mrem Collins 55 years old Male No 25 mrem INITIATING CUES:
1.
You are the Shift Manager in the Control Room.
2.
Perform the following:
a)
Calculate to two decimal places the total dose each worker would receive performing the rescue operation.
b)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, assess which two of the five workers are to be used to perform the rescue operation.
C)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the required approval prior to the rescue operation.
d)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the maximum TEDE exposure limit for the conditions given.
3.
Inform the evaluator when you are complete.
1201 NRC SRO ADMIN A.3 Page 5 of 10 Start Time Obtain a copy of EPIP-15, Emergency Exposure Guidelines.
STEP 2
SAT UNSAT Standard:
Copy of is obtained EPIP-15, Emergency Exposure Guidelines.
Provide a copy of EPIP-15, Emergency Exposure Guidelines.
Comment
1201 NRC SRO ADMIN A.3 Page 6 of 10 F
4.1 Guidance for Emergency Dose Limits SAT E.
Other factors being equal, older volunteers should be selected first.
UN A Critical Step a)
Comment Pat-tP PP PW PPPPflPr SP tPPPP P
-A.PtAfl4 -* P P PPPt* 4WnP 4P.P
- PAptW 4.0 REQUIREMENTS STEP 5 :
SAT 4.1 GuIdance for Emergency Dose Limits r
(
F.
Other factors being equal, selection of female volunteers capable i
of reproduction should be avoided.
t Critical Step
- P STEP 3
4.0 REQUIREMENTS 4.1 Guidance for Emergency Dose Limits P_*
PPP P*P P
VP--
PPP PP**
PI.
f
D.
Receipt of emergency dose limits shall be on a voluntary basi&
SAT UNSAT Critical Step Standard:
Comment
1201 NRC SRO ADMIN A.3 Page 7 of 10 4.1 Guidance for Emergency Dose Limits G.
During declared emergencies WA Administrative Dose Levels (ADLs) shall be amended as shown in Appendix D, Emergency Exposure Reference Guide, however, efforts shall be taken to hold F doses to the lowest practicable level that the emergency permits.
An individuals remaining allowable dose (RAD) is determined by subtracting the year-to-date dose from the applicable 1 OCFR2O exposure limit. Emergency responders that require additional dose in excess of IOCFR2O limits may obtain consent through the completion of Appendix A.
t
/
APPENDIX A ACKNOWLEDGMENT AND AUTHORIZATION TO EXCEEL OCCUPATIONAL DOSE LIMITS Examiner The Examinee may include Site Rad Protection Mgr, RSO, Plant Note:
Manager, and Site VP, however using the guidance of EPIP-1 5 these approvals are not required.
Comment STEP 6
4.0 REQUIREMENTS SAT UNSAT Critical Step READ THE FOLLOWING STATEMENT BEFORE SIGNING THIS FORM:
F I
Authorized by:
Site Emergency Director
- Date / Time Consult with the most senior Radiation Protection person prior to authorization Standard:
Examiner Note:
Both Crabtree and Roberts are expected to exceed the IOCFR limit of 5 rem/year during the rescue.
Standard:
Comment 1201 NRC SRO ADMIN A.3 Page 8 of 10 Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue:
the examiner.
STEP 7
Lifesaving or Protection of Large Populations 4.2 A.
Appendix 0, Emergency Exposure Reference Guide, may be used as a reference for exposure limits APPENDIX D EMERGENCY EXPOSURE REFERENCE GUIDE Emergency responders are volunteers who are qualified radiation woriters at WA and have not declared pregnancy.
YES SAT UNSAT Critical Step If conditions are not known, then answer is NO.
0 2
Continue accessing and modify exposure actions as necessary UPON DETERMINATION OF EXPOSURE LIMIT EPA PAGs are: 1 rem TEDE or REFER TO INSTRUCTIONS PRIOR TO 5 rem Thyroid CDE AUTHORIZING EXPOSURE Stop Time
1201 NRC SRO ADMIN A.3 Page 9 of 10 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
1.
Unit I is in MODE 3 2.
An event is in progress involving due to failed fuel.
3.
The TSC is not operational.
4.
An RP Technician reports that an operator working with him in the Unit 1 690 Penetration Room has fallen and is severely injured. He has moved the injured person to an area that is somewhat shielded. Due to rapidly increasing dose rates, the RP Technician leaves to get help. He believes the injuries are life threatening. He also stated that the individual could be retrieved but it would take two people to do so.
5.
RP has been contacted and estimates it will take at least 30 minutes to retrieve the victim.
Auxiliary Building Area Radiation Monitors indicate extremely high radiation levels.
6.
Dose rates at the area needing access are greater than 9.8 Rem/Hr.
7.
There are five people that are available to perform the rescue operation.
Worker Name Age Sex Volunteer YTD TEDE Dose Shearer 23 years old Male Yes 137 mrem Roberts 26 years old Male Yes 132 mrem Ferry 27 years old Female not declared pregnant Yes 121 mrem Crabtree 57 years old Female Yes 125 mrem Collins 55 years old Male No 25 mrem
1201 NRC SRO ADMIN A.3 Page 10 of 10 INITIATING CUES:
1.
You are the Shift Manager in the Control Room.
2.
Perform the following:
a)
Calculate to two decimal places the total dose each worker would receive performing the rescue operation.
b)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, assess which two of the five workers are to be used to perform the rescue operation.
c)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the required approval prior to the rescue operation.
d)
Using the guidance provided in EPIP-15 Emergency Exposure Guidelines, determine the maximum TEDE exposure limit for the conditions given.
3.
Inform the evaluator when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC SROADMINA.4
1201 NRC ADMIN SRO AA Page 2 of 10 SRO JOB PERFORMANCE MEASURE Task:
Classify the Event per the REP (Degraded Core With Possible Loss of Coolable Geometry and Likely Cntmt Failure)
Task#:
3440030302 Task Standard:
The Examinee classifies the event as a GENERAL EMERGENCY based on LOSS of any two barriers and Potential LOSS of third barrier (1.1.1.L AND 1.2.2.L or 1.2.L P AND 1.3.1.P or 1.3.2.P) and the Examinee completes a TVA Initial Notification for Site Area Emergency form with no errors on items noted with an.
Time Critical Task:
YES:
X NO:
KIA ReferencelRatings:
2.4.41. (2.9/4.6)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
/
Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
19 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC ADMIN SRO A.4 Page 3 of 10 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
2.
Any UNSAT requires comments.
Tools/EquipmentlProcedures Needed:
1.
EPIP-1, Emergency Plan Classification Matrix 2.
EPIP-5, General Emergency 3.
A clock must be available in classroom that all examinees and evaluator can see
References:
1.
EPIP 2.
EPIP-5 L
Reference Title Rev No.
L 1
Emergency Plan Initiating Conditions Matrix 46 I
General Emergency 39
Read to the examinee:
1201 NRC ADMIN SRO A.4 Page 4 of 10 DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
1.
Unit 1 is in MODE 3 following a plant event 2.
Both Containment Spray pumps have failed.
3.
All other required equipment started and is operating as designed 4.
The TSC has not been manned.
5.
The following data was observed Parameter Indication Source Range Counts 10 cps and decreasing RCS Pressure 1000 psig Pressurizer Level Off scale low Core exit thermocouples All 710° F and increasing slowly RCS Subcooling 10 °F superheat RVLIS Lower range 38% and decreasing Highest Steam Generator 22%
Level RCS Cold Leg Temp 245° F and decreasing slowly Containment Pressure 14 psig and decreasing slowly Wind speed at 46 meters 5 mph Wind direction at 46 meters 235 degrees INITIATING CUES:
1.
Using the data provided and the applicable procedure (s) classify the event.
2.
Raise your hand when classification is complete.
3.
When classification is complete, request from the examiner the correct TVA Initial Classification form, then complete the required form.
4.
Determine what, if any, Protective Action Recommendations are required.
5.
Raise your hand when you have completed the notification form.
6.
The is (are) an element (s) of this task that is (are) time critical.
1201 NRC ADMIN SRO A.4 Page 5 of 10 Start Time Obtain a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION STEP 1
MATRIX.
SAT UNSAT d
d Examinee obtains a copy of EPIP-1, EMERGENCY PLAN an ar CLASSIFICATION MATRIX.
Cue Provide a copy of EPIP-1, EMERGENCY PLAN CLASSIFICATION
MATRIX.
Comment Examiner Annotate start time when the examinee acknowledges the task is Note understood. Start time____________
INSTRUCTIONS Note:
A condition is considered to be MET if, in the judgment of the SED, the Procedure condition will be MET IMMINENTLY :(ie:
with two hours). The classification shall be made as soon as this determination is made.
STEP 2
1 In the matrix to the left, REVIEW the SAT initiating conditions in all three barrier columns and circle the conditions that UNSAT are MET.
2.
In each of the three barrier columns, IDENTIFY if any Loss or Potential Loss INITIATING CONDITIONS have been MET.
Examinee reviews the EMERGENCY PLAN CLASSIFICATION MATRIX Standard.
and identifies initiating conditions provided in the initial conditions.
Comment
1201 NRC ADMIN SROA.4 Page 6 of 10 EXAMINER This is a critical step because of the requirement to arrive at the NOTE:
correct classification within 15 minutes.
EXAMINER NOTE:
Annotate the stop time for the event classification here.
EXAMINER Examinee conUnues with the task to complete the State Notification NOTE:
Form using EPIP-5, GENERAL EMERGENCY. The critical time element continues.
EXAMINER NOTE:
Annotate the start time for the State Notification here.
EXAMINER NOTE:
The start data is provided to the examinee on the JPM briefing sheet.
EXAMINER NOTE:
Examinee transitions to EPIP-5, GENERAL EMERGENCY STEP 3
3.
COMPARE the number of barrier Losses and Potential losses to the criteria below and make the appropriate declaration.
Emergency Class Criteria General Emeruencv LOSS of any two barriers and Potential LOSS of third barrier SAT UNSAT Critical Step Standard:
LOSS DfthRC$iiiør I.Z2J (RCS leak resuis in, IRL.O$S &ThejCSJBarriert2.4 L (VALID RVLIS I LLI6371 withoRcPwnnin9)...
Comment J L ient spray.)
1201 NRC ADMIN SRO A.4 Page 7 of 10 Obtain a copy of EPIP-5, GENERAL EMERGENCY STEP 4
SAT UNSAT Standard:
Examinee obtains a copy of EPIP-5, GENERAL EMERGENCY.
Cue Provide a copy of EPIP-5, GENERAL EMERGENCY Comment NOTE:
IF there are personnel injuries, THEN IMPLEMENT EPIP-lO, Medical Emergency
Response
Procedure Note NOTE IF there are immathate hazards to plant personnel THEN consider immediately implementing EPlP-Personnel Accountability and Evacuation in parallel with this procedure 3.1 GENERAL EMERGENCY DECLARATION BY THE MAIN CONTROL ROOM STEP 5
SAT Upon classifying events as a GENERAL EMERGENCC, the SMISED shall:
UNSAT
[ij IF TSC is OPERATIONAL. (SED transferred to TSC), THEN GO TO Section 3.2.
El
[2j RECORD time of Declaration Time
[3]
ACTIVATE Emergency Paging System (EPS) as follows.
[a]
IF EPS has already been activated, THEN GO TO Step 4.
El
[b]
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.
El
[C]
IF ongoing events makes site access dangerous to the life and health of emergency responders, THEN SELECT STAGING AREA button on the EPS terminal INSTEAD of the EMERGENCY button.
El
[d]
ACTIVATE EPS using touch screen terminal. IF EPS fails to activate, THEN continue with step 4.
El Standard:
The examinee addresses steps 3.1.1 through 3.1.3 Comment
1201 NRC ADMIN SRO A.4 Page 8 of 10 UNSAT Examiner Note:
Appendix B PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer is NO.
Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.
GENERAL EMERGENCY DECLARED Note: Unknown conditions are assumed less than listed conditions.
Measured TABLE I Protective Action Guides (PAG)
Projected 3.9 E-6 micro Cifcc of Iodine 131 or I REM per hour External Dose I REM TEDE or 5 REM Thyroid CDE
1201 NRC ADMIN SROA.4 Page 9 of 10 1 3.1 SITE AREA EMERGENCY DECLARATION BY THE MAIN CONTROL RO0M STEP 7
[5]
COMPLETE Appendix C (TVA Initial Notification for General Emergency).
D, JIIIUIr WfI.W UNSAT it 4
harIiee cornps an Aptendk iL TVA IniflalNotifio rite Critical Step Standard:
aEnergency With no esnitemsnoted with an
- ontheaii4 key with 14 minutes ofevent declaration EXAMINER This is a critical step because of the requirement to provide notification NOTE:
of an event to the state within 15 minutes.
Examiner Note:
Annotate the stop time for the initiation of state notification._______
Cornrnent Terminating The task is complete when the Examinee completes the TVA STOP Cue:
Initial Notification for General Emergency.
Stop Time
JPM BRIEFING SHEET 1201 NRC ADMIN SROA.4 Page 10 of 10 DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
1.
Unit I is in MODE 3 following a plant event 2.
Both Containment Spray pumps have failed.
3.
All other required equipment started and is operating as designed 4.
The TSC has not been manned.
5.
The following data was observed Parameter Indication Source Range Counts 10 cps and decreasing RCS Pressure 1000 psig Pressurizer Level Off scale low Core exit thermocouples All 7100 F and increasing slowly RCS Subcooling 10°Fsuperheat RVLIS Lower range 38% and decreasing Highest Steam Generator 22%
Level RCS Cold Leg Temp 245° F and decreasing slowly Containment Pressure 14 psig and decreasing slowly Wind speed at 46 meters 5 mph Wind direction at 46 meters 235 degrees INITIATING CUES:
1.
Using the data provided and the applicable procedure (s) classify the event.
2.
Raise your hand when classification is complete.
3.
When classification is complete, request from the examiner the correct WA Initial Classification form, then complete the required form.
4.
Determine what, if any, Protective Action Recommendations are required.
5.
Raise your hand when you have completed the notification form.
6.
The is an (are) element (5) of this task that is (are) time critical.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
SEQUOYAH GENERAL EMERGENCY EPIP-5 1101 4agt Q Al1b% A.q Appendix C TVA INITIAL NOTIFICATION OF GENERAL EMERGENCY Sequoyah has declared a GENERAL EMERGENCY Unit 2 ElBoth Unit 1 and Unit 2 j
(_
A L.2 L2-t L
t.J)L..l fi I
ftv1inor releases within federally approved limits Minor releases within federally approved limits4 Releases above federally approd limits 1
Releases above federally approvelimits 1
Release information not known NRelease information not known 1ch Specs)
(
1 Thch Specs)
Time: tt1 4
!dTh Date:
(&ci /
- 7. The Meteorological Conditions are:
(Use 46 meter data from the Met Tower)
LI Recommendation I R
R X Recommendation 2 EVACUATE LISTED SECTORS (2 mile Radius E
WIND FROM E UATUSTEDSECTORS (2 4
jle and 10 miles downwind)
DEGREES Radius and 5 mile downwind)
SHELTER remainder of 10 mile EPZ
DIRECTION
SHELTER remainder of 10 mile EPZ CONSIDERissuanceofPOTASSIUM IODlDEin CONSIDERissuanceofPOTASSIUM accordance with the State Plan.
ar 2
IODIDE in accordance with the State Plan.
A-i, B-i, C-i, D-1, C-2, 7, -8, D-2,-3, -5, -6
12-49 A-i, B-i, C-i, D-i, C-2, D-2 A-i, B-i, C-i, D-i, D-2,-3,-4,-5,-6
50-70 A-i, B-i, C-i, D-i, D-2 A-lB-iC-iD-i, A-3,-4, D-2,-3,-4,-5
71 -112
A-lB-iC-iD-i, A-3,D-2 A-lB-iC-iD-i, A-2,-3,-4,-5,-6, D-4
113-146
A-lB-iC-iD-i, A-2,A-3, A-i, B-i, C-i, D-i, A-2, -3,-4,-5,-6, B-2 147-173 A-i, B-i, C-i, D-i, A-2, A-3, 8-2 A-lB-iC-iD-i, A-2,-5,-6, B-2,-3,-4
174-2i4
A-lB-iC-ID-i, A-2.B-2, A-lB-iC-iD-i, B-2,-3,-4,-5-6,-7,-8
215-258 A-lB-iC-iD-i, B-2,B-5, A-lB-iC-iD-i, 8-2-3-5-6-7,-B, C-2,-3,-4,-5,-6
259-331 B4G-1D-I, B-22-5C-2 A-i,B-i,C-i,D-i, 8-5, C-2,-3,-4,-5,-6,-7,-8 332-li A-lB-iC-iD-i, 8-5,C-2 El Recommendation 3 SHELTER all sectors.
CONSIDER issuance of Potassium Iodide in accordance with the State Plan.
- 9. Please repeat back the information you have received to ensure accuracy.
El
- 10. When completed, FAX this information to the ODS or TEMA as required by Sections 3.1 or 3.2. El PAGE 15 of 16 REVISION 39 a
1.
This isa Drill
- 2. This is affecting Unit
- 3. EAL Designator(s):
1 1
- 4. Brief Description of the Event:
LI This is an Actual Event
- Repeat - This is an Actual Event
- 5. Radiological Conditions:
Airhnrnc Rlscc OffRit (Check one under both Airborne and Liquid column.)
Liciuld Releases Offsite
- 6. Event Declared:
Wind Direction is FROM:
Wind Speed:
m.p.h
- 8. Provide Protective Action Recommendation:
(Check eith1 or2or3.)
..L.
FORWARD COMPLETED PROCEDURE TO EMERGENCY PREPAREDNESS MANAGER
I SEQUOYAH EMERGENCY PLAN CLASSIFICATION MATRIX EPIP-1 1
- 2. Primary Coolant Activity Level
Potential LOSS RCS sample activity is Not Applicable greater than 300 pCi/gm dose equivalent 1131
-OR-
- 3. Incore Thermocouple Hi Quad Average Potential LOSS Greater than 1200 °F on Greater than or equal to Xl-94-101 or 102 700 °F on Xl-94-101 or (EXOSENSOR) 102 (EXOSENSOR)
- OR
Potential LOSS Not Applicable VALID RVLIS level
<42% on Ll-68-368 or Ll-68-371 with no RCP running
-OR-
- 5. Containment Radiation Monitor Potential LOSS VALID reading of Not Applicable greater than:
2.5E+02 R/hr on RM-90-271A and -272A OR 1.5E+02 R/hr on RM-90-273A and 2.1E+02 R/hron RM-90-274A (see instruction note 4)
-OR-
- 6. SED Judgment Any condition that, in the judgment of the SM or SED, indicates loss or potential loss of the Fuel Clad Barrier comparable to the conditions listed above.
OR Heat Sink RED (FR-Hi) and RHR Shutdown Coolina not in service
-OR
- 2. RCS Leakae I LOCA Potential LOSS RCS leak results in Non Isolatable RCS leak subcooling <40 °F as exceeding the capacity indicated on Xl-94-101 of one charging pump in or 102 (EXOSENSOR).
the normal charging alignment OR RCS leakage results in entry into E-1
-OR-
- 3. Steam Generator Tube Rupture I*
Potential LOSS SGTR that results in a Not Applicable Safety Injection actuation OR Entry into E-3
-OR I 4.
Potential LOSS VAUD RVLIS level Not Applicable
<42% on Ll-68-368 or Ll-68-371 with no RCP running
-OR-
- 5. SED Judgment Any condition that, in the judgment of the SM or SED, indicates loss or potential loss of the RCS Barrier comparable to the conditions listed above.
- 1. Critical Safety Function Status Core Coaling Red FR-C.1 Potential LOSS 1 2 RCS Barrier I 1. Critical Safety Function Status Not Applicable Core Cooling Orange (FR-C.2)
OR Heat Sink RED (FR-Hi) and RHR Shutdown Coolinci not in service Potential LOSS OR Pressurized Thermal Shock Red (FR-P.i)
Page 9 of 47 Revision 46
I SEQUOYAH EMERGENCY PLAN CLASSIFICATION MATRIX EPIP-1 tLaUQAS Actions of FR-C.1 (Red Path) are INEFFECTIVE (i.e.: core TCs trendina uo
-OR-
- 2. Containment Pressure I H rdrogen Potential LOSS Rapid unexplained pressure Containment Hydrogen decrease following initial increases to >4% by volume on increase on PDI-30-44 or 45 H21-43-200 or 210 OR irQRwv Containment pressure or sump Pressure >2 8 PSIG (Phase B) level not increasing on LI 63 ith < one full train of 178 and 179 with a LOCA in aprnepry J
progress
-OR-
- 3. Containment Isolation Status i[
Potential LOSS Containment isolation, when Not Applicable required is incomplete and a
- .e path to the environment
-OR-
- 4. Containment Bypass
- I*.---
Potential LOSS RUPTURED SIG that is also Unexpected VALID increase in faulted outside containment (E2 area or ventilation RAD and E3) monitors adjacent to OR containment (with LOCA in
>4 hour secondary side release progress).
outside containment from a SIG with a S/G tube leak >T/S limits (AOP R.01 App A)
-OR-
- 5. Si nificant Radiation in Containment Potential LOSS Not Applicable VALID reading of greater than:
5.8E+03 R/hr on RM-90-271A and RM-90-272A OR 3.4E+03 R/hr on RM-90-273A and 4.9E+03 RIhr on RM-90-274A (see instruction note 4)
-OR
- 6. SED Judgment Any condition that, in the judgment of the SM or SED, indicates loss or potential loss of the Containment Barrier comparable to the conditions listed above.
1.
In the matrix to the left, REVIEW the initiating conditions in all three barrier columns and circle the conditions that are MET.
2.
In each of the three barrier columns, IDENTIFY if any Loss or Potential Loss INITIATING CONDITIONS have been MET.
3.
COMPARE the number of barrier Losses and Potential losses to the criteria below and make the appropriate declaration.
4.
Containment Radiation Monitors are temperature sensitive and can be affected by temperature-induced currents. These monitors should be used for trending only until containment temperature has been stable for approximately 5 minutes after a Steam Line Break or LOCA.
Note:
MONITOR the respective status tree criteria if a CSF is listed as an INITIATING CONDITION.
1 3 Containment Barrier
- 1. Critical Safety Function Status Not Applicable Containment Red (FR-Z.1)
INSTRUCTIONS Note:
A condition is considered to be MET if, in the judgment of the SED, the condition will be MET IMMINENTLY (i.e.:
with two hours). The classification shall be made as soon as this determination is made.
Emergency CIassT General Emergency LOSS of any two barriers Potential LOSS of third barrier Site Area Emergency LOSS or Potential LOSS of any two barriers Alert Any LOSS or Potential LOSS of Fuel Clad barrier OR Any LOSS or Potential LOSS of RCS barrier Unusual Event LOSS or Potential LOSS of Containment barrier Page 10 of 47 Revision 46
SEQUOYAH GENERAL EMERGENCY EPIP5 Appendix B PROTECTIVE ACTION RECOMMENDATIONS Note 1:
If conditions are unknown utilizing the flowchart, then answer is NO.
Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.
/ Is there a
/short term controlled
/
release whereas near
(
plant areas cannot be N
evacuated before /
N.
plume arrival?
/7 (see Note 2)
YES SHELTER remainder of 10 mile EPZ TABLE I Protective Action Guides (PAG)
TYPE LIMIT Measured 3.9 E-6 micro Ci!cc of Iodine 131 or 1 REM per hour External Dose Projected 1 REM TEDE or 5 REM Thyroid ODE PAGE 14 of 16 Note: Unknown conditions are assumed less than listed conditions.
REVISION 39
)
)NTINUE ASSESSMENT Modify protective actions based on available plant and field monitoring information.
Locate and evaluate localized hot spots.
Measured Dose greater RECOMMENDATION 3 SHELTER 10 mile EPZ YES I
RECOMMENDATION I EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ I
EVACUATE 2 miles radius and 5 miles downwind AND FORWARD COMPLETED PROCEDURE TO EMERGENCY PREPAREDNESS MANAGER
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC RO ADMIN A.1.a
1201 NRC ROADMINA.1.a Page 2 of 7 SRO JOB PERFORMANCE MEASURE Task:
Determine Main Turbine Acceleration and Loading Rates Task#:
0450020101 Task Standard:
Given plant data during a plant startup, the examinee will determine the following during a Main Turbine startup using TI-28, Plant Curve Book.
1.
Determine the minimum allowable period for turbine roll-up from turning gear speed to synchronous speed of 25 (22.5 to 27.5) minutes.
2.
Determine the maximum ACCELERATION RATE for turbine roll 72 (65.5 to 80) rpm/mm.
3.
Determine time to hold at 5% turbine load of 30 (25 to 35) minutes.
Time Critical Task:
YES:
NO:
X KIA Reference/Ratings:
2.1.25 (3.9/4.2)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
I Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
17 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC ROADMINA.1.a Page 3 of 7 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
Tools/EquipmentlProcedures Needed:
1.
0-GO-4 Power Ascension From Less than 5% Reactor Power to 30% Reactor Power, section 5.3 step 31 (page 39) 2.
Tl-28, Curve Book Figure 6 3.
Calculator
References:
Reference Title Rev No.
1.
0-GO-4 Power Ascension From Less than 5% Reactor 75 Power to 30% Reactor Power 2.
Tl-28, Figure 6 Curve Book 0244 Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1.
A Plant Startup is in progress in accordance with 0-GO-4, Power Ascension from Less than 5%
Reactor Power to 30% Reactor Power.
2.
The crew is preparing to roll the turbine.
3.
Turbine Impulse Metal Temperature on 1-TR-47-1 Pt. 1 indicates 150 degrees F.
INITIATING CUES:
1.
0-GO-4, section 5.3, Turbine Roll, step 31 you have been directed to determine the following:
a)
Determine the minimum allowable period for turbine roll-up from turning gear speed to synchronous speed.
b)
Determine the maximum ACCELERATION RATE for turbine roll.
2.
Then from 0-GO-4, section 5.4, Placing Main Generator In Service, step 38, you have been directed to time to hold at 5% turbine load.
3.
Record your answers on the JPM briefing sheet.
4.
Notify the Examiner when you are complete.
Obtain a copy of 0-GO-4 Power Ascension From Less than 5% Reactor STEP 1
Power to 30% Reactor Power, section 5.3 step 31 (page 39), section 5.4 SAT step 39 (page 64) and Tl-28, Curve Book Figure 6.
U N SAT Copy of 0-GO-4 Power Ascension From Less than 5% Reactor Power to Standard:
30% Reactor Power, section 5.3 step 31 (page 39), section 5.4 step 39 (page 64) and Tl-28, Curve Book Figure 6 are obtained.
Provide a copy of 0-GO-4 Power Ascension From Less than 5% Reactor Cue Power to 30% Reactor Power, section 5.3 step 31 (page 39), section 5.4 step 39 (page 64) and TI-28, Curve Book Figure 6.
Comment 5.3 Turbine Roll (continued>
STEP 2
[31]
DETERMINE the maximum ACCELERATION RATE for turbine roll using SAT recorder 1,2-TR-47-1 (Impulse Chamber Metal Temp, pt. #1) and Tl-28 Figure 6 Recommended Start-up and Loading Times.
by performing the U NSAT following:
[31.1]
RECORD the first stage metal temperature from 1,2-TR-47-1 (Impulse Chamber Metal Temp.. pt. #1).
Examinee the records first stage metal temperature from 1-TR-47-1 Standard:
(Impulse Chamber Metal Temp., pt. #1) of 150 deg F from the initial conditions.
Comment 1201 NRC RO ADMIN A.1.a Page 4 of 7 Start Time NOTE The minimum allowable period for turbine roll-up from turning gear speed to synchronous speed is determined by reading the first stage metal temperature then plotting a vertical line on Tl-28 figure 6 at that temperature. The allowable minimum time is read in minutes on the vertical axis where the vertical line crosses the bottom curve of figure 6. The initial first stage metal temperature is also used to determine the holding time at minimum load and for raising load to full capacity.
1201 NRC RO ADMIN A.1.a Page 5 of 7
/.4 4, 44..,
4 4/rt/4.4 4
4 5.3 Turbine Roll (continued)
STEP
[31]
DETERMINE the maximum ACCELERATION RATE for turbine roll using SAT recorder 1,2-TR-47-1 (Impulse Chamber Metal Temp., pt. #1) and Tl-28 Figure 6 Recommended Start-up and Loading Times.
by performing the U N SAT following:
r Critical Step
. 4/i - /4.4 4
/4 4/
/...
/
,. j. /
4/
4
[31.2]
DETERMINE the minimum allowable period for turbine roll-up from turning gear speed to synchronous speed USING Tl-28, Figure 6.
D 444ç-.4/4/
aiee4etemiries the piJrmum allowable pejod for tubjnej4-up Standard:
fromfuming gearpeed to *yric,hronous speed of 25 2Z5to 27,3 9l1rutes.
Comment 5.3 Turbine Roll (continued)
STEP 4
[31]
DETERMINE the maximum ACCELERATION RATE for turbine roll using SAT recorder 1,2-TR-47-1 (Impulse Chamber Metal Temp., pt. #1) and Tl-28 Figure 6 Recommended Start-up and Loading Times.
by performing the U NSAT following:
[31.3]
RECORD the time determined from Figure A.15 in the equation below.
Standard:
Examinee records the time obtained in JPM step 3.
Comment
/
- ,4444/4
/4
//%
/4
//
/
4.
4 5.3 Turbine Roll (continued)
STEP 5
[31]
DETERMINE the maximum ACCELERATION RATE for turbine roll using SAT recorder 1,2-TR-47-1 (Impulse Chamber Metal Temp., pt. #1) and Tl-28 Figure 6 Recommended Start-up and Loading Times.
by performing the UNSAT following:
/49I r
Critical Step
[31.4]
CALCULATE the Maximum Acceleration Rate from the equation below.
/
4/
1800 RPM divided by
=
Mm Sync Speed Minimum allowable Maximum Acceleration period for turbine rollup Rate
-U 44//
_r_,r, Standard lCU1atS The Maximum Acqeletation aateforturbi1etbllf 72 Comment
1201 NRC RO ADMIN A.1.a Page 6 of 7 5.4 PIacng Maui Generator In Service (continued)
STEP 6
[38]
DETERMINE time to hold at 5% turbine load on Tl-28 figure 6 and record minutes.
UNSAT minutes Standard Eedérmities the Urtifo hold at5°hturbine1oafromfl4 Critical Step fIgurØf30 2&to35) minutes, Comment Terminating The JPM is complete when the Examinee returns the JPM STOP Cue:
briefing sheet to the Examiner.
Stop Time
1201 NRC RO ADMIN A.1.a Page 7 of 7 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
1.
A Plant Startup is in progress in accordance with 0-GO-4, Power Ascension from Less than 5%
Reactor Power to 30% Reactor Power.
2.
The crew is preparing to roll the turbine.
3.
Turbine Impulse Metal Temperature on 1-TR-47-1 Pt. I indicates 150 degrees F.
INITIATING CUES:
1.
0-GO-4, section 5.3, Turbine Roll, step 31 you have been directed to determine the following:
a)
Determine the minimum allowable period for turbine roll-up from turning gear speed to synchronous speed.
b)
Determine the maximum ACCELERATION RATE for turbine roll.
2.
Then from 0-GO-4, section 5.4, Placing Main Generator In Service, step 38, you have been directed to time to hold at 5% turbine load.
3.
Record your answers on the JPM briefing sheet.
4.
Notify the Examiner when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
Figure 6 (Page 1 of 1)
RECOMMENDED START-UP AND LOADING TIMES NUCLEAR STEAM SYSTEM UNITS
+2
[LOl NILt 1LO SQN CURVE BOOK TI-28 Rev. 0244 Page 21 of 96 cri 2
Ui Li 0
C 400 INITiAL H.P TUJNE RRST STAGE METAL TDAPEPATU
I
[101 J11L V-u AJ SQN CURVE BOOK TI-28 Rev. 0244 Page 21 of 96 c-1 2
Ui Figure 6 (Pagelofi) 1 RECOMMENDED START-UP AND LOADING TIMES NUCLEAR STEAM SYSTEM UNITS INITIAL H. R TUNE RRS STAGE METAL TD4PEPAThE CE3I-F 71 S,
9 a
400
Ui Li
-J
- ito, I
SQN CURVE BOOK TI-28 Rev. 0244 Page 21 of 96 Figure6 (Page 1 of 1)
RECOMMENDED START-UP AND LOADING TIMES NUCLEAR STEAM SYSTEM UNITS 0
2c0 400 1NIT1AL H. P 1UNE F1RST STAGE MTL TAPATUR D-F
SQN POWER ASCENSION FROM LESS 0-GO-4 Unit I & 2 THAN 5% REACTOR POWER TO 30%
Rev. 0075 REACTOR POWER Page 39 of III STARTUP_______
Unit I
5.3 Turbine Roll (continued)
[
1]
DETERMINE the maximum ACCELERATION RATE for turbine roll using recorder 1,2-TR-47-1 (Impulse Chamber Metal Temp., pt. #1) and TI-28 Figure 6 Recommended Start-up and Loading Times.
by performing the following:
1.1]
RECORD the first stage metal temperature from 1,2-TR-47-1 (Impulse Chamber Metal Temp., pt. #1).
NOTE The minimum allowable period for turbine roll-up from turning gear speed to synchronous speed is determined by reading the first stage metal temperature then plotting a vertical line on TI-28 figure 6 at that temperature. The allowable minimum time is read in minutes on the vertical axis where the vertical line crosses the bottom curve of figure 6. The initial first stage metal temperature is also used to determine the holding time at minimum load and for raising load to full capacity.
[31.2]
ETERMINE the minimum allowable period for turbine roll-up from turning gear speed to synchronous speed USING Tl-28, Figure 6.
[31.3]
RECORD the time determined from Figure A.15 in the equation below.
[31.4]
CALCULATE the Maximum Acceleration Rate from the equation below.
1800 RPM divided by Mm Sync Speed Minimum allowable Maximum Acceleration period for turbine rollup Rate
SQN POWER ASCENSION FROM LESS 0-GO-4 Unit I & 2 THAN 5% REACTOR POWER TO 30%
Rev. 0075 REACTOR POWER Page 64 of III STARTUP_______
Unit I
Date 5.4 Placing Main Generator In Service (continued)
[38]
TERMINE time to hold at 5% turbine load on TI-28 figure 6 and record minutes.
minutes NOTES 1)
After generator is synchronized, governor valve (GV) hunting at low loads (2-3%)
could result in small load swings.
If small load swings occur, then load should be raised to further open GV5 and to obtain more stable load point.
2)
Step 5.4[39.2] contains contingency sub-steps if the Auto Sync-Check relay fails to operate. Approval from Plant Management is required to ensure conservative decision making prior to taking manual actions to close the generator breakers.
3)
Steps 5.4[39], 5.4[40], and 5.4[41] should be performed immediately after generator breaker closure.
[39]
CLOSE applicable generator PCB by performing the following:
[39.1]
WHEN synchroscope reaches 5 minutes before the 12:00 position, THEN CLOSE applicable generator breaker with IHS-57-241 or IHS-57-261.
Initials Time Date
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SEQUOYAH NUCLEAR PLANT RO ADMIN A.ib
1201 NRC RO ADMIN A.1.b Page 2 of 10 SRO JOB PERFORMANCE MEASURE Task:
Calculate Manual Makeup to the Volume Control Tank Task#:
0040250101 Task Standard:
Examinee calculates a manual make up to the VCT to raise level 10% of 173.03 (172.99-173.27) gallons water and 26.97 (26.73-27.01) gallons of boric acid.
Time Critical Task:
YES:
NO:
X KIA ReferencelRatings:
2.1.37 (4.6)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
I Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
22 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC ROADMINA.1.b Page 3 of 10 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
1.
Calculator 2.
0-SO-62-7, Boron Concentration Control.
3.
Tl-44, Boron Tables.
References:
Reference Title Rev No.
1.
0-SO-62-7 Boron Concentration Control 60 2.
Tl-44 Boron Tables 12 Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1.
Unit 2 is in MODE 1, 100%.
2.
Reactor coolant system boron concentration is 967 ppm.
3.
BAT boron concentration is 6820 ppm.
4.
B-b depletion value is 40 ppm 5.
REACTF software is not available for boron calculations.
INITIATING CUES:
1.
You are a Unit 2 RO and are to perform a calculation for a manual blended makeup to the Volume Control Tank level from 41% to 51 % using 0-SO-62-7, Boron Concentration Control appendix C.
2.
Notify the Examiner when the calculation is completed.
1201 NRC ROADMINA.1.b Page 4 of 10 Start Time Obtain a copy of 0-SO-62-7 BORON CONCENTRATION CONTROL and STEP 1
TI-44 BORON TABLES SAT UNSAT Examinee obtains a copy of 0-SO-62-7 BORON CONCENTRATION Standard:
CONTROL and Tl-44 BORON TABLES.
Provide a copy of 0-SO-62-7 BORON CONCENTRATION CONTROL Cue Appendix C and TI-44 BORON TABLES.
Comment STEP 2
[1]
OBTAIN Current RCS Boric Acid Concentration.
SAT UNSAT Examinee obtains the RCS Boric Acid Concentration of 967 ppm from the Standard:
initial conditions Comment STEP 3
[2]
OBTAIN Current BAT Boric Acid Concentration SAT UNSAT Standard:
Examinee obtains the BAT Boric Acid Concentration of 6820 ppm from the initial conditions Comment
1201 NRC RO ADMIN A.l.b Page 5 of 10
[4]
CALCULATE BAT Boric Acid Concentration Ratio (BACR): 6820 ppm Step [2] ppm =
Examinee calculates BAT Boric Acid Concentration Ratio to be 1.0.
STEP 4
[3]
OBTAIN B-10 depletion value from Rx Eng Information page SAT U N SAT Standard Examinee obtains the B-10 depletion value of 40 ppm from the initial conditions Comment Procedure Result in Step 141 should be rounded to second decimal place.
STEP 5
SAT U N SAT Critical Step Standard:
Comment Examiner Step 2 BAT Boric Acid Concentration of 6820 ppm was from the initial Note:
conditions.
1201 NRC ROADMINA.I.b Page 6 of 10 STEP 6
151 GALGULATE 8-10 Gorreoted boroh concentr3tlqn SAT UNSAT S11)
STEP1 B40 orrecteçl boion Critical Step
/
Standard:
Eaminee calculates B-I 0 corrected boron concentration obe927 Comment Examiner Step I RCS Boric Acid Concentration of 967 ppm is from the initial Note:
conditions Exm,er Step 2 B-i 0 depletion value of 40 ppm from the initial conditions STEP 7
[6]
DETERMINE Corrected rc Acid 9ow Rate and Controller SAT Setting using apprppriate Table from T1-44 Appendix C.
UNSAT a
C o ected Boric Acid Flow Rate T
Critical Step St d
d Examinee calculates the Corrected Boric Acid Flow Rate to be 10.91 an ar (10.to 10.93)
Comment Examiner The Corrected Boric Acid Flow Rate of was determined by calculating the Note:
difference of two points Tl-44 BORON TABLES Appendix C Page 3 of 10.
1201 NRC ROADMINA.1.b Page 7 of 10 t63 DETERMINE Gorrecjed Boric Acid Flow Rate and Cotrófler Selting using appropriate Table from Tl-44 Appnd&C Ib RECORD Qorecte4 Boric Acid Controller 44Appedix C Table 2 St d
d mIn Clcu3ts fhq Corrected Boric Acid Cotro1ler Setg ope.
an ar.
Comment Examiner The Corrected Boric Acid Flow Rate of was determined by calculating the Note:
difference of two points Tl-44 BORON TABLES Appendix C Page 8 of 10.
STEP 8
SAT U NSAT Critical Step
1201 NRC ROADMINA.1.b Page 8 of 10 The desired value of 51% and the actual value of 41% were given in the initial conditions.
STEP 10
[8]
[(Desired VCT
(Actual X
20 GAupercent
=
ToI level) level)
Standard:
xjntne ca1ultes the volume added tQ be addedto gat Comment SAT UNSAT Critical Step Examiner Note:
STEP 11 GPM 1
70 GPM GPM SAT 19 X I. (BACR from step 4)) +
=
Corrected Boric Acid Flow (Primary H 2
0)
Total Flow Rate Rate(Step[6]fa])
UNSAT Critical Step Standard:
ecteste Comment Examiner The Corrected Boric Acid Flow Rate calculated in procedure step 6a was Note:
10.91 (10.8-10.93). The BACR calculated in procedure step 4 was 1.0.
STEP 12
(__________
GPM GALS SAT
[101 GPM X BACR from step 4) ÷ Total Flow Rate X
Total Volume
=
CorrectedBonc AcidFiow (Obtdfr 1191 (Obtainedfromstep[81 UNSAT Rate (Step 161[a])
GALS Critical Step BORIC ACID iNTEGRATOR SETTING yr-V Standard cv r1.
Comment
1201 NRC ROADMINA.1.b Page 9 of 10 STEP 13 70 6PM GPM GALS
GALS SAT
[111 (Pbmery H 2
0)
TotaiFlow Rate X
Total Volume
PRIMARY WATER INTEGRATOR Obteined from step [9]
Obtainedfrom step SEllING U NSAT Critical Step Standard 1atthmi Water 1ntegrtor settIng ffT2.99-I7&27)
Comment Examiner The total flow rate calculated in procedure step 9 was 80.89. The total Note:
volume calculated in procedure step 8 was 200 gallons.
Calculation check: Step [10] results ÷ Step [11] results should Step [8]
STEP 14 results SAT UNSAT Standard:
Examinee verifies the calculation result Comment Terminating The JPM is complete when the Examinee returns the JPM STOP Cue:
briefing sheet to the examiner.
Stop Time
1201 NRC ROADMINA.1.b Page 10 of 10 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
1.
Unit 2 is in MODE 1,100%.
2.
Reactor coolant system boron concentration is 967 ppm.
3.
BAT boron concentration is 6820 ppm.
4.
B-b depletion value is 40 ppm 5.
REACTF software is not available for boron calculations.
INITIATING CUES:
1.
You are a Unit 2 RO and are to perform a calculation for a manual blended makeup to the Volume Control Tank level from 41% to 51% using 0-SO-62-7, Boron Concentration Control appendix C.
2.
Notify the Examiner when the calculation is complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
[1]
[2]
[3]
NOTE
[4]
[5]
[6]
APPENDIX C Page lof2 CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)
OBTAIN Current RCS Boric Acid Concentration 9 7 PPM OBTAIN Current BAT Boric Acid Concentration OBTAIN B-10 depletion value from Rx Eng Information page 14 PPM Result in Step [4] should be rounded to second decimal place.
CALCULATE BAT Boric Acid Concentration Ratio (BACR) 6820 ppm Step [2] ppm = I CALCULATE B-10 corrected boron concentration
Ia g 17 STEP [1]
STEP [3]
fdoron DETERMINE Corrected Boric Acid Flow Rate and Controller Setting using appropriate Table from Tl-44 Appendix C.
[a]
RECORD Corrected Boric Acid Flow Rate from TI-44 Appendix C Table 1.
/,...
GPM (/0q_f9
- M
[b]
RECORD Corrected Boric Acid Controller Setting from Tl-44 Appendix C Table 2 I
21 L I j
0/
[
0 X BACR from step 4
=
2 J3 I (Boric Acid Controller Setting)
Corrected Boric Acid ControllerSetting(Step[6][b])
(21.4 2
[7]
CONTINUED ON NEXT PAGE
fbi ILH2L 12o A.l.b SQk 0-SO-62-7 1 2 BORON CONCENTRATION CONTROL Rev. 60 Page 162 of 201 APPENDIX C Page 2 of 2
[8]
[
5!
X 2OGAL/percent
= 2oo GALS (Desired VCT (Actual VCT level) level)
(io IA GPM I
70 GPM GPM
[9]
1 X
(BACRfromstep4) +
2 Corrected Boric Acid Flow (Primary H 0)
Total Flow Rate Rate (Step [6][a])
-o.q3)
(_________
GPM GALS
[10]
10.?!
GPM X BACR from step 4)
Total Flow Rate X
Total Volume
=
Corrected Boric Acid Flow (Obtained from step [9]
(Obtained Rate (Step [6j[a])
2.0 L1/257 BORIC ACID INTEGRATOR (o.- s A?)
173 srlG GPM too GALS 70 GPM X
J13.o3
[11]
(Primary H 2
0)
Total Flow Rate Total Volume
PRIMARY Ri TEGRATOR Obtained from step [9]
Obtained from step [8]
SETTING Calculation check:
Step [101 results
+ Step [11] results should
= Step [8] results
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC RO ADMIN A.2
1201 NRC RO Admin JPM A.2 Page 2 of 15 SRO JOB PERFORMANCE MEASURE Task:
Perform RCS Leakage Calculation (0-Sl-OPS-068-1 37.0)
Task#:
0020010201 Task Standard:
The examinee performs a manual RCS Leakrate calculation using 0-SI-OPS-068-1 37.0 Appendix D obtains a result of 1.07 gpm, and discovers the acceptance criteria are not met.
Time Critical Task:
YES:
NO:
X KIA Reference!Ratings:
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
/
Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
20 minutes Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC RO Admin JPM A.2 Page 3 of 15 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
1.
0-Sl-OPS-068-137.0 Reactor Coolant System Water Inventory 2.
Chronological Test Log 3.
Calculator
References:
Reference Title Rev No.
1.
0-Sl-OPS-068-1 37.0 Reactor Coolant System Water Inventory 26 2.
Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1201 NRC RD Admin JPM A.2 Page 4 of 15 1.
Unit-2 is in MODEl.
2.
The performance of 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory is due.
3.
ICS is not available.
4.
Data for the 0-Sl-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix C is as follows:
5.
Parameter Final Initial VCT Level 42.9 50.1 Pressurizer level 58 58 RCS Temperature 578 578 RCS Pressure 2235 2235 PRT Level 12358 12349 RCDT Level 172.2 171.8 CLA#1 Level 7692 7692 CLA#2 Level 7677 7677 CLA#3 Level 7672 7672 CLA#4 Level 7680 7680 Appendix D is complete through section 1.4 SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd 6.
0-SI-CEM-000-050.2 and 2-SI-CEM-068-1 37.5 were completed last night at 2300.
7.
Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.
8.
CCPIT/HUT leakage and other leakage is 0 gpm.
9.
Data collected for performance of this leak rate is documented in Appendix C and was collected over 120 minutes INITIATING CUES:
1.
You are the Unit 2 CR0 and have been directed to complete a manual RCS Leakage calculation using 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix D 2.
All calculations should be carried out to two decimal places.
3.
Record your answers on the Appendix D.
4.
Identify all deviations (if any) on the Chronological Test Log 5.
Notify the Examiner when you are complete.
1201 NRC RO Admin JPM A.2 Page 5 of 15 Start Time Obtain a copy of 0-Sl-OPS-068-1 37.0 Reactor Coolant System Water STEP 1
Inventory.
SAT UNSAT Standard Copy of 0-Sl-OPS-068-1 37.0 Reactor Coolant System Water Inventory, is obtained.
Cue Provide a marked up copy of copy of 0-Sl-OPS-068-1 37.0 Reactor
Coolant System Water Inventory.
Comment RCS LEAKAGE CALCULATIONS NOTE I All calculatons must be performed manually. Verification may be performed using the computer.
NOTE 2 All calculations should be carried out to two places after the decimal.
Signs must be carried through all calculations.
NOTE 3 Calculations in this Appendix may need to be performed more than once.
If multiple calculations are required, copies of this Appendix may be used.
STEP 2
Standard:
1.0 TOTAL RCS LEAKAGE 1.1 Volume Control Tank (VCT)
VCT Leakage
=
%)]x1927gal1% r Initial Level Final Level UNSAT Critical Step mm. )
Time VCT Leakage =
GPM Comment
1201 NRC RO Admin JPM A.2 Page 6 of 15 NOTE I V (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the foHowing equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
STEP 3
1.0 TOTAL RCS LEAKAGE SAT 1.2 Pressurizer {Pzr) UNIT 2 only UNSAT
[1]
CALCULATE initial PZR volume by using the following equation:
Initial PZR Vc.1=( PZRLEel 1O0oPZRLeel 02 1l*ft/i j lb
- LGlevel G
100
- 3/
Initial P7R Vc,1
+
2.02 Initial P7R Vl =
Performed By Feviewed By Standard:
The Examinee determines Initial Pressurizer Volume is 4857.55 gallons Comment
1201 NRC RO Admin JPM A.2 Page 7 of 15 NOTE I V (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
STEP 4
10 TOTALRCSLEAKAGE SAT 1.2 Pressurizer (Pzr) UNIT 2 only UNSAT
[2] CALCULATE Final PZR volume by using the following equation:
=1-2 02 g aft 3
/lb
/elevel 0,)
100 Final PZR Jol=
/
÷--!-- r°2
/lb*%level
,lb I
in
/
in Final PZR Vol =
gal Performed By Revjewed By Standard:
The Examinee determines Final Pressurizer Volume is 4857.55 gallons Comment STEP 5
1.0 TOTAL RCS LEAKAGE SAT 1.2 Pressurizer (Pzr) UNIT 2 only UNSAT
[3] CALCULATE PZR leakage rate by using the following equation:
Initial PZR Volume Final PZR Volume PZR Leakage =
tiflie PZR Leakage =
PZR Leakage =
gpm Performed By Reojewed By Standard:
The Examinee determines Pressurizer Leakage is 0 gpm.
Comment
1201 NRC RO Admin JPM A.2 Page 8 of 15 NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
STEP 6
1.0 TOTALRCSLEAKAGE SAT 1.3 Pressurizer (Pzr) UNIT I only UNSAT Standard:
The Examinee addresses the step as not applicable.
Comment NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
STEP 7
1.0 TOTALRCSLEAKAGE SAT 1.4 RCS Temperature Correction[C.1]
UNSAT A.
Initial Conditions:
RCS pressure =
+ 14.7 =
psia RCS temperature =
Specific volume (v) =
ftIlbm Density 1/v 1 =
Ibm/ft 3
B. Final Conditions:
RCS pressure =
+ 14.7 psia RCS temperature =
Specific volume (v1) ft 3
llbm Density = 1/v =
Ibm/ft 3
C. Temperature Correction:
[(
lbm/ft 3
)(
lbm!ft 3
)J* 1298.l9gal*ft 3
/lbrn Temp Corr. =
Initial Density Final Density time Temperature Correction =
Standard:
The Examinee determines RCS Temperature Correction is 0 gpm.
Comment
10 TOTAL RCS LEAKAGE I t5 Total RCS Leakage TotalRCSLeakage=(
VCT PZR Temp Corr Total RCS Leakage =
GPM Performed By Reviewed By Standard:
çgcPJee4eteiwin, Total RCS4age is 1j6gp Comment NOTE Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tanks pressure.
If negative leakage is calculated under these conditions, that tanks leakage must be set equal to zero.
t-aa,-t 2.0 IDENTIFIED LEAKAGE 2.1 Pressurizer Relief Tank (PRT)
[ 2.1 Pressurizer Relief Tank (PRT)
STEP 8
1201 NRC RO Admin JPM A.2 Page 9 of 15 SAT UNSAT Critical Step STEP 9
-a. a
-a$asa 44
[C PRT Leakage =
Final Volume SAT UNSAT Critical Step PRT Leakage =
oat Initial Volume mm A Time GPM ire Relief Tank
NOTE 1201 NRC RO Admin JPM A.2 Page 10 of 15 RCDT Level (22) may be marked N/A if conditions do NOT permit obtaining RCDT level.
mm)
\\Time SAT UNSAT RCDT Leakage GPM Performed By Reviewed By The Examinee determines Reactor Coolant Drain Tank (RCDT) is zero Standard:
gpm.
Comment NOTE I SG leak rates are obtained by 1, 2SlCEM088137.5.
0SlCEM0000502 is performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and looks at activity levels which will determine if those leak rates from the last performance of 1, 2Sl--CEM068---137.5 have rEsen.
NOTE 2 Individual steam generator leakage may be N/Ad if activity is too low to be separately identified.
STEP 11 STEP 10 2.0 IDENTIFIED LEAKAGE 2.2 Reactor Coolant Drain Tank (RCDT)
RCDT Leakage =
Final Volume Initial Volume 2.0 IDENTIFIED LEAKAGE 23 Steam Generator (SG)
Ii A. SGI Leakage=
GPD B. SG2Leakage=
GPD C. SG3Leakage=________ GPD
npn
=
1440 minfday Comment
1201 NRC RO Admin JPM A.2 Page 11 of 15 STEP 12 2.0 IDENTIFIED LEAKAGE SAT 2.3 Steam Generator (SG)
U NSAT Date/Time OSlCEM000-050.2 performed:
I Date Time Date/Time 1. 2Sl-CEMO68137.5 performed:
/
Date Time Recorded by Standard The examinee obtains the date and time of the steam generator leakage surveillance from the initiating cue.
Comment
1201 NRC RO Admn JPM A.2 Page 12 of 15 NOTE CLA leakage calculations may be marked N/A if RCS pressure is greater than 683 psig and quantification of CLA leakage is required.
STEP 13 2.0 IDENTIFIED LEAKAGE SAT 2.4 Cold Leg Accumulators (CLA)
U NSAT
[(Final gall nitial Volume gal)]
Volume j
A. CLA 1 Leakage
(
minj CLA 1 Leakage
[(Final gal 1 1 lnitial Volume gal))
Volume j
B. CLA 2 Leakage
=
Time mm)
CLA 2 Leakage =
[(Final Volume gal)
- (Initial Volume gal))
C. CLA 3 Leakage
=
I Time mm)
CLA 3 Leakage
[(Final gal 1
- 1 lnitial Volume gal)]
Volume j
D. CLA 4 Leakage
(
rime mm)
CLA 4 Leakage =
Total CLA leakage =
GPM Performed By Reiiewed By Standard:
The Examinee determines the Cold Leg Accumulators (CLA) is zero.
Cornment
1201 NRC RO Admin JPM A.2 Page 13 of 15 NOTE The following value may be marked NIA if no additional identified leakage sources (Le., Appendix A) are to be included.
STEP 14 2.G IDENTIFIED LEAKAGE SAT 2.5 Other Identified Leakage UNSAT Other identified leakage (Appendix A) =
GPM Standard:
The Exarninee determines the Other Identified Leakage is zero.
Cornment NOTE If NO CCPIT de-pressurization 1 pressurization activity has occurred during The stabilization period, CCPIT/HUT leakage may be marked NIA STEP 15 Standard:
t,ta.*t 2.0 IDENTIFIED LEAKAGE 2.6 Total Identified Leakage Total ident.fied lea.age
=
SAT UNSAT Critical Step
+
-I-.____
+
+______
Total CLA CCPIT/HUT Other Total identified 1
Comment
1201 NRC RO Admin JPM A.2 Page 14 of 15 STEP 16 30 UNIDENTIFIED LEAKAGE SAT Unidentified leakage =
UNSAT Total leakage Identified leakage Critical Step Unidentified leakage =
GPM Perfomed By A
Reviewed By Standard:
hejflee determines Uniçentfied LeaagsjO7 Comment 5.0 ACCEPTANCE CRITERIA STEP 17
- d SAT A. The Technical Specification acceptance criteria is as follows:
UNSAT
- 1. The primarytosecondary leakage must be less than or equal to 150 GPD Critical Step through any one steam generator.
1
- 2. The total identified RCS leakage must be less than or equal to 10 GPM.
- 3. The total unidentified leakage must be less than or equal to 1 GPM.
B.
If any of the Technical Specification criteria are NOT satisfied, the SM must be notified and action requirement (b) of LCO 3.4.6.2 satisfied.
Standard:
Comment Terminating The JPM is complete when the Examinee returns the JPM briefing STOP Cue:
sheet to the Examiner.
- wq Stop Time
1201 NRC RO Admin JPM A.2 Page 15 of 15 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
1.
Unit 2 is in MODEl.
2.
The performance of 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory is due.
3.
ICS is not available.
4.
Data for the 0-SI-OPS-068-137.0, Reactor Coolant System Water Inventory Appendix C is as follows:
10.
Parameter Final Initial VCT Level 42.9 50.1 Pressurizer level 58 58 RCS Temperature 578 578 RCS Pressure 2235 2235 PRT Level 12358 12349 RCDT Level 172.2 171.8 CLA#1 Level 7692 7692 CLA#2 Level 7677 7677 CLA #3 Level 7672 7672 CLA#4 Level 7680 7680 Appendix D is complete through section 1.4 SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd 11.
0-SI-CEM-000-050.2 and 2-SI-CEM-068-137.5 were completed last night at 2300.
12.
Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.
13.
CCPIT/HUT leakage and other leakage is 0 gpm.
14.
Data collected for performance of this leak rate is documented in Appendix C and was collected over 120 minutes INITIATING CUES:
1.
You are the Unit 2 CR0 and have been directed to complete a manual RCS Leakage calculation using 0-SI-OPS-068-1 37.0, Reactor Coolant System Water Inventory Appendix D 1.
All calculations should be carried out to two decimal places.
2.
Record your answers on the Appendix D.
3.
Identify all deviations (if any) on the Chronological Test Log 4.
Notify the Examiner when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
I I
S SJjLo 11J kEj RCS LEAKAGE CALCULATIONS NOTE I All calculations must be performed manually. Verification may be performed using the computer.
NOTE 2 All calculations should be carried out to two places after the decimal.
Signs must be carried through all calculations.
NOTE 3 Calculations in this Appendix may need to be performed more than once.
If multiple calculations are required, copies of this Appendix may be used.
1.0 TOTAL RCS LEAKAGE 1.1 Volume Control Tank (VCT)
[(
-SO, I
%)(
%)1x19.27ga11%
VCT Leakage
=
Initial Level Final Level fl.0 mm.
Atnie,.
VCTLeakage=
j 1.2 Pressurizer (Pzr) UNIT 2 only
[1]
CALCULATE initial PZR volume by using the following equation:
NOTE I V1 (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
lb
- %level
/
m SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page500f6l AOL.
APPENDIX 0 Page 1 of 9
( PZRLeveI 100%
PZRLeve1 Initial PZR Vol = I
+
V1 Vg
)*
2 o
2 al
- ft3
A:.
1LQI NI4C ILO r
SQN REACTOR COOLANT 0-Sl-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page5lof6l APPENDIX D Page 2 of 9 Initial PZR Vol=[
5S 100 5 %
202 gal*ft3 1
+
/
/
ft 3/
ft 3/
/lb
/lb I
/m
/m)
- %level Initial PZR Vol =
gal
[2] CALCULATE Final PZR volume by using the following equation:
Performed By Reviewed By NOTE I NOTE 2 Vf (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
+
Final PZR Vol
=
PZRLeve1 100%
PZRLeve1 Vf Va 202
/
aal
- ft3 /
/lb
- %lex,el
/m Final PZR Vol = k17 55 gal Final PZR Vol
[
+
ft 3
/
/lb
/
m
- ft3/
/lb
- %level
/
rn Performed By Reviewed By
1101 MILL ILD LA
[3] CALCULATE PZR leakage rate by using the following equation:
APPENDIX D Page 3 of 9 PZR Leakage PZR Leakage =
Initial PZR Volume Final PZR Volume Atime 1a gal
7.al ta mm PZR Leakage =
0 gpm 1.3 Pressurizer (Pzr) UNIT I only N 4
[1] CALCULATE initial PZR volume using the following equation:
Performed By Reviewed By NOTE 1 NOTE 2 V1 (specific volume of a fluid) and V9 (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
201 ga1*ft3/
/lb
- %level
)
/
m Initial PZR Vol =
ft/
/lb Initial PZR Vol =
gal I
/
1 gal*fti /
/lbm * %level Performed By
SQN REACTOR COOLANT 0-SI-OPS-068-I 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page52of6l
+
Initial PZR Vol =
PZRLeve1 100%
PZRLeve1 Vr Vg 100 Reviewed By
17.01 NILC fZ()
T SQN REACTOR COOLANT 0-Sl-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page53of6l APPENDIX 0 Page 4 of 9
[2] NCALCULATE Final PZR volume using the following equation:
NOTE I V1 (specific volume of a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
Fal PZR Vol 1 PZRLeve1 100V PZRLeve1 201 gai
- ft/
Vg
)
/ ibm
/olevel Final PZR Vol
=[
ft
+ 100 ft ]*
2 olal *ft
- %level lb lbm Final PZR Vol =
gal Performed By Reviewed By CALCULATE PZR leakage rate using the following equation:
Initial PZR Volume Final PZR Volume PZR Leakage =
Atirne oal aal PZR Leakage =
mm PZRLeakage=
Performed By
Reviewed By
ho lEo 4A A.t I
SQN REACTOR COOLANT 0-Sl-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page54of6l APPENDIX D Page 5 of 9 1.4 RCS Temperature Correction[C.1]
NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
A.
Initial Conditions:
RCS pressure =
psig + 14.7 = 24?,7 psia RCSternperature= Sfl, Specific volume (v) =
022 q ft 3
/lbm Density = 1/v 1 =
g4(SM Ibm/ft 3
B. Final Conditions:
RCS pressure =
V23S psig + 14.7 =
psia RCStemperature=
°F Specific volume (v) = c O221 ft 3
/lbm Density=1/v 1
=
LIL/(7 Ibm/ft 3
C. Temperature Correction:
(
Lj(7 Ibm/ft 3 )
( II7 Ibm/ft 3 ) ]
- 1298.19 gal*ft 3
/ Ibm Temp Corr. =
Initial Density Final Density time Temperature Correction =
rLoJ VL (LO A.(
A SQN REACTOR COOLANT 0-SI-OPS-068-l 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page55of6l APPENDIX D Page 6 of 9 1.5 Total RCS Leakage TotalRCSLeakage=(
IiI&
PZR Temp Corr Total RCS Leakage=
11 GPM Performed By Reviewed By 2.0 IDENTIFIED LEAKAGE NOTE Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tanks pressure.
If negative leakage is calculated under these conditions, that tanks leakage must be set equal to zero.
2.1 Pressurizer Relief Tank (PRT)
Final Volume Initial Volume
(
12 mm)
A Time
NOTE RCDT Level (2.2) may be marked N/A if conditions do NOT permit obtaining RCDT level.
2.2 Reactor Coolant Drain Tank (RCDT) gal)(
l71 gal)]
RCDT Leakage =
Final Volume Initial Volume
(
i2 mm)
A Time RCDTLeakage=
Performed By VCT
[(
PRT Leakage =
Leakage
.g.i)(
JZ39 gal)]
Reviewed By
1]cJ
)RL SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 1&2 Page56of 61 APPENDIX D Page 7 of 9 2.3 Steam Generator (SG)
NOTE I SG leak rates are obtained by 1, 2SICEM0681 37.5.
0SICEM000-050.2 is performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and looks at activity levels which will determine if those leak rates from the last performance of 1, 2SICEM---0681 37.5 have risen.
NOTE 2 Individual steam generator leakage may be NIAd if activity is too low to be separately identified.
A. SG1 Leakage=
32-GPD B. SG2 Leakage =
..7.
GPD C. SG3 Leakage =
GPD D. SG4 Leakage =
GPD TotalSGleakage=
GPD =( OT GPM 0
1440 min/day Date/Time 0SICEM000050.2 performed:
/
Date Time Date/Time 1, 2-Sl--CEM0681 37.5 performed: L 4 Nh Date Time Recorded by
ILo I4ILC.
REACTOR COOLANT I 0-Sl-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 Page 57 of 61 2.4 Cold Leg Accumulators (CLA)
Page 8 of 9 NOTE CLA leakage calculations may be marked NIA if RCS pressure is greater than 683 psig and quantification of CLA leakage is n required.
A. CLA 1 Leakage CLA 1 Leakage =
B. CLA 2 Leakage =
gal)j
gall
[lFinal Volume Initial Volume
)]
I:
rzo mm)
A Time (7
GPM E( 7 gal)
(
7C77 gal 1
[Final Volume lnitial Volume
)j
(
mm)
A Time CLA 2 Leakage =
CLA 4 Leakage =
GPM (1iiialVol)]
ume 0
GPM Total CLA leakage =
p GPM Performed By SQN 1&2 APPENDIX D
[Final Volume C. CLA 3 Leakage CLA 3 Leakage =
D. CLA 4 Leakage 1_-O--min ATime 0
GPM El al
- I 7
[Final Volume
)
jnitial Volume mm ATime Reviewed By
ULO1 NILL ILO AAsAWb A.dL SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 26 I &2 Page58of 61 2.5 Other Identified Leakage APPENDIX D Page 9 of 9 NOTE The following value may be marked NIA if no additional identified leakage sources (i.e., Appendix A) are to be included.
Other identified leakage (Appendix A) =
NOTE GPM If NO CCPIT de-pressurization I pressurization activity has occurred during the stabilization period, CCPIT/HUT leakage may be marked N/A.
2.6 Total Identified Leakage Total identified leakage
= Ot
+
- 1) 0
+
+
Total CLA
+
+_____
CCPIT/HUT Other Total identified leakage =
),
GPM 3.0 UNIDENTIFIED LEAKAGE Unidentified leakage =
11, Total leakage p,oc/
Identified leakage UnIdentified leakage =
lO7 GPM Performed By Reviewed By
SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE 1201 NRC ROADMINA.3
1201 NRC RO ADMIN A.3 Page 2 of 6 SRO JOB PERFORMANCE MEASURE Task:
Pre Job Brief for Emergent Work in the RCA Task#:
3430290302 Task Standard:
In preparation for a Pre-job brief with an AUO, the Examinee chooses correct survey map and calculates a total dose of 480 mrem for the job.
Time Critical Task:
YES:
NO:
X KlAReferencelRatings:
2.3.13 (3.4/3.8)
Method of Testing:
Simulated Performance:
Actual Performance:
X Evaluation Method:
Simulator In-Plant Classroom X
Main Control Room Mock-up Performer:
Trainee Name Evaluator:
/
Name I Signature DATE Performance Rating:
SAT:
UNSAT:
Validation Time:
14 mm Total Time:
Performance Time:
Start Time:
Finish Time:
COMMENTS
1201 NRC RO ADMIN A.3 Page 3 of 6 SPECIAL INSTRUCTIONS TO EVALUATOR:
1.
Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
ToolslEquipmentlProcedures Needed:
1.
Calculator 2.
Survey map A216 U-i Pipe Chase 3.
Survey map A217 U-2 Pipe Chase 4.
Survey map 408 U-i Mixed Bed Valve Gallery 5.
Survey map 417 U-2 Mixed Bed Valve Gallery
References:
Reference Title Rev No.
2.
RCI-3 PERSONNEL MONITORING 48 Read to the examinee:
DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM.
I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME!
INITIAL CONDITIONS:
1.
Unit 2 is in MODE 1 2.
You are the CRC and are preparing for a pre-job brief for an AUO to make an emergent entry in to the RCA.
3.
The work is 1 meter from valve 2-63-750 Test Conn on RHR Suction from RWST located in the Auxiliary Bldg 653 elevation pipe chase.
4.
The total time to perform the job is 36 mm INITIATING CUES:
1.
Calculate the total dose that the worker will accumulate performing the job 2.
Inform the evaluator when you are complete.
Provide a copy of the following survey maps:
Survey map A216 U-i Pipe Chase Survey map A217 U-2 Pipe Chase Survey map 408 U-i Mixed Bed Valve Gallery Survey map 417 U-2 Mixed Bed Valve Gallery 1201 NRC RO ADMIN A.3 Page 4 of 6 pyofSurvy map.
Start Time SAT U NSAT Critical step Cue Comment Examiner Note Both the Unit I and Unit 2 Pipe Chase and Mixed Bed Valve Gallery survey maps are provided.
1201 NRC RO ADMIN A.3 Page 5 of 6 The work will be performed near valve 2-63-750 Test Conn on RHR Suction from RWST. General area dose rate from survey map A217 from a hot spot in the area is 800 mr/hr. The job as indicated from the initiating cue will take 36 minutes.
800 mremfhr ÷ 60 mm/i hr X 36 mm
= 480 mrem Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue:
the examiner.
STEP 2
5 Standard:
Exarrunee cacuIates a total dose of480 mrem wilibe.acuiei performing the task.
Comment SAT UNSAT Critical step Examiner Note Stop Time
1201 NRC RO ADMIN A.3 Page 6 of 6 JPM BRIEFING SHEET DIRECTIONS TO TRAINEE:
The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
INITIAL CONDITIONS:
1.
Unit 2 is in MODE I 2.
You are the CR0 and are preparing for a pre-job brief for an AUO to make an emergent entry in to the RCA.
3.
The work is 1 meter from valve 2-63-750 Test Conn on RHR Suction from RWST located in the Auxiliary Bldg 653 elevation pipe chase.
4.
The total time to perform the job is 36 mm INITIATING CUES:
1.
Calculate the total dose that the worker will accumulate performing the job 2.
Inform the evaluator when you are complete.
Acknowledge to the examiner when you are ready to begin.
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.