ML030580257
| ML030580257 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/18/2002 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-331/02-301 | |
| Download: ML030580257 (98) | |
Text
INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE DUANE ARNOLD EXAMINATION - NOVEMBER 2002
80 AlI!, Cf SITE: DAEC TASK TITLE: PERFORM AN APRM GAIN ADJUST JPM NUMBER: 2.1.7-02xx REV. 0 RELATED PRA INFORMATION:
TASK NUMBERS: 97.11 2.1.7 (3.714.4)
KIA NUMBERS: 2.1.20 (4.314.2) 2.1.30 (3.913.4) 2.1.31 (4.213.9)
APPLICABLE METHOD OF TESTING:
Discussion: [-] Simulate/walkthrough: [ Perform:
EVALUATION LOCATION: In-Plant: I Control Room:
Simulator: F -} Other:
Time for Completion: 15 Minutes Time Critical: NO Alternate Path /
Faulted: NO TASK APPLICABILITY: ROISRO Instructor Date "Validation Instructor Dafe (See JPM Validation Checklist, Attachment 1)
Training Supervisor-Operations Date RAtntiArv
- ..-* I if ,,f .. lA.,.-.
, r'-'*-j Retain in: Training Program File Disposition: Reviewer and Approver Page 1 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 JPM Number: 2.1.7-02 JPM
Title:
PERFORM AN APRM GAIN ADJUST Examinee:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: = j UNSAT: ZI Z COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retainedin examinee's recordif completed satisfactorily. If unsatisfactory performance is demonstrated,the entire JPM should be retained.
Page 2 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 JPM BRIEFING/TURNOVER Add requiredsite specific JPM briefing material here:
i.e., This section is readonce for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initialconditions and initiatingcue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approvedreference materials normally available includinglogs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
"* The plant is operating at power.
"* You are the on-shift RO.
"* "F" APRM gain is not within limits.
INITIATING CUES (IF APPLICABLE):
- The Shift Supervisor directs you to perform an APRM Gain Adjustment for APRM "F" (Foxtrot) per 01 878.4.
Page 3 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: 1. 01 878.4 "Average Power Range Monitoring System"
- 2. Small Screwdriver.
General
References:
01878.4 Rev 27 Task Standards: 1. Bypass APRM "F".
- 2. Adjust "F" APRMs to with in + or- 2%.
- 3. Restore APRM to normal bypass conditions.
Start Time:
01 878.4 Section 8.0 Performance Step: Determine desired APRM setting from computer point C133 or reactor heat Critical: N balance calculation.
Standard: Core power recorded from Computer Point C133 or reactor heat balance.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: If asked which power to used (computer point CI133 or the reactor heat balance) tell them to use computer point C133.
Page 4 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 Performance Step: If APRM adjustment is required, bypass the appropriate APRM per Section 6.1 Critical: N of this procedure.
Standard: Go to Section 6.1 to bypass the APRM.
Performance: SATISFACTORY UNSATISFACTORY Comments:
01 878.4 Section 6.1 Performance Step: Verify the two remaining APRM channels in the RPS trip system are operable Critical: N and not BYPASSED, otherwise comply with Tech Specs for inoperable RPS instrumentation.
Standard: Verifies remaining channels operable.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: if asked the remaining channels are operable.
Cue: If permission to bypass "F" APRM is requested, give the candidate permission to bypass "F" (Foxtrot) APRM.
Performance Step: Place the APRM BYPASS switch C51 B-S3 (C51 B-S6) on Panel 1C05 in the A, Critical: Y C, or E (B, D, or F) position for the channel to be bypassed.
Standard: Operator bypasses "F" APRM by taking C51 B-S6 to "F".
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 Performance Step: Observe that the bypass lights for the bypassed channel on Panel 1C37 and Critical: N Panel 1C05 are both ON.
Standard: Operator confirms the bypass light for "F" APRM on 1C37 and Panel 1C05 are both ON.
Performance: SATISFACTORY UNSATISFACTORY Comments:
01 878.4 Section 8.0 Performance Step: At 1C37, adjust APRM AUX card (Z31) R16 as necessary to correspond to the Critical: Y desired APRM setting.
Standard: At 1C37, adjust APRM AUX card (Z31) R16 as necessary to correspond to the desired APRM setting.
Adjust "F" APRMs to with in + or - 2% of computer point C133 or from the reactor heat balance.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Confirm appropriate APRM computer point (BOO0 through B005) agrees with Critical: N AS LEFT values on 1C37. If not, notify Reactor Engineering and the System Engineer.
Standard: Operator confirms the "A" APRM computer point B005 agrees with AS LEFT values on 1C37.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 6 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 Performance Step: Remove appropriate APRM from bypass per Section 6.2 if necessary.
Critical: N Standard: Go to Section 6.2 to un-bypass the "F" APRM.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: If requested give permission to un-bypass "F" (Foxtrot) APRM.
Cue: If asked what APRMs to bypass tell the operator to return the APRMs conditions he found them.
Performance Step:
01 878.4 Section 6.2 Performance Step: Before returning a bypassed APRM to service, verify the following for that Before returning a bypassed APRM to service, verify the following for that Critical: N APRM:
The APRM channel Mode Selector Switch on Panel 1C37 is in OPERATE.
Standard: Operator verifies the "F" APRM channel Mode Selector Switch on Panel 1 C37 is in OPERATE.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: The APRM upscale, inoperative, and if greater than 5% reactor power, Critical: N downscale trips on Panel 1C37 are reset.
Standard: Operator confirms "F" APRM downscale trips on Panel 1C37 are reset.
Performance: SATISFACTORY UNSATISFACTORY Comments:
I Page 7 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 Performance Step: The IRM/APRM recorders on Panel 1C05 indicate approximately the same Critical: N average power for the bypassed APRM as they do for the other APRM channels in operation.
Standard: Operator confirms "F" APRM recorder reads about the same as the other APRMs.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Place the APRM BYPASS switch C51 B-S3 or C51 B-S6 on Panel 1C05 in the Critical: N neutral (unbypassed) position.
Standard: Operator places C51B-S6 on Panel 1C05 in the neutral (unbypassed) position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Observe that the bypass light on Panel 1C05 is OFF.
Critical: N Standard: Operator verifies "F" APRM bypass light on Panel 1C05 is OFF.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: If desired, BYPASS a different APRM channel per section 6.1.
Critical: N Standard: Go to section 6.1 Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 8 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 0f 878.4 Section 6.1 Performance Step: Verify the two remaining APRM channels in the RPS trip system are operable Critical: N and not BYPASSED, otherwise comply with Tech Specs for inoperable RPS instrumentation.
Standard: Verifies remaining channels operable.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: if asked the remaining channels are operable.
Cue: If ask which APRM to Bypass have the operator return it to the APRM bypassed at the start of the JPM.
Performance Step: Place the APRM BYPASS switchC51B-S6) on Panel 1C05 in the A, C, or E (B, Critical: Y D, or F) position for the channel to be bypassed.
Standard: Operator bypasses the APRM "B" or "D" depending on the original setup.
Performance: SATISFACTORY UNSATISFACTORY Comments: Note: One APRM channel per RPS trip system is normally bypassed to prevent a full scram due to a single shared LPRM failure. During normal operation the preferred APRM channel bypass combinations are A & D or C & B.
Performance Step: Observe that the bypass lights for the bypassed channel on Panel 1C37 and Critical: N Panel 1C05 are both ON.
Standard: Operator confirms the bypass light for "B" OR "D" APRM on 1C37 and Panel 1C05 are both ON. This will depend on which APRM is bypassed on the "A" side.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: Terminate the JPM when the candidate has Bypassed the "B" or "D" APRM Stop Time:
Page 9 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 SIMULATOR SET UP:
- 1. Reset to any power IC > 25 %.
- 2. When the plant is stable, ensure the APRMs are set as follows:
"* "F" APRM +4 % of core thermal power.
"* "A-E" APRMs set to approximately +/- 0.5% of core thermal power.
"* Verify APRM channel bypassed is either A & D or C & B.
SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Page 10 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 TURNOVER SHEET INITIAL CONDITIONS:
- The plant is operating at power.
- You are the on-shift RO.
"* "F" APRM gain is not within limits.
INITIATING CUES (IF APPLICABLE):
The Shift Supervisor directs you to perform an APRM Gain Adjustment for APRM "F" (Foxtrot) per 01 878.4.
Page 11 of 12
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.7-xx, Perform An APRM Gain Adjust, Rev. 0 ATTACHMENT I JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly? Ei- Li
- 3. Can the required conditions for the JPM be appropriately U" El El established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in ElI E]
accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what Li Li controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data E9` 0I El or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon [] En actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if E Li i]
required?
- 9. Is the K/A appropriate to the task and to the licensee level if 0I Li// E required?
- 10. Have the performance steps been identified and typed (Critical /i Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task [a E n been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the [e/ li El trainee?
- 13. Have all required cues (as anticipated) been identified for the Ei Mi evaluator to assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Sc-/// , 0/-
Vah*idfion Personnel /Da{e f' Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 12 of 12
QF-1030-11 Rev. 1 (FP-T-SAT-30 A1 2?
JOB PERFORMANCE MEASURE (JPM)'
Committed to Nudear6xcegý SITE: DAEC TASK TITLE: C71A-K3C Logic Print Exercise.
JPM NUMBER: 2.1.24-xx REV. 0 RELATED PRA INFORMATION:
TASK NUMBERS: 50102 PR-07 Learning Objective and Enabling Objective 16.
KIA NUMBERS: Generic 2.1.24 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: Perform: I EVALUATION LOCATION: In-Plant: Control Room:
Simulator: - Other:
Time for Completion: 30 Minutes Time Critical: NO Alternate Path /
Faulted: NO TASK APPLICABILITY: ROISRO be added as needed.
retenuoin: LITe O policy + I uyrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 8
QF-1030-11 Rev. I (FP-T-SAT-30) 2.1.24-xx, C71A-K3C Logic Print Exercise, Rev 0 JPM Number: 2.1.24-xx JPM
Title:
C71A-K3C Logic Print Exercise.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: I j UNSAT:ZIZ COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retainedin examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated,the entire JPM should be retained.
Page 2 of 8
QF-1030-11 Rev. I (FP-T-SAT-30) 2.1.24-xx, C71A-K3C Logic Print Exercise, Rev 0 JPM BRIEFING/TURNOVER Add requiredsite specific JPM briefing materialhere:
i.e., This section is read once for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initialconditions and initiatingcue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approved reference materialsnormally available including logs. Make all written reports, oralreports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure,you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, ANDIOR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
"* The plant is at power.
"* During a panel walk down Relay C71A-K3C "RPS TRIP CHANNEL A2 C LINE MSIV 90% OPEN" was found deenergized.
"* There are no other indications that this relay is deenergized.
"* The STA evaluated logic print APED C71 and reports the following:
- There is a Fuse, F3C, in line with C71A-K3C and it could possibly be open and we also should have received a 1/2 Scram, an annunciator, and computer point alarm if this fuse is open.
INITIATING CUES:
- The OSM directs you to independently evaluate the logic print for this relay to determine if the STA is correct.
Page 3 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.1.24-xx, C71A-K3C Logic Print Exercise, Rev 0 JPM PERFORMANCE INFORMATION Required Materials: APED-C71-004 sheets 4, 6, 8, 14, and 15 General
References:
APED-C71-004 sheets 4, 6, 8, 14, and 15 Task Standards: 1. Determine Fuse F3C could possibly be the fuse and that the STA is correct
- 2. Determine there should not be a %Ascram and that the STA is NOT correct
- 3. Determine there should not be an annunciator and that the STA is NOT correct
- 4. Determine there should not be a computer point alarm and that the STA is NOT correct Start Time:
NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provideld when the examinee's actions 'warrant receiving the information (i.e. the examhinee looks or asks for the indication).
SNOTE: Critical steps, are marked with a "Y" below the'performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. ~~
Performance Step: Determine there is a fuse in the logic to C71A-K3C and that it is a possible reason Critical: Y for this condition.
Standard: Fuse F3C is identified as the possible fuse.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 4 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.1.24-xx, C71A-K3C Logic Print Exercise, Rev 0 Performance Step: Determine using the logic prints that a 1/2 scram should not occur ifthis fuse is Critical: Y open.
Standard: Determines that a 1/2 scram would not occur and the STA is incorrect.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine using the logic prints that an annunciator should not occur if this fuse Critical: N is open.
Standard: Determines that an annunciator would not occur and the STA is incorrect.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: Determine using the logic prints that a computer point alarm should not occur if Critical: N this fuse is open.
Standard: Determines that a computer point alarm would not occur and the STA is incorrect.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: When candidate has determined the STA is correct about the fuse but incorrect about the rest.
Stop Time:
Page 5 of 8
TURNOVER SHEET INITIAL CONDITIONS:
"* The plant is at power.
"* During a panel walk down Relay C71A-K3C "RPS TRIP CHANNEL A2 C LINE MSIV 90% OPEN" was found deenergized.
"* There are no other indications that this relay is deenergized.
"* The STA evaluated logic print APED C71 and reports the following:
- There is a Fuse, F3C, in line with C71A-K3C and it could possibly be open and we also should have received a 1/2 Scram, an annunciator, and computer point alarm if this fuse is open.
INITIATING CUES:
- The OSM directs you to independently evaluate the logic print for this relay to determine ifthe STA is correct.
Page 6 of 8
ATTACHMENT I JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly? El Eli
established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in N- El1 L accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what L--I El controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data 29ý El 1:I or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon Wl LI actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if LE] LI required?
- 9. Is the K/A appropriate to the task and to the licensee level if LI E
[]
required?
- 10. Have the performance steps been identified and typed (Critical / L Lii Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task 9" El E]
been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the 1ý,ý El E]
trainee?
- 13. Have all required cues (as anticipated) been identified for the LI ELI evaluator to assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
VValidation Personnel /Nai( Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 7 of 8
Validation Personnel /Date Validation Personnel/Date Page 8 of 8
QF-1030-11 Rev. I (FP-T-SA T-30)
J OB PERFORMANCE MEASURE (JPM) 1./f Comn~fted to Nucfear EXCO!!rn,"'
SITE: DAEC TASK TITLE: Respond to a RBM Rod Block annunciator and safety limit violation.
JPM NUMBER: 2.2.22-xx REV. 0 RELATED PRA INFORMATION:
TASK NUMBERS: Task 82.00 Objective 71.00.00.08 K/A NUMBERS: Generic 2.2.22 3.4/4.1 215002 A2.05 3.2/3.3 APPLICABLE METHOD OF TESTING:
Discussion: Sim ulate/walkthrough: Perform: W-T EVALUATION LOCATION: In-Plant: Control Room:
Simulator: LII] Other:
Time for Completion: 10 Minutes Time Critical: NO Alternate Path /
Faulted: NO TASK APPLICABILITY: RO/SRO be added as needed.
n..,....,X.... * !2 2i - - A reLention: LITe OT pOliCy + - uyrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
+aa ti
+;,,.I n I ,'.-1* ,*L 4 . .. .
I* ý;II',JII. L"IV" UI POUIILy " I UylI . Disposition: Reviewer and Approver Retain in: Training Program File Page 2 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 JPM Number: 2.2.22-xx JPM
Title:
Respond to a RBM Rod Block annunciator and safety limit violation.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish S........ Time
..... v PERFORMANCE RESULTS:
SAT: I UNSAT:
Delete this table if not required
_ Procedure adequately addresses task elements.
Enter Identifier here: 82.00 Monitor the Rod Block Monitoring System.
Other document adequately describes necessary task elements.
Enter Identifier here: 71.00.00.08 Official 3D Monicore the data provided by the interpret output.
COMMENTSIFEEDBACK: (Comments shall be made for any steps graded unsatisfactory). I EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retainedin examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 3 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 JPM BRIEFING/TURNOVER Add requiredsite specific JPM briefing materialhere:
i.e., This section is read once for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initial conditionsand initiatingcue(s)/tasks to be performed should be readand then provided to the examinee.
You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure,you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindicationis sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, ANDIOR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
"* You are performing a control rod sequence exchange and have just withdrawn the selected control rod.
"* The annunciators for "Rod Out Block" and "RBM Upscale or Inop" have just occurred.
INITIATING CUES (IF APPLICABLE):
Page 4 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 JPM PERFORMANCE INFORMATION Required Materials: ARP IC05B A-6 Rev 9 ARP IC05B B-6 Rev 10 Plant process computer 3D Case T.S.
Copy of a sequence exchange including the selected rod.
General
References:
ARP 1C05B A-6 Rev 9 ARP IC05B B-6 Rev 10 T.S.
Task Standards: Run 3D Case Identify T.S. Safety Limit violation.
Start Time:
NOTE: When poing"valuator Cues" to the examinee, care must be~exercised to avoid prompting~
the'examinee. Typically cues are only provided when the exam~inee's act~ions warrant receiving the linformation (ike. the examinee looks or asks for the indication).
NOTE: 'Critical steps are marked 1wit Iha "Y" be'Ilow the perform~ance step n11mber. Failure tomeet the~
stand~ard for any critical step shall result in failure of this JPM. ~
Performance Step: At Panel 1C-05, monitor RBM displays to determine the affected RBM channel.
Critical: N Standard: Determine the Rod Block is due to both RBMs upscale.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Page 5 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 Performance Step: 3.1 If UPSCALE light is ON and has not been anticipated as part of a sequence Critical: N exchange:
a) Verify with the Reactor Engineer that the proper rod withdrawal sequence is being used.
Standard: Operator will request ifthis is the proper rod withdrawal sequence Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: If asked if this is the correct rod withdrawal sequence reply that the Reactor Engineer has verified this to be the correct rod withdrawal sequence Performance Step: 3.2 b) Verify the proper rod is selected.
Critical: N Standard: The operator verifies the correct control rod is selected.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: If asked if this is the correct rod the answer is YES this is the correct control Rod.
Performance Step: 3.2 c) Run an OFFICIAL 3D CASE and follow with one of the below options:
Critical: Y Standard: An OFFICIAL 3D CASE is ran by typing RUN3D on the PPC.
Performance: SATISFACTORY UNSATISFACTORY Comments: Once the 3D Case is requested and prints out give the candidate the JPM 3D Case to review.
Page 6 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 Performance Step: 3.2 c)1) If a thermal limit has value in excess of 1.000, inform the OSS and comply with Critical: Y the Technical Specification requirements for Power Distribution Limits Standard: The operator will review the 3D Case and determine that MFLPD is reading 1.02 and the thermal limit is in excess of 1.000. Inform the OSS of the result.
He should also mention we should review T.S. for Power Distribution Limits.
However, this is not considered critical for satisfactory performance of this step.
Performance: SATISFACTORY UNSATISFACTORY __
Comments:
Terminating Cues: T.S. Thermal Limit has been identified as being exceeded.
Stop Time:
Page 7 of 11
QF-1 030-11 Rev. I (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 "SIMULATOR SET UP:
"* Reset to any >30% power IC.
"* Select a non-edge control rod.
SIMULATOR EVENT TRIGGERS::
None SIMULATOR MALFUNCTIONS:
Malfunction Discription Severity Ramp Delay Value nm09a RBMCHANNE FAILS-CHNL A 100 0 0 nm09b RBMCHANNE FAILS-CHNL B 100 0 0 On the VAX use SAIC Menu #8 then #3 and set MFLPD 1.02
"-- SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None I
Page 8 of 11
QF-1030-11 Re v-tFP -PSAU-3O) 2.2.22-xx, Respond to a RBM Rod Block annunciator TU RNoER SHE INITIAL CONDITIONS:
"* You are performing a control rod sequence exchange and have just withdrawn the selected control rod.
"* The annunciators for "Rod Out Block" and "RBM Upscale or Inop" have just occurred.
INITIATING CUES (IF APPLICABLE):
/
e 661 4'- ýrp 1
Page 9 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 ATTACHMENT I JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- El El]
- 3. Can the required conditions for the JPM be appropriately IT El El established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in - El El accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what E2[] E]
controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data 7El El1 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon ER" El E]
actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if " El required?
- 9. Is the K/A appropriate to the task and to the licensee level if
- El El required?
- 10. Have the performance steps been identified and typed (Critical / 1El El Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task " El El been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the [T El El trainee?
- 13. Have all required cues (as anticipated) been identified for the [9"' El1 El evaluator to assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
"Va
. ri"ation
. Personnel/Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 10 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) 2.2.22-xx, Respond to a RBM Rod Block annunciator and safety limit violation. Rev 0 Validation Personnel /Date Validation Personnel/Date I
Page 11 of 11
J, Ao0 14,3 D UANE A RINOLD ENERGY CENTER JOB PERFORMANCE MEASURE NUMBER: 2.3.1-04 TASK NUMBER: HP-SELF.004 I TITLE: Gain Access to a High Radiation Area Rev. 2 DEVELOPED BY:
Date Sla evIeeor VALIDATED BY: /c9-31-ol Date REVIEWED BY:
051a eviewer Date APPROVED BY:
1a/te o Date TDT-3.08 Rev. 5
DUANE ARNOLD ENERGY CENTER JOB PERFORMANCE MEASURE JPM No. 2.3.1-04 JPM
Description:
Gain access to a high radiation area Task No. Task
Description:
Prepare for Self Coverage HP-SELF.004 K/A
Reference:
2.6/3.6 2.3.1 APPLICABLE METHOD OF TESTING: RO/SRO Simulate Performance X Actual Performance Simulator In-Plant X Control Room Time for Completion: 30 minutes JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 7 through 10.
JPM No. 2.3.1-04 JPM Title Gain access to a high radiation area N
- 1. Task description and number, JPM description and number are identified
- 2. Task elements identified and K/A references are included
- 3. Performance location specified
- a. in-plant
- b. control room
- c. simulator
- 4. Initial conditions and cues identified
- a. setup, required materials, and procedure
- b. malfunctions and instructor actions
- c. initiating and terminating cues.
- 5. Task standards identified and verified by SME review
- 6. Critical tasks/steps identified meet criteria and identified with a "C"
- 7. Verify JPM steps fit the most curr nt procedures Procedure Rev. J10. Date 0? g/0 A C..f' 1)1 / . ,
- 8. Pilot test JPM 12
- a. verify cues both verbal and visual are free of conflict
- b. ensure performance time is accurate
- 10. When JPM is revalidated, SME/Instructor signs and dates JPM Date SME/Instructor Date SME/Instructor SME/Instructor Date JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
SIMULATOR SETUP:
None EVENT TRIGGERS:
None MALFUNCTIONS:
None OVERRIDES:
None REMOTE FUNCTIONS:
None JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
INSTRUCTOR ACTIONS:
- 1. Verify that the CAVs area is currently posted as a High Rad Area.
- 2. Start this JPM in the Reactor Building.
- 3. Read initial conditions and initiating cues to the operator.
TASK STANDARDS:
- 1. Operator does not attempt to enter the High Rad Area improperly.
- 2. The need to sign in on another RWP (which will allow entry) is identified.
- 3. Current survey map reviewed.
- 4. HP briefing requested.
REQUIRED MATERIALS:
RWP 10, Job Step 2 RWP 10, Job Step 6 RWP 33, Job Step 1 Marked-up copy of P&ID Bech-M189<3>
Digital picture of the CAVs area CAVs Area Survey Map GENERAL
REFERENCES:
ACP 1411.22, Control of Access to Radiological Areas JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
Read to the operator the following information:
NOTE:
Start this JPM in the Reactor Building.
INITIAL CONDITIONS:
- 1. The plant is in normal full power operation.
- 2. Assume you are a (Senior) Reactor Operator in the Reactor Building doing maintenance planning.
- 3. You are to demonstrate the proper verification techniques while performing this JPM.
INITIATING CUES:
As Shift Supervisor, I direct you to go to the CAVs Area and verify the out-of-service CAV vessel IT-415A isolation valves V-89-150, V-89-151, V-89-154, V-89-155 are closed, bypass valve V-89-153 and drain valve V-89-152 are open.
This task is not time critical.
Inform the evaluator when you have completed the task.
JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
PERFORMANCE INFORMATION NOTE:
Critical steps are denoted with a "C". Failure to meet the standard for this step constitutes failure.
Time Start CAUTION DO NOT allow the examinee to cross the roped-off boundary of the High Rad Area.
Use physical restraint if necessary. If an improper entry is attempted, the JPM will have been performed unsatisfactorily and should be ended by reading the Terminating Cue.
PERFORMANCE STEP: Operator identifies the need to enter a High Rad area.
Critical: C STANDARD: Operator does not attempt to enter the High Rad Area improperly.
COMMENTS:
The examinee need not enter the Reactor Building 786' level area if he recognizes that the CAV vessel valves are in a High Rad Area and begins to work on gaining access.
(After the need to enter a High Rad Area is identified),
CUE:
The intent of this JPM is to demonstrate the actions necessary to enter a High Rad Area.
An actual entry will not be performed but you are to continue to walkthrough your actions as if it were. I will role play plant support personnel as necessary.
Note:
Do not allow the on-shift HPs to become involved with this JPM other than to provide the book of survey maps.
PERFORMANCE STEP: Operator returns to Access Control to review and identify Critical: C an RWPT which will allow entry.
STANDARD: The need to sign in on another RWP (which will allow entry) is identified.
COMMENTS:
The correct RWP for operations duties in HRA/LHRA areas is RWP 10, Job Step 6.
Role Play the On-Shift Health Physics Technician (HP) as necessary. It is preferable for the candidate to identify the correct RWP but this information may be given by the HP/evaluator upon request.
JPM 2.3.1-04 2.3.1-04_jpm.doc Rev. 2
PERFORMANCE STEP: Review a current survey for specific locations of high dose Critical: C and low dose standby areas.
STANDARD: Current survey map reviewed.
COMMENTS:
(If not stated in the review of the survey map)
CUE:
Identify the maximum dose rates in the CAVs area. (z; 80 to 100 mR/hr.)
PERFORMANCE STEP: Request a pre-job briefing by the HP.
Critical: C STANDARD: HP briefing requested.
COMMENTS:
CUE: Instruct the student to provide a reverse brief.
The student should provide a reverse brief that contains the following items:
Review of the RWP.
Wearing Electronic Dosimetry.
Obtaining a dose rate instrument.
Wearing proper protective clothes.
May discuss locating low dose standby areas outside the CAVs area.
Note:
The operator should have already demonstrated the ability to sign in on a RWP, so signing in on the new RWP is not necessary.
Time Stop TERMINATING CUES: The intent of this JPM was to demonstrate the actions necessary to enter a High Rad Area. This JPM is complete.
JPM 2.3.1-04 2.3.1-04_jpm.doc Rev. 2
VERIFICATION OF COMPLETION JPM No.: 2.3.1-04 JPM
Description:
Gain access to a high radiation area Operator: Evaluator:
Licensee: Li RO L-i SRO Li SRO Cert Li STA LI NSPEO Result: LI SATISFACTORY n- UNSATISFACTORY COMMENTSIFEEDBACK: (Note any trainee discrepancies or misperformed steps.)
Evaluator's Signature Date JPM 2.3.1-04 2.3.1-04jpm.doc Rev. 2
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ADMINISTRATIVE ... CON .. ,' * ! A C P 1411.22 ACP 141-b t2 CONTROL OF ACCESS TO RADIOLOGICAL Rev. 12 2)
AREAS Page 6 of 10 (a) RWP numbers for scheduled work activities can be obtained directly from the schedule. These RWP numbers are assigned and entered by Radiation Protection personnel.
(b) RWP numbers for routine tours are the default RWPs for all personnel on-site.
(c) If the correct RWP number is not known for the entry, contact Health Physics at Access Control to obtain the correct RWP number and review the RWP if not already authorized.
(5) If the access control system indicates that you are not currently authorized for the RWP you are trying to sign in on, contact Health Physics to review the correct RWP and be authorized in the access control system.
(6) Health Physics will provide specific instructions for entries into highly contaminated or airborne areas.
3.2.4 PERSONNEL ACCESS TO A HIGH RADIATION AREA NOTE )
Personnel entering a high radiation area shall be monitored by TLD in accordance with 10 CFR 20.1502.
(1) Personnel requiring access to a high radiation area shall:
(a) Participate in a pre-job briefing with Health Physics prior to entry. The briefing shall review radiological information based on a representative survey of the area.
Exception: A situation due to a plant transient may occur where the immediate entry into a HRA or LHRA by Operations personnel could prevent further plant degradation.
The Operations Shift Supervisor may authorize a Plant Equipment Operator - Nuclear or Reactor Operator to bypass the HP briefing and make the emergency entry. The Operator shall be knowledgeable of the radiological conditions within the area, follow direction given in the associated RWP, and be equipped with an electronic dosimeter or a survey meter. The duty HP should be notified as soon as possible that the entry is being made. The Operator shall take precautions to maintain exposures ALARA.
The duty HP shall provide Health Physics support as determined appropriate. The Health Physics Supervisor shall be notified of each emergency HRA or LHRA entry.
(b) Review the RWP and follow instructions/requirements set forth.
(c) Wear electronic dosimetry. Personnel shall ensure that they recognize the alarm sounds and know the appropriate actions to take when the alarm is received. If )
personnel are entering an area where noise in the area may interfere with hearing an
ACP 1411.22 CONTROL OF ACCESS TO RADIOLOGICAL Rev. 12 AREAS Page 7 of 10 ED alarm, consideration should be given for the use of an ED alarm aid (e.g.,
earpiece, alarm light) or additional controls. Unusual circumstances may prohibit the use of Electronic Dosimetry, in this event, personnel shall follow the dosimetry requirements of the RWP or Health Physics direction.
(d) Be provided with or accompanied to the work area by one or more of the following:
e A radiation-monitoring device which continuously indicates the dose rate in the area.
- A radiation-monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received (i.e.,
Electronic Dosimetry). Entry into HRAs utilizing Electronic Dosimetry may be made after the dose rate level in the area has been established and entrants have been made knowledgeable of them.
0 An HP Technician with a radiation dose rate instrument who is responsible for providing Positive Exposure Control over activities in the area and performs periodic radiation surveys at the frequency specified by the H. P. Supervisor, on the RWP.
(2) Non-HP personnel that have provided self-coverage should report discrepancies in briefed upon radiological conditions to the on-shift or control point HP Technician. The HP Technician will document that conditions were discrepant in the HP Shift Log or designated HP form. The HP will take corrective actions as necessary.
(3) Health Physics job coverage details are provided in HPP 3104.01.
3.2.5 PERSONNEL ACCESS TO A LOCKED HIGH RADIATION AREA (1) Personnel accessing a locked high radiation area shall comply with the requirements of Section 3.2.4.
NOTE The keys to the Locked High Radiation Areas shall be issued only to individuals identified on the Self-Coverage Qualification Matrix.
(a) Obtain a key. Personnel who are issued a key are responsible for assuring that the area is locked upon exit and the key returned at the end of the work.
(2) Refer to ACP 1411.13, "Control of Locked High Radiation Areas" for additional instructions for LHRA key and area controls.
(3) Health Physics job coverage details are provided in HPP 3104.01.
(ýo A, q-SITE: DAEC TASK TITLE: Site Evacuation While Escorting A Visitor.
JPM NUMBER: 2.4.39-xx REV. 0 RELATED PRA INFORMATION:
TASK NUMBERS:
K/A NUMBERS: Generic 2.4.39 APPLICABLE METHOD OF TESTING:
Discussion:
i-- Simulate/walkthrough: 1i-I Perform: W EVALUATION LOCATION: In-Plant: W Control Room:
r-7 Simulator: S'Other:
Time for Completion: 30 Minutes Time Critical: YES Alternate Path /
Faulted: NO TASK APPLICABILITY: RO/SRO RO/SRO be be added as needed.
I ..F- ir "RtiinTWr"ai ni Retain in: Training Pllroay Programm-Ileyr.
File Disposition: Reviewer and Approver Page 1 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 JPM Number: 2.4.39-xx 2.4.39-xx JPM
Title:
Site Evacuation While Escorting A Visitor.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS:
SAT: I I UNSAT:I COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retainedin examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Page 2 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 JPM BRIEFING/TURNOVER Add required site specific JPM briefing materialhere:
i.e., This section is read once for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initialconditions and initiatingcue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approved reference materialsnormally available including logs. Make all written reports, oralreports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure,you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
- I am a visitor on site.
- I am properly badged and have been briefed by Security and Health Physics.
- I have been touring the plant with another operator.
- The current escort has an emergency at home and must leave.
- You are the Auxiliary Operator and the OSS has directed you to take over escort duties until someone else can relieve you.
- Security has authorized the exchange of escorts.
INITIATING CUES:
"* Take time to review the "Visitor and escort Security Regulations" card provided by the operator you are relieving.
"* Inform me when you have completed the review of the "Visitor and escort Security Regulations" and are ready to continue with the tour.
Page 3 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 JPM PERFORMANCE INFORMATION Required Materials: Duane Arnold Energy Center- Visitor and Escort Security Regulation card General
References:
EPIP 1.3 Rev 9 Task Standards: 1. Escort the visitor to the Security Control Point.
- 2. Report to the Control Room for accountability.
Start Time:
NOTE: 'Critical steps are marked with a "Y" belo~w the perform~ancle step numnber. Failure to meet the standard for any critical step shall result in failure of this JPM. ~
Performance Step:
The candidate receives indication of a plant assembly. (Attachment 2)
Critical: N Standard: The candidate recognizes that a plant assemble has been ordered.
Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: Hand the candidate Attachment 2 containing the plant announcement.
Note: Due to not having a visitor badge the passage through doors will not be the same as if the visitor had a visitor badge. This is not being evaluated and Attachment 2 explains this to the candidate.
Note: The time critical portion of this JPM starts after the candidate acknowledges he understands Attachment 2 or starts performing actions based on attachment 2.
Time Critical Start Time:
Page 4 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 Performance Step: Escort the visitor to the Security Control Point and inform Security you are turning Critical: Y over the visitor to the due to the evacuation alarm.
Standard: The candidate takes the visitor to the SCP and turns him over to Security.
Performance: SATISFACTORY UNSATISFACTORY Comments: When you reach the SCP act as Security and when an attempt to turn over the visitor is made inform the candidate that "Security has taken responsibility for me as the visitor and you are no longer acting as my escort. Continue with any further actions that you would take for this event."
Performance Step: As the Auxiliary operator the candidate should report to the Control Room for Critical: Y accountability.
Standard: Report to the Control Room.
Performance: SATISFACTORY UNSATISFACTORY Comments: If the candidate calls the control room, for the purposes of this JPM, he would have been accounted for and would satisfy this JPM step.
Tfhe candidate has to have the visitor to the SCP and returned to the control room or has notified the control room of his whereabouts within 30 minutes of the evacuation alarm to complete this step satisfactorily.
Terminating Cues: , When the control room has been reached or has been contacted for accountability and the visitor is at the SCP.
The candidate and visitor have to be accounted for within 30 minutes o meet the EP requirements.
Time Critical and JPM Stop Time:
'p Page 5 of 8
QF-1 030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 TURNOVER SHEET INITIAL CONDITIONS:
- I am a visitor on site.
- I am properly badged and have been briefed by Security and Health Physics.
- I have been touring the plant with another operator.
- The current escort has an emergency at home and must leave.
0 You are to take over escort duties.
- Security has authorized the exchange of escorts.
INITIATING CUES:
"* Take time to review the "Visitor and escort Security Regulations" card provided by the operator you are relieving.
"* Inform me when you have completed the review of the "Visitor and escort Security Regulations" and are ready to continue with the tour.
l4 L- o Page 6 of 8
QF-1030-11 Rev. 1 (FP-T-SAT-30) 2.4.39-xx, Site Evacuation While Escorting A Visitor, Rev 0 ATTACHMENT I
/
JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES_ NO NIA
- 1. Are all items on the signature page filled in correctly? 11"' 1 []
1:
- 3. Can the required conditions for the JPM be appropriately established in the 1V El El simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in [iý" El 1:
accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what controls, E3 LI L indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data or E El EL incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task oI El performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if required? Lj E" L
- 9. Is the K/A appropriate-to the task and to the licensee level if required? Ej" El El
- 10. Have the performance steps been identified and typed (Critical / Sequence E EI lI
/ Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been E] EL identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the trainee? M-' El LI
- 13. Have all required cues (as anticipated) been identified for the evaluator to F1 L EI assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statemerts are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Va'ration Personnel Ebate Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 7 of 8
ATTACHMENT 2 You hear a plant alarm for 5 to 10 seconds followed by the following announcement:
"Attention all personnel, an Alert has been declared. Emergency Response Personnel shall report to their designated Emergency Response Facilities. Emergency Personnel assigned to the EOF shall depart the site via the South access and report to the EOF. All other personnel shall report to their designated onsite Assembly locations."
The alarm and announcement is made two more times.
NOTE:
Passage through plant doors is NOT being evaluated during this JPM.
It is understood that the evaluator does NOT have a visitor badge and that passing through doors would be performed differently if they were wearing a visitors badge.
Egress through plant doors the same way as before this JPM began.
Page 8 of 8
<ýý?o ý4, ý o"_
SITE: DAEC TASK TITLE: DETERMINE "REPORTABILITY (GROUP 1 ISOLATION)
JPM NUMBER: 2.1.14-02 REV. 1 RELATED PRA INFORMATION:
TASK NUMBERS: SRO 1.03 K/A NUMBERS: 2.1.14 (SRO 3.3)
APPLICABLE METHOD OF TESTING:
Discussion: Sim ulate/walkthrough: [= Perform:
EVALUATION LOCATION: In-Plant: Control Room: W Simulator: Other: tim Time for Completion: 30 Minutes Time Critical: NO Alternate Path /
Faulted: NO TASK APPLICABILITY: SRO RetPntinnn I if= e*f e*nh*, _L 4nJ,,y Retain in: Training Program File Disposition: Reviewer and Approver Page 1 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) S02O JPM 2.1.14-02, Determine Reportability (Group 1 Isolation),
Rev. 1 JPM Number: 2.1.14-02 JPM
Title:
DETERMINE REPORTABILITY (GROUP I ISOLATION)
Examinee:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: = 1 UNSAT: ZZZ COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated,the entire JPM should be retained.
Page 2 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 JPM BRIEFINGITURNOVER Add requiredsite specific JPM briefing material here:
i.e., This section is read once for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initialconditions and initiatingcue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approved reference materials normally available including logs. Make all written reports, oralreports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the traineeto continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL
'.. CONCERNS AS APPLICABLE ARE FOLLOWED.
Evaluator:
Provide the operator with the STUDENT COPY of this information and ATTACHMENT 1:
AR information Sheets 1, 2 and 3.
INITIAL CONDITIONS:
"* Today is 11/18/2002 at approximately 1700.
"* The plant was operating at 1000 MWT with the C Main Steam line isolated due the "C" outboard MSIV failing to close within its T.S. required time limits.
"* The "C" outboard MSIV has been closed and de-activated per T.S. and ACP 1410.7
"* The only LCO in effect at the time was for the C Outboard MSIV (CV-4419), 3.6.1.3. Condition A.
"* The surveillance began at 1620. During this surveillance, while Turbine SV-2 was being closed, the "A" and "B" steam line flows increased dramatically and a Group 1 isolation occurred at 1630.
"* The cause of the flow problem is under investigation.
- All control rods inserted on the resulting scram.
- RPV water level dropped below 170 inches and was recovered with the Condensate and Feed system.
- HPCI and RCIC were manually started in CST-CST mode for pressure control. Neither system injected into the RPV.
Page 3 of 11
QF-1 030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 0 A preliminary review of this event questions the ability of the equalizing header to redistribute flow to the available turbine valves during testing. There is NO evidence of a steam leak in the Turbine building.
& The plant is now stable at normal RPV level and 900-950 psig.
- This event occurred 30 minutes ago.
INITIATING CUES (IF APPLICABLE):
As the OSM determine the reportability of this event by completing the "Event Review" Section of the Action Request provided. (Attachment I sheet 3.)
Also state the requirements for:
"* Reporting Time limits
"* Who should be notified Page 4 of 11
QF-10301 1ev. (FP-T-SAT-30)
JPM Determine Reprtability (Group 1 Isolation),NRevT 1 STUDENT COPY --
"' INITIAL CONDITIONS:
0 Today is 11/18/2002 at approximately 1700.
0 The plant was operating at 1000 MWT with the C Main Steam line isolated due the "C" outboard MSIV failing to close within its T.S. required time limits.
The "C" outboard MSIV has been closed and de-activated per T.S. and ACP 1410.7 0 The only LCO in effect at the time was for the C Outboard MSIV (CV-4419), 3.6.1.3.
Condition A.
0 The surveillance began at 1620. During this surveillance, while Turbine SV-2 was being closed, the "A" and "B" steam line flows increased dramatically and a Group 1 isolation occurred at 1630.
S The cause of the flow problem is under investigation.
0 All control rods inserted on the resulting scram.
0 RPV water level dropped below 170 inches and was recovered with the Condensate and Feed system.
0 HPCI and RCIC were manuallv startedr in C.-T_.C'£T
--- .f..
- r. mrAT .f . . ,., iJ:,i. . ys.e......c.e.
into the RPV.
- A preliminary review of this event questions the ability of the equalizing header to redistribute flow to the available turbine valves during testing. There is NO evidence of a steam leak in the Turbine building.
- The plant is now stable at normal RPV level and 900-950 psig.
- This event occurred 30 minutes ago.
INITIATING CUES:
"_ As the OSM determine the reportability of this event by completing the "Event Review" Section of the Actio/
Request provided. (Attachment I sheet 3.)
(Note: This will normally be done on computer but manually fill out the form for the purposes of this exa Also state the requirements for:
"* Reporting Time limits
"* Who should be notified by title 1< C- 191 -
11 of ýf 67,poe:111 e5 5
Page Page 5 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 JPM PERFORMANCE INFORMATION Required Materials: DAEC Technical Specifications (ITS)
ACP 1402.3, "Plant Regulatory Reporting Activities" ACP 114.5, "Action Request System" 10CFR50 ACP 101.6, "Fitness for Duty" NGD 114.5, AR Form 294001-17 (Attachment A of this JPM)
EPIP 1.1 General
References:
DAEC Technical Specifications (ITS)
ACP 1402.3, Rev. 16 ACP 114.5, Rev. 22 10CFR50 ACP 101.6, Rev. 05 EPIP 1.1, Rev. 18 Task Standards: 1. INE checked Yes.
- 2. RE checked Yes.
- 3. Four-Hour Report identified.
Start Time: _____
NOTE: W en provdin "Evaluator Cues" to the6 examinee, care must be exersd to avoid prompiipng examinee Typially cues are only provided ~when the examinee's actionwartreivg the nfomaton (i.e. ~the ex~aminee looks or asks for the indication).
the NOTE: Criticlsepj1marked r with a "Y", below teprfrma~nce step number.Falrtometh stnadfor an rtcal step shalliresult in failure of this JPW air~oiee I Page 6 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 Performance Step: Determine if this event should be an Immediate Notification Event (INE)
Critical: Y Standard: INE Selected.
Performance: SATISFACTORY UNSATISFACTORY Comments: 10CFR 50.72(b)(2)(iv)(B) is the correct reference for the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reportability. It is not necessary for successful completion of this step.
10CFR 50.72(b)(3)(iv)(A) is the correct reference for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportability. It is not necessary for successful completion of this step.
This is a VALID ESF actuation per ACP 1402.3, Section 2.0 and Section 3.2.1.
and a valid RPS actuation.
Per ACP 1402.3 Section 2.0, an INE is any incident that requires a 1, 4, 24 ENS telephone notification to the NRC.
Performance Step: Determine if this event should be a Reportable Event. (RE)
Critical: Y Standard: RE Selected.
Performance: SATISFACTORY UNSATISFACTORY __
Comments: 10CFR 50.73(a)(2)(iv)(A) is the correct reference. It is not necessary for successful completion of this step.
Per ACP 1402.3 Attachment 2, Page 1 of 6.
Page 7 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 Performance Step: Determine if this event should be reported as an Emergency Class Event.
Critical: N Standard: EAL either selected or not selected. (Probably not selected)
Performance: SATISFACTORY UNSATISFACTORY __
Comments: There is no EPIP classification for this event. If the OSM/OSS declares an Unusual Event HU5 based on his own judgment, then the answer can be Yes.
Performance Step: Determine if this event resulted in a Limiting Condition for Operation (LCO).
Critical: N Standard: LCO not selected.
Performance: SATISFACTORY UNSATISFACTORY __
Comments:
Performance Step: Determine if this event resulted in a Technical Specification Violation.
Critical: N Standard: TSV either selected or not selected. (Probably not selected)
Performance: SATISFACTORY UNSATISFACTORY __
Comments: A possible reference to T.S. 5.4.1 could be made but more information would probably be required.
Page 8 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 Performance Step: Determine if the requirements of ACP 101.6 "Fitness for Duty" is applicable to Critical: N this event.
Standard: FFD either selected or not selected. (Probably not selected)
Performance: SATISFACTORY UNSATISFACTORY Comments: This is a judgment call on the part of the OSM/OSS per ACP 101.6, Section 3.1.11.
Performance Step: Determine the requirements for time of notification.
Critical: Y Standard: Four Hour Report identified.
Performance: SATISFACTORY UNSATISFACTORY Per ACP 1402.3 Attachment 3, Page 5 of 9.
Comments:
There is also an 8-hour ESF actuation report but it is not the most limiting and not a critical step.
Performance m _
Step:
Performance Step: Notify designated plant management personnel as soon as time/resources Critical: N permit.
Standard: The required personnel are notified:
"* Operations Manager
"* Manager, Licensing
"* Plant Manager
"* Site Vice President
"* NRC Resident Inspector
"* NRC Telephone via FTS-2000 Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: Applicable portions of the AR Event Review is complete.
Stop Time:
Page 9 of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 TURNOVER SHEET INITIAL CONDITIONS:
- Today is 11/18/2002 at approximately 1700.
- The plant was operating at 1000 MWT with the C Main Steam line isolated due the "C" outboard MSIV failing to close within its T.S. required time limits.
- The only LCO in effect at the time was for the C Outboard MSIV (CV-4419), 3.6.1.3. Condition A.
- The surveillance began at 1620. During this surveillance, while Turbine SV-2 was being closed, the "A" and "B" steam line flows increased dramatically and a Group 1 isolation occurred at 1630.
- The cause of the flow problem is under investigation.
- All control rods inserted on the resulting scram.
- RPV water level dropped below 170 inches and was recovered with the Condensate and Feed system.
- HPCI and RCIC were manually started in CST-CST mode for pressure control. Neither system injected into the RPV.
- A preliminary review of this event questions the ability of the equalizing header to redistribute flow to the available turbine valves during testing. There is NO evidence of a steam leak in the Turbine building.
- The plant is now stable at normal RPV level and 900-950 psig.
- This event occurred 30 minutes ago.
INITIATING CUES (IF APPLICABLE):
As the OSM determine the reportability of this event by completing the "Event Review" Section of the Action Request provided. (Attachment I sheet 3.)
Also state the requirements for:
- Reporting Time limits
- Who should be notified by title Page 10 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.1.14-02, Determine Reportability (Group 1 Isolation), Rev. 1 ATTACHMENT I JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly? [lý El El
- 3. Can the required conditions for the JPM be appropriately El El [*
established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in E 0l EI accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what i El Eli controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data Ifl El El or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon El E]
Li actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if 0- El El required?
- 9. Is the K/A appropriate to the task and to the licensee level if '* Li El required?
- 10. Have the performance steps been identified and typed (Critical 9 -- EL El Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task E1111 E ]l been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the [ El El trainee?
- 13. Have all required cues (as anticipated) been identified for the El: El evaluator to assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Dat6 Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 11 of 11
( ( (
ATTACHMENT 1 AR Information Sheet I of 3 Initiation !I Initiation (Cont.) I Event Review Assignment History -B Resolution/Approval AR # 27123 Parent AR 1 0 Initiator: (Required) Department . Group:
ED HARRISON I
I~OPERATIONS 71NONE ( CAQ (- CA (" CNAQ Initiated Date: Status: Signficance Level:
.11/18/2002 Open ITopic:
2i, Group I Isolation during turbine testing
Description:
'(RFe*
1FjII
- 1*
While operating with "C" Main Steam Line isolated, Turbine Stop Valve Testing was attempted. When _j
- 2 Stop Valve was tested, A and B Main Steam Line flow increased to the isolation setpoint. A Group 1 isolation and Reactor scram occurred at 1630 this date.
Immediate Actionsý Taken: [Required)
IPOI 5 completed. Commenced Cool down per IPOI 4. j I Keywords:
1__.GROIUP I REACTOR SCRAM.,
Assigned Person: Assigned Department: Due/Closed Date:
( (
ATTACHMENT I AR Information Sheet 2 of 3 II..272 - Actio Reus Inforn-t r * .. ... ... - * .. ..... .
Initiation 'Initiation L[fa*t j Event Review A Resolution/Approval Comments:
I-r F
J=
Associated Work Orders I Associated Documents I f
.1w i Change Requests I
Associated Equipment 1ID IN+m ISUS IQL lISI lIST IEQ HP Reviews 9
F 6
I I
fAdd A~achmnerit I
+ Dlete Attachmenit iF
(. ( (
ATTACHMENT I AR Information Sheet 3 of 3
..vie, II W,
Assignment History Resolution/Approval F Daily Review Complete r Operability Review Required r Review on hold for Opera.ions ModeIRUN MWTTH j1000 Current LCOs 3.6.1.3 A Outboard MSIV inoperable F INE I F RE F EAL F LCO. FT3V'. I- FFD F ",.R R/Y F Paft 21 Immediate Actions
-1 ITitle Person Contacted Date/Time Comments Operability Review Attachment Add 4ttachment OS5/AR Admin: Date/Time:
IVI1 I_ __
QF-1030-11 Rev. I (FP-T-SAT-30) 'ý5 ý' 0 114,r/, I L' to Nu" cellenc JOB PERFORLMANCIE MEASURE (JPM) 1 SITE: DAEC TASK TITLE: CORE ALTERATION-DETERMINE ACTIONS FOR A MISPLACED FUEL ASSEMBLY DURING A CORE RE-LOAD JPM NUMBER: 2.2.27-01 REV. 0 RELATED PRA INFORMATION:
TASK NUMBERS: SRO 1.04 K/A NUMBERS: GENERIC 2.2.27 (2.6/3.5)
APPLICABLE METHOD OF TESTING:
Discussion: Sim ulate/walkthrough: Perform:
EVALUATION LOCATION: In-Plant: Control Room:
Simulator: LKI Other: LI--
Time for Completion: 40 Minutes Time Critical: NO Alternate Path /
Faulted: NO TASK APPLICABILITY:
- ~D~e~ged by:, r/ -
Instructor Date 4ý
\Validation Instructor DYate (See JPM Validation Checkli,Attachment 1)
APPAP e /710-,?
Training Supervisor-Operations Date Date
- Iu'J U' I. I 1UJI 0I PUIII y "r I Uyli . Disposition: Reviewer and Approver Retain in: Training Program File Page I of 11
QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 JPM Number: 2.2.27-01 JPM
Title:
CORE ALTERATION-DETERMINE ACTIONS FOR A MISPLACED FUEL ASSEMBLY DURING A CORE RE-LOAD Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT:ZIZ UNSAT:ZIZ COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retained in examinee's recordif completed satisfactorily. If unsatisfactory performance is demonstrated,the entire JPM should be retained.
Page 2 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 JPM BRIEFING/TURNOVER Add requiredsite specific JPM briefing materialhere:
i.e., This section is read once for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initial conditions and initiating cue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approved reference materials normally available including logs. Make all written reports, oralreports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure,you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, ANDIOR RADIOLOGICAL
- CONCERNS AS APPLICABLE ARE FOLLOWED.
Evaluator: Give the candidate the following:
SATTACHMENT 1: RF-016 Fuel Moving Plan SSpent Fuel Pool map
- Core map INITIAL CONDITIONS:
- It is 12:10 hours
- The plant is in a re-fueling outage and a core off-load/shuffle has just begun.
- The CORE ALTERATIONS PREREQUIST CHECKLIST ATTACHMENT 1 has been completed satisfactorily.
- You have just received a turnover and are the SRO in charge of the refueling activities on the refuel floor.
- You are currently on step 14 of the Fuel Moving Plan.
- The first 13 steps were moves from the Core to the Spent Fuel Pool.
- Fuel Assembly YJ9902, in the Core at coordinates 13-10 has been verified and grappled, and being pulled from the core.
INITIATING CUES (IF APPLICABLE):
- Given the Fuel Moving Plan, the Spent Fuel Pool and Core map, walk the evaluator through the next Five (5) fuel moving steps.
Page 3 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 JPM PERFORMANCE INFORMATION Required Materials: RFP 403 General
References:
RFP 403, Rev. 6 Task Standards: 1. When the error is discovered, Stop Core Alterations
- 2. Identify the step when the error occurred.
- 3. Review and does not approve the Correction Fuel Moving plan.
Start Time:
,NOTE:*- ritical steps are marked with a Y eow the st nmer Failure to meet t .e.
standard for any critical step s'halJ result in failure of this JPMJ.
Page 4 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 Performance Step: SRO will review the fuel-moving plan and determine that there is a Fuel Critical: Y Assembly in the position where the currently grappled bundle is going. (17-04).
He will then perform the following:
"* Stop core alterations, (fuel move)
"* Direct that the current bundle be set back in its previous position. (13-10).
"* Notify the SM in the control room Standard: "* Stop core alterations, (fuel move)
"* Direct that the current bundle be set back in its previous position. (13-10).
He may ask for the REs concurrence. (Due to the situation the below prompt may be given to remind the Candidate that 13-10 is being moved. If prompted and he gives the correct response, the task is SAT.)
"* Notify the SM in the control room Performance: SATISFACTORY UNSATISFACTORY Comments: If the SRO does not mention the Fuel Assembly that is currently grappled:
As the SM, ask the SRO what he intends to do with the grappled Fuel Assembly?
Response: Fuel Assembly should go back where it originally came from Evaluator In this space write the response given by the SRO if it is different than the Standard.
If the SRO does not identify why he is taking actions:
Role-Play as the RE and ask why we are stopping the fuel move. When he indicates an error has been made ask him to show you the error so he can prepare a corrected Fuel Moving plan.
Page 5 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 Performance Step: SRO will review the Fuel Moving Plan and determine that in step 4, Fuel Critical: Y Assembly 17-14 was taken, and it should have been 17-04.
Standard: Identify the error occurred in step #4 Performance: SATISFACTORY UNSATISFACTORY Comments: Cue: When the error has been located, inform the SRO that the RE has developed a Fuel Moving Plan that will correct the error. Ask the SRO to review the new Fuel Moving Plan.
CUE: Provide the candidate with ATTACHMENT 2: Fuel Moving Plan correction sheet.
Performance Step:
Performance Step: SRO will review the new plan, and determine an error in the plan. The fuel Critical: Y assembly that will be taken back will have the wrong SFP coordinates on it Standard: Error in the correction plan discovered (SFP Coordinate 04-12-00 should be 03-12-00)
Performance: SATISFACTORY UNSATISFACTORY Comments: While the Candidate is reviewing the corrected fuel plan, if he asks if YJ4501 is the correct number on the wrong assembly, inform him that the number has been verified to be correct.
After the SRO reviews the new plan:
- If he finds the error, inform him that the RE will correct the error and return with another copy of the plan then terminate the JPM.
Terminating Cues: Terminate the scenario when RE leaves to correct the error in the new plan.
Stop Time:
Page 6 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
,PM 2.2.27-01, Core Alterations- Dete rmin eAcin
( for a Misplaced Fuel Assembly
- . ~During a Core Re-load Rev. 0 TURNOVER SHEET
- ATTACHMENT 1: RF-016 Fuel Moving Plan
- Spent Fuel Pool
- Core map INITIAL CONDITIONS:
- It is12:10 hours
- The plant is in a re-fueling outage and a core off-load/shuffle has just begun.
- The CORE ALTERATIONS PREREQUIST CHECKLIST ATTACHMENT 1 completed satisfactorily.
- You have just received a turnover and are the SRO in charge of the refueling activities on the refuel floor.
- You are currently on step 14 of the Fuel Moving Plan.
- The first 13 steps were moves from the Core to the Spent Fuel Pool.
- Fuel Assembly YJ9902, in the Core at coordinates 13-10 has been verified and grappled, and being pulled from the core.
INITIATING CUES (IF APPLICABLE):
- Given the Fuel Moving Plan, the Spent Fuel Pool and Core map, walk the evaluator through the next five (5) fuel moving steps.
Page 7 of 11
QF-1 030-11 Rev. I (FP-T-SAT-30)
JPM 2.2.27-01, Core Alterations-Determine Actions for a Misplaced Fuel Assembly During a Core Re-load, Rev. 0 ATTACHMENT I JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly? D' lI El
- 3. Can the required conditions for the JPM be appropriately []
El [l established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in El Dl L accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what i El LI controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data EK El El or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon El Ql actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if d El El required?
- 9. Is the K/A appropriate to the task and to the licensee level if 9- El El required?
- 10. Have the performance steps been identified and typed (Critical I El El Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task 0_ El El been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the El- El El trainee?
- 13. Have all required cues (as anticipated) been identified for the 9"' El E evaluator to assist task completion? I II __
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Validation Personnel /Dat6 Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 8 of 11
QF-1o030-i Rev. I (FP-T-SAT-30) ( (,Jr ,il 2.2.27-01 ATTACHMENT 1 Page 1 Of 38 RF-016 Fuel Moving Plan Plan Number 98003 Serial Comp ICA Move from Orient ICA Move to Orient Blade Cont Date Of Time Z-pos RPE SRO Assemb As...b Step of Chan Dechan Coord Coord Guide Rod Xfer Num. Number type Orient W/I Xfer 1 YJF372 FA COR 29-08 SW SFP 03-13-02 ANY N/A I Today 0950 140.2 F SW' 2 YJ9865 FA COR 23-10 NE SFP 05-15-02 NE N/A I Today 1000 140.3 7 SR5 3 YJ9839 FA COR 21-24 SW SFP 05-15-07 NE N/A I Today 1010 140.1 F SRG 4 YJ5405 FA COR 17-04 SW SFP 03-12-00 ANY N/A I Today 1020 140.2 F -Rj 5 YJ5374 FA COR 15-34 NE SFP 03-12-01 ANY N/A I Today 1030 140.3 9 SRG 6 YJ5462 FA COR 05-28 SW SFP 03-12-02 ANY N/A I Today 1040 140.1 97 SRG 7 YJ5434 FA COR 05-32 SW SFP 03-12-03 ANY N/A I Today 1050 140.2 7 =5" 8 YJ5469 FA COR 17-06 SE SFP 03-12-04 ANY N/A I Today 1105 140.3 F SR5" 9 YJ5441 FA COR 13-06 SE SFP 03-12-05 ANY N/A I Today 1115 140.1 57 5RG 10 YJ5377 FA COR 15-12 NW SFP 03-12-06 ANY N/A I Today 1130 140.2 -7 S-*f 11 YJ5428 FA COR 31-22 NE SFP 03-12-07 ANY N/A I Today 1140 140.3 F SRG 12 YJ5373 FA COR 11-16 NW SFP 03-13-00 ANY N/A I Today 1150 140.1 9 SRf 13 YJ5437 FA COR 05-14 SE SFP 03-13-01 ANY N/A I Today 1200 140.2 7 SRG NOTE: BEGINNING IN-CORE MOVES 14 YJ9902 FA COR 13-10 SE COR 17-04 SW N/A 1 15 YJF273 FA COR 11-28 NW COR 15-34 NE N/A 1 16 YJL501 FA SFP 04-20-05 SW COR 11-28 NW N/A 1 17 YJF344 FA COR 09-30 SE COR 05-28 SW N/A 1 18 YJL437 FA SFP 04-17-00 SW COR 09-30 SE N/A 19 YJ9807 FA COR 09-28 SW COR 05-32 SW N/A COMMENTS Page 9 of 11
QF-1030-11 Rev. I (FP-T-SAT-30)
( (Jr-n1 2.2.27-01 ATTACHMENT 2 Page la Of 38 Fuel Moving Plan correction sheet Plan Number 9800 3a____ ______ ____
Corn ICA Move from Orient ICA Move Orient Blade Cont Date Of Time Z- RPE SRO Assem b Assemb Dechan Step Serial Cha to Guide Rod Xfer of pos Num. Number P Coord type Coord Orient W/I Xfer n 13a YJ5401 FA SFP 04-12-00 SW COR 17-14 SE N/A I 13b YJ5405 FA COR 17-04 SW SFP 03-12-00 ANY N/A I COMMENTS The serial number of the incorrectly moved Fuel Assembly was YJ5401. This bundle has been verified at Position 03-12-00 in the Spent Fuel Pool. This is where the correction Fuel Moving Plan will begin. It will end when the Fuel Assembly at 17-04 is placed in the Spent Fuel Pool in position 03-12-00. Then this plan will be exited and the original plan will be continued at step 14.
APPROVED:
Page 10 of 11
QF-1030-11 Rev. I (FP-T-SAT-30) JPM 2.2.27-01 K-,-l Page 11 of 11
44 432- -
40 .--
39 S 396 _
35 34 32 27- 26 23 24 23'2 20 19 16 14 07 04
&AI '
Locations within the spent fuel pool are referred to by the following scheme: section number-row-column.
For example, the location reference for the shaded I box shown on the map belowwould be 04-15-03.
CASK P OL FPME 432109 87 D1 11109 8 7 65 43 2 1 38 37 DPW F- - F- F- - F ---I----t-- -
36 65 4 3210 35 7 65 4 3 21 0 9 87 6 5 43 2 1 0 7 6 5 4 2 1 0 34 I I I I I 1 I I I I I I I I II Il I 33 3 2 133 109 8 7 8 5 I~I I IITA]11 I 1 I I I I[ I I I I I II Il F LlII I I I[ I II I { I I I I I L L L " L I I I - I. . 1 1" .' I I I t
-m
- I 11111 Iii ii liii ii I I I I I I I I I I F-i- I I I I I I I I I I I I I I I I I I- --111TJ E I
11-111 k
1 1L i
I -- +
ii l . .
++ + - + -+..
T '+/-L- + I I8I654I21oIoI8765-
+- + -+ - 77 1 *g6-
-321o 7 1 0 7 6 4321C L 8765432 11 9 10 98765432 1 0 11 10
QF-1030-11 Rev. I (FP-T-SAT-30) 5Ro /ilký_
N~M#-7> I Cwmftted to Nuder EXcellence JOB PERFORMANCE MEASURE (JPM)
SITE: DAEC TASK TITLE: Dispatch An Operator Into The Plant When The TSC/OSC Are Not Activated JPM NUMBER: 2.4.38-02 REV. 3 RELATED PRA INFORMATION:
TASK NUMBERS: SRO 3.01 KIA NUMBERS: 2.4.38 SRO 4.0 APPLICABLE METHOD OF TESTING:
Discussion: Simulate/walkthrough: 3 Perform: -
EVALUATION LOCATION: In-Plant: LII Control Room:
Simulator: SJOther:
Time for Completion: 20 Minutes Time Critical: N Alternate Path /
N Faulted:
TASK APPLICABILITY: SRO Additional signatures may be added as needed.
Instructor Date Vaiain Instructor /"Date (See JPM Validation Checklist, Attachment 1)
Training Supervisor Date Retention: Lite ot policy + lOyrs. Disposition: Reviewer and Approver Retain in: Training Program File Page 1 of 13
QF-1 030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSCIOSC are not activated., Rev. 3 JPM Number: 2.4.38-02 JPM
Title:
Dispatch an operator into the plant when the TSC/OSC are not activated.
Examinee: Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS: SAT: [1 ] UNSAT: L l COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EVALUATOR'S SIGNATURE:
NOTE: Only this page needs to be retainedin examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated,the entire JPM should be retained.
Page 2 of 13
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 JPM BRIEFING/TURNOVER Add requiredsite specific JPM briefing materialhere:
i.e., This section is readonce for the entire package of JPMs. It is not requiredto review this section for every JPM being performed in the package. The initialconditionsand initiatingcue(s)/tasks to be performed should be read and then provided to the examinee.
You may use any approvedreference materials normally available includinglogs. Make all written reports, oralreports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are requiredto be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator,the JPM administratorshould only give cues that are not indicated on the simulator. If simulatorindication is sufficient to indicate the completion of a step, the JPM administratorshould not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, ANDIOR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
EVALUATOR: Provide Candidate with ATTACHMENT A: DOSE PROJECTION & ARM DATA SHEET EVALUATOR: Provide Candidate with SEP 305 ATTACHMENT I marked up to step 7(c).
INITIAL CONDITIONS:
"* You are on weekend duty as the Shift Manager.
"* An Alert emergency FA-1 has been declared due to a Loss of Coolant accident.
"* The Evacuation alarm has been sounded and a Plant Assembly has been initiated.
"* RPV level is being maintained at approximately 20 inches with both Core Spray pumps, aligned to the CSTs, and the A Loop of RHR in the LPCI mode.
"* There is no indication of fuel damage at this time, but radiation levels are rising in the Reactor Building.
Refuel Floor ARM readings have doubled and some readings on the Reactor Bldg. 3rd floor have risen by a factor of 10. At present, there are no EOP-3 entry conditions. Operators are continuing to monitor in-plant and effluent radiation levels. See Attachment A of this JPM.
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QF-1 030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3
- " 0 There are indications of RHR suction strainer blockage on the B Loop of RHR. Operators are performing "ECCS Suction Strainer Blockage" SEP 305 Attachment 1. The Radwaste operator confirmed that V-1 9 9 was closed. Operators have completed up to Step 7(c) and are prepared to back flush around the D RHR pump as soon as an operator can be dispatched.
- I will role-play the operator being dispatched.
INITIATING CUES (IF APPLICABLE):
0 Dispatch an operator to back flush around the D RHR pump in this plant condition.
This task is NOT time critical.
Inform the evaluator when you have completed the task.
Page 4 of 13
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSCIOSC are not activated., Rev. 3 JPM PERFORMANCE INFORMATION Required Materials: EPIP 2.5 SEP 305 Provide a copy of Attachment A, In-Plant Radiation Level.
Provide a copy of SEP 305 Attachment 1 marked up to Step 7(c).
General
References:
EPIP 2.5 SEP 305 Task Standards: 1. Determines that the OSM/OSS has the authority to dispatch operators.
- 2. Operator briefed on radiological concerns.
Start Time:
Performance Step: (TSC and OSC not operational) If suspected abnormal radiological conditions Critical Y exist, dispatch of Operations personnel will be at the discretion of the OSM/OSS.
Standard: Determines that the OSM/OSS has the authority to dispatch operators.
(Consider this step completed if the operator is dispatched.)
Performance: SATISFACTORY UNSATISFACTORY Comments: Abnormal radiological conditions exist per handout Attachment A and per an SEP 305 Caution.
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QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSCIOSC are not activated., Rev. 3 Performance Step: Operators should be briefed on associated precautions and pertinent Critical N operational information utilizing ATTACHMENT 2, "In-Plant Briefing Form",
Standard: As part of the briefing, instruct the operator he will be performing SEP 305 "ECCS Suction Strainer Blockage".
Performance: SATISFACTORY UNSATISFACTORY Comments: A brief of how to perform SEP 305 is NOT required but that the task to be performed is SEP 305 should be part of the briefing.
Performance Step: Emergency Coordinator informed during his Control Room briefing.utilizing Critical N Form CR-04, 'Control Room to TSC Command and Control Transfer Checklist'.
Standard: Logs or notes that the operator is being sent to perform SEP 305 on Form CR-04.
Performance: SATISFACTORY UNSATISFACTORY Comments: It is not critical to log these on Form CR-04 but it needs to identified some way to provide the information to the oncoming EC.
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QF-1030-11 Rev. 1 (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 Performance Step: Operators should be briefed on associated precautions and pertinent Critical Y operational information utilizing Attachment 2, "In-Plant Operator Briefing Form", to include:
(1) Expected radiological conditions (2) Stay times (3) Access routes (4) Associated precautions (5) Increased exposure limits (6) Estimates of total exposure Standard: Expected radiological conditions
"* e.g.: High Rads in upper elevations of RB
"* e.g.: Rad levels may change when backflow has been initiated3 Stay times
"* e.g.: Sets a time limit for this operation
"* e.g.: Exit if/when ED alarms Access routes
"* e.g.: Enter the RB through Access Control
"* e.g.: "Don't go out the back door"
"* e.g.: Return/exit through Access Control Associated precautions
"* e.g.: Don't go to upper elevations of RB
"* e.g.: Take a Dose Rate instrument
"* e.g.: Monitor ED (Continued on next page)
Page 7 of 13
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 Increased exposure limits (Continued from previous "* e.g.: Use an Emergency ED (with higher limits) page)
"* e.g.: Sets an exposure limit Estimates of total exposure
"* e.g.: Determine exposure based on the estimated time required for the job and dose rates in the area.
"* An area dose rate of 20 mR/hr would give 1mr per 5 minutes and would be consistent with the expected exposure 0
S S
0 Performance: SATISFACTORY UNSATISFACTORY Comments: CUE: If asked about area dose rates inform the candidate that the HP has determined that general area rad levels in the area are 20 mR/hr.
Performance Step: Personnel dispatched should don protective clothing, dosimetry, respiratory Critical: N equipment as necessary, and obtain a high range survey instrument.
Standard: Determine dosimeter and high range survey instruments must be used.
Performance: SATISFACTORY UNSATISFACTORY Comments: OSS may direct the operator to stop at access to get the appropriate equipment or assign an HP to assist in determining the required protective equipment.
Sending or assigning the HP to assist satisfies the satisfactory performance of this step.
I Page 8 of 13
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 Performance Step: Health Physics Technician informed of the operator actions and instruct him to Critical: N provide assistance as necessary.
Standard: HP informed of the operator actions and to provide assistance.
Performance: SATISFACTORY __ UNSATISFACTORY Comments: CUE: Role play as the HP and inform the OSM/OSS that you are standing by at access ready to support the operator.
If HP is brought to the Control Room for the briefing to support the task then this step should be marked as satisfactory.
Performance Step: Personnel closely monitor in-plant and effluent radiation levels Critical: N (trends/changes).
Standard: May verify that someone is monitoring in-plant and effluent radiation levels.
(Given in Initiating Cue)
Performance: SATISFACTORY UNSATISFACTORY Comments: If asked someone is still tracking plant radiation readings.
Performance Step: All personnel dispatched should exit through Access Control.
Critical: N Standard: Direct the operator to enter and exit the plant through access control.
Performance: SATISFACTORY UNSATISFACTORY Comments:
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QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 Performance Step: Dispatch the operator into the plant.
Critical: N Standard: Operator dispatched into the plant.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Stop Time:
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QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 TURNOVER SHEET INITIAL CONDITIONS:
"* You are on weekend duty as the Shift Manager.
"* An Alert emergency FA-1 has been declared due to a Loss of Coolant accident.
"* The Evacuation alarm has been sounded and a Plant Assembly has been initiated.
"* RPV level is being maintained at approximately 20 inches with both Core Spray pumps, aligned to the CSTs, and the A Loop of RHR in the LPCI mode.
"* There is no indication of fuel damage at this time, but radiation levels are rising in the Reactor Building.
Refuel Floor ARM readings have doubled and some readings on the Reactor Bldg. 3rd floor have risen by a factor of 10. At present, there are no EOP-3 entry conditions. Operators are continuing to monitor in-plant and effluent radiation levels. See Attachment A of this JPM.
"* There are indications of RHR suction strainer blockage on the B Loop of RHR. Operators are performing "ECCS Suction Strainer Blockage" SEP 305 Attachment 1. The Radwaste operator confirmed that V-1 9 9 was closed. Operators have completed up to Step 7(c) and are prepared to back flush around the D RHR pump as soon as an operator can be dispatched.
"* The TSC and OSC are not yet operational.
"* I will role-play the operator being dispatched.
INITIATING CUES (IF APPLICABLE):
- Dispatch an operator to back flush around the D RHR pump in this plant condition.
This task is NOT time critical.
Inform the evaluator when you have completed the task.
Page 11 of 13
QF-1030-11 Rev. I (FP-T-SAT-30)
JPM 2.4.38-02, Dispatch an operator into the plant when the TSC/OSC are not activated., Rev. 3 ATTACHMENT I
-' JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly? 1Z Ei El
- 3. Can the required conditions for the JPM be appropriately LI I established in the simulator if required?
- 4. Does the performance steps accurately reflect trainee's actions in E2- ElI LI accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what a EL LI controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6. Has the completion time been established based on validation data Li [-E L]
or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon LI El actual task performance requirements?
- 8. Is the Licensee level appropriate for the task being evaluated if LI LII required?
- 9. Is the K/A appropriate to the task and to the licensee level if [] El E]
required?
- 10. Have the performance steps been identified and typed (Critical / El LI Sequence I Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task LI LI been identified and made available to the trainee?
- 12. Are all references identified, current, accurate, and available to the 7 Li LI trainee?
- 13. Have all required cues (as anticipated) been identified for the EL I: LI evaluator to assist task completion?
All questions/statements must be answered "YES" or the JPM is not valid for use. If all questions/statements are answered "YES" then the JPM is considered valid and can be performed as written. The individual(s) performing the validation shall sign and date this form.
Psn
'Valida-ion /Date -Validation Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Validation Personnel /Date Validation Personnel/Date Page 12 of 13
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DOSE PROJECTION & ARM DATA SHEET MONITOR # MONITOR LOCATION UNITS ALARM MAX NORM MAX TIME TIME TIME TIME LEVEL SAFE :00 :15 :30 :45 RT-9180 RB 747' WASTE COLL, mR/hr 250.0 1 1 RT-9166 RB 716'SW, RW PUMP ROOM mR/hr 50.0 3 3 RT-9178 RB 855' SPENT FUEL STORAGE AREA mR/hr 19.0 100 1000 3 6 RT-9163 REFUEL FLOOR NORTH mR/hr 10.0 10 100 1.5 3 RT-9176 RB 757' TIP mR/hr 100.0 60 600 5 6 RT-9170 CRD REPAIR ROOM mR/hr 22.0 15 150 3 4 RT-9167 RB 757' RR ACCESS mR/hr 12.0 10 100 1.5 2 RT-9162 CONTROL ROOM mR/hr 3.0 1 1 RT-9173 RB 786' RESIN HANDLING mR/hr 80.0 100 1000 50 60 RT-9177 RB 786' CU PH. SEPARATOR mR/hr 100.0 20 200 t0 15 RT-9155 RB 812' JUNGLE ROOM, C/U DEMIN mR/hr 2500.0 60 600 2.5 2.5 AREA RT-9156 RB 786' RWCU PUMP ROOM mR/hr 1000.0 1000 10000 22 30 RT-9157 RB 786' RWCU HEAT EXCH. mR/hr 2000.0 1000 10000 30 37 RT-9171 RB 812' VENTILATION EQUIP. mR/hr 2.2 60 600 2 4 RT-9153 Rx B 855 NEW FUEL STORAGE AREA mR/hr 10.0 10 100 2 7 RT-9168 RB 757' CRD NORTH mRlhr 10.0 10 100 3 4 RT-9175 RB 833' COND. PH. SEPARATOR TANK mRPhr 150.0 3 25 RT-9169 RB 757' CRD SOUTH mR/hr 10.0 10 100 1 2 RT-9164 REFUEL FLOOR SOUTH mR/hr 20.0 10 100 1 2 RT-9159 TB 734' FEED PUMP AREA mRlhr 2.3 .3 .3 RT-9158 TB 734'COND. PUMP AREA mR/hr 5.0 .5 .5 RT-9160 TB 734'LUBE OIL AREA mR/hr 10.0 .5 .5 RT-9174 TB 734' SUMP AREA mR/hr 2.5 .4 .4 RT-9172 HOT LAB mR/hr 2.5 .2 .4 RT-9179 TB 780' TURBINE FRONT STANDARD mRlhr 25.0 10 10 RT-9161 MACHINE SHOP mRPhr 5.0 .06 .07 RT-9151 RW CONTROL ROOM mR/hr 2.7 .3 1.0 RT-9152 RW 786' RW, SAMPLE TANK mR/hr 20.0 .6 2 CORRIDOR RT-9154 RW 757' RW, DRUMMING AREA mR/hr 15.0 .5 .6 RT-9165 ACCESS CONTROL mR/hr 2.5 03 .03 CR 01-U3 REVO 01/16/98 ATTACHMENT A
SEP 305 ECCS SUCTION STRAINER BLOCKAGE ATTACHMENT I BACKFLUSHING "B" RHR STRAINER The instructions provided below should only be performed when directed by the OSS. Operators should take precautions and coordinate Reactor Building entry with Health Physics when possible due to the potential for high radiological conditions in the plant.
11 (1) Ensure that "A" RHR Loop is pressurized by either of the following: 6 (a) RHR Pumps 1P-229A/C per 01-149.
(b) EOP Alternate Injection Systems:
System Procedure RHRSW AlP 401 ESW AlP 402 GSWIWW AlP 403 Fire Water AlP 404 Cond SW AlP 405 (2) Secure RHR Pumps 1P-229B and 1P-229D. 6 (3) At Panel 1C03, verify that the following valves are closed:
Valve Description MO-1903 OUTBD DRYWELL SPRAY MO-1904 OUTBD LPCI INJECT MO-1 932 OUTBD TORUS COOLING/SPRAY MO-1 920 D PUMP SHUTDOWN CLG SUCTION MO-1912 B PUMP SHUTDOWN CLG SUCTION SEP 305 Page 1 of 4 Rev- 2
SEP 305 ECCS SUCTION STRAINER BLOCKAGE ATTACHMENT I BACKFLUSHING "B" RHR STRAINER (4) At Panel 1 C03, verify that the following valves are open:
Valve Description MO-1940 B HEAT EXCH BYPASS MO-1989 TORUS SUCTION NOTE V-19-9, RHR DRAIN HEADER TO RW SURGE TANK ISOLATION, is normally closed. The position of V-19-9 may be verified by either of the following methods:
"* Locally verify position, V-19-9 is located at Bay 14 in the Torus Room.
" After the flowpath to the suction strainers is established, the Radwaste operator can be contacted to determine if the valve is open by observing Radwaste Surge Tank levels in lieu of physically checking valve position.
(5) Verify V-19-9, RHR DRAIN HEADER TO RW SURGE TANK ISOLATION, closed.
6 (6) At Panel 1C03, verify open MO-2010, RHR CROSSTIE, to pressurize the "B" RHR Loop.
NOTE The backflush flowpath can be established around either or both RHR Pumps, 1 P-229B or 1 P-229D. A backflush flowpath around RHR Pump 1P-229D is preferred because the manual isolation valves are more accessible.
SEP 305 Page 2 of 4 Rev. 2
SEP 305 ECCS SUCTION STRAINER BLOCKAGE ATTACHMENT 1 BACKIFLUSHING "B" RHR STRAINER CAUTION Secure backflushing if torus level increases above 16 feet.
(7) To backflush around RHR Pump1P-229D, proceed as follows:
(a) At Panel 1C03, open MO-1 921, D PUMP TORUS SUCTION.
(b) At Panel 1C03, close MO-1913, B PUMP TORUS SUCTION, if backflush around RHR Pump 1P-229B will not be performed.
(c) In the NW Corner Room, open V-19-7, 1P-229D SUCTION HEADER DRAIN TO RADWASTE ISOL.
(d) In the NW Corner Room, throttle open V-19-12, 1P-229D DISCHARGE HDR TO RW SURGE TANK ISOLATION, to start the backflush.
(8) To backflush around RHR PumplP-229B, proceed as follows:
(a) At Panel 1C03, open MO-1913, B PUMP TORUS SUCTION.
(b) At Panel 1C03, close MO-1921, D PUMP TORUS SUCTION, if backflush around RHR Pump 1P-229D will not be performed.
(c) In the NW Corner Room, open V-19-10, 1P-229B SUCTION HDR TO RW SURGE TANK ISOLATION.
(d) In the NW Corner Room, throttle open V-1 9-13, 1 P-229B DISCHARGE HDR TO RW SURGE TANK ISOLATION, to start the backflush.
SEP 305 Page 3 of 4 Rev. 2
SEP 305 ECCS SUCTION STRAINER BLOCKAGE ATTACHMENT I BACKFLUSHING "B" RHR STRAINER (9) Backflush "B" RHR suction strainer for one-two minutes, then close the respective isolations:
(a) If backflushing via RHR Pump 1P-229D, close V-1 9-7 and V-19-12.
(b) If backflushing via RHR Pump 1 P-229B, close V-19-10 and V-19-13.
(10) Coordinate with the OSS to either:
(a) Repeat the backflush per Steps (1) through (9).
(b) Restore the RHR System to the mode of operation specified by the OSS per 01-149.
SEP 305 Page 4 of 4 Rev- 2