ML17205A382
| ML17205A382 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/23/2017 |
| From: | Jesse Seymour Operations Branch III |
| To: | NRC/RGN-III/DRS/OLB |
| Shared Package | |
| ML16319A344 | List: |
| References | |
| Download: ML17205A382 (413) | |
Text
JPM JOB PERFORMANCE MEASURE Page 1 of 14 JPM TITLE: Review a RCS Leak Rate Determination JPM NUMBER: PBN JPM P119.223e.SRO REV. 0 TASK NUMBER(S) / PBN P119.223.SRO / Review completed procedures TASK TITLE(S):
K/A NUMBERS: 2.1.7 K/A VALUE: 4.4 / 4.7 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform:
EVALUATION LOCATION: In-Plant: Control Room:
Simulator: Other:
Lab:
Time for Completion: 15 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 2 of 14 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 3 of 14 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 4 of 14 SIMULATOR SET-UP: (Only required for simulator JPMs)
Simulator Setup Instructions:
1.
2.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: 1. OI-55, Primary Leak Rate Calculation (Procedure marked up as completed through step 5.5.8 and Attachment A completed through step 5.0)
- 2. Calculator General
References:
- 1. OI-55, Primary Leak Rate Calculation
- 2. Technical Specifications Task Standards: Review and identify errors associated with OI 55 Primary Leak Rate Calculation and determine TSAC impact per OI-55.
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 5 of 14 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:
You are OS2.
Unit 1 is operating at stable full reactor power with indications of a primary leak.
The Letdown Gas Stripper (LDGS) is bypassed per OI 17, Letdown Gas Stripper Operation.
AOP-1A Unit 1 Reactor Coolant Leak was entered and is currently in progress.
The PAB AO has reported the following Charging Pumps seal leak rates:
1P-2A = 20 cc/min 1P-2B = 15 cc/min 1P-2C = 25 cc/min Steam Generator Tube Leakage (SGTL ) LRSGTL = 0 Reactor Component Leak Rate LRRC = 0 Non RCPB Leakage LRP3 = 0 The following plant parameters were observed at time 0400:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 46.0 %
VCT Level 45.0 %
U1 PRT level 74.7%
U1 RCDT Level 52 %
The following plant parameters were observed at time 0420:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 45.7%
VCT Level 43.8 %
U1 PRT level 74.7%
U1 RCDT Level 52.5 %
No borations, dilutions or diverts to HUT took place.
There is no Chemistry sampling in progress.
C04 has completed OI 55 through Attachment A, Primary Leak Rate Worksheet, up to Step 6.0 and has presented it to you for your review.
INITIATING CUES (IF APPLICABLE):
Review the Primary Leak Rate Worksheet Complete remaining steps of OI 55, Primary Leak Rate Calculation, starting at Step 5.6.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 6 of 14 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 Attachment A Critical N 2.0 RECORD the following data:
RCS LEAK RATE DATA Standard: The examinee checks data accurately entered from the initial conditions and calculates the results.
Time change 20 minutes RC Terror (Terr) change is 0°F PZR Level change is 0.3 % = 19.47 gal.
VCT Level change is 1.2 % = 15.168 gal.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 2 Attachment A Critical N 2.0 RECORD the following data:
RMW AND BA ADDITIONS Standard: The examinee verifies that this step does not apply Evaluator Note: Per the initial conditions, no RMW or acid additions occurred.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 7 of 14 Performance Step: 3 Attachment A Critical N 2.0 RECORD the following data:
DIVERT Standard: The examinee verifies that this step does not apply Evaluator Note: Per the initial conditions, no diverts occurred.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 4 Attachment A Critical Y 3.0 Calculate RCS leak rate:
CALCUALTED RCS LEAK RATE Standard: The examinee calculates RCS leak rate of 1.732 gpm (1.725 to 1.735 gpm) and determines that recorded RCS leak rate is in error.
Evaluator Note: First error Time change of 30 min vice 20 min was used to calculate LRRCS.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 8 of 14 Performance Step: 5 Attachment A Critical N 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.1 CALCULATE Identified RCS Leak Rate:
IDENTIFIED RCS LEAK RATE DATA Standard: The examinee checks data accurately entered from the initial conditions and calculates the results.
Time change 20 minutes PRT Level change 0 gpm The examinee calculates RCDT Level change of 0.088 gpm.
SG Tube Leakage (LRSGTL) 0 gpm Reactor Component Leak Rate (LRRC) 0 gpm Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 6 Attachment A Critical Y 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.2 CALCULATE Non Reactor Coolant Pressure Boundary :
Non Reactor Coolant Pressure Boundary Standard: The examinee calculates Charging Pump Seals (LRP2) of 0.016 gpm and determines the recorded value is in error.
Non RCPB Leakage (LRP3) 0 gpm Evaluator Note: Second error Charging pump seal leakage was miscalculated by a factor of 10.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
PBN JPM P119.223e.SRO, Review a RCS Leak Rate JPM Determination, Rev. 0 Page 9 of 14 Performance Step: 7 Attachment A Critical Y 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.3 CALCULATE RCS Unidentified leakage:
UNIDENTIFIED RCS LEAK RATE Standard: Based on corrected values, the examinee recalculates Unidentified Leak Rate (LRUID) to be 1.628 gpm (1.625 to 1.635 gpm) rather than the original value of 0.909 gpm. (errors carried forward)
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 8 5.6 IF the Unit is in Mode 5, THEN perform Attachment B, Cold Critical N Shutdown Primary Leak Rate Worksheet as follows:
Standard: The examinee verifies that this step is not applicable.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 9 5.7 IF the plant is in Mode 1 through 4, AND Pressure Boundary Critical N leakage is detected, THEN ENTER Technical Specification LCO 3.4.13 Action Condition B.
Standard: The examinee verifies that the action condition entry is not required at this time.
Evaluator Cue: Relief crew is preparing for a containment entry to inspect for pressure boundary leakage.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P119.223e.SRO, Review a RCS Leak Rate Page 10 of Determination, Rev. 0 14 Performance Step: 10 5.8 IF RCS Unidentified Leakage shows a significantly increasing trend, Critical N OR reaches 0.15 gpm, THEN PERFORM the following actions:
5.8.1 INFORM the Shift Manager and Duty Station Manager.
5.8.2 CHECK the following at least once per hour:
- a. Containment particulate monitor (RE 211) high and low values.
- b. Containment radiogas monitor (RE 212) high and low values.
- c. Containment humidity.
5.8.3 PERFORM the RCS leakrate calculation of Section 5.5 or 5.6 as applicable at least once per shift.
5.8.4 OBTAIN a sump A sample and have Chemistry analyze to aid in determining the source of leakage.
5.8.5 DIRECT Chemistry to sample and analyze Containment atmosphere for hydrogen content and REPORT the results to the SM.
5.8.6 NOTIFY Engineering to review Containment Air Cooler performance and cleaning frequencies to determine if an adverse long term trend exists.
5.8.7 IF a containment inspection is warranted to localize the source of leakage, THEN the inspection should consist of the following:
- a. Evidence of steam in containment.
- b. Wetness on the floor.
- c. Boric Acid deposits.
- d. Abnormal packing or gasket leakage.
Note: A thorough examination should be performed of the reactor vessel head using binoculars or other methods allowed by RP.
- e. Reactor vessel head locations as permitted by Health Physics.
Evaluator Cue: Shift Manager will have OS2 address actions contained in step 5.8 Standard: The examinee identifies actions required as listed by procedure Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P119.223e.SRO, Review a RCS Leak Rate Page 11 of Determination, Rev. 0 14 Performance Step: 11 5.9 IF the RCS leak rate approaches 0.20 gpm and the cause is known, Critical N THEN the priority of the work order associated with the contributor SHALL be increased.
Standard: The examinee verfies that this step is not applicable because the cause of the leakage is unknown.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 12 5.10 IF the plant is in Mode 1 through 4, AND Unidentified Leakage Critical Y exceeds one gpm, THEN ENTER Technical Specification LCO 3.4.13 Action Condition.
Standard: The examinee identifies RCS unidentified leakage >1 gpm is in excess of limit for Technical Specifications LCO 3.4.13.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 13 5.11 IF Unidentified Leakage is greater than 1.0 gpm OR Identified Critical N Leakage is greater than 10 gpm, THEN INITIATE AOP 1A, Reactor Coolant Leak.
Standard: The examinee identifies that AOP 1A is already in effect, per initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P119.223e.SRO, Review a RCS Leak Rate Page 12 of Determination, Rev. 0 14 Performance Step: 14 5.12 IF the plant is in Mode 1 through 4, AND Identified Leakage Critical N exceeds 10 gpm, THEN ENTER Technical Specification LCO 3.4.13 Action Condition.
Standard: The examinee identifies RCS identified leakage is less than 10 gpm.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Terminating Cues: JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
JPM PBN JPM P119.223e.SRO, Review a RCS Leak Rate Page 13 of Determination, Rev. 0 14 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Filename: PBN JPM P119.223e.SRO Rev 0.doc TR-AA-230-1003-F10 Revision 1 Page 13 of 14
JPM JOB PERFORMANCE MEASURE Page 14 of 14 TURNOVER SHEET INITIAL CONDITIONS:
You are OS2.
Unit 1 is operating at stable full reactor power with indications of a primary leak.
The Letdown Gas Stripper (LDGS) is bypassed per OI 17, Letdown Gas Stripper Operation.
AOP-1A Unit 1 Reactor Coolant Leak was entered and is currently in progress.
The PAB AO has reported the following Charging Pumps seal leak rates:
1P-2A = 20 cc/min 1P-2B = 15 cc/min 1P-2C = 25 cc/min Steam Generator Tube Leakage (SGTL ) LRSGTL = 0 Reactor Component Leak Rate LRRC = 0 Non RCPB Leakage LRP3 = 0 The following plant parameters were observed at time 0400:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 46.0 %
VCT Level 45.0 %
U1 PRT level 74.7%
U1 RCDT Level 52 %
The following plant parameters were observed at time 0420:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 45.7%
VCT Level 43.8 %
U1 PRT level 74.7%
U1 RCDT Level 52.5 %
No borations, dilutions or diverts to HUT took place.
There is no Chemistry sampling in progress.
C04 has completed OI 55 through Attachment A, Primary Leak Rate Worksheet up to Step 6.0 and has presented it to you for your review.
INITIATING CUES (IF APPLICABLE):
Review the Primary Leak Rate Worksheet Complete remaining steps of OI 55, Primary Leak Rate Calculation, starting at Step 5.6.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Filename: PBN JPM P119.223e.SRO Rev 0.doc TR-AA-230-1003-F10 Revision 1 Page 14 of 14
JPM JOB PERFORMANCE MEASURE Page 1 of 11 JPM TITLE: Complete a Calculation Review of TS 32 JPM NUMBER: PBN P119.203d.SRO REV. 1 TASK NUMBER(S) / P119.203.SRO TASK TITLE(S): Maintain Required Logs and Records K/A NUMBERS: 2.2.23 K/A VALUE: 4.6 Justification (FOR K/A VALUES <3.0): N/A TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other: X Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 2 of 11 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 3 of 11 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0 New JPM Rev. 1 Updated for the 2017 NRC ILT Exam.
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 4 of 11 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: TS 32, Miscellaneous Equipment Checks (Monthly) Unit 1 Calculator Steam Tables General
References:
TS 32, Miscellaneous Equipment Checks (Monthly) Unit 1 Task Standards: Identify discrepancies (two) not properly noted by the Control Operator, and determine that test results for CET based subcooling margin are NOT within acceptance criteria.
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 5 of 11 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:
Both Units are at rated power.
UNIT 1 PPCS Yellow Core Exit Thermocouple indications were acting erratically and have since been repaired.
PPCS is available.
CO3 just completed a partial TS 32, Miscellaneous Equipment Checks (Monthly) Unit 1, Attachment B, Calculations.
CO3 has just requested that you conduct the SRO review for the completed TS 32, Attachment B.
INITIATING CUES:
You are directed you to perform the SRO review of TS 32, Attachment B.
Evaluator Note: This JPM requires supplying a copy of TS 32 filled out up to the applicable steps of the procedure and Attachment A and B. Provide a calculator and steam tables if the JPM is not conducted in the simulator or control room.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 6 of 11 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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.
NOTE: Will need to provide the student with a copy of TS 32 completed through steps to conduct attachment A and B for the Yellow Subcooling channel on tan paper; and a calculator if one if not readily available.
Performance Step: 1 Reviews Procedure and Attachments Critical N Standard: The examinee reviews TS 32 prior to beginning calculation verification Evaluator Note: Provide a copy of TS 32 with required steps and Attachments A and B for Yellow Subcooling monitor being completed Performance: SATISFACTORY UNSATISFACTORY Comments:
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 7 of 11 Performance Step: 2 Reviews Attachment B calculations prior to signing that review is complete.
Critical N Standard: Reviews Attachment B calculations and determines that errors exist Evaluator Note: The next three JPM steps list the errors that are in the attachment, it is not critical that the errors be discovered in the order listed in the JPM, but all three must be identified.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Reviews procedure step:
Critical Y 2.0 DETERMINE average Core Exit Thermocouple temperature for each channel:
- b. T/C Yellow Channel.
Standard: The examinee determines that T/C Avg was calculated incorrectly.
The examinee calculates a correct value for T/C Avg of 604.4°F, and corrects the error carried forward to Steps 3.b. and 5.e. based on this result.
Evaluator Cue: If notified of error in calculation then acknowledge report and ask student to continue with performance of the procedure. The error may not be reported until review is completed.
Evaluator Note: For Step 2.b the acceptable range =603.7 to 604.8°F For Step 3.b and 5.e: °FSUBCOOLED = 49.7°F (Acceptable range = 49.3 to 50.4°F)
Performance: SATISFACTORY UNSATISFACTORY Comments:
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 8 of 11 Performance Step: 4 Review procedure step:
Critical Y 5.0 PERFORM a channel check for Core Exit Thermocouple based subcooling margin:
Standard: The examinee determines that at Step 5.g. the wrong value was entered, and enters the correct value of 40.9°F from Table 2.
Evaluator Cue: If notified of error, then acknowledge report and ask student to continue with performance of the procedure. The error may not be reported until review is completed.
Evaluator Note: The incorrect value of 47.8 was taken from Subcooling Monitor (RTD) vice Subcooling Monitor(T/C) on Table 2.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 Review procedure step:
Critical Y 5.0 PERFORM a channel check for Core Exit Thermocouple based subcooling margin:
- h. The difference between all three Yellow Channel values is less than or equal to 7.9°F (CIRCLE one) SAT / UNSAT Standard: The examinee determines that the difference between Yellow Channel values is greater than 7.9°F , and that the step is UNSAT.
Evaluator Cue: If notified of error in calculation then acknowledge report and ask student to continue with performance of the procedure. The error may not be reported until review is completed.
Evaluator Note: Once errors have been corrected for values at steps 5.e and 5.g, the examinee should identify a difference of 8.8°F.
Performance: SATISFACTORY UNSATISFACTORY Comments:
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 9 of 11 Performance Step: 6 Reports errors in calculations and asks for CO to review data and does not Critical N sign for calculation verification Standard: The examinee does not sign calculation verification until deficiencies are resolved Evaluator Cue: Acknowledge report Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: That completes this JPM.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
JPM PBN JPM P119.203d.SRO, Complete a Calculation Review of TS 32, Rev. 1 Page 10 of 11 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
JPM JOB PERFORMANCE MEASURE Page 11 of 11 TURNOVER SHEET INITIAL CONDITIONS:
Both Units are at rated power.
UNIT 1 PPCS Yellow Core Exit Thermocouple indications were acting erratically and have since been repaired.
PPCS is available.
CO3 just completed a partial TS 32, Miscellaneous Equipment Checks (Monthly) Unit 1, Attachment B, Calculations.
CO3 has just requested that you conduct the SRO review for the completed TS 32, Attachment B.
INITIATING CUES:
You are directed you to perform the SRO review of TS 32, Attachment B.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JOB PERFORMANCE MEASURE JPM Page 1 of 15 JPM TITLE: Review IT 90 TRAIN B, Atmospheric Steam Dump Valve Train B Unit 1 JPM NUMBER: PBN JPM P119.231.SRO REV. 0 TASK NUMBER(S) / PBN P119.231.SRO / Perform surveillances per the Plant Inspection TASK TITLE(S): Program K/A NUMBERS: 2.2.12 K/A VALUE: 3.7 / 4.1 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: Other: X Lab:
Time for Completion: 15 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 2 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 3 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 4 of 15 SIMULATOR SET-UP: (Only required for simulator JPMs)
None SIMULATOR SETUP INSTRUCTIONS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: Marked up copy (with errors) of IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 General
References:
IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 Task Standards: Identify the two inserted deficiencies during supervisory review of IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1.
Assess test results to identify that the ADV is OPERABLE, but does not meet IST acceptance criteria, and initiate required actions.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 5 of 15 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:
You are OS1.
The third license just completed IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 and has requested that you perform the supervisory review prior to exiting TSAC 3.7.4.A.1.
INITIATING CUES (IF APPLICABLE):
Complete the supervisory review for IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 6 of 15 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 Review the cover page for accuracy and completeness:
Critical N Verified Current Copy List pages used for Partial Performance Controlling Work Document Numbers Standard: The examinee reviews the cover page and determines it is accurate and complete:
Verified Current Copy List pages used for Partial Performance Controlling Work Document Numbers Evaluator Note: Verified Current Copy (Signature / Date / Time correctly filled in)
List pages used for Partial Performance (None)
Controlling Work Document Numbers (as noted)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 7 of 15 Performance Step: 2 Review Step 2.1 stopwatch data for accuracy and completeness:
Critical N ID No.
Calibration Due Date Standard: The examinee checks stopwatch data and notes that ID No. is filled in, and Calibration Due Date is NOT past due.
Evaluator Note: No errors with this step.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Review Step 4.0, Initial Conditions for accuracy and completeness:
Critical N 4.1 This test is being done to satisfy:
IST Coordinator availability Permission to Perform Test Standard: The examinee reviews Step 4.0, Initial Conditions and notes that it is complete and accurate.
4.1 This test is being done to satisfy:
4.2 IST Coordinator availability 4.3 Permission to Perform Test Evaluator Note: No errors in this section.
4.1 This test is being done to satisfy: (Checked and includes Task Sheet No.)
4.2 IST Coordinator: N/A (not PMT) 4.3 Permission to Perform Test (Signature / Date / Time)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 8 of 15 Performance Step: 4 Review Steps 5.1.1 through 5.1.6 for accuracy and completeness:
Critical N Date / time Pressures Initials IV initial Standard: The examinee reviews Steps 5.1.1 through 5.1.6 and notes they are accurate and complete.
Evaluator Note: No errors this section.
5.1.1 Date / Time 5.1.3 Value should be 800 psig 5.1.4 b Value should be 1050 psig 5.1.5 i Should be marked N/A 5.1.5 j Should be marked N/A 5.1.6 b Value should be 800 psig 5.1.6 d Value should be 1050 psig 5.1.6 m Should be marked N/A Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 Review Step 5.1.7 through 5.1.9 for accuracy and completeness:
Critical N Date / Time Initials IV initials Standard: The examinee reviews Step 5.1.7 through 5.1.9 and notes they are accurate and complete.
Evaluator Note: 5.1.9 Date / Time Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 9 of 15 Performance Step: 6 Review Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the Critical N table for Steps 5.1.5 b Control Room Time to OPEN Local Positon Indication Control Room Position Indication Standard: The examinee reviews Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the table for Steps 5.1.5 b and determines it is accurate and complete.
Control Room Time to OPEN Local Positon Indication Control Room Position Indication Evaluator Note: Control Room Time to OPEN (11.77)
Local Positon Indication (OPEN)
Control Room Position Indication (ON / OFF)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 10 of 15 Performance Step: 7 Review Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the Critical N table for Steps 5.1.5 e.
Control Room Time to SHUT Local Positon Indication Control Room Position Indication Standard: The examinee reviews Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the table for Steps 5.1.5 e and determines it is accurate and complete.
Control Room Time to SHUT Local Positon Indication Control Room Position Indication Evaluator Note: Control Room Time to SHUT (34.56)
Local Positon Indication (SHUT)
Control Room Position Indication (OFF / ON)
The examinee may identify that Time to SHUT does not meet IST acceptance criteria. This will be critical for JPM Step 11.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 11 of 15 Performance Step: 8 Review Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the Critical Y table for Steps 5.1.6 g Control Room Time to OPEN Local Positon Indication Control Room Position Indication Standard: The examinee identifies the Step 5.1.6 g transposition error (entered value of OFF /
ON rather than the required value of ON / OFF).
Evaluator Note: Control Room Time to OPEN (11.78)
Local Positon Indication (OPEN)
Control Room Position Indication (OFF / ON), (First of two inserted errors.)
Evaluator Cue: If the examinee questions the CO about the incorrect valve position indication, report that the actual indication was Red Light ON and Green Light OFF.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 9 Review Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the Critical N table for Steps 5.1.6 i Control Room Time to SHUT Local Positon Indication Control Room Position Indication Standard: The examinee reviews Attachment A, 1MS-2015 Valve Stroke Verification data recorded in the table for Steps 5.1.6 i and determines it is accurate and complete.
Control Room Time to SHUT Local Positon Indication Control Room Position Indication Evaluator Note: No errors this section.
Control Room Time to SHUT (34.48)
Local Positon Indication (SHUT)
Control Room Position Indication (OFF / ON)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 12 of 15 Performance Step: 10 Review Attachment A, 1MS-2015 Valve Stroke Verification data recorded after the Critical Y table for:
LVFST Satisfied for all tested valves in Attachment A: (SAT / UNSAT)
IST Data Satisfied for all tested valves in Attachment A: (SAT / UNSAT)
Performer, Date / Time Remarks Standard: The examinee identifies that SAT was circled in error for the IST Data Satisfied for all tested valves in Attachment A.
Evaluator Note: LVFST Satisfied for all tested valves in Attachment A: (SAT circled)
IST Data Satisfied for all tested valves in Attachment A: (SAT circled) (Second of two inserted errors.)
Performer, Date / Time (Signature / Date / Time)
Remarks (Comment addressing IST out-of-spec for step 5.1.5 e)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 13 of 15 Performance Step: 11 Completes Step 6.1: Operations Analysis Critical Y Standard: The examinee:
Completes Step 6.1.1 - signature / date / time Step 6.1.2 - marks step as N/A Step 6.1.3 - marks step as N/A Completes Step 6.1.4 - actions request submittal and IST Engineer notification Evaluator Cue: When the step is addressed, notify the SRO that the CO has written an AR.
AR # 1234567 When the step is addressed, notify the SRO that the IST Engineer has been informed of his required review.
Evaluator Note: The critical attribute of this step is that direction be given to generate the AR and to notify the IST Engineer.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.231.SRO, Review Atmospheric Steam Dump Valve JPM Train B Unit 1, Rev. 0 Page 14 of 15 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 15 of 15 TURNOVER SHEET INITIAL CONDITIONS:
You are OS1.
The third license just completed IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 and has requested that you perform the supervisory review prior to exiting TSAC 3.7.4.A.1.
INITIATING CUES (IF APPLICABLE):
Complete the supervisory review for IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 12 JPM TITLE: Review a Discharge Calculation (OI 140B)
JPM NUMBER: PBN JPM P119.223d.SRO REV. 0 TASK NUMBER(S) / PBN P119.223.SRO / Review completed procedures TASK TITLE(S):
K/A NUMBERS: 2.3.6 K/A VALUE: 3.9 / 4.2 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: Other: X Lab:
Time for Completion: 15 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: N0 Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 2 of 12 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 3 of 12 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 4 of 12 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
None SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: OI 140B, Standard Radioactive Batch Liquid Release - Waste Distillate Tanks PBNP Liquid Waste Discharge Permit for the A Waste Distillate Tank CAMP 031, Data Sheet 1 - Permits for Batch Discharge of Liquid Radioactive Water
- OI-38, Circulating Water System Operation
- TLB 23, Waste Distillate Tank T-104 A/B
- Make these references available to the examinee only when requested.
General
References:
OI 140B, Standard Radioactive Batch Liquid Release - Waste Distillate Tanks PBNP Liquid Waste Discharge Permit for the A Waste Distillate Tank CAMP 031, Data Sheet 1 - Permits for Batch Discharge of Liquid Radioactive Water Task Standards: Review and identify the three errors on CAMP 031, Data Sheet 1 - Permits for Batch Discharge of Liquid Radioactive Water associated with the discharge of the A Waste Distillate Tank.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 5 of 12 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:
You are the Shift Manager on mids A A Waste Distillate Tank discharge was recently completed on your shift and the paperwork was routed to you for review and approval.
INITIATING CUES (IF APPLICABLE):
Complete the Permit review by Shift Manager section of CAMP 031, Data Sheet 1 - Permits for Batch Discharge of Liquid Radioactive Water for the A Waste Distillate Tank prior to routing to the Chemistry Manager.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 6 of 12 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 Review Completed Prior to Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
Initials for actual dilution flow Initials for number of Circulating Water pumps operating (2)
Initials and Date/Time for Shift Manager Review/Approval to Start Discharge Standard: The examinee reviews the Completed Prior to Discharge section for accuracy and completeness:
Initials for actual dilution flow Initials for number of Circulating Water pumps operating (2)
Initials and Date/Time for Shift Manager Review/Approval to Start Discharge Evaluator Cue: Provide a copy of OI-38, Circulating Water System Operation, if requested.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 7 of 12 Performance Step: 2 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
The two Notes Ensure flow response option circled The initial flow calculation / data recorded in the box The final flow calculation / data recorded in the box.
Standard: The examinee reviews the Completed During Discharge section for accuracy and completeness for the following:
The two Notes (circle / slashed)
Ensure flow response option (circled) - LW-15 Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
Discharge START Date/Time and initials Standard: The examinee reviews the Completed During Discharge section for the following:
Discharge START Date/Time and initials Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
Discharge START Level and initials Standard: The examinee reviews the Completed During Discharge section for the following:
Discharge START Levels and initials - 78%
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 8 of 12 Performance Step: 5 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
Discharge STOP Date/Time and initials Standard: The examinee reviews the Completed During Discharge section for the following:
Discharge STOP Date/Time and initials Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical N Permits for Batch Discharge of Liquid Radioactive Water for the following:
Discharge STOP Level and initials Standard: The examinee reviews the Completed During Discharge section for the following:
Discharge STOP Level and initials Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 9 of 12 Performance Step: 7 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical Y Permits for Batch Discharge of Liquid Radioactive Water for the following:
Actual Discharge Volume (gal)
Standard: The examinee reviews the Completed During Discharge section for the following:
Actual Discharge Volume (gal)
Determines that the recorded volume of 7410 gal is incorrect. The correct volume is 8610 gal.
Evaluator Note: The recorded volume of 7410 gal does not account for 1200 gal in the tank below the 0% level indication. See TLB 23 and OI-140B P&L 3.15. The actual volume discharged is 8610 gal.
Evaluator Cue: Provide a copy of TLB 23 if requested.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical Y Permits for Batch Discharge of Liquid Radioactive Water for the following:
Actual Discharge Rate (gpm)
Standard: The examinee reviews the Completed During Discharge section for the following:
Actual Discharge Rate (gpm)
AND Determines that the discharge rate calculation is NOT accurate.
Evaluator Note: The values used for both discharged volume and time are incorrect. Using the corrected value for volume discharged (JPM Step 7) and the correct time of 2 hr, 32 min (152 min) the Actual Discharge Rate is 56.6 gpm. [8610 gal / 152 min =
56.6 gpm]
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 10 of 12 Performance Step: 9 Review Completed During Discharge section of CAMP 031, Data Sheet 1 -
Critical Y Permits for Batch Discharge of Liquid Radioactive Water for the following:
Actual Discharge Rate (gpm)
Standard: The examinee reviews the Completed During Discharge section for the following:
Actual Discharge Rate (gpm)
AND Determines that the corrected Actual Discharge Rate exceeds the Maximum Release Rate as specified on the Discharge Permit.
Evaluator Note: The corrected value for Actual Discharge Rate is 56.6 gpm is greater than the Maximum Release Rate of 50 gpm as specified on the Discharge Permit.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P119.223d.SRO, Review a Discharge Calculation JPM (OI 140C), Rev. 0 Page 11 of 12 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 12 of 12 TURNOVER SHEET INITIAL CONDITIONS:
You are the Shift Manager on mids A A Waste Distillate Tank discharge was recently completed on your shift and the paperwork was routed to you for review and approval.
INITIATING CUES (IF APPLICABLE):
Complete the Permit review by Shift Manager section of CAMP 031, Data Sheet 1 - Permits for Batch Discharge of Liquid Radioactive Water for the A Waste Distillate Tank prior to routing to the Chemistry Manager.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
SRO Admin JPM 5 (Emergency Plan)
PERFORM REQUIRED NOTIFICATIONS (Facility JPM Number: PBN JPM P119.214c.SRO)
Exam material withheld from public disclosure due to proprietary content.
JPM JOB PERFORMANCE MEASURE Page 1 of 19 JPM TITLE: Perform RCS Leak Rate Determination JPM NUMBER: PBN JPM P002.005a.COT REV. 6 TASK NUMBER(S) / P002.005.COT / Perform RCS Leak Rate Determinations TASK TITLE(S):
K/A NUMBERS: 009 EA 2.33 K/A VALUE: 3.3 / 3.8 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform:
EVALUATION LOCATION: In-Plant: Control Room:
Simulator: Other:
Lab:
Time for Completion: 20 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 2 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 3 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 6 Updated for the 2017 NRC ILT Exam.
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 4 of 19 SIMULATOR SET-UP: (Only required for simulator JPMs)
Simulator Setup Instructions:
1.
2.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: 1. OI-55, Primary Leak Rate Calculation
- 2. Calculator General
References:
- 1. OI-55, Primary Leak Rate Calculation
- 2. Technical Specifications Task Standards: Accurately calculate RCS leakage and determine TSAC impact per OI-55.
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 5 of 19 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:
Unit 1 is operating at stable full reactor power with indications of a primary leak.
The Letdown Gas Stripper (LDGS) is bypassed per OI-17, Letdown Gas Stripper Operation.
AOP-1A Unit 1 Reactor Coolant Leak was entered and is currently in progress.
The PAB AO has reported the following Charging Pumps seal leak rates:
1P-2A = 15 cc/min 1P-2B = 5 cc/min 1P-2C = 25 cc/min Steam Generator Tube Leakage (SGTL ) LRSGTL = 0 Reactor Component Leak Rate LRRC = 0 Non RCPB Leakage LRP3 = 0 The following plant parameters were observed at time 0400:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 46.0 %
VCT Level 45.0 %
U1 PRT level 74.7%
U1 RCDT Level 52 %
The following plant parameters were observed at time 0420:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 45.5%
VCT Level 43.5 %
U1 PRT level 74.7%
U1 RCDT Level 52.5 %
No borations, dilutions or diverts to HUT took place.
There is no Chemistry sampling in progress.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to perform OI-55, Primary Leak Rate Calculation NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 6 of 19 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.5 IF the Unit is in Mode 1, 2, 3, or 4, THEN determine RCS Leak Rate Critical N as follows:
5.5.1 RECORD initial set of parameter readings on Attachment A, Primary Leak Rate Worksheet Standard: The examinee determines the Unit is in Mode 1 per initial conditions.
Records data in Attachment A, Section 2.0 Evaluator Note: See JPM Step 10.
No action is required for procedure step 5.5.2 because the parameter readings are given.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 2 5.5.3 Using the same instrumentation channels as for the first set of Critical N readings, RECORD second set of parameter readings when T (error) meter is the same as in initial data set.
Standard: None, the second set of data is given to the examinee per initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Evaluator Note: See JPM Step 10.
Comments:
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 7 of 19 Performance Step: 3 5.5.4 IF dilution or boration took place, THEN CORRECT the leak rate Critical N by using the different totalizer readings.
Standard: The examinee determines no dilution or boration took place.
Evaluator Cue: IF asked, THEN remind the examinee that no boration or dilution occurred as delineated per the initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 4 5.5.5 IF operator timed manual full divert was used, THEN Critical N CALCULATE the number of gallons diverted by multiplying the letdown flow in gpm times minutes diverted.
Standard: The examinee determines no divert took place.
Evaluator Cue: IF asked, THEN remind the examinee that no diverts took place as delineated per the initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 8 of 19 Performance Step: 5 5.5.6 QUANTIFY known contributors to RCS Identified leakage during Critical N performance of RCS leak rate calculation.
Standard: The examinee calculates Identified RCS Leak Rate Evaluator Cue: IF asked, THEN refer the examinee to INITIAL CONDITIONS.
Evaluator Note: Recorded in Attachment A, Section 4.1, See JPM Step 14 Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 6 5.5.7 QUANTIFY known non-RCPB leakage during performance of Critical N RCS leak rate calculation.
Standard: The examinee calculates Non Reactor Coolant Pressure Boundary leakage.
Evaluator Cue: IF asked, THEN refer the examinee to INITIAL CONDITIONS.
Evaluator Note: Recorded in Attachment A, Section 4.2, See JPM Step 15 Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 7 5.5.8 CALCULATE and RECORD leak rate.
Critical N Standard: The examinee calculates RCS Unidentified leakage.
Evaluator Note: Recorded in Attachment A, Section 4.3, See JPM Step 16 Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
PBN JPM P002.005a.COT, Perform RCS Leak Rate JPM Determination, Rev. 6 Page 9 of 19 Performance Step: 8 Attachment A Critical N 1.0 MONITOR AND MAINTAIN the following during the performance of this test:
1.1 Reactor Power Stable.
Standard: The examinee verifies reactor power stable.
Evaluator Note: Per initial conditions, reactor power has not changed.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 9 Attachment A Critical N 1.2 The Letdown Gas Stripper (LDGS) meets ONE of the following:
1.2.1 The LDGS is operating normally with controls in AUTO AND with no level adjustments being made 1.2.2 The LDGS is bypassed per OI-17, Letdown Gas Stripper Operation Standard: Determine LDGS is bypassed from given initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 10 of Determination, Rev. 6 19 Performance Step:10 Attachment A Critical N 2.0 RECORD the following data:
RCS LEAK RATE DATA Standard: The examinee records data accurately from the initial conditions and calculates the results.
Time change 20 minutes RC Terror (Terr) change is 0°F PZR Level change is 0.5 % = 32.45 gal.
VCT Level change is 1.5 % = 18.96 gal.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 11 Attachment A Critical N 2.0 RECORD the following data:
RMW AND BA ADDITIONS Standard: The examinee N/As this step as it does not apply Evaluator Note: Per the initial conditions, no RMW or acid additions occurred.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 11 of Determination, Rev. 6 19 Performance Step: 12 Attachment A Critical N 2.0 RECORD the following data:
DIVERT Standard: The examinee N/As this step as it does not apply Evaluator Note: Per the initial conditions, no diverts occurred.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 13 Attachment A Critical Y 3.0 Calculate RCS leak rate:
CALCUALTED RCS LEAK RATE Standard: The examinee calculates RCS leak rate of 2.571 gpm (2.50 to 2.70 gpm).
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 14 Attachment A Critical Y 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.1 CALCULATE Identified RCS Leak Rate:
IDENTIFIED RCS LEAK RATE DATA Standard: Time change 20 minutes PRT Level change 0 gpm RCDT Level change 0.088 gpm SG Tube Leakage (LRSGTL) 0 gpm Reactor Component Leak Rate (LRRC) 0 gpm RCS Identified Leak Rate (LRID) of 0.088 gpm (0.08 to 0.10 gpm).
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 12 of Determination, Rev. 6 19 Performance Step: 15 Attachment A Critical Y 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.2 CALCULATE Non Reactor Coolant Pressure Boundary :
Non Reactor Coolant Pressure Boundary Standard: Charging Pump Seals (LRP2) 0.012 gpm (0.010 to 0.014 gpm)
Non RCPB Leakage (LRP3) 0 gpm Evaluator Note: 1P-1A, 1P-2B and 1P-2C Charging Pumps have pre-identified leakage of 15 cc/min, 5 cc/min and 25 cc/min respectively.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 16 Attachment A Critical Y 4.0 CALCULATE RCS Unidentified Leak Rate as follows:
4.3 CALCULATE RCS Unidentified leakage:
UNIDENTIFIED RCS LEAK RATE Standard: The examinee calculates Unidentified Leak Rate (LRUID) 2.471 gpm (2.450 to 2.500 gpm)
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 13 of Determination, Rev. 6 19 Performance Step: 17 Attachment A Critical N 5.0 Primary Leak Rate calculation COMPLETE.
6.0 Primary Leak Rate calculation review COMPLETE.
Standard: The examinee indicates that the leak rate calculation is complete and provided Attachment A to SRO for review.
Evaluator Cue: Inform the examinee that the SRO review of the leak rate calculation is complete and to continue with OI 55.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 18 5.6 IF the Unit is in Mode 5, THEN perform Attachment B, Cold Critical N Shutdown Primary Leak Rate Worksheet as follows:
Standard: The examinee should determine this step is not applicable.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 14 of Determination, Rev. 6 19 Performance Step: 19 5.7 IF the plant is in Mode 1 through 4, AND Pressure Boundary Critical N leakage is detected, THEN ENTER Technical Specification LCO 3.4.13 Action Condition B.
Standard: The examinee should determine that action condition entry is not required at this time.
Evaluator Cue: Relief crew is preparing for a containment entry to inspect for pressure boundary leakage.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 15 of Determination, Rev. 6 19 Performance Step: 20 5.8 IF RCS Unidentified Leakage shows a significantly increasing trend, Critical N OR reaches 0.15 gpm, THEN PERFORM the following actions:
5.8.1 INFORM the Shift Manager and Duty Station Manager.
5.8.2 CHECK the following at least once per hour:
- a. Containment particulate monitor (RE 211) high and low values.
- b. Containment radiogas monitor (RE 212) high and low values.
- c. Containment humidity.
5.8.3 PERFORM the RCS leakrate calculation of Section 5.5 or 5.6 as applicable at least once per shift.
5.8.4 OBTAIN a sump A sample and have Chemistry analyze to aid in determining the source of leakage.
5.8.5 DIRECT Chemistry to sample and analyze Containment atmosphere for hydrogen content and REPORT the results to the SM.
5.8.6 NOTIFY Engineering to review Containment Air Cooler performance and cleaning frequencies to determine if an adverse long term trend exists.
5.8.7 IF a containment inspection is warranted to localize the source of leakage, THEN the inspection should consist of the following:
- a. Evidence of steam in containment.
- b. Wetness on the floor.
- c. Boric Acid deposits.
- d. Abnormal packing or gasket leakage.
Note: A thorough examination should be performed of the reactor vessel head using binoculars or other methods allowed by RP.
- e. Reactor vessel head locations as permitted by Health Physics.
Evaluator Cue: Shift Manager will have OS2 address actions contained in step 5.8 Standard: The examinee identifies actions required as listed by procedure Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 16 of Determination, Rev. 6 19 Performance Step: 21 5.9 IF the RCS leak rate approaches 0.20 gpm and the cause is known, Critical N THEN the priority of the work order associated with the contributor SHALL be increased.
Standard: The examinee should determine that this step is not applicable because the cause of the leakage is unknown.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 22 5.10 IF the plant is in Mode 1 through 4, AND Unidentified Leakage Critical Y exceeds one gpm, THEN ENTER Technical Specification LCO 3.4.13 Action Condition.
Standard: The examinee identifies RCS unidentified leakage >1 gpm is in excess of limit for Technical Specifications LCO 3.4.13.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Performance Step: 23 5.11 IF Unidentified Leakage is greater than 1.0 gpm OR Identified Critical N Leakage is greater than 10 gpm, THEN INITIATE AOP 1A, Reactor Coolant Leak.
Standard: The examinee identifies that AOP 1A is already in effect, per initial conditions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 17 of Determination, Rev. 6 19 Performance Step: 24 5.12 IF the plant is in Mode 1 through 4, AND Identified Leakage Critical N exceeds 10 gpm, THEN ENTER Technical Specification LCO 3.4.13 Action Condition.
Standard: The examinee identifies RCS identified leakage is less than 10 gpm.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments:
Terminating Cues: JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
JPM PBN JPM P002.005a.COT, Perform RCS Leak Rate Page 18 of Determination, Rev. 6 19 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
Filename: PBN JPM P002.005a.COT Rev 6.doc TR-AA-230-1003-F10 Revision 1 Page 18 of 19
JPM JOB PERFORMANCE MEASURE Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS:
Unit 1 is operating at stable full reactor power with indications of a primary leak.
The Letdown Gas Stripper (LDGS) is bypassed per OI-17, Letdown Gas Stripper Operation.
AOP-1A Unit 1 Reactor Coolant Leak was entered and is currently in progress.
The PAB AO has reported the following Charging Pumps seal leak rates:
1P-2A = 15 cc/min 1P-2B = 5 cc/min 1P-2C = 25 cc/min Steam Generator Tube Leakage (SGTL ) LRSGTL = 0 Reactor Component Leak Rate LRRC = 0 Non RCPB Leakage LRP3 = 0 The following plant parameters were observed at time 0400:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 46.0 %
VCT Level 45.0 %
U1 PRT level 74.7%
U1 RCDT Level 52 %
The following plant parameters were observed at time 0420:
RCS Tavg 575.6 °F RCS T(Terr) 0 °F PZR Level 45.5%
VCT Level 43.5 %
U1 PRT level 74.7%
U1 RCDT Level 52.5 %
No borations, dilutions or diverts to HUT took place.
There is no Chemistry sampling in progress.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to perform OI-55, Primary Leak Rate Calculation NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Filename: PBN JPM P002.005a.COT Rev 6.doc TR-AA-230-1003-F10 Revision 1 Page 19 of 19
JOB PERFORMANCE MEASURE JPM Page 1 of 13 JPM TITLE: Perform TS-32 Miscellaneous Equipment Checks (Monthly) Unit 1 JPM NUMBER: PBN JPM P083.019b.COT REV. 1 TASK NUMBER(S) / PBN P083.019.COT / Operate the PPCS Keyboard TASK TITLE(S):
K/A NUMBERS: 2.1.19 K/A VALUE: 3.9 / 3.8 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 2 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 3 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 1 Updated for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 4 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
Any at power IC where you can access the 1C20 panel and PPCS to perform applicable portions of TS-32.
SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: Partial TS-32 Miscellaneous Equipment Checks (Monthly) Unit 1 to perform section 5.2 manually entering data from PPCS.
Steam Tables and Calculator General
References:
TS-32 Miscellaneous Equipment Checks (Monthly) Unit 1 Task Standards: Record data and perform calculations to determine that the subcooling margin monitoring system for the Yellow channel CETs is operating within acceptance criteria.
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 5 of 13 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:
Both Units are at rated power.
PPCS Yellow Core Exit Thermocouple indications were acting erratically and have since been repaired.
You are the 3 License.
rd PPCS is available.
INITIATING CUES:
OS1 has directed you to perform a partial TS-32 Miscellaneous Equipment Checks (Monthly) Unit 1 for Post Maintenance Testing of Yellow CETs starting with Step 5.2.3.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 6 of 13 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.2.3 IF PPCS is available, THEN RECORD data on Attachment A, Subcooling Critical N Margin Monitoring System Data Sheet, Table 1.
Standard: The examinee accurately records required data from PPCS in Table 1.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 5.2.4 ENSURE the following ASIP Panel switches are SET to the TC position.
Critical N 1TSS-971, RC Loop B Subcooling Monitor Selector Standard: The examinee verifies the switch is in the TC position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 7 of 13 Performance Step: 3 5.2.5 RECORD Core Exit Thermocouples based Subcooling margin on Critical N Attachment A, Subcooling margin Monitoring System Data Sheet, Table 2.
1TI-971 Standard: The examinee accurately records data in Table 2.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 5.2.6 PLACE the following ASIP Panel switches to RTD position.
Critical Y 1TSS-971, RC Loop B Subcooling Monitor Selector Standard: The examinee places the subcooling monitor switch to the RTD position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 8 of 13 Performance Step: 5 5.2.7 RECORD RTD based Subcooling margin on Attachment A, Subcooling Critical N margin Monitoring System Data Sheet, Table 2.
1TI-971 Standard: The examinee accurately records data in Table 2.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 5.2.8 PLACE the following ASIP Panel switches to TC position.
Critical Y 1TSS-971, RC Loop B Subcooling Monitor Selector Standard: The examinee places the subcooling monitor switch to the TC position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 9 of 13 Performance Step: 7 5.2.9 IF PPCS is available, THEN PERFORM the following.
Critical Y a. RECORD data on Attachment A, Subcooling Margin Monitoring System Data Sheet, Table 2 PPCS calculated Core Exit Thermocouples based Subcooling margin using points TC-970 and T-971C PPCS calculated RTD based Subcooling margin using points T-970R and T-971R
- b. COMPLETE Attachment B, Calculations, using the data recorded in Attachment A, Subcooling Margin Monitoring System Data Sheet Standard: The examinee accurately records data in Table 2 and performs calculations in Attachment B.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Attachment B Critical Y 5.0 PERFORM a channel check for Core Exit Thermocouple based on subcooling margin:
- h. The difference between all three Yellow Channel values is less than or equal to 7.9°F Standard: The examinee determines that the difference between all three Yellow Channel values is less than or equal to 7.9°F.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 10 of 13 Performance Step: 9 Attachment B Critical Y 6.0 PERFORM a channel check for RTD based on subcooling margin:
- h. The difference between all three Yellow Channel values is less than or equal to 7.9°F Standard: The examinee determines that the difference between all three Yellow Channel values is less than or equal to 7.9°F.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 5.2.10 IF the PPCS is NOT available, THEN PERFORM Attachment D, Critical N Subcooling Margin Monitor Checks With PPCS Unavailable.
Standard: The examinee identifies that PPCS is available, then N/As step.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 11 5.2.11 IF any subcooling margin indication differs from its associated channel Critical N calculated subcooling margin by an amount greater than the tolerance listed for that channel, THEN SUBMIT an Action Request per PI-AA-204, Condition Identification and Screening Process, AND NOTE the discrepancy in the Remarks Section.
Standard: The examinee identifies that the Yellow channel is within tolerance, no CAP is required and then N/As step.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 11 of 13 Performance Step: 12 Complete TS-32, Miscellaneous Equipment Checks Monthly Unit 1 and informs OS Critical N of status.
Standard: The examinee completes TS-32, Miscellaneous Equipment Checks Monthly Unit 1 and informs OS of status.
Evaluator Cue: The OS acknowledges your report.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P083.019b.COT, Perform TS-32 Miscellaneous JPM Equipment Checks (Monthly) Unit 1, Rev. 1 Page 12 of 13 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS:
Both Units are at rated power.
PPCS Yellow Core Exit Thermocouple indications were acting erratically and have since been repaired.
You are the 3rd License.
PPCS is available.
INITIATING CUES:
OS1 has directed you to perform a partial TS-32 Miscellaneous Equipment Checks (Monthly) Unit 1 for Post Maintenance Testing of Yellow CETs starting with Step 5.2.3.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 14 JPM TITLE: Perform Atmospheric Steam Dump Valve Train B Unit 1 JPM NUMBER: PBN JPM P039.005.COT REV. 0 TASK NUMBER(S) / PBN P039.005.COT / Dump steam through the atmospheric steam dump TASK TITLE(S): valves 2.2.12 3.7 / 4.1 K/A NUMBERS: K/A VALUE:
035 A3.02 3.7 / 3.5 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 2 of 14 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 3 of 14 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 4 of 14 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
Load any IC with both units at 100%, steady state Use LOA1SGN026 [final value = 0 - close] to shut 1MS-244, HX-1B SG MS-2015 Dump to Atmosphere Inlet.
Walk down control boards to verify plant conditions match initial conditions described by the JPM.
Save to an IC for multiple use.
Multiple Uses:
Load the saved IC for this JPM.
Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Resave if required.
SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 Stop watch General
References:
IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 Task Standards: Complete control room valve stroke timing in accordance with IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1.
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 5 of 14 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:
You are the third license.
IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 is in progress and completed through Step 5.1.2.
There is an AO stationed locally at 1MS-244, HX-1B SG MS-2015 Dump To Atmospheric Inlet to support the test.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to continue with IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 beginning with Step 5.1.3.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 6 of 14 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.1.3 RECORD 1PI-478, HX-1B SG Steam Pressure: _____ psig.
Critical N Standard: The examinee records 1PI-478, HX-1B SG Steam Pressure.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 5.1.4 ENSURE 1HC-478, SG B Atmospheric Steam Dump Controller, in Critical N AUTOMATIC.
Standard: The examinee ensures 1HC-478, SG B Atmospheric Steam Dump Controller is in AUTOMATIC.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 7 of 14 Performance Step: 3 5.1.4 ENSURE 1HC-478, SG B Atmospheric Steam Dump Controller, in Critical N AUTOMATIC
- a. ENSURE 1HC-478, SG B Atmospheric Steam Dump Controller, set at 250 psig greater than B Steam Generator pressure.
Standard: The examinee ensures 1HC-478, SG B Atmospheric Steam Dump Controller is set 250 psig greater than B Steam Generator pressure.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 5.1.4 ENSURE 1HC-478, SG B Atmospheric Steam Dump Controller, in Critical N AUTOMATIC
- b. RECORD 1HX-478 Controller setting: _____ psig.
Standard: The examinee records 1HX-478 Controller setting.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 8 of 14 Performance Step: 5 5.1.4 ENSURE 1HC-478, SG B Atmospheric Steam Dump Controller, in Critical Y AUTOMATIC
- c. POSITION 1HC-478 SG B Atmospheric Steam Dump manual control potentiometer to FULL OPEN.
Standard: The examinee rotates the 1HC-478 SG B Atmospheric Steam Dump manual control potentiometer to full open. (Fully clockwise)
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical Y Control, as follows:
Standard: The examinee:
Places 1HC-478, SG B Atmospheric Steam Dump Controller to MANUAL AND Times the valve stroke to full open Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 9 of 14 Performance Step: 7 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- b. RECORD required data on Attachment A.
Standard: The examinee records the required data on Attachment A.
Evaluator Cue: IF asked, report 1MS-2015 indicates OPEN locally.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- c. NOTE any indication (loud noise, etc) 1MS-244, HX-1B SG MS-2015 Dump To Atmospheric Inlet, is leaking by.
- 1. RECORD results in Attachment A.
Standard: The examinee:
Checks with the AO stationed locally at 1MS-244, HX-1B SG MS-2015 Dump To Atmospheric Inlet for abnormal indications AND Records results in Attachment A Evaluator Cue: IF asked, THEN report that 1MS-244, HX-1B SG MS-2015 Dump To Atmospheric Inlet is NOT leaking by.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 10 of 14 Performance Step: 9 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical Y Control, as follows:
Standard: The examinee:
Places 1HC-478, SG B Atmospheric Steam Dump Controller in AUTO AND Times the valve stroke to full shut Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- e. RECORD results in Attachment A.
Standard: The examinee records the results in Attachment A.
Evaluator Cue: IF asked, report 1MS-2015 indicates SHUT locally.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 11 of 14 Performance Step: 11 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- f. POSITION 1HC-478, SG B Atmospheric Steam Dump Controller manual control potentiometer to FULL SHUT.
Standard: The examinee rotates the 1HC-478, SG B Atmospheric Steam Dump Controller manual control potentiometer to FULL SHUT.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 12 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- g. SET 1HC-478, SG B Atmospheric Steam Dump Controller at 1050 psig and in AUTO Standard: The examinee sets 1HC-478, SG B Atmospheric Steam Dump Controller to 1050 psig.
Evaluator Note: Evaluator to initial for Independent Verfication.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 12 of 14 Performance Step: 13 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical Y Control, as follows:
- h. EVALUATE valve operability with acceptance criteria shown on Attachment A.
Standard: The examinee evaluates valve operability with acceptance criteria shown on Attachment A.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 5.1.5 Stroke time test of 1MS-2015, HX-1B SG Hdr Atmospheric Steam Dump Critical N Control, as follows:
- i. IF both the open and shut stroke times are within the listed IST band, THEN N/A remainder of steps 5.1.5 through 5.1.6, AND PROCEED to step 5.1.7.
Standard: The examinee:
Determines that the open and stroke times are within the listed IST band, N/As the remaining steps 5.1.5 and 5.1.6 AND Proceeds to Step 5.1.7.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P039.005.COT, Perform Atmospheric Steam Dump JPM Valve Train B Unit 1, Rev. 0 Page 13 of 14 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 14 of 14 TURNOVER SHEET INITIAL CONDITIONS:
You are the third license.
IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 is in progress and completed through Step 5.1.2.
There is an AO stationed locally at 1MS-244, HX-1B SG MS-2015 Dump To Atmospheric Inlet to support the test.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to continue with IT 90 Train B, Atmospheric Steam Dump Valve Train B Unit 1 beginning with Step 5.1.3.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
RO Admin JPM 4 (Emergency Plan)
ACTIVATE ERDS (Facility JPM Number: PBN JPM P083.019a.COT)
Exam material withheld from public disclosure due to proprietary content.
JOB PERFORMANCE MEASURE JPM Page 1 of 18 JPM TITLE: PERFORM ROD EXERCISE TEST JPM NUMBER: PBN JPM P001.020.COT REV. 6 TASK NUMBER(S) / PBN P001.020.COT / Perform Control Rod Exercises TASK TITLE(S):
001.K4.02 3.8 / 3.8 K/A NUMBERS: 001.A3.05 K/A VALUE: 3.5 / 3.5 001.A4.03 4.0 / 3.7 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 2 of 18 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 3 of 18 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0-4 See historical records.
Rev. 5 Updated for the 2014 operational exam.
Rev. 6 Updated for the 2017 NRC ILT Exam.
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 4 of 18 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
- 1. Initialize into IC-2.
- 2. Load the following codes and insert trigger 1.
- 3. Verify Rod Counter readings are at 228 (225)* for all banks except CB D which should be set at 220.
- 4. Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
- 5. Make any necessary adjustments or corrections.
- 7. Save to an IC for multiple uses (if necessary).
- Consult STPT 5.1 for current Unit 1 Cycle for ARO position.
SIMULATOR MALFUNCTIONS:
None SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
Setup:
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-CR-RESET BANK LOA1CRF003 OVERLAP 00:00:00 00:00:00 1 00:00:00 595 594 PRELOAD COUNTER RESET Required Materials: 1. TS-5, Rod Exercise Test Unit 1
- 2. REI 7.0, Control Rod Position Determination General
References:
- 1. TS-5, Rod Exercise Test Unit 1
- 2. REI 7.0, Control Rod Position Determination Task Standards: Bank D rods have been exercised, bank overlap counter discrepancy corrected and bank D rods returned to their original position.
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 5 of 18 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:
You are CO3.
Unit 1 is at 100% power, steady state Xenon.
INITIATING CUES (IF APPLICABLE):
The SRO has directed you to perform TS-5, Rod Exercise Test Unit 1.
The pre-job brief has been completed.
An AO is standing by in the Unit 1 Rod Drive MG Set Room to assist in the performance of the test.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 6 of 18 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.1 RECORD the following indications:
Critical N 5.1.1 RDC-LOGIC Cabinet (Key #21):
Bank Overlap Counter reading Standard: The examinee contacts Unit 1 Turbine Hall Operator and obtains the Bank Overlap Counter reading.
Evaluator Note: Counter reading is in the rod control cabinet in the Rod Drive MG Set Room.
Evaluator Cue: AO reports that the Bank Overlap Counter is reading 594.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 7 of 18 Performance Step: 2 5.1.2 Status of the Group Select Lights for the following power Critical N cabinets:
1AC - Group Select Light C 2AC - Group Select Light C 1BD - Group Select Light B Standard: The examinee contacts the U1 TH Operator and obtains the status of the lights.
Evaluator Note: Light status is found on the power cabinets in the RD MG Set Room.
Evaluator Cue: AO Reports C lights lit for 1AC and 2AC and B light lit for 1BD.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 3 5.1.3 1C04, Rod Bank Group (Demand) counters:
Critical N Control Bank A Group 1 Etc.
Standard: The examinee correctly records Control and Shutdown Bank Group Demand counter readings.
Evaluator Note: All Bank Demand counters should indicate 228 (225) steps except Bank D which should indicate 220 steps.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 8 of 18 Performance Step: 4 5.1.4 1C-120A, RPI #1, Bank Position Display Critical N Bank A Bank B Bank C Bank D Standard: The examinee correctly records bank positions on 1C-120A.
Evaluator Note: Bank Positions are indicated behind the Main Control Boards on 1C-120A.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 5 5.2 COMPARE the Bank Overlap Counter reading to Control Bank Critical N position (Step Counters) in REI 7.0, Control Rod Position Determination.
Standard: The examinee obtains a copy of REI 7.0 and compares the Control Bank position with the Bank Overlap Counter and determines that there is disagreement between the two.
Evaluator Note: The examinee should determine that the Control Bank position and Bank Overlap Counter do NOT agree.
With Control Bank D at 220 steps, the Bank Overlap Counter should read 595.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 9 of 18 Performance Step: 6 5.3 IF the Control Bank Position AND Bank Overlap Counter reading Critical Y do NOT agree, THEN PERFORM Attachment A.
Standard: The examinee determines the readings do not agree and goes to Attachment A.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 7 ATTACHMENT A Critical Y 1.0 PLACE Rod control selector to Manual.
Standard: The examinee places Rod control selector switch to the Manual position.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 8 2.0 STEP Control Bank D OUT 1 step from its current position.
Critical Y Standard: The examinee steps Control Bank D out 1 step.
Evaluator Cue:
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 10 of 18 Performance Step: 9 3.0 BUMP STEP Control Bank D IN one step.
Critical Y Standard: The examinee bumps Control Bank D in one step.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 10 4.0 CHECK card A105 has BOTTOM LIGHT ILLUMINATED (top Critical N row, 3rd card from the left in the Rod Control Logic Cabinet directly above the Bank Overlap Counter).
Standard: The examinee contacts the Auxiliary Operator in the Rod Drive Room and obtains status of card A105 bottom light.
Evaluator Note: Based on the report from the AO, steps 5.0 and 6.0 of Attachment A will be N/A Evaluator Cue: The AO reports card A105 has the bottom light illuminated.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 11 of 18 Performance Step: 11 7.0 Compare the Bank D Demand Position (Step Counters) to the Critical N Bank Overlap Counter.
Standard: The examinee contacts the AO for the Bank Overlap Counter reading and compares the Step Counter for Bank D to the obtained Bank Overlap Counter reading.
Evaluator Cue: AO reports the Bank Overlap Counter reads 595.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 12 8.0 IF the Control Bank D Position (Step Counters) and the Bank Critical N Overlap Counter do not agree, THEN adjust the Bank Overlap Counter at RDC Logic Cabinet by depressing the +1 or -1 button as necessary until the proper value correlating to the Control Rod Bank D Position (Step Counters).
Standard: The examinee determines step is not required to be performed and N/As the step.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 12 of 18 Performance Step: 13 9.0 Return the Control Rod selector switch to AUTO.
Critical N Standard: The examinee places Control Rod selector switch to AUTO.
Evaluator Note: When examinee asks for an Independent Verification of this step, initial the step for IV.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 14 5.4 IF printed PPCS data is required, THEN OBTAIN a screen print Critical N of PPCS display page 2121 prior to and following movement of each rod group.
Standard: The examinee requests whether PPCS printed data is required.
Evaluator Note: The examinee may wish to print the data, inform him/her that it is not required.
Evaluator Cue: Printed PPCS data is not required.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 13 of 18 Performance Step: 15 5.5 IF Control Bank D is NOT fully inserted, THEN PERFORM the Critical Y following exercise test:
5.5.1 PLACE the Control Rod Bank Selector switch to the CBD position.
Standard: The examinee places the Control Rod Bank Selector switch to the CBD position.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 16 5.5.2 PERFORM the following rod step sequence twice:
Critical N a. STEP Control Bank D OUT 1 step from its current position.
Standard: The examinee steps Control Bank D out 1 step.
Evaluator Note: This step and the next will be repeated.
Evaluator Cue:
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 14 of 18 Performance Step: 17 b. BUMP STEP Control Bank D IN one step.
Critical N Standard: The examinee bumps Control Bank D in one step.
Evaluator Note: This step and the previous will be repeated.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 18 5.5.3 INSERT OR WITHDRAW Control Bank D at least 10 Critical Y steps but NO more than 20 steps while OBSERVING movement on individual Control Bank D rods.
Standard: The examinee inserts Control Bank D at least 10 but not more than 20 steps.
Evaluator Note: The examinee must recognize that there is not enough room to withdraw the rods 10 steps and must therefore insert the rods the required distance.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 15 of 18 Performance Step: 19 5.5.4 WITHDRAW OR INSERT Control Bank D to the position Critical Y recorded in Step 5.1.3 Standard: The examinee withdraws Control Bank D to its original position recorded in Step 5.1.3.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 20 5.5.5 WITHDRAW Control Bank D one step.
Critical Y Standard: The examinee withdraws Control Bank D one step.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 21 5.5.6 INSERT Control Bank D one step.
Critical Y Standard: The examinee inserts Control Bank D one step.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 16 of 18 Performance Step: 22 5.5.7 Ensure Control Bank D is in the position recorded in Step Critical N 5.1.3.
Standard: The examinee ensures the Control Bank D Group Demand Counter reading matches the number obtained in step 5.1.3.
Evaluator Note: CB D Demand Counter should read 220.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Terminating Cues: JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
PBN JPM P001.020.COT, PERFORM ROD EXERCISE TEST, JPM REV. 6 Page 17 of 18 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
JOB PERFORMANCE MEASURE JPM Page 18 of 18 TURNOVER SHEET INITIAL CONDITIONS:
You are CO3.
Unit 1 is at 100% power, steady state Xenon.
INITIATING CUES (IF APPLICABLE):
The SRO has directed you to perform TS-5, Rod Exercise Test Unit 1.
The pre-job brief has been completed.
An AO is standing by in the Unit 1 Rod Drive MG Set Room to assist in the performance of the test.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JOB PERFORMANCE MEASURE JPM Page 1 of 12 JPM TITLE: Manually Makeup to the VCT JPM NUMBER: PBN JPM P004.027b.COT REV. 8 TASK NUMBER(S) / PBN P004.027.COT / Manually Blend to the VCT / RWST TASK TITLE(S):
K/A NUMBERS: 004 A4.12 K/A VALUE: 3.8 / 3.3 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 15 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 2 of 12 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 3 of 12
{C001}
UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0-2 See historical records Updated to current revision of QF-1075-01. Updated RCS boron concentration to match current IC-2 Rev. 3 concentration.
Updated RCS boron concentration to match current IC-2 concentration. Revised JPM for use during the Rev. 4 2012 ILT NRC Exam to match changes in OP-5B. Added additional malfunction to set RMUW controller to 50 gpm.
Changed to Rev. 5 to account for simultaneous development of JPM (Rev. 4) used for 2012 Annual Rev. 5 NRC Exam.
New Fleet Template. Added SIM setup instructions for 1HC-111 to 50 gpm. Modified the initial Rev. 6 conditions and turnover page for the gas stripper to be off-line.
Rev. Updated for the 2014 operational exam.
Added an evaluator note in step J. Hinze 1/30/15 Requested by the NRC Pen and 1 to identify which reference the for the 2015 ILT NRC student would T Larson Rev. 8 Updated for the 2017 NRC ILT Exam.
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 4 of 12 SIMULATOR SET-UP: (Only required for simulator JPMs)
Simulator Setup Instructions:
Load IC 2.
Walk down the control boards to ensure plant conditions accurately reflect the JPM's initial conditions. Make any necessary adjustments.
Ensure the RMUW Flow controller is set at 0 gpm.
Ensure the Boric Acid Flow controller is set at 0 ppm Place 1CV-112A to DIVERT to establish VCT level at ~30%, THEN return 1CV-112A to AUTO.
Save IC for multiple uses.
Provide a copy of OP 5B Attachment G with Initial Conditions signed off.
AFTER the blend is started and STABLE, insert TRIGGER 1 to cause the RMUW controller to fail. DO NOT insert the malfunction until the blend is started and stable.
SIMULATOR MALFUNCTIONS:
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-FIC111 Insert on event DILUTION FLOW X14I161T==1.
CNH1CVC009B 00:00:20 00:00:10 1 00:00:00 - 50 INDICATOR CTLR (Reactor Makeup SW FIXED OUTPUT to START)
SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: OP 5B, Blender Operation / Dilution / Boration General
References:
Blender Data Manual ARB 1C04 1C 3-8, Reactor Makeup Water Flow Deviation Task Standards: The examinee starts to raise VCT level, determines improper operation of the Reactor Makeup Water flow controller and secures the blend to the VCT or takes manual control of 1HC-111 adjusting RMW flow prior to VCT level rise of >15%.
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 5 of 12 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:
You are the Unit 1 Operator at the Controls.
Leakage at the charging pump seals has resulted in the need to manually blend to the VCT to maintain normal VCT level.
The CVCS system is in operation with a single letdown orifice in service.
Unit 1 RCS boron concentration is 866 ppm.
The on-service boric acid storage tank, T-6A, concentration is 3.75%.
Unit 1 Letdown Gas Stripper is on-line.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to raise VCT level approximately 15% at the current RCS boron concentration per OP 5B, Blender Operation / Dilution / Boration, Attachment G, Manual Blend to the RCS.
NOTE: The blend may be left in the CVCS piping since frequent blends are currently required.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 6 of 12 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 4.1 DETERMINE the desired blender output concentration.
Critical N Standard: The examinee determines the existing acid and water flow setpoints for the present boron concentration by referencing:
Operating experience, or Using the Blender Data Manual Evaluator Note: The examinee should reference Table 4 of the Blender Data Manual to determine if the boron concentration is set correctly.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 7 of 12 Performance Step: 2 4.2 SET HC-111, RMUW Flow Controller, to desired FLOWRATE.
Critical Y The examinee determines that controller HC-111 is set at 0 gpm and Standard:
resets to desired flowrate.
Evaluator Note: HC-111 should normally be set to 40 gpm, but may be set to a different value as long as the correct ratio of water-acid for current RCS boron concentration is used.
Evaluator Cue: If the incorrect controller setting for 1HC-111, RMUW Flow controller, is reported to OS1, then acknowledge the report and direct the examinee to set the controller to the correct setting and continue making up to the VCT.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 3 4.3 SET HC-110, Boric Acid Flow Hand Controller, to desired Critical: Y FLOWRATE.
Standard: The examinee determines that controller 1HC-110 is set to 0 gpm and resets to desired flowrate.
Evaluator Note: The boric acid controller should be set at approximately 6.0 gpm (for a 40 gpm RMUW setting).
Evaluator Cue: If the incorrect controller setting for 1HC-110, BA Flow controller, is reported to OS1, then acknowledge the report and direct the examinee to set the controller to the correct setting and continue making up to the VCT.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 8 of 12 Performance Step: 4 4.4 ENSURE the following valve control switch positions:
Critical N CV-111, RMW to Z-1 BA Blender Flow Control, in AUTO CV-110A, BA TO Z-1 BA Blender Inlet FCV, in AUTO CV-110B, Z-1 BA Blender Outlet FCV in AUTO OR IF VCT BYPASSED, THEN OPEN (circle one).
CV-110C, T-4 VCT Boric Acid Inlet Flow Control in AUTO OR IF VCT BYPASSED, THEN OPEN (circle one).
Standard: The examinee determines:
1CV-111, RMW to Z-1 BA Blender Flow Control is in AUTO 1CV-110A, BA TO Z-1 BA Blender Inlet FCV is in AUTO 1CV-110B, Z-1 BA Blender Outlet FCV is in AUTO 1CV-110C, T-4 VCT Boric Acid Inlet Flow Control is in AUTO Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 5 4.5 PLACE the Reactor Makeup Mode Selector Switch to BLEND.
Critical Y Standard: The examinee places the Reactor Makeup Mode Selector Switch to the BLEND position.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 9 of 12 Performance Step: 6 4.6 PLACE the Reactor Makeup Control Switch to START.
Critical Y Standard: The examinee places the Reactor Makeup Control Switch to the START position and ensures the RED light is LIT.
Evaluator Note: Verification of the RED light is NOT critical.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 7 4.7 WHEN required to maintain VCT pressure and level, THEN Critical N PLACE CV-112A, VCT Level Control Divert, to DIVERT.
Standard: The examinee acknowledges the guidance of this step and returns to it as it is needed to control VCT pressure and level, and moves on with the procedure.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Performance Step: 8 4.8 While CONTINUING with this procedure, CHECK system for Critical N proper response AND MONITOR the following parameters:
VCT level / pressure RCP seal leakoff flow Rx Power / Count Rate RCS temperature Standard: The examinee monitors the listed parameters.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
NOTE: AFTER THE BLEND IS STARTED AND IS STABLE, TRIGGER 1 WILL INSERT TO CAUSE THE RMUW CONTROLLER TO FAIL.
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 10 of 12 Performance Step: 9 The examinee responds to the RMUW deviation alarm or increased Critical Y dilution rate and takes action to secure makeup to the VCT or takes manual control of 1HC-111 and adjusts RMW flow to ~40 gpm.
Standard: The examinee secures makeup to the VCT or takes manual control of 1HC-111 and adjusts RMW flow to ~40 gpm prior to VCT level rise of
> 15%.
Evaluator Note: ARB 1C04 1C 3-8, Reactor Makeup Water Flow Deviation, allows either option to respond.
The RMW deviation alarm may NOT actuate if makeup is promptly secured.
Performance: SATISFACTORY UNSATISFACTORY Comments: ______________________________________________________
Terminating Cues: This completes the JPM.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
PBN JPM P004.027b.COT, Manually Makeup to the VCT, JPM Rev. 8 Page 11 of 12 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
JOB PERFORMANCE MEASURE JPM Page 12 of 12 TURNOVER SHEET INITIAL CONDITIONS:
You are the Unit 1 Operator at the Controls.
Leakage at the charging pump seals has resulted in the need to manually blend to the VCT to maintain normal VCT level.
The CVCS system is in operation with a single letdown orifice in service.
Unit 1 RCS boron concentration is 866 ppm.
The on-service boric acid storage tank, T-6A, concentration is 3.75%.
Unit 1 Letdown Gas Stripper is on-line.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to raise VCT level approximately 15% at the current RCS boron concentration per OP-5B, Blender Operation / Dilution / Boration, Attachment G, Manual Blend to the RCS.
NOTE: The blend may be left in the CVCS piping since frequent blends are currently required.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JOB PERFORMANCE MEASURE JPM Page 1 of 19 JPM TITLE: Fill the Accumulators JPM NUMBER: PBN JPM P006.002.COT REV. 10 TASK NUMBER(S) / PBN P006.002.COT / Fill the Accumulators TASK TITLE(S):
K/A NUMBERS: 006.A1.13 K/A VALUE: 3.5 / 3.7 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 30 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 2 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 3 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 10 Updated for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 4 of 19 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
Load any IC with both units at 100%, steady state Drain 1T-34B, Unit 1 B SI Accumulator until annunciator C01B 3-8, 1T-34B ACCUMULATOR LEVEL HIGH OR LOW alarms per OI-100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1. (LOW alarm setpoint = 9%) Ensure accumulator pressure remains within band after level is lowered.
Walk down control boards to verify plant conditions match initial conditions described by the JPM.
Save to an IC for multiple use.
Multiple Uses:
Load the saved IC for this JPM.
Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Resave if required.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: OI 100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1 Stopwatch Calculator General
References:
OI 100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1 Task Standards: The examinee raises the 1T-34B, Unit 1 B SI accumulator level to 20% (
3%) in accordance with OI 100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1, Section 5.2.
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 5 of 19 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:
Unit 1 is operating at 100% steady-state conditions.
Annunciator C01B 3-8, 1T-34B ACCUMULATOR LEVEL HIGH OR LOW is lit.
Emergency Diesel Generators G-01, G-02, G-03 and G-04 are OPERABLE and in a normal at-power alignment.
1-TS-ECCS-002 Train A and 1-TS-ECCS-002 Train B, Safeguards System Venting (Monthly) Unit 1 were performed last shift for 1P-15A and 1P-15B, Unit 1 safety injection pumps.
Combined Control Room Log accumulator level drop rate (daily accumulator leakage) is currently 0.3
% per day over the past 30 days.
Unit 1 RWST Boron concentration is 2950 ppm.
INITIATING CUES (IF APPLICABLE):
You are the 3rd Control Operator.
The SRO directs you to raise 1T-34B, Unit 1 B SI accumulator level to approximately 20% in accordance with OI 100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1, Section 5.2.
Unit 1 Control Operator has been assigned the duties of monitoring accumulator parameters per your request.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 6 of 19 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.2.1 Perform the following as applicable:
Critical N a. IF filling 1T-34A, Safety Injection Accumulator, THEN PERFORM Attachment A, Step 1.0.
Standard: The examinee notes this step is N/A.
Evaluator Cue:
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 5.2.1 Perform the following as applicable:
Critical N b. IF filling 1T-34B, Safety Injection Accumulator, THEN PERFORM Attachment B, Step 1.0.
Standard: The examinee completes Attachment B, 1T-34B Accumulator Level/Pressure Change Data Sheet, Section 1.0.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 7 of 19 Performance Step: 3 5.2.1 Perform the following as applicable:
Critical N c. Use Control Room Log data to determine accumulator leak rate over past 30 days, OR since accumulator was last filled (whichever time period is shorter):
Accumulator leak rate (% per day): _____
Standard: The examinee fills in the given leak rate.
Evaluator Cue: 1T-34B, Safety Injection Accumulator leak rate is 0.3 % per day over last 30 days.
If asked, the last accumulator fill was greater than 30 days ago.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 5.2.1 Engineering Verification Critical N d. IF accumulator leakage is greater than 0.7% / day, THEN NOTIFY Engineering to perform additional evaluation.
Standard: The examinee N/As Step 5.2.1.d and proceeds to Step 5.2.2.
Evaluator Cue:
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 8 of 19 Performance Step: 5 5.2.2 Align 1P-15A, Safety Injection Pump, recirc flow path as follows:
Critical N a. Ensure LOCKED OPEN 1SI-876A, P-15A SI Pump Discharge Recirc to SI Test Line.
Standard: The examinee ensures that the 1SI-876A, P-15A SI pump discharge recirc to SI test line valve is locked open by dispatching the Primary Auxiliary Building Auxiliary Operator to verify 1SI-876As status.
Evaluator Cue: The Primary Auxiliary Building Auxiliary Operator reports that the 1SI-876A, P-15A SI pump discharge recirc to SI test line valve is locked open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 5.2.2 Align 1P-15A, Safety Injection Pump, recirc flow path as follows:
Critical N b. At C01R, ensure OPEN 1SI-897A, SI Test Line Return.
Standard: The examinee ensures that the 1SI-897A, SI test line return isolation AOV is open. (The green light is off, the red light is on and the control switch for 1SI-897A is in the open position.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 JPM Page 9 of 19 Performance Step: 7 5.2.2 Align 1P-15A, Safety Injection Pump, recirc flow path as follows:
Critical N c. At C01R, ensure OPEN 1SI-897B, SI Test Line Return Second Off Isolation.
Standard: The examinee ensures that the 1SI-897B, SI test line return isolation AOV is open. (The green light is off, the red light is on and the control switch for 1SI-897B is in the open position.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 5.2.3 ENSURE the following valves are OPEN:
Critical N 1SI-825A, 1T-13 RWST Outlet to P-15A/B SI Pump 1SI-825B, 1T-13 RWST Outlet to P-15A/B SI Pump 1SI-896A, 1P-15A SI Pump Suction 1SI-866A, Cold Leg Injection Line Isolation Standard: The examinee ensures all of the following valves are open:
1SI-825A, P-15A/B SI pump suction from RWST MOV. (The green light is off, the red light is on and the control switch is in the auto position.)
1SI-825B, P-15A&B SI pump suction from RWST MOV. (The green light is off, the red light is on and the control switch is in the auto position.)
1SI-896A, 1P-15A pump suction isolation valve is open. (The green light is off, the red light is on and the control switch is in the spring return to center position.)
1SI-866A, 1P-15A pump discharge header MOV is open. (The green light is off, the red light is on and the control switch is in the spring return to center position.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 10 of 19 Performance Step: 9 5.2.4 Declare 1P-15A, Safety Injection Pump INOPERABLE, and Critical N ENTER the Action Condition of TS 3.5.2.
Standard: The examinee notifies the SRO to declare 1P-15A, Safety Injection Pump INOPERABLE, and enter TS 3.5.2 Action Condition A.
Evaluator Cue: The SRO informs you that 1P-15A, Safety Injection Pump is INOPERABLE, TS 3.5.2 Action Condition A has been entered and that the Narrative Log has been updated.
IF asked, THEN report that the opposite train standby emergency power supply has been verified operable (per initial conditions).
IF asked, THEN report that Unit 1 B Train of ECCS has been walked down and verified to be Operable.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 5.2.5 Vent 1P-15A SI pump in accordance with Attachment C.
Critical N Standard: Step 5.2.5 is marked N/A. The examinee proceeds to Step 5.2.6.
Evaluator Note: Step 5.2.5 is marked N/A because 1-TS-ECCS-002 Train A, Safeguards System Venting (Monthly) Unit 1 has been completed within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is one of the Initial Conditions.
Evaluator Cue: IF examinee begins to implement action to vent 1P-15A, THEN inform him that venting is not required. (See initial conditions.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 11 of 19 Performance Step: 11 5.2.6 Ensure proper oil level in 1P-15A as follows:
Critical N a. Check for visible level in 1P-15A oil sightglass located next to the oiler bulb.
- b. IF oil is NOT visible in sight glass, THEN go to Attachment E.
- c. Check 1P-15A oiler bulb at or above one-half full.
- d. IF oiler bulb less than one-half full, THEN GO TO Attachment E.
Standard: The examinee directs the Primary Auxiliary Building Auxiliary Operator to:
Check for visible level in the 1P-15A, safety injection pump oil sight glass located next to the oiler bulb. When told there is oil visible in the sight glass he N/As step b.
Ensure that the 1P-15A, safety injection pump oil bulb is at or above one-half full. When told the oiler bulb is two-thirds full, he N/As step d.
Evaluator Cue: The Primary Auxiliary Building Auxiliary Operator reports that:
There is oil visible in the 1P-15A, safety injection pump oil sight glass located next to the oiler bulb.
The 1P-15A, safety injection pump oil bulb is two-thirds full.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 12 5.2.7 IF one EDG is aligned to supply both Units A05 standby Critical N emergency power, THEN perform the following:
Standard: Step 5.2.7 is marked N/A. The examinee proceeds to Step 5.2.8.
Evaluator Note: Step 5.2.7 is marked N/A because G-01, G-02, G-03 and G-04 are in a normal at-power alignment. This is one of the Initial Conditions.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 12 of 19 Performance Step: 13 5.2.8 RECORD the position of 1P-15A-CS, Safety Injection Pump Critical N Control Switch.
Control Switch position: _________
Standard: The examinee records the position of 1P-15A-CS, Safety Injection Control Switch.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 5.2.9 START 1P-15A, Safety Injection Pump.
Critical Y Standard: The examinee places the control switch for 1P-15A, Safety Injection Pump to the Start position. (The green light is off, the red light is on, 1FI-925, 1P-15A High Head SI Flow, 1P-923, 1P-15A SI Pump Disch Pressure and AC AMPS, 1P-15A SI Pump Current are as read.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 13 of 19 Performance Step: 15 5.2.10 MONITOR all available channels for accumulator pressure and Critical N level during accumulator fill.
Standard: The examinee notes which indicators he will be monitoring during accumulator fill.
Evaluator Note: Initial conditions stated that the Unit 1 Control Operator is available to monitor accumulator parameters per direction of the examinee. The Booth operator may be used for this function.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 16 5.2.11 IF filling 1T-34A, Safety Injection Accumulator, THEN Critical N PERFORM the following:
Standard: Step 5.2.11 is marked N/A. The examinee proceeds to Step 5.2.12.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 14 of 19 Performance Step: 17 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical Y PERFORM the following:
- a. OPEN 1SI-835B, T-34B SI Accumulator Fill AOV, AND START stopwatch.
Standard: The examinee places the control switch for the 1SI-835B, T-34B SI Accumulator Fill From Cold Leg SI to the Open position (The green light is off and the red light is on.)
And starts the stopwatch.
Evaluator Note: The critical portion of this step is opening 1SI-835B.
If examinee directs another operator to use the stopwatch, the evaluator will assign the booth operator to this task.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 18 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical Y PERFORM the following:
- b. FILL SI accumulator to desired level as indicated on the following level indicators:
1LI-934, 1T-34B Accumulator Level Indicator 1LI-935, 1T-34B Accumulator Level Indicator Standard: The examinee monitors level indication for 1T-34B and raises the level to 20% ( 3%).
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 15 of 19 Performance Step: 19 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical Y PERFORM the following:
- c. SHUT 1SI-835B, T-34B SI Accumulator Fill AOV AND STOP timing. RECORD time below:
Standard: The examinee:
Places the control switch for the 1SI-835B, 1T-34B accumulator fill AOV to the Close position (The green light is on and the red light is off)
And records the fill time.
Evaluator Note: The critical portion of this step is closing 1SI-835B.
If examinee directs another operator to use the stopwatch, the evaluator will assign the booth operator to this task.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 20 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical N PERFORM the following:
- d. RECORD AFT in Step 2.1 of Attachment B, 1T34B Accumulator Level/Pressure Change Data Sheet.
Standard: The examinee records Accumulator Fill Time on Attachment B.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 16 of 19 Performance Step: 21 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical N PERFORM the following:
- e. IF fill of 1T-34A, Safety Injection Accumulator, is NOT required, THEN STOP 1P-15A, Safety Injection Pump.
Standard: The examinee places the control switch for 1P-15A, Safety Injection Pump to the Stop position. (The green light is on, the red light is off, 1FI-925, 1P-15A High Head SI Flow, 1PI-923, 1P-15A SI Pump Disch Pressure and AC AMPS, 1P-15A SI Pump Current are as read.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 22 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical Y PERFORM the following:
- f. IF fill of 1T-34A, SI Accumulator is NOT required, THEN ENSURE 1P-15A-CS is returned to position recorded at step
5.2.8. Standard
The examinee ensures that the control switch for 1P-15A, Safety Injection Pump is in the Auto (after trip) position.
Evaluator Cue: Another license has performed an independent verification of 1P-15A-CS, Safety Injection Pump Control Switch position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 17 of 19 Performance Step: 23 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical N PERFORM the following:
- g. DECLARE 1P-15A OPERABLE Standard: The examinee informs the SRO to declare 1P-15A, Safety Injection Pump OPERABLE.
Evaluator Cue: The SRO acknowledges your report.
The SRO reports that 1P-15A, safety injection pump is OPERABLE and the Narrative Log has been updated.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 24 5.2.12 IF filling 1T-34B,Safety Injection Accumulator, THEN Critical N PERFORM the following:
- h. Exit Action Condition for TS 3.5.2 for Unit 1.
Standard: The examinee informs the SRO to exit TS 3.5.2 Action Condition for 1P-15A, Safety Injection pump.
Evaluator Cue: The SRO informs you that the Technical Specification Action Condition associated with 1P-15A, Safety Injection Pump has been exited and the Narrative Log has been updated.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
JPM PBN JPM P006.002.COT, FILL THE ACCUMULATORS, REV. 10 Page 18 of 19 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS:
Unit 1 is operating at 100% steady-state conditions.
Annunciator C01B 3-8, 1T-34B ACCUMULATOR LEVEL HIGH OR LOW is lit.
Emergency Diesel Generators G-01, G-02, G-03 and G-04 are OPERABLE and in a normal at-power alignment.
1-TS-ECCS-002 Train A and 1-TS-ECCS-002 Train B, Safeguards System Venting (Monthly) Unit 1 were performed last shift for 1P-15A and 1P-15B, Unit 1 safety injection pumps.
Combined Control Room Log accumulator level drop rate (daily accumulator leakage) is currently 0.3
% per day over the past 30 days.
Unit 1 RWST Boron concentration is 2950 ppm.
INITIATING CUES (IF APPLICABLE):
You are the 3rd Control Operator.
The SRO directs you to raise 1T-34B, Unit 1 B SI accumulator level to approximately 20% in accordance with OI 100 Unit 1, Adjusting SI Accumulator Level and Pressure Unit 1, Section 5.2.
Unit 1 Control Operator has been assigned the duties of monitoring accumulator parameters per your request.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 20 JPM TITLE: Establish Feed Flow From Condensate System JPM NUMBER: PBN JPM P041.003a.COT REV. 0 TASK NUMBER(S) / PBN P041.003.COT / Operate the condenser steam dump control system in TASK TITLE(S): various modes K/A NUMBERS: 041 A4.08 K/A VALUE: 3.0 / 3.1 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 25 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 2 of 20 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 3 of 20 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 4 of 20 SIMULATOR SET-UP: (Only required for simulator JPMs)
Simulator Setup Instructions:
Load a 100% IC Load all commands listed in table below Start the simulation Insert Trigger 1 Perform EOP set actions through CSP-H.1 Unit 1, Step 13.c.
Make any necessary adjustments or corrections Update documentation if required Save to an IC for multiple use Multiple Use:
Load the saved IC and schedule file for this JPM Walk down the control boards to ensure plant conditions accurately reflect the JPM initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required SIMULATOR MALFUNCTIONS:
INITIAL FINAL MALFUNCTION No. MALFUNCTION TITLE DELAY RAMP ET DELETE IN NOTES VALUE VALUE AUX FWP TURBINE MAL1AFW001 00 :00 :00 - - 00 :00 :00 - - PRELOAD OVERSPEED 1-P53 AUXILIARY Shaft PMP1AFW004 00 :00 :00 - - 00 :00 :00 - PRELOAD FEEDWATER PUMP Seizure 1-B5212C P-38A AUX BKR1AFW001 SG FEED PUMP 00 :00 :00 - - 00 :00 :00 - Failasis PRELOAD CKTBKR 2-B5231C P-38B AUX BKR1AFW002 SG FEED PUMP 00 :00 :00 - - 00 :00 :00 - Failasis PRELOAD CKTBKR 2-EP-5268 2P53 LOA2EPS101 SUPPLY BREAKER 00 :00 :00 - - 00 :00 :00 - Rackout PRELOAD RACKOUT RTD BYPASS LOOP A MAL1RCS003A 00 :00 :00 - 1 00 :00 :00 - 75 PLE HOT LEG LINE LEAK 1-HC468 LOOP A ATM As Is CNH1PCS011 SD HAND 00 :00 :00 - - 00 :00 :00 - PRELOAD Auto/Man CONTROLLER 1-HC478 LOOP B ATM As Is CNH1PCS013 SD HAND 00 :00 :00 - - 00 :00 :00 - PRELOAD Auto/Man CONTROLLER Condenser A Loss of MAL1CFW005A 00 :00 :00 - - 00 :00 :00 - 1000 Vacuum Condenser B Loss of MAL1CFW005B 00 :00 :00 - - 00 :00 :00 - 1000 Vacuum 1MS-234 SG A Main LOA1SGN022 00 :00 :00 - 3 00 :00 :00 - 1-open Steam Bypass TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 5 of 20 1MS-236 SG B Main LOA1SGN024 00 :00 :00 - 5 00 :00 :00 - 1-open Steam Bypass 1CS-2190 FWP 1P-28A Cntrl_Pwr_
VLV1CFW015 00 :00 :00 - 7 00 :00 :00 - MFP discharge MOV Disch Stop Vlv Fuse 1CS-2189 FWP 1P-28B Cntrl_Pwr_
VLV1CFW013 00 :00 :00 - 9 00 :00 :00 - MFP discharge MOV Disch Stop Vlv Fuse SIMULATOR OVERRIDES:
See above SIMULATOR REMOTE FUNCTIONS:
See above Required Materials: CSP-H.1 Unit 1, Response To Loss Of Secondary Heat Sink General
References:
CSP-H.1 Unit 1, Response To Loss Of Secondary Heat Sink Task Standards: Establish feed flow from condensate system /depressurize at least one steam generator to less than 280 psig by dumping steam to the condenser at maximum rate from selected steam generator using the condenser dump valve test switches in accordance with CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink.
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 6 of 20 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:
You are the fourth license.
A RCS leak in excess of charging pump capacity necessitated a manual reactor trip, Safety Injection and Containment Isolation.
1P-53, Motor-Driven AFW Pump seized on startup, 1P-29, Turbine-Driven AFW Pump tripped on overspeed and both P-38A and P-38B, SSG Feed Pumps failed to start.
2P-53, Motor-Driven AFW Pump is OOS for repairs.
Upon transitioning from EOP-0, the crew entered CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink, and has completed up to Step 13.d EOP-0, Attachment A, Automatic Action Verification, is complete.
The third license is working to recover 1P-29, Turbine-Driven AFW Pump.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to perform CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink, starting at Step 13.d, Depressurize at least one SG to less than 280 psig, using the A steam generator.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 7 of 20 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 13.d Depressurize at least one S/G to less than 280 psig:
Critical N 1) Shut MSIV and MSIV bypass valve for Non-selected S/G Standard: The examinee:
Shuts the MSIV for the non-selected (B) SG by taking its associated control switch to the CLOSE position.
Evaluator Note: A SG is the selected SG.
Evaluator Cue: OS1 confirms that the MSIV bypass valves are administratively closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 8 of 20 Performance Step: 2 13.d Depressurize at least one S/G to less than 280 psig:
Critical N 2) Dump steam to condenser at maximum rate from selected S/G:
a) Place Steam Dump Mode Selector switch in Manual b) Shift Condenser Steam Dump Controller to manual:
1HFC-484 c) Fully open two condenser steam dump control valves:
Standard: The examinee determines that the CSDs will not operate due to the condenser not available, and goes to Step 13.d 2) RNO.
Evaluator Note: The examinee may attempt to perform the steps to open the CSD valves, but the valves will not open. The condenser is not available.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 9 of 20 Performance Step: 3 13.d Depressurize at least one S/G to less than 280 psig:
Critical N 2) RNO Manually or locally dump steam at maximum rate from selected S/G:
Standard: The examinee attempts to manually dump steam at the maximum rate from the selected S/G by:
Taking the selected S/G atmospheric hand controller to manual AND Rotating the potentiometer in the Open direction Evaluator Note: IF the examinee directs the PAB AO to locally dump steam from the selected steam generator, THEN provide the following cue:
The examinee may recommend or attempt to dump steam using the B SG ADV, if asked the OS/SM would concur with this action.
Evaluator Cue: Both atmospheric steam dump valves will not open locally.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 10 of 20 Performance Step: 4 13.d Depressurize at least one S/G to less than 280 psig:
Critical N 2) RNO Manually or locally dump steam at maximum rate from selected S/G:
- b. IF atmospheric steam dump is NOT available, THEN dump steam using alternate means:
- 1. Open MSIV bypass valve:
o 1MS-234 for S/G A o 1MS-236 for S/G B Standard: The examinee:
Directs the PAB AO to open the selected MSIV bypass valve Evaluator Note: If the examinee shuts both MSIVs in an earlier step, then opening one bypass valve becomes critical.
Evaluator Cue: Open MSIV bypass valve as directed:
Insert Trigger 3 for 1MS-234 (A SG)
AND / OR Insert Trigger 5 for 1MS-236 (B SG)
AO reports that the selected MSIV bypass valve is open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 11 of 20 Performance Step: 5 13.d Depressurize at least one S/G to less than 280 psig:
Critical Y 2) RNO Manually or locally dump steam at maximum rate from selected S/G:
- b. IF atmospheric steam dump is NOT available, THEN dump steam using alternate means:
- 3. Direct plant personnel to stay clear of LP turbine rupture disks.
Standard: The examinee:
Rotates the dump valve test switches for 1MS-2050 through 2057 to the test position on 1C03R.
Directs plant personnel to stay clear of the LP turbine rupture disks Evaluator Note: Critical actions are bolded.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 12 of 20 Performance Step: 6 13.d Depressurize at least one S/G to less than 280 psig:
Critical Y 2) RNO Manually or locally dump steam at maximum rate from selected S/G:
- b. IF atmospheric steam dump is NOT available, THEN dump steam using alternate means:
- 4. Operate steam dump pressure controller in manual:
a) IF any MSIV is open, THEN fully open two condenser steam dumps.
b) IF both MSIVs are shut, THEN open all condenser steam dumps Standard: The examinee:
Shifts 1HFC-484, Condenser Steam Dump Controller to MANUAL and adjusts the potentiometer so that two condenser steam dumps are fully open. (all open if both MSIVs are shut)
Evaluator Note: 1HFC-484 may already be in manual if the examinee attempted to use the condenser steam dumps in procedure step 13.d.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 13 of 20 Performance Step: 7 13.d Depressurize at least one S/G to less than 280 psig:
Critical N 2) RNO Manually or locally dump steam at maximum rate from selected S/G:
- c. IF No S/G can be depressurized, THEN go to Step 15.
Standard: The examinee marks this sub-step N/A and proceeds to sub-step 13.e.1).
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 13.e Establish condensate flow to depressurized S/G:
Critical N 1) Ensure main feed AC lube oil pumps running:
1P-73B 1P-73A Standard: The examinee ensures the main feed AC lube oil pumps are running.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 14 of 20 Performance Step: 9 13.e Establish condensate flow to depressurized S/G:
Critical N 2) Place MFP control switch to pull-out:
1P-28A 1P-28B Standard: The examinee places 1P-28A and 1P-28B MFP control switches to pull-out.
Evaluator Note:
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 13.e Establish condensate flow to depressurized S/G:
Critical N 3) Check MFP Mini Recirc Flow Control Valves - CLOSED 1CS-2180 1CS-2186 Standard: The examinee checks that 1CS-2180 and 1CS-2186 MFP Mini Recirc Control Valves are closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 15 of 20 Performance Step: 11 13.e Establish condensate flow to depressurized S/G:
Critical Y 4) Open main feed pump discharge MOVs:
a) Open main feed pump discharge MOVs and hold switches in OPEN position:
1CS-2190 1CS-2189 Standard: The examinee opens 1CS-2190 and 1CS-2180, Main Feed Pump Discharge MOVs and holds the switches in the open position.
Evaluator Note: The examinee may elect to perform Step 13.e.4)a) and b) one train at a time.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 12 13.e Establish condensate flow to depressurized S/G:
Critical N 4) Open main feed pump discharge MOVs:
b) Open breaker for open MOVs 1B52-417M for 1CS-2190 1B52-417J for 1CS-2189 Standard: The examinee directs opening for 1B52-417M for 1CS-2190 and 1B52-417J for 1CS-2189.
Evaluator Cue: When directed:
Insert Trigger 7 to open 1B52-417M for 1CS-2190.
Insert Trigger 9 to open 1B52-417J for 1CS-2189.
Report as AO when actions are complete.
Evaluator Note: The examinee may elect to perform Step 13.e.4)a) and b) one train at a time.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 16 of 20 Performance Step: 13 13.e Establish condensate flow to depressurized S/G:
Critical N 5) Manually shut low pressure Feedwater heater bypass valve:
1CS-2273 Standard: The examinee takes the hand controller for 1CS-2273, Feedwater Heater Bypass Valve to manual and adjusts the potentiometer in the close direction until it stops.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 13.e Establish condensate flow to depressurized S/G:
Critical N 6) Ensure Feedwater isolation valves - OPEN:
1CS-3124 1CS-3125 Standard: The examinee verifies that 1CS-3124 and 1CS-3125, Feedwater Isolation Valves are open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 17 of 20 Performance Step: 15 13.e Establish condensate flow to depressurized S/G:
Critical N 7) Reset Feedwater regulating valve bypasses:
Standard: The examinee depresses the Feedwater Regulating Valve Bypass Reset pushbutton.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 16 13.e Establish condensate flow to depressurized S/G:
Critical Y 8) Manually or locally open Feedwater regulating valve bypass on depressurized S/G:
o 1CS-480 for S/G A o 1CS-481 for S/G B Standard: The examinee:
Places the selected Feedwater Regulating Valve Bypass Controller to manual AND Adjusts the potentiometer in the open direction Evaluator Note:
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 18 of 20 Performance Step: 17 13.f Verify feed flow to depressurized S/G:
Critical N o Core exit thermocouples - LOWERING OR o Level in depressurized S/G - RISING o Wide range o Narrow range Standard: The examinee verifies feed flow to the depressurized steam generator by observing:
o Core exit thermocouples - LOWERING OR o Level in depressurized S/G - RISING o Wide range o Narrow range Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P041.003a.COT, Establish Feed Flow From Condensate JPM System, Rev. 0 Page 19 of 20 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 20 of 20 TURNOVER SHEET INITIAL CONDITIONS:
You are the fourth license.
A RCS leak in excess of charging pump capacity necessitated a manual reactor trip, Safety Injection and Containment Isolation.
1P-53, Motor-Driven AFW Pump seized on startup, 1P-29, Turbine-Driven AFW Pump tripped on overspeed and both P-38A and P-38B, SSG Feed Pumps failed to start.
2P-53, Motor-Driven AFW Pump is OOS for repairs.
Upon transitioning from EOP-0, the crew entered CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink, and has completed up to Step 13.d EOP-0 Attachment A, Automatic Action Verification, is complete.
The third license is working to recover 1P-29, Turbine-Driven AFW Pump.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to perform CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink, starting at Step 13.d, Depressurize at least one SG to less than 280 psig, using the A steam generator.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 11 JPM TITLE: Secure Containment Spray JPM NUMBER: PBN JPM P026.005.COT REV. 10 TASK NUMBER(S) / PBN P026.005.COT / Secure containment spray TASK TITLE(S):
K/A NUMBERS: 026 A2.08 K/A VALUE: 3.2 / 3.7 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform:
EVALUATION LOCATION: In-Plant: Control Room:
Simulator: Other:
Lab:
Time for Completion: 10 Minutes Time Critical: Yes No Alternate Path [NRC]: Yes No Alternate Path [INPO]: Yes No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 2 of 11 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 3 of 11 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0-5 See historical records.
Rev. 6 Reformatted to the current revision of QF-1075-01. Revised to Rev. 35 of EOP 1.1, SI Termination.
Reformatted to the current revision of QF-1075-01. Added additional evaluator notes, corrected Rev. 7 typos.
Rev. 8 Updated to new template Rev. 9 Updated for the 2015 Operational Exam.
Rev. 10 Updated for the 2017 NRC ILT Exam.
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 4 of 11 SIMULATOR SET-UP: (Only required for simulator JPMs)
Simulator Setup Instructions:
Initial Setup:
Load a 100% IC.
Load all commands listed in table below.
Start the simulation.
Insert Trigger 1 Perform actions of the EOP set through EOP-1.1, SI Termination, Step 6. Ensure 1P-14A is the pump secured in EOP-0, Attachment A. Ensure containment pressure is < 15 psig prior to snapping the IC.
Walk down the control boards to ensure plant conditions accurately reflect JPM initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Save to an IC for multiple use.
Multiple Use:
Load the saved IC for this JPM.
Walk down the control boards to ensure plant conditions accurately reflect the JPM initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Resave if required SIMULATOR MALFUNCTIONS:
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE SG A MAIN STEAM MAL1SGN003A LINE BREAK INSIDE 00:00:00 00:00:00 1 00:00:00 0 5E6 PLE CNMT SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
None Required Materials: EOP-1.1 Unit 1, SI Termination General
References:
EOP-1.1 Unit 1, SI Termination Task Standards: Containment spray is secured and in the standby mode.
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 5 of 11 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:
You are in EOP-1.1 Unit 1, SI Termination following a steam line break inside containment on Unit 1 A S/G.
Containment pressure has lowered to less than 20 psig.
EOP-1.1 Unit 1 has been completed through Step 6.
1P-14A containment spray pump is in Pullout due to actions taken in EOP-0 Unit 1, Reactor Trip or Safety Injection, Attachment A, Automatic Action Verification, Step A12.
INITIATING CUES (IF APPLICABLE):
The OS1 directs you to secure containment spray in accordance with EOP-1.1 Unit 1, Step 7.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 6 of 11 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 7. Check If Containment Spray Should Be Stopped:
Critical N a. Check containment spray pumps - ANY RUNNING.
Standard: The examinee:
Checks spray pumps running by observing breaker positions on C01.
Recognizes 1P-14B, Spray Pump is running and 1P-14A, Spray Pump is secured.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
Performance Step: 2 7. Check If Containment Spray Should Be Stopped:
Critical N b. Containment pressure - LESS THAN 20 PSIG Standard: The examinee:
Checks containment pressure indication on C01.
Recognizes pressure <20 psig.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 7 of 11 Performance Step: 3 7. Check If Containment Spray Should Be Stopped:
Critical Y c. Reset containment spray signal Standard: The examinee resets containment spray on the rear of C01 by depressing Train A and Train B Containment Spray pushbuttons (the examinee should check C01 B2-6 annunciator is cleared but this is not critical to task completion).
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
Performance Step: 4 7. Check If Containment Spray Should Be Stopped:
Critical N d. Ensure containment spray pump RWST suction MOVs - OPEN 1SI-870A 1SI-870B Standard: The examinee verifies:
1SI-870A, Containment Spray Pump RWST Suction MOV red light on, green light off.
1SI-870B, Containment Spray Pump RWST Suction MOV red light on, green light off.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 8 of 11 Performance Step: 5 7. Check If Containment Spray Should Be Stopped:
Critical Y e. Stop both containment spray pumps and place in auto:
1P-14A 1P-14B Standard: The examinee takes:
1P-14A, Containment Spray Pump Control Switch out of pull-out and places in auto-after-stop position.
1P-14B, Containment Spray Pump Control Switch to stop and then places in auto-after-stop position.
Evaluator Note: 1P-14A, Containment Spray Pump will be in pull-out due to earlier procedure actions.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
Performance Step: 6 7. Check If Containment Spray Should Be Stopped:
Critical Y f. Shut containment spray pump discharge valves and place in auto-after shut position:
1SI-860A 1SI-860B 1SI-860C 1SI-860D Standard: The examinee turns1SI-860A, B, C & D, Containment Spray Pump Discharge Valves to the shut position and observes green indicating lights.
Evaluator Note: Alarm C01B 1-6, Containment Spray Full Flow Discharge Valves Not in Auto will annunciate.
Evaluator Note: 1SI-860 B&D will spring return to the AUTO position, but A&C are maintained so will need to be manually returned to the AUTO position.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 9 of 11 Performance Step: 7 7. Check If Containment Spray Should Be Stopped:
Critical N g. Ensure both spray additive eductor suction valves - shut 1SI-836A 1SI-836B Standard: The examinee checks shut 1SI-836A & B, Spray Additive Eductor Suction Valves by noting white lights out on the Unit 1 SI-Spray Active Panel and/or noting close indication on controller.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
Performance Step: 8 Inform OS1 that step 7 of EOP-1.1 Unit 1 is complete.
Critical N Standard: The examinee informs OS1 of completion of step 7 of EOP-1.1 Unit 1.
Evaluator Cue: OS1 acknowledges report.
Performance: SATISFACTORY _____ UNSATISFACTORY _____
Comments: _____________________________________________________
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
PBN JPM P026.005.COT, Secure Containment Spray, Rev. JPM 10 Page 10 of 11 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
JOB PERFORMANCE MEASURE JPM Page 11 of 11 TURNOVER SHEET INITIAL CONDITIONS:
You are in EOP-1.1 Unit 1, SI Termination following a steam line break inside containment on Unit 1 A S/G.
Containment pressure has lowered to less than 20 psig.
EOP-1.1 Unit 1 has been completed through Step 6.
1P-14A containment spray pump is in Pullout due to actions taken in EOP-0 Unit 1, Reactor Trip or Safety Injection, Attachment A, Automatic Action Verification, Step A12.
INITIATING CUES (IF APPLICABLE):
The OS1 directs you to secure containment spray in accordance with EOP-1.1 Unit 1, Step 7.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JOB PERFORMANCE MEASURE JPM Page 1 of 15 JPM TITLE: SECURE THE DIESEL GENERATOR JPM NUMBER: PBN JPM P064.005aCOT REV. 3 TASK NUMBER(S) / P064.005.COT TASK TITLE(S): SECURE THE EMERGENCY DIESEL GENERATOR 064 A1.03 3.2 / 3.3 064 A3.03 3.4 / 3.3 K/A NUMBERS: 064 A3.06 K/A VALUE: 3.3 / 3.4 064 A4.01 4.0 / 4.3 064 A4.02 3.3 / 3.4 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 2 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 3 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 3 Updated for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 4 of 15 SIMULATOR SET-UP: (Only required for simulator JPMs)
Initial Setup:
Load an IC where conditions support 100% steady state conditions.
Start the simulation.
Using TS-81 as a guide, start emergency diesel generator G-01 in the Exercise mode.
Parallel emergency diesel generator G-01 to 1A-05 and increase load to 2600-2700 kW and 300-800 KVAR.
Freeze the simulator.
Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Save to an IC for multiple use.
Multiple Use:
Load the saved IC for this JPM.
Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Resave if required.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: TS 81, Emergency Diesel Generator G-01 Monthly General
References:
TS 81, Emergency Diesel Generator G-01 Monthly Task Standards: The examinee secures G-01, Emergency Diesel Generator in accordance with TS 81, Emergency Diesel Generator G-01 Monthly.
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 5 of 15 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:
G-01, Emergency Diesel Generator is running loaded after an exercise start in accordance with TS 81, Emergency Diesel Generator G-01 Monthly.
TS 81 has been completed through Step 5.50.
Attachment B, Fuel Oil Transfer System Surveillance, has been completed.
An Auxiliary Operator is stationed at G-01, Emergency Diesel Generator.
INITIATING CUES (IF APPLICABLE):
The full-load run time requirements have been met and the OS orders G-01, Emergency Diesel Generator to be secured in accordance with TS 81, Emergency Diesel Generator G-01 Monthly; beginning at Step 5.51.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 6 of 15 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.51 WHEN G-01 has run a minimum of 60 min. at full load, (2600-2700 Critical N kW and 300-800 KVARs), THEN PERFORM the following:
5.51.1 ENSURE G-01 Emergency Diesel Generator Logsheet LOADED PRIOR TO SHUTDOWN Section is COMPLETE.
Standard: The examinee checks with the test Auxiliary Operator(s) to ensure the G-01 Emergency Diesel Generator Log sheet LOADED PRIOR TO SHUTDOWN Section is complete.
Evaluator Cue: The test Auxiliary Operator(s) reports that the G-01 Emergency Diesel Generator Logsheet LOADED PRIOR TO SHUTDOWN Section is completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 7 of 15 Performance Step: 2 5.51 WHEN G-01 has run a minimum of 60 min. at full load, (2600-2700 Critical N kW and 300-800 KVARs), THEN PERFORM the following:
5.51.2 IF required, THEN ENSURE Attachment E, G-01EDG Vibration is COMPLETE.
Standard: The examinee checks to see if test was required.
Evaluator Cue: Attachment E, G-01 EDG Vibration has been completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 5.51 WHEN G-01 has run a minimum of 60 min. at full load, (2600-2700 Critical Y kW and 300-800 KVARs), THEN PERFORM the following:
5.51.3 REDUCE load to about 300 kW with G-01 Diesel Generator Governor control switch.
Standard: The examinee reduces load to about 300 kW (100 - 500 kW) using the G-01 Diesel Generator Governor control switch.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 8 of 15 Performance Step: 4 5.51 WHEN G-01 has run a minimum of 60 min. at full load, (2600-2700 Critical Y kW and 300-800 KVARs), THEN PERFORM the following:
5.51.4 DRIVE KVARs to zero with G-01 Generator Voltage Regulator control switch.
Standard: The examinee drives KVARs to zero using the G-01 Generator Voltage Regulator control switch.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 5.51 WHEN G-01 has run a minimum of 60 min. at full load, (2600-2700 Critical Y kW and 300-800 KVARs), THEN PERFORM the following:
5.51.5 PLACE 1A52-60-CS, G-01 Diesel Generator to Bus 1A-05 Breaker Control switch to TRIP AND record time.
Standard: The examinee places the control switch for the G-01 Diesel Generator to Bus 1A-05 breaker, 1A52-60 to the trip position. (critical)
Records the time. (not critical)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 9 of 15 Performance Step: 6 5.52 Record G-01 total time at full load (step 5.51.5 minus step 5.42).
Critical N Standard: The examinee records the G-01 total time at full load.
Evaluator Cue: Total time is 68 minutes.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 5.53 Perform the following on 1A52-60:
Critical N 5.53.1 CLOSE 1-271X-B03/A05-TS knife switches on 1A52-60:
Knife Switch F Knife Switch H 5.53.2 CLOSE 1-272X-B03/A05-TS knife switches on 1A52-60 Knife Switch F Knife Switch H 5.53.3 INSTALL and TIGHTEN the plastic switch cover for 1-271X-B-3/A-05-TS.
5.53.4 INSTALL and TIGHTEN the plastic switch cover for 1-272X-B03/A05-TS.
5.53.5 REMOVE Danger - Energized Electrical Equipment signs.
Standard: The examinee directs the test Auxiliary Operator(s) to perform Step 5.53 and to report back when completed.
Evaluator Cue: The test Auxiliary Operator(s) reports that Step 5.53 has been completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 10 of 15 Performance Step: 8 5.54 VARY G-01 output voltage approximately +100 and -100 volts from Critical N nominal voltage to wipe the voltage regulator potentiometer.
Standard: The examinee manipulates the G-01 Diesel Generator Voltage Regulator control switch to vary G-01 output voltage approximately +100 and -100 volts from nominal voltage to wipe the voltage regulator potentiometer.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 9 5.55 ADJUST G-01 frequency to 60 Hz.
Critical Y Standard: The examinee positions the G-01 Diesel Generator Governor Control Switch to obtain 60 Hz. (59.7 - 60.3 Hz)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 11 of 15 Performance Step: 10 5.56 ADJUST G-01 voltage to 4160 VAC.
Critical Y Standard: The examinee Positions the G-01 Diesel Generator Voltage Regulator control switch to obtain 4050 - 4300 volts.
Evaluator Note: After the examinee adjusts G-01 voltage, initial for Step 5.57 and provide the following cue:
Evaluator Cue: Step 5.57; Independent verification of G01 EDG settings has been completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 11 5.58 ENSURE Sump Tank level is greater than 400 gallons.
Critical N Standard: The examinee checks with the test Auxiliary Operator(s) to ensure that the G-01 sump tank level is greater than 400 gallons.
Evaluator Cue: The test Auxiliary Operator(s) report that the G-01 sump tank level is 450 gallons.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 12 of 15 Performance Step: 12 5.59 PLACE G-01 Diesel Generator Control Switch to STOP.
Critical Y Standard: The examinee places the G-01 Diesel Generator Control Switch to the Stop position Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 13 5.60 IF required to reset misalignment light, THEN PLACE 1A52-60-CS to Critical Y TRIP, AND BACK TO AUTO.
Standard: The examinee places 1A52-60 G-01 Diesel Generator to Bus 1A-05 breaker control switch to the Trip position and then to the Auto position.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 5.61 IF required to reset misalignment light, THEN PLACE 2A52-73-CS to Critical N TRIP, AND BACK TO AUTO.
Standard: The examinee N/As the step.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 13 of 15 Performance Step: 15 5.62 PLACE G-01 Diesel Generator Mode selector switch to AUTO to Critical Y return G-01 to standby status.
Standard: The examinee places the G-01 Diesel Generator Mode selector switch to the Auto position to return G-01 to a standby status.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P064.005a.COT, SECURE THE DIESEL GENERATOR, JPM REV. 3 Page 14 of 15 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 15 of 15 TURNOVER SHEET INITIAL CONDITIONS:
G-01, Emergency Diesel Generator is running loaded after an exercise start in accordance with TS 81, Emergency Diesel Generator G-01 Monthly.
TS 81 has been completed through Step 5.50.
Attachment B, Fuel Oil Transfer System Surveillance, has been completed.
An Auxiliary Operator is stationed at G-01, Emergency Diesel Generator.
INITIATING CUES (IF APPLICABLE):
The full-load run time requirements have been met and the OS orders G-01, Emergency Diesel Generator to be secured in accordance with TS 81, Emergency Diesel Generator G-01 Monthly; beginning at Step 5.51.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 10 JPM TITLE: Test High Flux at Shutdown Alarm JPM NUMBER: PBN JPM P015.004a.COT REV. 2 TASK NUMBER(S) / PBN P015.004.COT TASK TITLE(S): Monitor the Nuclear Instrument System for Proper Operation K/A NUMBERS: 015.A3.02 K/A VALUE: 3.7 / 3.9 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 10 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 2 of 10 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 3 of 10 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 2 Updated for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 4 of 10 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
Initial Setup:
Load IC-14 (both units shutdown and draindown) or similar IC.
Start the simulation.
Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Save to an IC for multiple use.
Multiple Use:
Load the saved IC for this JPM.
Set up Source Range counter as follows:
Audio multiplier set to 1K Display/Preset = Counts/Sec Thunbwheel = 00100 Start pushbutton depressed - Gate light is lit Walk down the control boards to ensure plant conditions accurately reflect the JPMs initial conditions.
Make any necessary adjustments or corrections.
Update documentation if required.
Resave if required.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: RP-1A, Preparation for Refueling, Attachment D General
References:
RP-1A, Preparation for Refueling RP-1A, Preparation for Refueling, Attachment A, Reactor Vessel Head Lift Check off Data Sheet Task Standards: High Flux at Shutdown Alarm tested satisfactorily TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 5 of 10 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:
You are the Unit 1 BOP.
Unit 1 has just been drained down in preparation for removing the Reactor Vessel Head.
The crew is performing RP-1A, Preparation for Refueling, Attachment A, Reactor Vessel Head Lift Checkoff Data Sheet.
Both Source Range Detectors N-31 and N-32 are in service.
There is an Auxiliary Operator stationed in Containment to support RP-1A, Attachment A evolutions.
INITIATING CUES (IF APPLICABLE):
The SRO has requested that you perform Attachment D, Test the High Flux at Shutdown Alarm, to support the completion of RP-1A, Attachment A, Reactor Vessel Head Lift Checkoff Data Sheet.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 6 of 10 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 1.0 Test N-31 if in service (otherwise N/A)
Critical Y 1.1 On N-31 PLACE the Level Trip switch to BYPASS, to enable Operator Select switch.
Standard: The examinee positions the Level Trip switch to BYPASS.
Evaluator Note: An alarm will come in at 1C04 and N-31 cabinet when this switch is positioned.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 1.0 Test N-31 if in service (otherwise N/A)
Critical Y 1.2 On N-31 POSITION the Operator Select switch to the LEVEL ADJUST position.
Standard: The examinee positons the Operator Select switch to the LEVEL ADJUST position.
Evaluator Note: An alarm will come in at 1C04 and N-31 cabinet when this switch is positioned.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 7 of 10 Performance Step: 3 1.0 Test N-31 if in service (otherwise N/A)
Critical Y 1.3 UNLOCK and INCREASE level adjust potentiometer to INCREASE counts to bring in alarm. VERIFY alarm in both control and containment.
Standard: The examinee:
Adjusts the Level adjust potentiometer up to increase counts AND Verifies alarms in both control and containment.
Evaluator Note: An alarm will come in at 1C04 and N-31 cabinet when this pot is adjusted.
Evaluator Cue: When AO is contacted, inform examinee that the audible alarm has been received in containment.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 1.0 Test N-31 if in service (otherwise N/A)
Critical N 1.4 REPOSITION level adjust back to zero and LOCK. VERIFY alarms CLEAR.
Standard: The examinee:
Adjusts the Level adjust potentiometer back to zero AND Verifies alarms clear.
Evaluator Note: An alarm will clear on 1C04 and N-31 cabinet when this pot is re-positioned.
Evaluator Cue: When the AO is contacted, report alarm is clear.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 8 of 10 Performance Step: 5 1.0 Test N-31 if in service (otherwise N/A)
Critical Y 1.5 POSITION Operator Selector switch to NORMAL.
Standard: The examinee re-positions the Operator Selector switch to NORMAL.
Evaluator Note: An alarm will clear on 1C04 and N-31 cabinet when this switch is re-positioned.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 1.0 Test N-31 if in service (otherwise N/A)
Critical Y 1.6 POSITION Level Trip switch to NORMAL.
Standard: The examinee re-positions the Level Trip switch to NORMAL.
Evaluator Note: An alarm will clear on 1C04 and N-31 cabinet when this switch is re-positioned.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P015.004a.COT, TEST HIGH FLUX AT SHUTDOWN JPM ALARM, REV. 2 Page 9 of 10 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 10 of 10 TURNOVER SHEET INITIAL CONDITIONS:
You are the Unit 1 BOP.
Unit 1 has just been drained down in preparation for removing the Reactor Vessel Head.
The crew is performing RP-1A, Preparation for Refueling, Attachment A, Reactor Vessel Head Lift Checkoff Data Sheet.
Both Source Range Detectors N-31 and N-32 are in service.
There is an Auxiliary Operator stationed in Containment to support RP-1A, Attachment A evolutions.
INITIATING CUES (IF APPLICABLE):
The SRO has requested that you perform Attachment D, Test the High Flux at Shutdown Alarm, to support the completion of RP-1A, Attachment A, Reactor Vessel Head Lift Checkoff Data Sheet.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 19 JPM TITLE: Respond to Circulating Water Malfunction JPM NUMBER: PBN JPM P000.052.COT REV. 1 TASK NUMBER(S) / PBN P000.052.COT Respond to Circulating Water System TASK TITLE(S): Malfunctions K/A NUMBERS: 075.A2.02 K/A VALUE: 2.5/2.7 Justification (FOR K/A VALUES <3.0): JPM to be used for ILT Exam TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:
Simulator: X Other:
Lab:
Time for Completion: 20 Minutes Time Critical: NO Alternate Path [NRC]: YES Alternate Path [INPO]: YES Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 2 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 3 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0 New JPM Rev. 1 Updated for the 2017 NRC ILT Exam.
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 4 of 19 SIMULATOR SET-UP:
- 1. Develop an IC with Unit 2 on Ice Melt, (per OI-38)
- 2. Override lake temperatures and ambient air temperatures to frazzle ice conditions
- 3. Ensure unit 2 is on full ice melt (CW-1 full open, CW-3 shut)
- 5. Save IC for multiple uses
- 6. Prior to starting JPM ensure MET recorder has CW System trends called up SIMULATOR MALFUNCTIONS:
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE U1 Traveling MAL1CWS002A 90 1 55 75 PLE Screen plugging U1 Traveling MAL1CWS002A 55 PRELOAD Screen plugging 0-TE3599-2 North XMT1CWS003A Outer Ring H-Pile 39.1 33.3 PRELOAD Fixed Output 0-TE3599-4 Unit XMT1CWS005A 2 Inlet Temp RTD 39 33.2 PRELOAD Fixed Output 0-TE3599-6 Unit XMT1CWS007A 2 Inlet Temp RTD 39.4 34.6 PRELOAD Fixed Output 0-TE3599-7 XMT1CWS008A Forebay Temp 39.32 32.9 PRELOAD RTD Fixed Output SIMULATOR OVERRIDES:
None SIMULATOR REMOTE FUNCTIONS:
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE Primary Tower ENV1MET003 56 19.5 PRELOAD 45M Temperature Primary Tower 10 ENV1MET007 55 21 PRELOAD Temp (M1TL)
Inside Ambient Air ENV1MET015 21 21 PRELOAD Temperature Inland Tower ENV1MET014 19.5 19.5 PRELOAD Temp (M3TL)
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 5 of 19 Required Materials: AOP-13A Circulating Water System Malfunction General
References:
AOP-13A Circulating Water System Malfunction EOP-0 Reactor Trip or Safety Injection OI 38, Circulating Water System Operations Task Standards: Respond per AOP-13A to a loss of circulating water: tripping Unit 1 reactor, performing immediate actions, and follow on AOP actions to shut MSIVs and stop Circulating Water Pump.
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 6 of 19 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:
Unit 2 is on Ice Melt per OI 38, Circulating Water System Operations 2CW-1 Ice Melt Valve is 100% Open 2CW-3 Seal Well Outlet Valve is Closed C01A 4-5, Traveling Screen Differential Level High, alarm is in.
Due to lowering circulating water temperatures and traveling screen alarm, AOP-13A Circulating Water System Malfunction was entered by OS1.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to start implementing AOP-13A, starting with Step 1, while he starts making notifications.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 7 of 19 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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.
Evaluator Note: To account for variations in examinee pace, Steps 1 through 12 of AOP-13A are included as non-critical steps (JPM steps 1 through 13). Once forebay level drops to -11.5 ft, the examinee should go to AOP Step 2 per Foldout Page (JPM Step 14).
Performance Step: 1 1. Circulating Water System - INTACT Critical N Standard: The examinee verifies that the Circ Water system is intact by no turbine hall alarms lit in control room.
Evaluator Cue: There are no reports from the field of pipe ruptures.
Evaluator Note: Booth Operator: enter Trigger 1 as the examinee starts the JPM.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 8 of 19 Performance Step: 2 2. Check Circulating Water Pumps - ONLY ONE RUNNING PER Critical N UNIT Unit 1 o 1P-30A o 1P-30B Unit 2 o 2P-30A o 2P-30B Standard: The examinee verifies only one circulating pump running per unit.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 3. Check Forebay Level - GREATER THAN -11.5 FEET Critical N PPCS point 1LT-3586B PPCS point 2LT-3586B YR-5832 Standard: The examinee verifies Forebay level > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 9 of 19 Performance Step: 4 4. Check Forebay Level - GREATER THAN -13 FEET Critical N PPCS point 1LT-3586B PPCS point 2LT-3586B YR-5832 Standard: The examinee verifies Forebay level > -13 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 5. Check South Pumpbay Level - GREATER THAN -11.5 FEET Critical N PPCS point 1LT-3586A YR-5832 Standard: The examinee verifies South Pumpbay level > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 6. Check North Pumpbay Level - GREATER THAN -11.5 FEET Critical N PPCS point 2LT-3586A YR-5832 Standard: The examinee verifies North Pumpbay level > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 10 of 19 Performance Step: 7 7. Check Level in Both Pumpbays - GREATER THAN -11.5 FEET Critical N PPCS point 1LT-3586A PPCS point 2LT-3586A YR-5832 Standard: The examinee verifies Both Pumpbay levels > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 8. Check Forebay AND BOTH Pumpbay Levels - GREATER Critical N THAN -11.5 FEET PPCS point 1LT-3586A PPCS point 2LT-3586A PPCS point 1LT-3586B PPCS point 2LT-3586B YR-5832 Standard: The examinee verifies Forebay and both Pumpbay levels > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 11 of 19 Performance Step: 9 9. Check at Least One Unit At Power Critical N Standard: The examinee verifies both units are at power.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 10. Stop Liquid Discharges Critical N Standard: The examinee determines no discharges need to be stopped.
Evaluator Cue: When asked, there are no discharges currently in progress.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 11 11. Check Any Unit Aligned For Ice Melt Operation Critical N Standard: The examinee determines Unit 2 is aligned for ice melt operations.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 12 of 19 Performance Step: 12 12. Check Circulating Water Inlet Temperature - Greater Than 38ºF Critical N YR-5832 Standard: The examinee determines temperature is below 38ºF and transitions to the RNO.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 13 12. RNO Raise intake crib temperature Critical N a. Fully open ice melt valve CW-1.
- b. Throttle seal well outlet valve to establish intake temperature greater than 38ºF.
CW-3 Standard: The examinee notes CW-1 is fully open and CW-3 is fully closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 Foldout Page monitored to determine Forebay or Pump Bay levels Critical N less than -11.5 feet Standard: The examinee determines Forebay and/or Pump Bay level < -11.5 feet and returns back to Step 2.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 13 of 19 Performance Step: 15 2. Check Circulating Water Pumps - ONLY ONE RUNNING PER Critical N UNIT Unit 1 o 1P-30A o 1P-30B Unit 2 o 2P-30A o 2P-30B Standard: The examinee verifies only one Circulating Pump running per unit.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 16 3. Check Forebay Level - GREATER THAN -11.5 FEET Critical N PPCS point 1LT-3586B PPCS point 2LT-3586B YR-5832 Standard: The examinee verifies Forebay level > -11.5 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 14 of 19 Performance Step: 17 4. Check Forebay Level - GREATER THAN -13 FEET Critical N PPCS point 1LT-3586B PPCS point 2LT-3586B YR-5832 Standard: The examinee verifies Forebay level > -13 ft.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 18 5. Check South Pumpbay Level - GREATER THAN -11.5 FEET Critical N PPCS point 1LT-3586A YR-5832 Standard: The examinee verifies Forebay level is less than -11.5 ft and goes to the RNO.
Evaluator Note: Only RNO steps requiring actions are contained in the following steps.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 15 of 19 Performance Step: 19 Step 5 RNO Perform the following:
Critical N a. Enter TRM TLCO 3.7.7 action condition B for both units.
- b. Enter TS LCO 3.6.6 action condition C for both units.
Standard: The examinee informs the OS of the need to enter TRM TLCO 3.7.7 action condition B for both units and, TS LCO 3.6.6 action condition C for both units.
Evaluator Cue: IF directed, THEN acknowledge the need to enter TRM TLCO 3.7.7 action condition B for both units and, TS LCO 3.6.6 action condition C for both units.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 20 Step 5 RNO Perform the following:
Critical Y e. Trip Unit 1 reactor Standard: The examinee trips Unit 1 reactor by depressing the Reactor Trip Pushbuttons.
Evaluator Cue: IF asked, THEN direct the examinee to carry out the RNO Actions.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 16 of 19 Performance Step: 21 Step 5 RNO Perform the following:
Critical Y f. Stabilize plant using EOPs while continuing with this procedure Standard: The examinee performs immediate actions of EOP 0 for Unit 1.
Reactor Tripped (yes)
Turbine Tripped (yes)
Safeguards Buses Energized (yes from offsite)
Check if SI is required (not required)
Evaluator Cue: Cue examinee after completion of immediate actions, that they have been verified so continue with AOP-13A actions.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 22 Step 5 RNO Perform the following:
Critical Y g. Shut both Unit 1 MSIVs MS-2018 MS-2017 Standard: The examinee shuts Unit 1 MSIVs by positioning 1MS-2017-CS and 1MS-2018-CS to CLOSE after immediate actions completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 17 of 19 Performance Step: 23 Step 5 RNO Perform the following:
Critical Y i. Stop both Unit 1 circulating water pumps:
1P-30A 1P-30B Standard: The examinee takes the control switch for the operating circulating water pump (1P-30A) to STOP.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: This completes the JPM NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
PBN JPM P000.052.COT Respond to Circulating Water JPM System Malfunctions, Rev. 1 Page 18 of 19 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 19 of 19 TURNOVER SHEET INITIAL CONDITIONS:
Unit 2 is on Ice Melt per OI 38, Circulating Water System Operations 2CW-1 Ice Melt Valve is 100% Open 2CW-3 Seal Well Outlet Valve is Closed C01A 4-5, Traveling Screen Differential Level High, alarm is in.
Due to lowering circulating water temperatures and traveling screen alarm, AOP-13A Circulating Water System Malfunction was entered by OS1.
INITIATING CUES (IF APPLICABLE):
OS1 directs you to start implementing AOP-13A, starting with Step 1, while he starts making notifications.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 13 JPM TITLE: LOCALLY OPERATE A CHARGING PUMP JPM NUMBER: PBN JPM P004.010b.AOT REV. 4 TASK NUMBER(S) / P004.010.AOT / LOCALLY OPERATE A CHARGING PUMP TASK TITLE(S):
004 K4.04 3.2 / 3.1 K/A NUMBERS: K/A VALUE:
004 A1.11 3.0 / 3.0 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: X Perform:
EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 2 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 3 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
REASON FOR AR/TWR PREPARER DATE
- DESCRIPTION OF CHANGE CHANGE # SUPERVISOR DATE Rev. 0-1 See microfilm.
Reformatted to current revision of QF-1075-01. Update procedure step numbering to match OI 15 Rev. 2 Rev 19.
Rev. 3 Updated to new Fleet Template Rev. 4 Updated for the 2017 NRC ILT Exam.
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 4 of 13 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
1.
2.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: OI-15, Charging Pump Local Control Station Operation General
References:
OI-15, Charging Pump Local Control Station Operation Task Standards: Control of 2P-2C, Charging Pump transferred to the VFD and speed raised to 30%.
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 5 of 13 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:
You are the PAB operator.
Both units are at 100% power.
2P-2A and 2P-2C, Charging Pumps are currently running.
The control room has lost speed control for 2P-2C, Charging Pump.
Controller demand for 2P-2C, Charging Pump is at 20%.
INITIATING CUES (IF APPLICABLE):
The OS2 directs you to transfer pump control for 2P-2C, Charging Pump to Rack 24 (RK-24) in accordance with OI-15, Charging Pump Local Control Station Operation, steps 5.1.1 -
5.1.4.
It is NOT desired to transfer breaker control for 2P-2C, Charging Pump.
The procedure has just been obtained from the C-59 area.
Following transfer of pump control, contact the control room for speed adjustment instructions.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 6 of 13 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical N Operation 5.1.1 Match the speed potentiometer setting on RK-24 to the indicated controller demand on C-04 (preferred) or to the indicated motor RPM on the VFD.
Standard: The examinee adjusts the RK speed potentiometer to 200 by turning the pot clockwise to rise or counter-clockwise to lower to the desired setting.
Evaluator Note: Pot setting taken from Attachment A (200 = 20%)
Pot has a collar - not critical Evaluator Cue: RK-24 potentiometer reads 200 Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 7 of 13 Performance Step: 2 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical N Operation 5.1.2 Notify Control that Annunciator C01 B 4-5 (C 4-7), UNIT 1(2)
SHUTDOWN EQUIPMENT LOCAL CONTROL will alarm.
Standard: The examinee may NA the step since breaker control is not to be transferred.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical N Operation 5.1.3 IF transfer of breaker control is desired, THEN place applicable transfer switch 1(2)N-04 or 1(2)N-11 to LOCAL Standard: The examinee may NA the step since the switch will not be manipulated.
Evaluator Note: The switch should not be taken to LOCAL since breaker control transfer is not desired. Position of the switch will not impact remainder of JPM.
Evaluator Cue: IF examinee desires to manipulate switch, THEN do not allow opening N-04 cabinet, instead have examinee describe operation.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 8 of 13 Performance Step: 4 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical N Operation 5.1.4 IF transfer of pump control to RK-24 is desired, THEN place the Mode Select NORMAL/EMERGENCY switch on the VFD to EMERGENCY.
Standard: The examinee positions the Mode Select NORMAL/EMERGENCY switch on the VFD to EMERGENCY.
Evaluator Cue: The Mode Select NORMAL/EMERGENCY switch on the VFD is positioned to EMERGENCY.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 Inform CR that 2P-2C, Charging Pump control is aligned to RK-24 Critical N and request instructions for speed adjustment.
Standard: The examinee contacts the control room for speed adjustment instructions.
Evaluator Cue: The control room acknowledges your report and directs that you raise speed of 2P-2C, Charging Pump from the current 2C04 controller demand of 20% to the equivalent of 30% 2C04 controller demand per Step 5.1.6.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 9 of 13 Performance Step: 6 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical N Operation 5.1.6 Control charging pump speed and flow to maintain Pressurizer Level and RCP Labyrinth Seal DP using one of the following (local indication in pipe ways 1 & 4)
Potentiometer on the RK-24 panel Standard: The examinee raises 2P-2C, Charging Pump speed demand from 20% to 30% on RK-24 by turning the potentiometer clockwise from 200 to 300.
Evaluator Note: Pot setting taken from Attachment A (300 = 30%)
Pot has a collar - not critical Evaluator Cue: RK-24 potentiometer reads 300 IF asked, THEN report that there is no audible change in speed from 2P-2C, Charging Pump.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 Inform CR 2P-2C speed demand set to 30%.
Critical N Standard: The examinee informs the control room that 2P-2C, Charging Pump speed demand has been raised to 30%.
Evaluator Cue: CR reports that there is no change in charging flow, directs transfer of pump control to the VFD per OI-15 Step 5.1.5 and to report when the transfer is completed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 10 of 13 Performance Step: 8 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical Y Operation 5.1.5 IF transfer of charging pump control to the VFD is desired, THEN perform the following:
- a. DEPRESS and HOLD the MANUAL start pushbutton on the VFD
- b. Place the Mode Select MANUAL/AUTO switch on the front of the VFD to MANUAL.
- c. RELEASE the MANUAL start pushbutton on the VFD.
Standard: The examinee:
Depresses the Manual Start pushbutton while positioning the Mode Selector to MANUAL.
Informs the control room that 2P-2C, Charging Pump control is aligned to VFD (not critical).
Evaluator Cue: You have depressed and are holding the start pushbutton. The Mode Selector is now in MANUAL and manual start pushbutton is released.
CR requests that you raise speed of 2P-2C from the current 2C04 controller demand of 20% to the equivalent of 30% 2C04 controller demand per Step 5.1.6.
Current speed indication on the VFD is 765 RPM Performance: SATISFACTORY UNSATISFACTORY Comments:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 11 of 13 Performance Step: 9 5.1 VFD Operation - Transfer From REMOTE To LOCAL- Pump In Critical Y Operation 5.1.6 Control charging pump speed and flow to maintain Pressurizer Level and RCP Labyrinth Seal DP using one of the following (local indication in pipe ways 1 & 4)
VFD UP and DOWN arrows on the VFD keyboard Standard: The examinee adjusts 2P-2C, Charging Pump speed demand from 20% to 30% by using UP arrow on the VFD keypad.
Evaluator Note: Speed setting taken from Attachment A (905 RPM = 30%)
Evaluator Cue: Pump speed on VFD keypad indicates 905 Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
PBN JPM P004.010b.AOT, Locally Operate a Charging JPM Pump, Rev. 4 Page 12 of 13 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 13 of 13 TURNOVER SHEET INITIAL CONDITIONS:
You are the PAB operator.
Both units are at 100% power.
2P-2A and 2P-2C, Charging Pumps are currently running.
The control room has lost speed control for 2P-2C, Charging Pump.
Controller demand for 2P-2C, Charging Pump is at 20%.
INITIATING CUES (IF APPLICABLE):
The OS2 directs you to transfer pump control for 2P-2C, Charging Pump to Rack 24 (RK-24) in accordance with OI-15, Charging Pump Local Control Station Operation, steps 5.1.1 -
5.1.4.
It is NOT desired to transfer breaker control for 2P-2C, Charging Pump.
The procedure has just been obtained from the C-59 area.
Following transfer of pump control, contact the control room for speed adjustment instructions.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
JOB PERFORMANCE MEASURE JPM Page 1 of 17 JPM TITLE: Fuel Oil Transfer Between Storage Tanks JPM NUMBER: PBN JPM P157.003.AOT REV. 0 TASK NUMBER(S) / PBN JPM P157.003.AOT TASK TITLE(S): Transfer Fuel Oil K/A NUMBERS: 064 K1.03 K/A VALUE: 3.6 / 4.0 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: X Perform:
EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 20 Minutes Time Critical: No Alternate Path [NRC]: No Alternate Path [INPO]: No Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 2 of 17 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 3 of 17 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 0 Developed for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 4 of 17 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
1.
2.
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: OI 145, Fuel Transfer Between Storage Tanks General
References:
OI 145, Fuel Transfer Between Storage Tanks Task Standards: Transfer fuel oil from T-175B to T-175A with Fuel Oil Transfer Pump P-207B in accordance with OI 145, Fuel Oil Transfer Between Storage Tanks.
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 5 of 17 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:
You are a relief crew AO.
Both Units are at operating at 100% steady-state conditions.
G04 EDG is OOS for radiator fan work. G03 EDG is aligned to both 1A-06 and 2A-06 safeguards buses in accordance with OI-35A.
Engineering has requested confirmation of the ability to transfer fuel oil from T-175B to T-175A Fuel Oil Storage Tanks.
INITIATING CUES (IF APPLICABLE):
The relief crew supervisor directs you to transfer 500 gallons (approximately 2%) from T-175B to T-175A with Fuel Oil Transfer Pump P-207B in accordance with OI 145, Fuel Oil Transfer Between Storage Tanks, starting at Step 5.3.6.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 6 of 17 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 5.3.6 POSITION the valves listed below in preparation for fuel oil Critical Y transfer:
Standard: The examinee:
Removes the red lock AND Opens FO-207, P-207B G-04 EDG FOTP Discharge to T-175A G-01/G-02 FOST by turning the valve handwheel in counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: The red lock is removed and the valve handwheel for FO-207, P-207B G-04 EDG FOTP Discharge to T-175A G-01/G-02 FOST is turned in the counter-clockwise direction until the valve stem is fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 7 of 17 Performance Step: 2 5.3.6 POSITION the valves listed below in preparation for fuel oil Critical Y transfer:
- b. UNLOCK AND OPEN FO-170, P-206A/P-207A G-01/G-02 FOTP Disch Isol. To T-175B/T-176A/B.
Standard: The examinee:
Removes the red lock AND Opens FO-170, P-206A/P-207A G-01/G-02 FOTP Disch Isol. To T-175B/T-176A/B by turning the valve handwheel in counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: The red lock is removed and the valve handwheel for FO-170, P-206A/P-207A G-01/G-02 FOTP Disch Isol. To T-175B/T-176A/B is turned in the counter-clockwise direction until the valve stem is fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 8 of 17 Performance Step: 3 5.3.6 POSITION the valves listed below in preparation for fuel oil Critical Y transfer:
Standard: The examinee opens FO-168, P-206A/P-207A G-01/G-02 EDG FOTP st Test Line 1 Off Isol. by turning the valve handwheel in the counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: The valve handwheel for FO-168, P-206A/P-207A G-01/G-02 EDG FOTP Test Line 1st Off Isol. is turned in the counter-clockwise direction until the valve stem is fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 9 of 17 Performance Step: 4 5.3.6 POSITION the valves listed below in preparation for fuel oil Critical Y transfer:
Standard: The examinee opens FO-169, P-206A/P-207A G-01/G-02 EDG FOTP Test Line 2nd Off Isol. by turning the valve handwheel in the counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: The valve handwheel for FO-169, P-206A/P-207A G-01/G-02 EDG FOTP Test Line 2nd Off Isol. is turned in the counter-clockwise direction until the valve stem is fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 5.3.6 POSITION the valves listed below in preparation for fuel oil Critical Y transfer:
Standard: The examinee shuts FO-214, P-207B G-04 EDG FOTP Disch to T-176B G-04 EDG Day Tank by turning the valve handwheel in the clockwise direction until the valve stem is fully inserted.
Evaluator Cue: The valve handwheel for FO-214, P-207B G-04 EDG FOTP Disch to T-176B G-04 EDG Day Tank is turned in the clockwise direction until the valve stem is fully inserted.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 10 of 17 Performance Step: 6 5.3.7 NOTIFY Control Room transfer is about to being and to monitor Critical N Fuel Oil Tank Alarms.
Standard: The examinee notifies the Control Room that transfer is about to being and to monitor for fuel oil tank alarms.
Evaluator Cue: The control room acknowledges you request.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 5.3.8 START P-207B, G-04 EDG Fuel Oil Transfer Pump to begin Critical Y transfer.
Standard: The examinee starts P-207B, G-04 EDG Fuel Oil Transfer Pump by placing the control switch to ON.
Evaluator Cue: The control switch for P-207B, G-04 EDG Fuel Oil Transfer Pump is placed to ON. The green light is off, the red light is on and the pump comes up to speed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 11 of 17 Performance Step: 8 5.3.9 WHEN the desired amount has been transferred from T-175B to Critical Y T-175A, THEN STOP P-207B, G-04 EDG Fuel Oil Transfer Pump.
Standard: The examinee stops P-207B, G-04 EDG Fuel Oil Transfer Pump by placing the control switch to AUTO.
Evaluator Note: Control switch placed in either AUTO or OFF is acceptable. The critical attribute of this step is that the pump is stopped.
Evaluator Cue: Inform the examinee that 500 gallons of fuel oil has been transferred. The level of the fuel oil storage tank being monitored has changed by approximately 2%. (T-175B ; T-175A )
Evaluator Cue: The control switch for P-207B, G-04 EDG Fuel Oil Transfer Pump is placed in AUTO. The green light is on, the red light is off and the pump slows to stop.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 9 5.3.10 OPEN FO-214, P-207B G-04 EDG FOTP Disch to T-176B G-Critical Y 04 EDG Day Tank.
Standard: The examinee opens FO-214, P-207B G-04 EDG FOTP Disch to T-176B G-04 EDG Day Tank by turning the valve handwheel in the counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: The valve handwheel for FO-214, P-207B G-04 EDG FOTP Disch to T-176B G-04 EDG Day Tank is turned in the counter-clockwise direction until the valve stem is fully extended.
Valve position is independently verified and initialed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 12 of 17 Performance Step: 10 5.3.11 SHUT FO-169, P-206A/P-207A G-01/G-02 EDG FOTP Test Critical Y* Line 2nd Off Isol.
Standard: The examinee shuts FO-169, P-206A/P-207A G-01/G-02 EDG FOTP Test Line 2nd Off Isol. by turning the valve handwheel in the clockwise direction until the valve stem is fully inserted.
Evaluator Cue: The valve handwheel for FO-169, P-206A/P-207A G-01/G-02 EDG FOTP Test Line 2nd Off Isol. is turned in the clockwise direction until the valve stem is fully inserted.
Valve position is independently verified and initialed.
Performance: SATISFACTORY UNSATISFACTORY
- See Evaluator Note in Step 13.
Comments:
Performance Step: 11 5.3.12 SHUT FO-168, P-206A/P-207A G-01/G-02 EDG FOTP Test Critical Y* Line 1st Off Isol.
Standard: The examinee shuts FO-168, P-206A/P-207A G-01/G-02 EDG FOTP Test st Line 1 Off Isol. by turning the valve handwheel in the clockwise direction until the valve stem is fully inserted.
Evaluator Cue: The valve handwheel for FO-168, P-206A/P-207A G-01/G-02 EDG st FOTP Test Line 1 Off Isol. is turned in the clockwise direction until the valve stem is fully inserted.
Valve position is independently verified and initialed.
Performance: SATISFACTORY UNSATISFACTORY
- See Evaluator Note in Step 13.
Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 13 of 17 Performance Step: 12 5.3.13 SHUT AND LOCK FO-170, P-206A/P-207A G-01/G-02 FOTP Critical Y* Disch Isol. To T-175B/T-176A/B.
Standard: The examinee:
Shuts FO-170, P-206A/P-207A G-01/G-02 FOTP Disch Isol. To T-175B/T-176A/B by turning the valve handwheel in clockwise direction until the valve stem is fully inserted.
AND Installs the red lock Evaluator Cue: The valve handwheel for FO-170, P-206A/P-207A G-01/G-02 FOTP Disch Isol. To T-175B/T-176A/B is turned in the clockwise direction until the valve stem is fully inserted.
The red lock is installed.
Valve position is independently verified and initialed.
Performance: SATISFACTORY UNSATISFACTORY
- See Evaluator Note in Step 13.
Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 14 of 17 Performance Step: 13 5.3.14 SHUT AND LOCK FO-207, P-207B G-04 EDG FOTP Critical Y* Discharge to T-175A G-01/G-02 FOST.
Standard: The examinee:
Shuts FO-207, P-207B G-04 EDG FOTP Discharge to T-175A G-01/G-02 FOST by turning the valve handwheel in clockwise direction until the valve stem is fully inserted.
AND Installs the red lock
- Evaluator Note: It is critical that at least one of the valves from Steps 10 thru 13 is shut to isolate the flowpath from T-175A.
Evaluator Cue: The valve handwheel for FO-207, P-207B G-04 EDG FOTP Discharge to T-175A G-01/G-02 FOST is turned in the clockwise direction until the valve stem is fully inserted.
The red lock is installed.
Valve position is independently verified and initialed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 5.3.15 RECORD EDG Fuel Oil Storage Tank levels:
Critical N T-175A ______ % (LI-3985A)
T-175B ______ % (LI-3985B)
Standard: The examinee records the EDG Fuel Oil Storage Tank levels.
Evaluator Cue: EDG Fuel Oil Storage Tank levels:
T-175A: 92 % (LI-3985A)
T-175B: 91 % (LI-3985B)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 15 of 17 Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P157.003.AOT, FUEL OIL TRANSFER BETWEEN JPM STORAGE TANKS, REV. 0 Page 16 of 17 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 17 of 17 TURNOVER SHEET INITIAL CONDITIONS:
You are a relief crew AO.
Both Units are at operating at 100% steady-state conditions.
G04 EDG is OOS for radiator fan work. G03 EDG is aligned to both 1A-06 and 2A-06 safeguards buses in accordance with OI-35A.
Engineering has requested confirmation of the ability to transfer fuel oil from T-175B to T-175A Fuel Oil Storage Tanks.
INITIATING CUES (IF APPLICABLE):
The relief crew supervisor directs you to transfer 500 gallons (approximately 2%) from T-175B to T-175A with Fuel Oil Transfer Pump P-207B in accordance with OI 145, Fuel Oil Transfer Between Storage Tanks, starting at Step 5.3.6.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
JOB PERFORMANCE MEASURE JPM Page 1 of 12 JPM TITLE: START AN AIR COMPRESSOR TO A DEPRESSURIZED RECEIVER JPM NUMBER: PBN JPM P000.008a.AOT REV. 10 TASK NUMBER(S) / P000.008.AOT / START AIR COMPRESSOR(S) TO DEPRESSURIZED TASK TITLE(S): RECEIVERS K/A NUMBERS: 078 A3.01 K/A VALUE: 3.1 / 3.2 Justification (FOR K/A VALUES <3.0):
TASK APPLICABILITY:
RO SRO STA Non-Lic SRO CERT OTHER:
APPLICABLE METHOD OF TESTING: Simulate/Walkthrough: Perform: X EVALUATION LOCATION: In-Plant: X Control Room:
Simulator: Other:
Lab:
Time for Completion: 15 Minutes Time Critical: No Alternate Path [NRC]: Yes Alternate Path [INPO]: Yes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner Date TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 2 of 12 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1. Are all items on the signature page filled in correctly?
- 3. Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4. Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5. Is the standard for each performance item specific as to what 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 or incumbent experience?
- 7. If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8. Is the job level appropriate for the task being evaluated if required?
- 9. Is the K/A appropriate to the task and to the licensee level if required?
- 10. Is justification provided for tasks with K/A values less than 3.0?
- 11. Have the performance steps been identified and classified (Critical /
Sequence / Time Critical) appropriately?
- 12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?
- 13. Are all references identified, current, accurate, and available to the trainee?
- 14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
- 15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)
- 16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM?
TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.
All questions/statements must be answered YES or N/A or the JPM is not valid for use. If all questions/statements are answered YES or N/A, then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.
Protected Content: (CAPRs, corrective actions, licensing commitments, etc. associated with this material)
{C001}
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 3 of 12 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
SUPERVISOR DATE Rev. 10 Updated for the 2017 NRC ILT Exam.
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 4 of 12 SIMULATOR SET-UP: (Only required for simulator JPMs)
SIMULATOR SETUP INSTRUCTIONS:
SIMULATOR MALFUNCTIONS:
SIMULATOR OVERRIDES:
SIMULATOR REMOTE FUNCTIONS:
Required Materials: AOP 5B, Loss of Instrument Air General
References:
AOP 5B, Loss of Instrument Air Task Standards: Compressor K2A started and aligned to T-33B.
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 5 of 12 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:
Service water is lined up for normal operation.
Instrument air compressor K2A is not running.
Air receiver T-33B is depressurized following leak repair.
INITIATING CUES (IF APPLICABLE):
The OS1 directs you to start instrument air compressor K2A in accordance with AOP-5B, Loss of Instrument Air, Attachment BB, Air Compressor Startup to Supply Depressurized Receiver.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 6 of 12 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
NOTE: 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: 1 BB1 Place K2A In Operation:
Critical N a. Check K2A total closure valve shut IA-226 Standard: The examinee recognizes IA-226, Total Closure Valve open and proceeds to the RNO column.
Evaluator Cue: IA-226, Total Closure Valve position indicator points to OPEN (It is preferable to physically indicate position using an object such as a pen or laser pointer, rather than a verbal indication.)
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 7 of 12 Performance Step: 2 a. RNO Perform the following:
Critical Y 1) Shut total closure valve operating air at receiver T33B.
IA-205 Standard: The examinee shuts IA-205, Total Closure Valve Operating Air at Receiver T33B by rotating the valve handwheel in the clockwise direction until the valve stem is fully inserted.
Evaluator Cue: The valve handwheel for IA-205, Total Closure Valve Operating Air at Receiver T33B is turned clockwise until the valve stem is fully inserted.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 a. RNO Perform the following:
Critical Y 2) Uncap and open K2A total closure air line vents.
IA-218 IA-219 Standard: The examinee:
Uncaps IA-218 and IA-219, K2A Total Closure Air Line Vents by rotating the caps in the counter-clockwise direction until they are removed AND Opens IA-218 and IA-219, K2A Total Closure Air Line Vents by rotating the handwheels in the counter-clockwise direction until the valve stems are fully extended.
Evaluator Note: A combination wrench hangs on the south wall of the air compressor room.
Evaluator Cue: The caps for IA-218 and IA-219, K2A Total Closure Air Line Vents are removed.
AND The valve handwheels for IA-218 and IA-219, K2A Total Closure Air Line Vents are turned in the counter-clockwise direction until the valve stems are fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 8 of 12 Performance Step: 4 a. RNO Perform the following:
Critical Y 3) Using a red combination wrench, shut K2A total closure valve.
IA-226 Standard: The examinee shuts IA-226, K2A, Total Closure Valve by rotating the valve stem counter-clockwise to the Closed position.
Evaluator Note: A combination wrench hangs on the south wall of the air compressor room.
Evaluator Cue: IA-226, K2A, Total Closure Valve local indicator indicates Closed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 a. RNO Perform the following:
Critical Y 2) Shut and cap K2A total closure air line vents.
IA-218 IA-219 Standard: The examinee:
Shuts IA-218 and IA-219, K2A Total Closure Air Line Vents by rotating the handwheels in the clockwise direction until the valve stems are fully inserted.
AND Caps IA-218 and IA-219, K2A Total Closure Air Line Vents by rotating the caps in the clockwise direction until they are hand tight.
Evaluator Note: Cap installation is not a critical element of this step.
Evaluator Cue: The valve handwheels for IA-218 and IA-219, K2A Total Closure Air Line Vents are turned in the clockwise direction until the valve stems are fully inserted.
AND The caps for IA-218 and IA-219, K2A Total Closure Air Line Vents are installed.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 9 of 12 Performance Step: 6 BB1 Place K2A In Operation:
Critical N b. Start K2A Standard: The examinee contacts the Control Room to start K2A Evaluator Cue: The Control Room acknowledges your request AND Reports that K2A has been started K2A is running locally Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 BB1 Place K2A In Operation:
Critical Y c. Using a red combination wrench, open K2A total closure valve IA-226 Standard: The examinee opens IA-226, K2A, Total Closure Valve by rotating the valve stem clockwise to the Open position.
Evaluator Cue: IA-226, K2A, Total Closure Valve local indicator indicates Open.
Performance: SATISFACTORY UNSATISFACTORY Comments:
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 10 of 12 Performance Step: 8 BB1 Place K2A In Operation:
Critical N d. Check air receiver pressure greater than 30 psig Standard: The examinee checks air receiver pressure locally and proceeds to BB1.d RNO Evaluator Cue: Receiver pressure indicates 12 psig and rising.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 9 d. RNO WHEN pressure greater than 30 psig, THEN perform Step BB1e.
Critical Y OBSERVE CAUTION PRIOR TO STEP BB2 and continue with Step BB2.
BB1 Place K2A In Operation:
- e. Ensure total closure operating air open at receiver T33B IA-205 Standard: The examine opens IA-205, Total Closure Operating Air to Receiver T33B by rotating the valve handwheel in the counter-clockwise direction until the valve stem is fully extended.
Evaluator Cue: Time has passed; receiver pressure indicates 31 psig and slowly rising.
The handwheel for IA-205, Total Closure Operating Air to Receiver T33B is turned in the counter-clockwise direction until the valve stem is fully extended.
Performance: SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues: The JPM is complete.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
Stop Time:
TR-AA-230-1003-F10, Revision 2
PBN JPM P000.008a.AOT, Start An Air Compressor To A JPM Depressurized Receiver, Rev. 10 Page 11 of 12 Examinee: Evaluator:
RO SRO STA Non-Lic SRO CERT Date:
LOIT RO LOIT SRO PERFORMANCE RESULTS: SAT: UNSAT:
Remediation required: YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).
EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
TR-AA-230-1003-F10, Revision 2
JPM JOB PERFORMANCE MEASURE Page 12 of 12 TURNOVER SHEET INITIAL CONDITIONS:
Service water is lined up for normal operation.
Instrument air compressor K2A is not running.
Air receiver T-33B is depressurized following leak repair.
INITIATING CUES (IF APPLICABLE):
The OS1 directs you to start instrument air compressor K2A in accordance with AOP-5B, Loss of Instrument Air, Attachment BB, Air Compressor Startup to Supply Depressurized Receiver.
NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.
TR-AA-230-1003-F10, Revision 2
SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 15E LMS Rev. Date:
SEG TITLE: 2017 NRC Exam Scenario 1 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner (Line) Date Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _1___________ Op-Test No.: _2017____
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Unit 1 is at approximately 100%. 1PT-950, Loop B Containment Pressure has ___
been removed from service. Repairs are expected to be complete during the upcoming refueling____
outage. 1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure. ________________
Turnover: Normal Shift routine. Lower power utilizing OP 3A, Power Operation to Hot Standby at _
30%/hr in preparation for refueling outage _______________________________________________
Event Malf. No. Event Event No. Type* Description I-BOP 1 XMT1CNM014A I-SRO 1PT-947, Loop A Containment Pressure Transmitter fails low TS-SRO I-BOP 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller 2 CNH1CFW003F I-SRO oscillates in automatic 3 XMT1AFW005A TS-SRO 0LT-4040, T-24A CST Level Transmitter fails low R-RO 4 ANN-C02D-A09 N-BOP 1X01, Main Transformer loss of cooling (rapid down power)
R-SRO C-RO 5 CNH1PCS004F 1P-2A, Auto Charging Pump controller oscillation failure C-SRO 6 MAL1RCS001 M-ALL Large Break LOCA BKR1RHR001 C-BOP 1P-10A, RHR pump fails to start in Auto 7 MOT1RHR002 1P-10B, RHR pump trips upon starting RLY1PPL020 8 RLY1PPL021 C-BOP Containment Spray fails to actuate
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to the failures listed below in accordance with plant procedures:
- 1. 1PT-947, Loop B Containment Pressure Transmitter failing low / removing from service
- 3. 0LT-4040 Condensate Storage Tank Level transmitter fails low
- 4. 1X-01, Main Transformer loss of cooling
- 5. Auto charging pump controller oscillating in automatic only
- 6. Instantaneous Large Break LOCA
- 7. RHR pump failures
- 8. Containment Spray failing to actuate Embedded within these events is the expectation to properly utilize Technical Specifications.
Enabling None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 1. 0-SOP-IC-001 BLUE, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels
- 2. 0-SOP-IC-002, Technical Specifications LCO - Instrument Cross Reference
- 3. AOP-1D Unit 1, Chemical And Volume Control System Malfunction
- 5. AOP-17A Unit 1, Rapid Power Reduction
- 6. AOP-24, Response to Instrument Malfunctions
- 8. ARP C01 A 2-9, T-24A or B Condensate Storage Tanks - Level High or Low
- 9. CSP-P.1 Unit 1, Response To Imminent Pressurized Thermal Shock Condition
- 10. EOP-0 Unit 1, Reactor Trip Or Safety Injection Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG
- 11. EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant
- 13. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients
- 14. OP-3A Unit 1, Power Operation To Hot Standby Unit 1
- 15. RMS Alarm Setpoint And Response Book
- 16. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021.
Operating N/A Experience:
Risk Significant HEP-RHR-EOP13-LL, OPS FAIL TO ALIGN SI FLOR LOW CONT SUMP Operator Actions: RECIRC (LLOCA/MLOCA), FV: 4.46E-03 Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 35
PBN LOI 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Unit 1 is at approximately 100% EOL.
1PT-950, Loop B Containment Pressure has been removed from service.
Repairs are expected to be complete during the upcoming refueling outage.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
Normal Shift routine will be to lower power at 30%/hr utilizing OP-3A Unit 1, Power Operation To Hot Standby Unit 1.
Events:
1PT-947, Loop A Containment Pressure Transmitter fails low 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040 Condensate Storage Tank Level transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto Large Break LOCA RHR pump malfunctions 1P-10A, RHR Pump fails to auto start 1P-10B, RHR Pump trips Containment Spray fails to actuate Terminate the scenario when crew has completed Step 21 of EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation - Low Head Injection and is waiting for RWST level to lower to 34%.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SEQUENCE OF EVENTS Event # Description
- 1. 1PT-947, Loop A Containment Pressure Transmitter fails low Once the crew has taken the shift, 1PT-947, Loop A Containment Pressure Transmitter fails low.
The crew should implement AOP-24, Response to Instrument Malfunctions and take the channel out of service in accordance with 0-SOP-IC-001 BLUE, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE.
Address Technical Specifications.
- 2. 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic After identifying the malfunction, the crew may shift 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller to manual to mitigate the transient per OM 3.7, AOP and EOP Procedure Usage for Response to Plant Transients The crew should implement AOP-2B Unit 1, Feedwater System Malfunction and lower turbine load to maintain reactor power less than 100% in accordance with AOP-17A Unit 1, Rapid Power Reduction if required.
The crew may reference and or implement AOP-24, Response to Instrument Malfunctions.
- 3. 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low The crew should reference ARP C01 A 2-9 and ARB C01 A 3-9 for the failed level transmitter and determine the applicable Technical Specifications Required Actions.
- 4. 1-X01, Main Transformer loss of cooling Unit 1, 1X-01, Main Transformer B phase incurs a loss of cooling as indicated by annunciator C02 D 1-9, 1X-01 Main Trans Loss of Cooling.
The crew should implement ARP C02 D1-9, 1X-01 Main Trans Loss of Cooling and based on field reports, begin ramping the unit off-line in accordance with AOP-17A Unit 1, Rapid Power Reduction.
- 5. 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto During the load reduction, 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto.
The should take manual control of 1HC-428A, 1P-2A Charging Pump Hand Controller and implement AOP-1D Unit 1, Chemical and Volume Control System Malfunction.
The crew may implement/reference AOP-24, Response to Instrument Malfunctions (not required).
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG
- 6. Large Break LOCA The crew should implement EOP-0 Unit 1, Reactor Trip or Safety Injection, EOP-1 Unit 1, Loss of Reactor or Secondary Coolant and EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation, Low Head Injection.
- 7. RHR pump malfunctions: 1P-10A, RHR Pump fails to auto start and 1P-10B, RHR Pump trips The crew should address the failures by starting 1P-10A, RHR Pump:
After EOP-0 Unit 1 Immediate Actions are complete in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients OR EOP-0 Unit 1, ATTACHMENT A, AUTOMATIC ACTION VERIFICATION Step A3.b.RNO.
- 8. Containment Spray fails to actuate The crew should address the failures by aligning the Containment Spray System:
After EOP-0 Unit 1 Immediate Actions are complete in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients OR EOP-0 Unit 1, ATTACHMENT A, AUTOMATIC ACTION VERIFICATION Step A12.a.RNO.
STOP Terminate the scenario when crew has completed Step 21 of EOP-1.3 Unit 1, Transfer To Containment Sump Recirculation - Low Head Injection and is waiting for RWST level to lower to 34%.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
General Instructions Simulator Setup Instructions:
Load IC-3 and go to run Open the saved Event and Schedule files from the secure drive:
Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)
Reposition bistable switches for: 1PT-950, Loop B Containment Pressure Transmitter Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:
Load saved IC and go to run Open the saved Event and Schedule files:
Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:
Setup: 1PT-950, Loop B Containment Pressure Transmitter is out of service / 1W-3B, CTL Rod Drive Shroud Fan MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT950 LOOP B CONT XMT1CNM017A PRESSURE 00 :00 :00 - 90 Preload XMTR FIXED OUTPUT Simulator Setup:
- 1. Place OOS magnet at PT-950, Containment Pressure
- 2. Place a RED dot on C01 B 1-5, U1 Containment Pressure Channel Alert
- 4. Install an orange Guarded magnet at 1W-3A.
SIMULATOR MALFUNCTIONS:
Event 1: / 1P-947, Loop A Containment Pressure Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT947 LOOP A CONT XMT1CNM014A PRESSURE 00 :00 :00 00 :00 :00 1 00 :00 :00 - -6 SETUP XMTR FIXED OUTPUT Expected field communications:
- 1. None Event 2: 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PC2273 FW HTR EMER CNH1CFW003F BYPASS VLV 00 :00 :00 00 :01 :00 5 00 :00 :00 - 90 PLE CNTRL OSC AUTO ONLY Expected field communications:
- 1. IF directed to locally monitor Feedwater Heater level, THEN report #2 Feedwater Heater level is (was) low and that the level control system is responding in automatic to restore level.
With the controller in automatic:
IF an operator is dispatched to locally investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two minutes report that the valve is cycling open and close in response to the air signal being supplied.
With the controller in manual:
IF an operator is dispatched to locally investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two minutes report that the valve is stable (matching the control rooms indication).
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 3: 0LT-4040 Condensate Storage Tank T-24A Level Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 0-LT4040 COND STOR TK T24A 00 : 00 XMT1AFW005A 00 :00 :00 00 :00 :03 11 - 0 PLE LEVEL FIXED :00 OUTPUT Expected Communications:
- 1. IF an AO is sent to locally investigate 0LT-4040, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally.
Event 4: 1X-01, Main Transformer loss of cooling MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE MAIN TRANS ANN-C02D-A09 1X01 LOSS OF 00 :00 :00 - 9 00 :00 :00 - ON PLE COOLING 1-P99A SGFP SEAL WATER LOA1CFW083 00 :01 :00 - 11 00 :00 :00 - ON PLE INJECT PUMP C.S.
1-P99B SGFP SEAL WATER LOA1CFW084 00 :01 :10 - 11 00 :00 00 - ON PLE INJECT PUMP C.S.
Expected field communications:
- 1. IF an AO is directed to locally investigate 1X-01, Main Transformer; wait two minutes and THEN report breaker 8MN in the Cooler Control Cabinet for phase B is in the tripped condition and none of the cooling units are running.
- 2. IF an AO is directed to locally start 1P-99A and 1P-99B, Main Feed Pump Seal Water Pumps; insert Trigger 11 and THEN report when they are running.
Event 5: 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-HC428A P-2A CHARGE PUMP CNH1PCS004F SPEED HAND 00 :00 :00 00 :00 :10 13 00 :00 :00 - 100 PLE CTLR OSC AUTO ONLY Expected field communications:
- 1. IF the PAB AO is directed to check that there are no charging pump relief valves lifting on unit 1; wait two minutes and THEN report that no charging pump relief valves on are lifting Unit 1.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 6: Large Break LOCA MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE HOT MAL1RCS001 DBA LOCA 00 :00 :00 00 :00 :00 15 00 :00 :00 - PLE LEG A 0-SW-322 1HX-12A CC LOA1SWS048 00 :04 :00 00 :00 :30 17 00 :00 :00 - 0.4 When directed by crew HTEXCH OUTLET 1-CC-744B BA EVAP HX-8A LOA1CCW018 00 :07 :00 00 :00 :30 17 00 :00 :00 - 0 When directed by crew RETURN STOP VALVE 1-CC-740A NON-REGEN LOA1CCW016 00 :01 :00 00 :00 :30 17 00 :00 :00 - 0 When directed by crew HX-3A&B INLET VALVE 1-CC-750A LOA1CCW021 SEAL STR HX-5 00 :02 :30 00 :00 :30 17 00 :00 :00 - 0 When directed by crew INLET VALVE 1-SI-897A LOA1SIS030 HANDWHEEL 00 :01 :00 00 :00 :30 19 00 :00 :00 - 0 When directed by crew GAG 1-SI-897B LOA1SIS031 HANDWHEEL 00 :02 :00 00 :00 :30 19 00 :00 :00 - 0 When directed by crew GAG Expected field communications:
- 1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.
- 2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.
- 3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.
- 4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.
- 5. WHEN directed to perform Attachment A of EOP-1.3; insert trigger 17, wait for the valves to finish stroking and THEN report that the CCW alignment is complete.
- 6. WHEN directed to locally shut 1SI-897A and B, SI Test Line Return Isolation AOVs; insert trigger 19, wait for the valves to finish stroking, and THEN report the valves are closed.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG Event 7: RHR pump malfunctions: 1P-10A, RHR Pump fails to auto start and 1P-10B, RHR Pump trips MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-B5212A P-10A FAIL BKR1RHR001 RH REMOVAL 00 :00 :00 - - 00 :00 :00 - AUTO PRELOAD PUMP CKTBKR CL P-10B RH RESIDUAL WINDING MOT1RHR002 00 :00 :00 - - 00 :00 :00 - GROUND PRELOAD HEAT REMOVAL PUMP Expected field communications:
- 1. IF the PAB AO is directed to check 1P-10B, RHR Pump; wait two minutes and THEN report that the motor is not running, discolored, hot to the touch and smells acrid. IF asked; THEN report that there is no fire.
- 2. IF an AO is directed to locally investigate breaker 1B52-21A on 1B-04 for 1P-10B, RHR Pump; wait two minutes and THEN report that breaker has tripped on overcurrent.
Event 8: Containment Spray fails to actuate MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-CS-10X TRAIN A CONT FAIL AS RLY1PPL020 00 :00 :00 - - 00 :00 :00 - PRELOAD SPRAY IS AUXILIARY 1-CS-20X TRAIN B CONT FAIL RLY1PPL021 00 :00 :00 - - 00 :00 :00 - PRELOAD SPRAY AS IS AUXILIARY Expected field communications:
- 1. None Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.
Crew Shift Turnover Information: See Attached Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Crew takes the Normal Shift routine will be to lower power CREW Implements OP-3A Unit 1, Power Operation To Hot Standby Unit 1, utilizing OP-3A Unit 1, Power Operation To Hot starting at Step 5.1.9.
watch: ________ Standby Unit 1.
Event 1: Trigger 1 [XMT1CNM017A, 1-PT-947 LOOP A BOP The crew responds to the containment pressure alarm and diagnoses that 1PT-947, Loop A CONT PRESSURE XMTR FIXED alarm being due to an instrument failure.
Containment OUTPUT, Value = -6, Ramp = 0 sec]
Pressure OS Implements AOP-24, Response to Instrument Malfunctions Transmitter fails After completion of crew turnover and the BOP 1. Identify Failed Instrument low examinees have assumed the watch, insert Trigger 2 Check If Failed Instrument Is A Controlling Channel 1 to cause 1PT-947, Loop A Containment Pressure 3. Establish Manual Control As Required Transmitter to fail low. 4. Return Affected Parameter(s) To Desired Value(s)
Start: _________ 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE Plant Response: REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is 1PT-947, Loop A Containment Pressure Transmitter NOT An Input To RTO fails low bringing in a containment pressure PPCS 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, Alarm. ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE Cues: 7. Return Controls To Automatic If Desired 1C20 D 2-1, PPCS Priority Alarm 8. Check Failure For Technical Specification Or TRM Applicability Containment Pressure PPCS Alarm 9. Return To Procedure And Step In Effect Expected Communications: OS Implements 0-SOP-IC-001 BLUE, ROUTINE MAINTENANCE None BOP PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE Instructor Note: If the crew decides to NOT 1. In cabinet C-115, place the following bistable trip switches in the remove the failed containment pressure TRIP position (toggle switch up) and check expected response channel from service, have the Shift Manager SAFEGUARD ACTUATION (P/947) provide a cue directing the crew to take action CONTAINMENT SPRAY LOGIC (P/947) to remove it from service. 2. Remove from scan PPCS point ID PT947, CNMT LR PRESS BLU.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: Reference Technical Specifications Once the crew has completed taking the channel Technical Specifications:
out of service per 0-SOP-IC-001 BLUE and has OS Reference 0-SOP-IC-002:
addressed Technical Specifications, or at the Table 3.3.2-1 D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> discretion of the Lead Examiner, proceed with the inoperable Item 1c OR next event.
item 2c D.2.1 Be on MODE 3 item 3c AND 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> item 4d-2 D.2.2 Be in MODE 4 item 4e-2 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> item 5c item 6c Table 3.3.3-1 item 11 Table 3.3.5-1 item 2 Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 2: Trigger 5 [CHN1CFW003F, 1-PC2273 FW HTR BOP Identifies 1PC-2273, Feedwater Heater Emergency Bypass Valve 1PC-2273, EMER BYPASS VLV CNTRL OSC Controller malfunction by indicated 1PC-2273, Feedwater Heater Feedwater Heater AUTO ONLY = 90; Ramp = 00:01:00] Emergency Bypass Valve Controller output oscillating (90% of scale),
Emergency 1CS-2273, Feedwater Heater Emergency Bypass Valve indication Bypass Valve Insert Trigger 5 to cause 1PC-2273, Feedwater showing intermediate (Red and Green lights lit), rise in reactor power, Controller Heater Emergency Bypass Valve Controller to SG A and B level deviations with corresponding annunciators for SG A oscillates in oscillate in automatic. and B level deviations. May take manual control of 1PC-2273, automatic Feedwater Heater Emergency Bypass Valve Controller to mitigate the Plant Response: transient.
1PC-2273, Feedwater Heater Emergency Bypass Start: __________ Valve Controller output oscillates (90% of scale), OS1 Implements AOP-2B Unit 1, Feedwater System Malfunction 1CS-2273, Feedwater Heater Emergency Bypass Monitor Foldout Page Valve indication shows intermediate (Red and OATC 1. Maintain Reactor Power Less Than or Equal to 100%
Green lights lit, rise in reactor power, SG A and B RNO: Reduce power per AOP-17A Unit 1, Rapid Power Reduction level deviations with corresponding annunciators for as necessary to maintain reactor power less than or equal SG A and B level deviations. to 100%.
- 2. Determine the Secondary System Malfunction AND go to the Cues: appropriate step (16) 1PC-2273, Feedwater Heater Emergency Bypass 16. Perform the following:
Valve Controller output oscillates (90% of scale) BOP a. Check Main Feed Pump Suction Pressure - GREATER THAN 1CS-2273, Feedwater Heater Emergency Bypass 190 PSIG Valve indication shows intermediate (Red and b. Check LP Feedwater Heater Bypass Valve - SHUT Green lights lit) RNO: Perform the following:
Reactor power rises 1) IF 1CS-2273 open due to controller malfunction, SG A and B level deviated from normal program THEN perform the following:
band a) Ensure LP feedwater heater bypass Annunciators: controller set at 25 psig below main feed 1C03 1E2 1-2, Steam Generator A Level pump suction pressure in auto Setpoint Deviation/Trouble 1PC-2273 1C03 1E2 1-5, Steam Generator B Level b) IF controller will NOT operate in auto, THEN Setpoint Deviation/Trouble place controller in manual and place LP 1C03 1F 3-1, LP Feedwater Heater 1, 2, or 3 feedwater heater bypass valve in desired Level Low position.
- c. Return to Step 2
- 3. Check Plant Conditions - STABLE
- 4. Check Secondary System Alignment - NORMAL
- 5. Check Change in Reactor Power - LESS THAN 15% IN ANY ONE HOUR
- 6. Notify the DSM Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE The crew should implement AOP-2B Unit 1, OS Feedwater System Malfunction, and lower turbine 7. Return to Procedure and Step in Effect load to maintain reactor power less than 100%. OS Implements AOP-17A Unit 1, Rapid Power Reduction (if necessary)
Prompt action by the crew to take manual control of 1CS-2273 may eliminate the need to take action to OATC 1. Check Power - GREATER THAN 100%
reduce turbine load. 2. Reduce Load - LESS THAN 100%
- a. Manually insert control rods 10 steps to initially lower RCS If the overpower condition is recognized before the temperature.
crew has diagnosed the secondary malfunction, the b. WHEN control rod movement has started, THEN reduce turbine crew may enter AOP-17A first to address the load.
overpower condition. 1) Select Turbine Manual.
BOP 2) Reduce turbine load by 2% by pulsing GV Down IF the crew discusses returning to full power, THEN pushbutton.
monitor for proper reactivity control implementation OATC/BOP c. Commence Boration per shiftly reactivity brief.
and supervisor oversight. d. IF NI power is still greater 100%, THEN reduce turbine load in 1% increments and adjust rods as necessary until less than Expected Communications: 100%.
IF directed to locally monitor Feedwater Heater OATC e. Return control rods to auto.
level, THEN report #2 Feedwater Heater level OATC f. IF less than 100% AND additional load reduction is required, is (was) low and that the level control system is THEN Go to Step 3.
responding in automatic to restore level. RNO Perform the following:
With the controller in automatic: 1) Restore Tavg-Tref differential to <1°F using rod IF an operator is dispatched to locally control in manual.
investigate 1CS-2273, Feedwater Heater 2) Return affected controls to automatic per Shift Emergency Bypass Valve, THEN after two Management.
minutes report that the valve is cycling open and Turbine controls close in response to the air signal being Rod Control supplied. 2) Go to Procedure and Step In Effect.
With the controller in manual:
IF an operator is dispatched to locally investigate 1CS-2273, Feedwater Heater Emergency Bypass Valve, THEN after two minutes report that the valve is stable (matching the control rooms indication).
Continuation Criteria:
After the crew has addressed the 1CS-2273 failure per AOP-2B Unit 1, or at the discretion of the Lead Examiner, continue on with the next event.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 7 [XMT1AFW005A, 0-LT4040 COND BOP CO Identifies the failed level channel for T-24A Condensate Storage Tank, 0LT-4040 STOR TK T24A LEVEL FIXED dispatches an AO to investigate and references ARP C01 A 2-9, T-Condensate OUTPUT, VALUE = 0, RAMP = 3 sec] 24A or B Condensate Storage Tanks - Level High or Low and ARB Storage Tank T- C01 A 3-9, T-24A or B Condensate Storage Tanks Level Low-Low.
24A Level Insert Trigger 7 to cause 0LT-4040 Condensate Transmitter fails Storage Tank T-24A Level Transmitter to fail low. OS Reference Technical Specifications low Plant Response: Technical Specifications:
Start: _________ Indicated tank level goes to 0%. 3.3.3 Post Accident Monitoring (PAM) Instrumentation is not met (2 required channels).
Cues:
CONDITION REQUIRED ACTION COMPLETION C01 A 2-9, T-24A or B Condensate Storage TIME Tanks - Level High or Low C01 A 3-9, T-24A or B Condensate Storage A. One or more A.1 Restore 30 days Tanks Level Low-Low Functions with required PPCS: L-4040 CST LVL A low one required channel to channel OPERABLE Expected Communications: inoperable. status.
IF an AO is sent to locally investigate 0LT-4040 T-24A Condensate Storage Tank Level Transmitter, wait two minutes and THEN report that there doesnt seem to be anything out-of-normal locally.
Continuation Criteria:
One the crew has addressed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 9 [ANN-C02D-A09, MAIN TRANS 1X01 LOSS BOP Acknowledge the alarm and refer to Alarm Response Procedure for 1-X01, Main OF COOLING = ON] C02 D 1-9, 1X-01 Main Tran Loss of Cooling.
Transformer loss of cooling Insert Trigger 9 to override on the annunciator for OS Implements ARP C02 D 1-9, 1X-01 Main Tran Loss of Cooling C02 D 1-9, 1X-01 Main Tran Loss of Cooling. 3.1 DISPATCH AO to validate alarm for the affected Main Start: _________ Transformer(s) and PERFORM the following:
Plant Response: CHECK cooler fan operation Annunciator only. CHECK oil cooler operation CHECK local alarm panel Cues: 3.2 INSTRUCT AO to perform the following for affected transformer(s):
C02 D 1-9, 1X-01 Main Tran Loss of Cooling 3.2.1 Continuously MONITOR Winding and Oil temperature indicators and REPORT temperature changes to Control Outside air temperature for this scenario is 24°F (- Room.
4.44°C). Per the table using a conservative 3.2.2 CONTINUE attempts to restore cooling at each affected temperature of 0°C, time to get the unit off-line transformer using the flowing steps as applicable:
should be 2.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. a. CHECK affected Transformer Phase Cooling Control Cabinet(s) for alarms Expected Communications: b. OPEN affected Cooling Control Cabinet(s) and CHECK WHEN an AO is directed to locally investigate 1X-01, for tripped Main Power Supply breaker 8MN.
Main Transformer; wait two minutes and THEN report h. IF no cooling banks can be started, THEN immediately breaker 8MN in the Cooler Control Cabinet for phase TAKE Main Generator OFF-LINE AND DE-ENERGIZE B is in the tripped condition and none of the cooling Main Transformer based on loading and ambient units are running. temperature as follows:
- 1. REFER to AOP-17A Unit 1, Rapid Power Continuation Criteria: Reduction AND REDUCE power at a rate When the crew begins reducing load per AOP-17A, determined by Shift Management Rapid Power Reduction, or at the discretion of the Lead Examiner, continue with the next event.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS Implements AOP-17A Unit 1, Rapid Power Reduction OATC/BOP 1. Check Power - GREATER THAN 100%
- 3. Determine Desired Power Level Or Condition To Be Met Control Room Supervisor announce desired power level or condition using less than or equal to 3%/min ramp rate.
- 4. Commence Boration As Necessary to Target Load
- a. Set boric acid flow totalizer to desired quantity
- b. Set boric acid flow controller to desired flow rate
- c. If desired, start second boric acid transfer pump
- d. Place Reactor Makeup Mode Selector Switch to Borate.
- e. Place Reactor Makeup Control Switch to Start
- 5. Select Turbine Rate And Reduce Load o Operator Automatic Load Rate Control
- a. Ensure EH controls are set for Operator Auto
- b. Ensure First Stage In is selected
- c. IF first stage pressure is unavailable, THEN select First Stage Out OS d. Ensure the appropriate load rate is selected on load rate thumb-wheel
- e. Select target end-point on reference control OATC/BOP f. WHEN temperature reduction of at least 0.5°F is observed on Tavg-Tref indicator, THEN depress GO push-button
- g. Continue with next step Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS 6. Notify Power System Supervisor (PSS) Of Load Reduction Expected Communications: 7. Check Rod Control System - IN AUTO IF an AO is directed to locally start 1P-99A and 1P- OATC/BOP 8. Energize Pressurizer Backup Heaters 99B, Main Feed Pump Seal Water Pumps; insert 9. Check PZR Pressure - CONTROLLING IN AUTO Trigger 11 and THEN report when they are running. 10. Check PZR Level - CONTROLLING IN AUTO
- 11. Check Steam Generator Level - CONTROLLING IN AUTO
- 13. Maintain RCS Tavg:
Greater than 540°F Less than 577°F Within 7°F of program Tavg
- 14. Check AFD - WITHIN LIMITS:
o PPCS Screen AFD PLOT o ROD 1.2, HFP EQUIL DELTA FLUX
- 15. Control MSR temperatures - LESS THAN 500°F o HC-2085
- 16. Determine Desired End-Point - LESS THAN 60% TURBINE LOAD Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5: Trigger 13: [CNH1PCS004F, P-2A CHARGE PUMP SPEED HAND CTLR OSC AUTO OATC Acknowledges the annunciator and identifies 1HSC-428A, 1P-2A 1HC-428A, 1P-2A, Charging Pump Speed Hand Controller output oscillating between 0 Charging Pump ONLY, Value = 100]
and 100% output and takes manual control to stabilize pump speed Hand Controller and pressurizer level.
oscillates in auto Insert Trigger 13 to cause 1P-2A, Charging Pump Speed to oscillate between minimum and maximum OS Implements AOP-1D Unit 1, Chemical and Volume Control System flow while in automatic. OATC Malfunctions Start: __________ 1. Check RCS Leak - NOT IN PROGRESS Plant Response: 2. Determine CVCS Malfunction:
1P-2A, Charging Pump Speed will oscillate between IF any of the following is true, THEN go to Step 3 minimum and maximum flow while in automatic.
Any charging pump - TRIPPED Cues: OR Any charging pump - NOT OPERATING PROPERLY 1C04 1C 1-8, Charging Pump Speed Control OR Trouble Any charging pump controller - Not RESPONDING 1C03 1D 2-1, 1P-1A or B RCP LABYR Seal dP PROPERLY Low 3. Check Any Charging Pump - RUNNING 1HSC-428A, 1P-2A Charging Pump Speed Hand 4. Check Charging Flow - STABLE Controller output oscillating between 0 and 100% RNO: Perform the following:
output. a. Place running charging pumps - IN MANUAL
- b. IF charging flow NOT stable, THEN stop all charging Expected Communications: pumps and go to Step 10 IF the PAB AO is directed to check that there are 5. Check Charging Pump Relief - NOT LIFTED no charging pump relief valves lifting on Unit 1; 6. Check Charging Pump Suction Supply - ADEQUATE wait two minutes and THEN report that Unit 1 7. Check Charging System Response:
charging pump relief valves are NOT lifting. Desired Charging Pumps - RUNNING Labyrinth seal P - GREATER THAN 20 INCHES Letdown line pressure - STABLE PZR Level - STABLE AT OR TRENDING TO PROGRAM LEVEL
- 8. Notify Duty Station Manager
- 9. Return to Procedure And Step In Effect Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS May implement AOP-24, Response to Instrument Malfunctions When the crew has addressed the failure per AOP- OATC 1. Identify Failed Instrument 1D Unit 1 and is pursuing returning the system to RNO: IF a controller has failed, THEN go to Step 3 automatic, or at the discretion of the Lead 3. Establish Manual Control as Required:
Examiner, continue with the next event. o Place affected controller in manual OR o Place any affected equipment controls in manual
- 4. Return Affected Parameter(s) To Desired Value(s)
BOP 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO.
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFGUARDS OR PROTECTION SENSOR FROM SERVICE RNO: IF failed instrument channel can NOT be removed from service OR is NOT addressed in 0-SOP-IC-001, THEN perform the following:
- a. IF failed channel can NOT be removed from service, THEN inform SM of failed channel status.
- 7. Return Controls To Automatic If Desired
- 8. Check Failure For Technical Specification Or TRM Applicability
- 9. Return To Procedure And Step In Effect Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 6: Trigger 15: [MAL1RCS001, DBA LOCA HOT LEG OATC DIAGNOSE a large break LOCA event.
Large Break A]
LOCA OS Implements EOP-0, Unit 1 Reactor Trip or Safety Injection Insert Trigger 15 to cause a Large Break LOCA. OATC 1. Verify Reactor Trip Start: _________ 1P-10A, RHR Pump fails to auto start and 1P-10B, 2. Verify Turbine Trip RHR Pump trips. 3. Verify Power to AC Safeguards Buses
- 4. Check if SI is Actuated Plant Response: a. Any SI annunciators LIT Rapid depressurization of RCS, automatic SI b. Both trains of SI - Actuated actuation. RNO: Manually actuate both trains of SI and CI Cues: BOP Rapid drop in RCS pressure Auto SI Event 7: Preloads: [BKR1RHR001, 1-B5212A P-10A RH BOP NOTE: Following immediate actions, CREW may manually RHR pump Removal Pump CKTBKR, Fail Auto start RHR and realign the Containment Spray system malfunctions: 1P- Close] in accordance with OM 3.7, AOP And EOP Procedure 10A, RHR Pump [MOT1RHR002, P-10B RH Removal Usage For Response To Plant Transients.
fails to auto start Pump, Winding Ground]
and 1P-10B, RHR Pump trips Event 8:
Preloads: [RLY1PPL020, 1-CS-10X TRAIN A Containment CONT SPRAY AUXILIARY, Fail As Is]
Spray fails to [RLY1PPL021, 1-CS-20X TRAIN B actuate CONT SPRAY AUXILIARY, Fail As Is]
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: OATC EOP-0 continued ...
IF the PAB AO is directed to check 1P-10B, RHR Monitor Foldout Page Criteria: RCP Trip Criteria Pump; wait two minutes and THEN report that the IF both conditions listed below occur, THEN trip both RCPs:
motor is not running, discolored, hot to the touch and RCS subcooling - LESS THAN [36 ºF] 26 ºF smells acrid. IF asked; THEN report that there is no fire. SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF IF an AO is directed to locally investigate breaker 1B52- DELIVERING FLOW 21A on 1B-04 for 1P-10B, RHR Pump; wait two minutes and THEN report that breaker has tripped on BOP 5. Perform ATTACHMENT A, Automatic Action Verification while overcurrent. continuing with this procedure OATC 6. Verify AFW pumps - Running
- 7. Check RCP Seal Cooling
- 8. Check RCS Temperatures
- 9. Check PZR PORVs and Spray Valves
- 10. Check if RCPs should be stopped
- 11. Check if SGs are NOT Faulted
- 12. Check if SG Tubes are NOT Ruptured
- 13. Check if RCS is Intact RNO: Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT The LOCA / SI injection will result in meeting a May implement CSP-P.1, Response to Imminent Pressurized Critical Safety Function INTEGRITY RED path Thermal Shock Condition.
condition. Depending on when this condition is 1. Check RCS pressure - GREATER THAN [450 PSIG] 325 PSIG.
identified, the crew may enter, then immediately exit RNO: IF RHR flow is greater than 550 gpm, THEN return to procedure CSP-P.1, Response to Imminent Pressurized and step in effect.
Thermal Shock Condition, at Step 1.
STA CUE: Identify and report the INTEGRITY Critical Safety Function RED path when appropriate.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service Water valves, LW-61 and 62, THEN report both
- CT-5, Manually start at least one Low-Head ECCS Pump valves are closed.
WHEN directed to locally check CW pump house A3 Verify ECCS Pumps RUNNING temperature <105 ºF, wait 3 minutes and THEN a. SI Pumps - BOTH RUNNING report the temperature is 72 ºF and stable. b. RHR Pumps - BOTH RUNNING WHEN directed to locally check G03/G04 RNO WHEN SI sequence is complete, THEN manually start Switchgear Room temperature <95 ºF, wait 3 RHR pumps minutes and THEN report the temperature is 75 ºF A4 Verify Service Water Pumps RUNNING and stable. A5 Verify Containment Accident Cooling Units RUNNING IF directed to periodically check the status of A6 Verify Component Cooling Water Pumps - ONLY ONE spent fuel cooling, wait 5 minutes and THEN RUNNING A7 Check If Main Steam Lines Can Remain Open report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable. A8 Verify Containment Spray Not required
- a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig RNO Perform the following:
- 1) Check containment spray actuated:
Annunciator {C01 B 2-6}, CONTAINMENT SPRAY, lit IF containment spray has NOT actuated, THEN manually actuate containment spray.
A9 Verify ECCS Flow A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 Verify Proper ECCS Valve Alignment Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP *CT-3, Manually actuate containment cooling A12 Check Containment Spray NOT ACTUATED RNO Check containment spray alignment
- 1. Ensure all containment spray pump discharge MOVs are open
- 2. Ensure at least one containment spray pump is running
- 3. IF two containment spray pumps are running, THEN place one containment spray pump in pull out
- 4. WHEN containment spray has been actuated for GREATER THAN two minutes, THEN ensure spray additive educator suction valve is open on running train A13 Stop any boration via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling OS Implements EOP-1, Loss of Reactor or Secondary Coolant Monitor Foldout Page criteria:
Containment Sump Recirculation Switchover Criteria IF either condition below is satisfied, THEN Go to EOP-1.3, TRANSFER TO CONTAINMENT SUMP RECIRCULATION - LOW HEAD INJECTION RWST level - LESS THAN 60%
OR RCS pressure less than [450 psig] 325 psig AND RHR flow greater than 550 gpm Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: OS Implements EOP-1.3 Unit 1, Transfer to Containment Sump Recirculation - Low Head Injection WHEN directed to perform Attachment A of EOP-1.3; 1 Reset SI insert trigger 17, wait for the valves to finish stroking BOP and THEN report that the CCW alignment is complete. OATC 2 Check RCS Break Size 3 Align CCW per ATTACHMENT A, LOCAL ALIGNMENT OF COMPONENT COOLING WATER While Continuing With The Procedure BOP 4 Direct Unnecessary Personnel To Evacuate The PAB 5 Check if Containment Sump pH Must Be Adjusted 6 Check if Train 'A' SI Flow Should Be Stopped
- a. Check Train 'B; RHR injection flow - GREATER THAN 550 GPM
- a. RNO Go to Step 7 7 Check if Train 'B' SI Flow Should Be Stopped
- a. Check Train 'A; RHR injection flow - GREATER THAN 550 GPM
- b. Stop train B SI pump and place in pull out
- c. Stop train B RHR pump and place in pull out 8 Monitor Core Cooling
- a. Maintain core exit thermocouple temperatures - LESS THAN 700º F 9 Evaluate Control Room Conditions:
- a. Check Control Room RMS high alarms - CLEAR 1RE-101 1RE-235 Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: BOP 10 Isolate Component Cooling Flow To Containment
- a. Check RCPs - BOTH STOPPED WHEN directed to locally shut 1SI-897A and B, SI Test b. Shut containment equipment CC supply header isolation Line Return Isolation AOVs; insert trigger 19, wait for the valves to finish stroking, and THEN report the valves valve:
are closed. 1CC-719 11 Isolate Component Cooling Flow to Non-Regenerative Heat Exchanger 12 Check Service Water Pumps - SIX RUNNING 13 Check Service Water Ring Header - CONTINUOUS FLOWPATH ESTABLISHED 14 Establish Component Cooling Flow To RHR Heat Exchangers:
- a. Ensure component cooling pumps - AT LEAST ONE RUNNING
- b. Open only one RHR heat exchanger shell side inlet valve:
1CC-738A 1CC-738B
- c. Start second component cooling pump
- d. Open second RHR heat exchanger shell side inlet valve:
1CC-738A 1CC-738B 15 Ensure RV Injection MOVs - BOTH OPEN 16 Align SI Test Lines For Recirculation
- a. Check containment spray discharge valves - AT LEAST ONE OPEN IN EACH TRAIN Train A o 1SI-860A o 1SI-860B (preferred)
Train B o 1SI-860C o 1SI-860D (preferred)
1SI-897A 1SI-897B Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Termination Criteria: BOP 17 Align RHR Sump Suction Valves Terminate the scenario when crew has completed a. Open train A RHR pump suction from containment sump B Step 21 of EOP-1.3 Unit 1, Transfer To isolation valve:
Containment Sump Recirculation - Low Head 1SI-850A Injection and is waiting for RWST level to lower to RNO: Locally open valve:
34% or at the discretion of the Lead Examiner. b. Open train B RHR pump suction from containment sump B isolation valve 1SI-850B 18 Check Train 'A' - READY FOR RECIRCULATION 19 Check Train 'B' - READY FOR RECIRCULATION 20 Check Battery Chargers Supplying DC Buses - ENERGIZED 21 Check RHR Trains - At Least One Ready For Recirculation Train A OR Train B 22 Check RWST Level - LESS THAN OR EQUAL TO 34%
RNO: Perform the following:
- a. WHEN RWST level is less than or equal to 34%, THEN immediately return to this procedure and continue with Step 23.
- b. Implement Critical Safety Procedures and continue with Procedure And Step In Effect.
- END OF SCENARIO ***
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
1PT-947, Loop A Containment Pressure Transmitter fails high 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040, Condensate Tank T-24A Level Transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto After EOP Entry:
RHR pump malfunctions 1P-10A, RHR Pump fails to auto start 1P-10B, RHR Pump trips Containment Spray fails to actuate Abnormal Events:
1PT-947, Loop A Containment Pressure Transmitter fails high 1PC-2273, Feedwater Heater Emergency Bypass Valve Controller oscillates in automatic 0LT-4040, Condensate Tank T-24A Level Transmitter fails low 1-X01, Main Transformer loss of cooling 1HC-428A, 1P-2A, Charging Pump Hand Controller oscillates in auto Major Transients:
Large Break LOCA Critical Tasks:
- 1. CT-3 Manually actuate containment cooling
- 2. CT-5 Manually Start at Least One Low-Head ECCS Pump Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG CT-3 Manually actuate containment cooling Applicable ERG LP Version Applicable ERG E-0, ECA-0.2, FR-Z.1 Critical Task:
Manually actuate at least one Containment Spray pump before an extreme (RED path) challenge develops to the containment CSF.
Plant Conditions:
Containment cooling is required but the minimum required complement of containment cooling equipment is not automatically actuated (instrument failure is not the cause of the requirement for containment cooling)
The minimum required complement of containment cooling equipment can be manually actuate from the control room Cues:
Indication and/or annunciation that containment cooling is required (containment pressure > 25 psig)
Indication and/or annunciation that Containment Spray is not actuated Performance Indicator:
Manipulation of controls as required to actuate at least one Containment Spray Pump Feedback:
Indication and/or annunciation that at least one Containment Spray pump is running Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 35
PBN LOI NRC 15E, 2017 NRC Exam Scenario 1, Rev. 0 SEG CT-5 Manually Start at Least One Low-Head ECCS Pump Applicable ERG HP, LP Version Applicable ERG E-0, ECA-0.2 Critical Task:
Manually start at least one low-head ECCS pump before transition out of EOP-0 Plant Conditions:
Large-break LOCA Reactor trip SI RCS pressure below the shutoff head of the low-head ECCS pumps Both low-head ECCS pumps fail to automatically start upon SI At least one low-head ECCS pump can be started provided that manual action is taken as necessary Cues:
Indication and/or annunciation that low-head ECCS pumped injection is required
- SI actuation
- RCS pressure below the shutoff head of the low-head ECCS pumps AND Indication and/or annunciation that no low-head ECCS pump is injecting into the core
- Control switch indication that the circuit breakers or contactors for both low-head ECCS pumps are open
- All low-head ECCS pump discharge pressure indicators read zero
- All flow rate indicators for low-head pumped injection read zero Performance Indicator:
Manipulation of controls as required to start at least one low-head ECCS pump
- Control switch indication that the circuit breaker for at least one low-head ECCS pump is closed Feedback:
Indication and/or annunciation that at least one low-head ECCS pump is injecting
- Flow rate indication of injection from at least one low-head ECCS pump Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 35
TURNOVER INFORMATION SEG 1.0 Plant Conditions:
Unit 1 Unit 2 Time in Core Life (MWD/MTU): 19,400 Reactor Power: 100%
Boron Concentration: 11 ppm Rod Height: CBD @ 220 2.0 Equipment Out of Service:
1PT-950, U1C High Range Pressure Transmitter 1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:
LCO NOT Met TSAC Required Actions Completion Time 3.3.2 A. One or more Functions with one A.1 Enter the Condition referenced in Immediately or more channels or trains Table 3.3.2-1 for the channel(s) or inoperable. train(s).
D. One channel inoperable D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 4.0 Planned Evolutions:
Normal Shift routine will be to lower power at 30%/hr utilizing OP-3A Unit 1, Power Operation To Hot Standby Unit 1.
5.0 Common
Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.
Filename: NRC Scenario 1 draft.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 35
SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 16E LMS Rev. Date:
SEG TITLE: 2017 NRC Exam Scenario 2 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner (Line) Date Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _2___________ Op-Test No.: _2017____
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Unit 1 is in OP 1C, Startup to Power Operation, at approximately 29% post _
chemistry hold coming out of a forced outage. Chemistry has requested a bump of Main Feed and _
Condensate pumps for iron flushing in accordance with Step 5.31. 1W-3B, Control Rod Shroud Fan _
is OOS due to imminent motor failure. 1PT-950, Loop B Containment Pressure has been removed _
from service. Repairs are expected to be complete during the upcoming refueling outage.__________
Turnover: Start 1P-28B, SGFP and 1P-25B, Condensate Pump then secure 1P-28B SGFP, and _
1P-25B Condensate Pump after 5 minutes for iron flushing. Raise power to 50%. ________________
Event Malf. No. Event Event No. Type* Description N-BOP 1 Bump SG Feed Pump and Condensate Pump N-SRO R-RO 2 N-BOP Raise power to 50%
R-SRO I-BOP 3 XMT1SGN001A I-SRO 1FI-464, SG Steam Flow fails slowly high TS-SRO I-BOP 4 XMT1MSS009A I-SRO 1PT-486, Turbine First Stage Pressure fails low TS-SRO C-RO 1P-1B, RCP Seal leak develops, which degrades requiring reactor 5 MAL1RCP001B C-SRO trip 6 MAL1RCS003F M-ALL Small Break LOCA from RTD Bypass Line occurs on reactor trip MAL1PPL001A C-RO Reactor fails to trip 7 MAL1PPL001B (CSP-S.1, Response to Nuclear Power Generation/ATWS)
MOT1SIS001 C-BOP 1P-15A, SI Pump trips upon starting 8 BKR1SIS002 1P-15B, SI Pump fails to start in Auto
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to the failures listed below in accordance with plant procedures:
1FT-464, SG Steam Flow Transmitter fails high (no auto shift to single element)
PT-486, Turbine First Stage Pressure fails low 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria Small Break LOCA Reactor fails to trip (ATWS)
Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Embedded within these events is the expectation to properly utilize Technical Specifications.
Enabling None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators
References:
- 1. 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels
- 2. 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Red Channels
- 3. 0-SOP-IC-002, Technical Specifications LCO - Instrument Cross Reference
- 4. OP 1C, Startup to Power Operation Unit 1
- 5. AOP-1B Unit 1, Reactor Coolant Pump Malfunction
- 7. AOP-24, Response to Instrument Malfunctions
- 8. ARP 1C03 1E2 3-2, Steam Generator A Feed Water Flow Channel Alert
- 9. ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert
- 10. CSP-S.1 Unit 1, Response to Nuclear Power Generation / ATWS
- 11. EOP-0 Unit 1, Reactor Trip Or Safety Injection Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG
- 12. EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant
- 13. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients
- 14. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021 Rev. 9.
Operating N/A Experience:
Risk Significant HEP-ODA-EOP12-05, FAILURE TO COOLDOWN AN DEPRESSURIZE Operator Actions: RS FO LONG TERM COOLING BY SECONDARY STEA, FV: 3.86E-02 Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Unit 1 is in OP 1C Unit 1, Startup to Power Operation Unit 1 at approximately 28%
post chemistry hold coming out of a forced outage. Chemistry has requested a bump of the idle main feed and condensate pumps for iron flushing in accordance with Step 5.31.
Start and run 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump for 5 minutes for iron flushing.
Raise power to 50% in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.
OOS Equipment 1PT-950, Loop B Containment Pressure has been removed from service.
Repairs are expected to be complete during the upcoming refueling outage.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
Events 1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element) 1PT-486, Turbine First Stage pressure transmitter fails low 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria Small Break LOCA Reactor fails to trip (ATWS)
Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Terminate the scenario when crew has completed Step 13 of EOP-1 Unit 1, Loss of Reactor or Secondary Coolant.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description
- 1. Start and run 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump for 5 minutes for iron flushing beginning with OP-1C Unit 1, Startup to Power Operation Unit 1, Step 5.31.
- 2. Raise power to 50% (or per Lead Examiner) in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.
The crew should respond by taking 1FIC-466A, 1 HX-1A Primary Flow Indicating Controller to manual and controlling steam generator level.
The crew should implement AOP-24, Response to Instrument Malfunctions and 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Red Channels to shift to a new controlling channel and take the flow transmitter out of service.
The crew may implement ARP 1C03 1E2 2-2, Steam Generator A Feed Water Flow High to shift to a new controlling channel.
- 4. 1PT-486, Turbine First Stage Pressure Transmitter fails low The crew should implement :
ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert and realign the condenser steam dump system for continued operation.
AOP-24, Response to Instrument Malfunction and 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service -
Blue Channels to take the transmitter out of service Technical Specifications for the failed channel
- 5. 1P-1B, Reactor Coolant Pump seal leak develops, then degrades requiring a reactor trip Unit conditions degrade such that AOP-1B Unit 1, Foldout Page criteria are met and a transition to Step 18 to trip the unit and secure the pump is warranted.
- 6. Small Break LOCA from RTD bypass line Will result in a Safety Injection signal Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG
- 7. Reactor fails to trip (ATWS)
Upon failure of the reactor to trip from the control room, the crew should transition from AOP-1B Unit 1/EOP-0 Unit 1, Reactor Trip or Safety injection to CSP-S.1 Unit 1, Response to Power Generation / ATWS.
After completing the actions in CSP-S.1 Unit 1, the crew should transition back to EOP-0 Unit 1, Step 1 RNO.
Concurrent with the implementation of EOP-0 Unit 1, the crew should complete the remainder of AOP-1B Unit 1 Step 18 which was suspended when entering CSP-S.1Unit 1.
The crew should complete the actions of EOP-0 Unit 1 and transition to EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant and then to EOP-1.2 Unit 1, Post LOCA Cooldown and Depressurization to address the Small Break LOCA.
- 8. Safety Injection Pump failures: 1P-15A, Safety Injection pump trips upon starting and 1P-15B, Safety Injection pump fails to auto start Following immediate actions of EOP-0 Unit 1, The crew may manually start a Safety Injection Pump in accordance with OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients, otherwise pump start is addressed in EOP-0 Unit 1, Attachment A, Step A3.a.RNO .
STOP Terminate the scenario when crew has completed Step 9 of EOP-1 Unit 1, Loss of Reactor or Secondary Coolant.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
General Instructions Simulator Setup Instructions:
Load IC-7 and go to run Open the saved Event and Schedule files from the secure drive:
Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)
Reposition bistable switches for: 1PT-950, Loop B Containment Pressure Transmitter Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:
Load saved IC and go to run Open the saved Event and Schedule files:
Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:
Setup: 1PT-950, Loop B Containment Pressure Transmitter is out of service MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT950 LOOP B CONT XMT1CNM017A PRESSURE 00 :00 :00 - 90 Preload XMTR FIXED OUTPUT Simulator Setup:
- 1. Place OOS magnet at PT-950, Containment Pressure
- 2. Place a RED dot on C01 B 1-5, U1 Containment Pressure Channel Alert
- 4. Install an orange Guarded magnet at 1W-3A.
SIMULATOR MALFUNCTIONS:
Event 1: Start and run 1P-28B, Main Feedwater Pump and 1P-25B, Condensate Pump for 5 minutes for iron flushing.
Event 2: Raise power to 50% in accordance with OP 1C Unit 1, Startup to Power Operation Unit 1.
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-P73A 1P-28B LOA1CFW079 SGFP AC LUBE - - 11 `- - ON Directed from Crew OIL PUMP CS Expected field communications:
- 1. [5.31.6] 1CS-182B, 1P-25B-M Cond Pump Motor Cooling Condensate Return To Suction has been adjusted for 30 gpm to motor bearing cooling.
- 2. [5.31.7] Prestart checks for the idle Main Feedwater Pump have been completed.
- 3. [5.31.9] 1P-28BA is aligned per Step 5.31.9.
- 4. [5.31.10] 1P-28B temperatures are as follows:
1TI-3156B, Top Case Temp 294°F 1IT-3157B, Bottom Case Temp 302°F 1IT-2191 SGFP Discharge Temp 310°F
- 6. [5.31.16] When directed to perform step, use LOA1CFW079 to stop 1P-73A, report actions completed SAT, and that oil pressure is normal at 18 psig..
- 9. [5.31.17.d.2)] 1P-25B, Condensate pump is stopped and not rotating backwards.
Event 3: 1FT-464, 1HX-1A SG Steam Flow Transmitter fails high (no auto shift to single element)
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-FT464 LOOP A XMT1SGN001A STEAM FLOW 00 :00 :00 00 :00 :45 1 00 :00 :00 - 2.0 PLE FIXED OUTPUT Expected field communications:
- 1. None Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Event 4: 1PT-486, Turbine First Stage Pressure Transmitter fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-PT486 FIRST STAGE XMT1MSS009A PRESSURE 00 :00 :00 00 :00 :05 3 00 :00 :00 - 0 PLE XMTR FIXED OUTPUT Expected field communications:
- 1. IF and AO is dispatched to locally investigate 1PT-486, Turbine First Stage Pressure Transmitter, wait two minutes and THEN report that locally there doesnt seem to anything out of normal.
Event 5: 1P-1B, Reactor Coolant Pump seal leak develops, then degrades to trip criteria MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE RCP #1 SEAL MAL1RCP001B FAILURE PUMP 00 :00 :00 00 :05 :00 5 00 :00 :00 - 5 PLE B
1-CV-300B P-1B Per When directed by the LOA1CVC048 RCP SEAL INJ 00 :00 :00 00 :00:00 - 00 :00 :00 - Crew Crew THROTTLE Direct.
RCP #1 SEAL MAL1RCP001B FAILURE PUMP 00 :00 :00 00 :01 :00 7 00 :00 :00 5 300 PLE B
Expected field communications:
- 1. IF the PAB AO is dispatched to monitor Unit 1 Reactor Coolant Drain Tank level; call up Instructor Station Drawing 1WPS1 and THEN report as indicated. The change in RCDT level should indicate a <1% change in 5 minutes.
- 2. IF the PAB AO is directed to throttle 1CV-300B, 1P-1B RCP Seal Injection Throttle Valve; coordinate with the Control Room and THEN make adjustments using LOA1CVC048, 1-CV-300B P-1B RCP SEAL INJ THROTTLE as directed.
Event 6: Small Break LOCA MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE RTD BYPASS 1C04 Trip pushbuttons LINE LEAK 9 MAL1RCS003F 00 :00 :00 00 :00 :30 75 [X14I055A == 1 l X14I057A ==
LOOP B Cond 1]
COMMON Expected field communications:
- 1. None Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG Event 7: Reactor fails to trip (ATWS)
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE REACTOR TRIP Fails to MAL1PPL001A BREAKER 00 :00 :00 - - 00 :00 00 - PRELOAD Open 52/RTA FAILURE REACTOR TRIP Fails to MAL1PPL001B BREAKER 00 :00 :00 - - 00 :00 :00 - PRELOAD Open 52/RTB FAILURE Expected field communications:
- 1. FOLLOWING the PA announcement for ATWS or when directed to locally open the reactor trip breakers, allow 2 minutes for travel to the Rod Drive Room and THEN report to the control room. WHEN directed to open the Unit 1 reactor trip breakers change MAL1PPL001A and MAL1PPL001B to Trip and THEN report the reactor trip breakers are open Event 8: Safety Injection Pump failures: 1P-15A, Safety Injection pump trips upon starting and 1P-15B, Safety Injection pump fails to auto start MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-P15A SAFETY Winding MOT1SIS001 INJECTION 00 :00 :00 - - 00 :00 :00 - PRELOAD Ground PUMP 1-A5285 P-15B Failauto BKR1SIS002 SAFETY INJ 00 :00 :00 - - 00 :00 :00 - PRELOAD cl PUMP CKTBKR Expected field communications:
- 1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.
- 2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.
- 3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.
- 4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.
- 5. IF an AO is dispatched to locally investigate 1P-15A, Safety Injection pump, wait 2 minutes and THEN report that the motor is hot to the touch and there is a faint acrid smell in the area. There is no fire.
- 6. IF an AO is dispatched to locally investigate breaker 1A52-59, Pwr to 1P-15A, Safety Injection Pump, wait 2 minutes and THEN report the breaker has tripped.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.
Crew Shift Turnover Information: See Attached Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 1: Unit 1 is in OP 1C, Startup to Power Operation CREW Implements OP 1C Unit 1, Startup to Power Operation Unit 1 Start and run 1P- Unit 1, at approximately 28% post chemistry 5.31.4 WHEN directed by Shift Management, THEN START the second 28B, Main hold coming out of a forced outage. Chemistry Condensate Pump AND RECORD date/time.
Feedwater Pump has requested a bump of the idle main feedwater 5.31.5 N/A and 1P-25B, and condensate pumps for iron flushing in 5.31.6 IF 1P-25B was started in Step 5.31.4.b, THEN OBSERVE 1FI-Condensate Pump accordance with Step 5.31. 3116B, 1HX-84B Cond Pump Motor Cooler Cooling Water Flow for 5 minutes for Ind, AND ADJUST 1CS-182B, 1P-25B-M Cond Pump Motor iron flushing. Expected Communications: Cooling Condensate Return To Suction, for 30 gpm to motor
[5.31.4] An AO is standing by to monitor pump bearing cooler.
Start: ________ start, reports as SAT following pump start. 5.31.7 ENSURE the following Prestart Checks for the idle Main
[5.31.6] 1CS-182B, 1P-25B-M Cond Pump Motor Feedwater Pump have been completed in accordance with OP Cooling Condensate Return To Suction has been 13A Unit 1, Secondary Systems Startup Unit 1:
adjusted for 30 gpm to motor bearing cooling. 5.31.8 N/A
[5.31.7] Prestart checks for the idle Main 5.31.9 IF 1P-28B is the idle Main Feedwater Pump, THEN ENSURE the Feedwater Pump have been completed. following are aligned as indicated:
[5.31.9] 1P-28B is aligned per Step 5.31.9. 5.31.10 Locally RECORD the following temperatures for the idle SGFP
[5.31.10] 1P-28B temperatures are as follows: and MARK remaining pump N/A:
1TI-3156B, Top Case Temp 294°F 5.31.11 POSITION the control switch for the idle SGFP to AUTO and OBSERVE its mini-recirc valve stroke full OPEN: MARK as N/A 1TI-3157B, Bottom Case Temp 302°F pump not selected.
1TI-2191 SGFP Discharge Temp 310°F
- b. 1P-28B-CS, 1P-28B Steam Generator Feed Pump Control
[5.31.14.b] 1FIC-2188, 1P-28B SGFP Suction Switch, paired with 1CS-2188, 1P-28B SGFP Mini Recirc Flow Indication Controller, is indicating properly.
Flow Control 5.31.12 START the Second Main Feed Pump and RECORD date/time and MARK step for pump NOT started N/A 5.31.13 N/A 5.31.14 IF 1P-28B was started, THEN PERFORM the following:
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE
[5.31.16] When directed to perform step, use 5.31.15 N/A LOA1CFW079 to stop 1P-73A. report actions 5.31.16 IF 1P-28B was started THEN PERFORM the following: (NOT completed SAT, and that oil pressure is normal MODELED) at 18 psig. 5.31.17 WHEN a minimum of 5 minutes of flushing is obtained on the train
[5.31.17.c] 1P-73B-CS, P-73B SGFP AC Lube of main feed and condensate, THEN DETERMINE main feed and Oil Pump Local Stl Station is ON. (Trigger 11) condensate train to be secured as follows:
[5.31.17.c.3)] Lowering suction flow at 1FI-2188, a. ENSURE 1PC-2273, Low Pressure Heater Bypass Pressure 1P-28B SGFP Suction Flow Indicator. Controller, SET to 190 psig
[5.31.17.c..6] MFP coastdown SAT b. N/A
[5.31.17.d.2)] 1P-25B, Condensate pump is c. IF 1P-28B, Steam Generator Feed Pump, will be STOPPED, stopped and not rotating backwards. THEN PERFORM the following:
- 2) SHUT 1CS-2189, 1P-28B SGFP Discharge MOV by positioning 1CS2189-CS, 1P-28B SGFP Discharge MOV control switch, to CLOSE.
- 3) MONITOR 1CS-2189 closure and decreasing suction flow at 1FI-2188, 1P-28B SGFP Suction Flow Indicator.
- 4) BEFORE 1CS-2189 reaches fully SHUT, THEN HOLD 1CS-2189-CS in CLOSE position.
- 6) STOP 1P-28B by positioning 1P-28B-CS, 1P-28B Steam Generator Feed Pump Control Switch, to STOP.
- 7) RELEASE 1CS-2189-CS.
- d. STOP a Condensate Pump
- 1) POSITION selected condensate pump control switch in PULLOUT. Remaining pump control switch may be marked N/A:
- 2) Locally ENSURE pump selected in STEP 5.3.17.d.1) has stopped (NOT rotating backwards)
- 3) RETURN condensate pump control switch in PULLOUT, to AUTO. Remaining pump control switch may be marked N/A:
5.31.18 NOTIFY Chemistry MFP / Cond pump bump is complete.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE 5.32 WHEN directed by Shift Management, THEN PLACE an additional feed train in service as follows:
Deferred to 50% - 60% power 5.33 Restriction For Continued Load Escalation 5.33.1 IF Step 5.27 was performed, THEN BEFORE continued load escalation, PERFORM the following:
- a. DETERMINE magnitude and rate of continued load escalation and RECORD below: (15%/hr)
- b. INITIATE notification of continued load escalation in accordance with NP 2.1.5, Electrical Communications, Switchyard Access and Work Planning.
5.33.2 WHEN power is approximately 35%, THEN CHECK the following indications:
5.34 Load Escalation 5.34.1 NOTIFY Turbine Hall Operator to monitor the following:
5.34.2 NOTIFY Primary Auxiliary Building (PAB) Operator, to PERFORM the following:
5.34.3 IF determined necessary by Operations Shift Management, THEN LOWER the PPCS constants for SG Blowdown Flow by 5 KLBS/hr.
5.34.4 IF required, THEN PLACE an additional Letdown Orifice in service.
5.35.1 IF Step 5.32 was performed, THEN ENSURE one hour has elapsed beyond the time recorded in Step 5.32.5.32.2.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 2: Raise power to 50% in accordance with OP 1C 5.35.2 WHEN Reactor Engineering activities are complete, THEN Raise power to Unit 1, Startup to Power Operation Unit 1. RESUME power escalation, observing any other required Reactor 50% in Engineering hold points.
accordance with 5.35.3 On 1C03, ENSURE 1DTIC-2525, T-23 HDT Differential OP 1C Unit 1, Expected Communication: SM Temperature Indicator Ctlr, is selected to AUTO Startup to Power If necessary, prompt the crew to continue 5.35.4 CONTINUE load escalation as follows:
Operation Unit 1. with the power ascension. a. ENSURE Governor Valves are off Valve Positon Limiter If requested, report that NP 2.1.5 (VPL)
Start: ________ notifications have been completed. b. MOVE Valve Position Limiter (VPL) to its desired position (e.g., 100% value)
Continuation Criteria: c. SELECT the desired EH Control System mode of Operation Once the crew has raised reactor power about 3% and MARK mode NOT selected N/A:
to 5%. Or at the discretion of the Lead Examiner, d. SHIFT to the selected rate recorded ins Step 5.33.1.a.
continue to the next event. 5.36 Continuous Action During Power Increase 5.36.1 MAINTAIN controls in AUTO as practicable 5.36.2 MAINTAIN Control Banks within the insertion, sequence, and overlap limits specified in the COLR. LCO 3.1.6 5.36.3 MAINTAIN Tavg within 1.5°F of Tref 5.36.4 ADJUST Power Range NIS as directed by 1-TS-RE-001, Power Level Determination Unit 1 5.36.5 MAINTAIN VARS OUT while keeping the null meter zeroed.
5.36.6 MAINTAIN the controller setpoint for the LP Feed Water Heater Bypass Valve (1CS-2273, LP FWH Bypass Press Controller) at 25 psig below SG Feed Pump suction pressure 5.36.7 MONITOR FWH/MSR high level alarms to check the dump valves control level 5.36.8 MONITOR Ice Melt operations as necessary.
5.36.9 IF required, THEN CONTINUE OPENING MSR Control Valves using manual operation of controller 1HX-2085 at the rate of less than or equal to 25°F per 30 minutes.
5.36.10 WHEN power is approximately 35%, THEN CHECK the following:
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 1 [XMT1SG001A, 1-FT464 LOOP A BOP Acknowledges alarms, identifies 1FT-464, 1HX-1A SG Steam Flow 1FT-464, 1HX-1A STEAM FLOW FIXED OUTPUT, RAMP Transmitter has failed to a higher value and references the ARPs.
SG Steam Flow = 00 :00 :20, VALUE = 2.0]
Transmitter fails Implements AOP-24, Response to Instrument Malfunctions high (no auto shift Insert Trigger 1 to cause 1FT-464, 1HX-1A SF 1. Identify Failed Instrument to single element) Steam Flow Transmitter to fail high (no auto shift to 2 Check If Failed Instrument Is A Controlling Channel single element. 3. Establish Manual Control As Required Start: _________ OS1 4. Return Affected Parameter(s) To Desired Value(s)
Plant Response: BOP 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE 1HX-1A Steam Generator level deviates bringing in REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is alarms for 1C03 1E2 1-2, Steam Generator A Level NOT An Input To RTO Setpoint Deviation / Trouble and 1C03 1E2 2-2, 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, Steam Generator A Feed Water Flow High. The ROUTINE MAINTENANCE PROCEDURE REMOVAL OF Steam Generator Water Level Control System - SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE level dominant system response then drives 7. Return Controls To Automatic If Desired affected steam generator level back to normal level. 8. Check Failure For Technical Specification Or TRM Applicability
- 9. Return To Procedure And Step In Effect Cues:
1C03 1E2 1-2, Steam Generator A Level Setpoint May implement AOP-2B, Feedwater System Malfunction Deviation / Trouble 1. Maintain Reactor Power Less Than Or Equal To 100%
1C03 1E2 3-2, Steam Generator A Feed Water 2. Determine The Secondary System Malfunction And Go To the Flow Channel Alert Appropriate Step 1FI-464 increasing to 2E6 PPH. OS1 12. Perform The Following For Feed Regulating Valves:
- a. Check Feed Regulating Valve Response - NORMAL Expected Communications: RNO None BOP a. Perform the following:
- 1) Place the affected feedwater regulating valve controller to The crew may elect to exercise the ARP to switch manual or single element control.
controlling channels prior to implementing 0-SOP- 2) Match feed flow to steam flow IC-001 Red, Routine Maintenance Procedure 3) Stabilize steam generator level.
Removal Of Safeguards Or Protection Sensor From 4) IF transient caused by instrument failure, THEN defeat failed Service - Red Channels. instrument per AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP Implements 0-SOP-IC-001 Red, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Red Channels Remove from Service NOTE: Steps 1 through 4 may be N/Ad if both transfer switches are already in WHITE.
- 1. PLACE Feedwater Regulating Valve in MANUAL:
FIC-466A, HX-1A Primary Flow Indicating Controller NOTE: Controlling channel will be FT-465.
- 2. PLACE SG A Steam Flow Control Transfer Switch to 465 (WHITE).
NOTE: Controlling change will be FT-467.
- 4. PLACE Feedwater Regulating Valve Controller in AUTO unless directed otherwise by Shift Management:
FIC-466A, HX-1A Primary Flow Indicating Controller
- 5. In cabinet C-112, PLACE the following bistable trip switches in the TRIP positon (toggle switch up) and CHECK expected response.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS Reference Technical Specifications Technical Specifications:
Table 3.3.1-1 item 14- D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 SF/FF Mismatch inoperable OR D.2 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Table 3.3.2-1 item 4d- D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 SLI-High Steam inoperable OR Flow D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Table 3.3.2-1 item D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4e-1 SLI-High Steam inoperable OR Flow D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS1 Implement ARP 1C03 1E2 3-2, Steam Generator A Feed Water Flow Once the crew has Channel Alert Switched controlling channels BOP 3.4 IF alarm is due to an instrument failure, THEN PERFORM the Placed the FRV in auto, AND following to select an operable control channel unless directed Addressed technical specifications otherwise by Shift Management:
or at the discretion of the Lead Examiner, continue 3.4.1 IF an of the following transmitters is failed, THEN with the next event. PERFORM Steps 3.4.1.a through 3.4.1.e:
1FT-464, Steam Flow Loop A
- a. IF 1PT-468, Steam Generator Pressure Loop A has failed, THEN ENSURE 1HC-468, SG A Atmospheric Steam Dump Controller in MANUAL.
- d. PLACE SG A Steam Flow Control Transfer Switch, to 465 (WHITE).
- e. PLACE 1FIC-466A, 1HX-1A Primary Flow Indicating Controller in AUTO unless directed otherwise by Shift Management.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 3 [XMT1MSS009A, 1-PT486 FIRST BOP Acknowledges alarm and references ARP 1C03 1E2 4-2, Tavg Steam 1PT-486, Turbine STAGE PRESSURE XMTR FIXED Dump Channel Alert.
First Stage OUTPUT, VALUE = 0, RAMP = 5 sec]
Pressure Implements ARP 1C03 1E2 4-2, Tavg Steam Dump Channel Alert Transmitter fails Insert Trigger 3 to cause 1PT-486, Turbine First 3.1 CHECK condition of steam dump system low Stage Pressure Transmitter to fail low. 3.2 CHECK to see if steam dump required, TavgTref with turbine runback or trip.
Plant Response: 3.3 IF the alarm is due to an instrument failure, AND it is desired to defeat Arms condenser steam dumps and alarms the failed channel, THEN PERFORM the following unless directed Start: __________ annunciator 1C03 1E2 4-2, Tavg Steam Dump otherwise by shift management:
Channel Alert. 3.3.1 PLACE the Condenser Steam Dump Controller 1HFC-484 in MANUAL, AND ENSURE controller output is ZERO on C03.
Cues: 3.3.2 PLACE the Steam Dump Mode Selector Switch in MANUAL 1C03 E2 4-2, Tavg Steam Dump Channel Alert on C03.
1PI-486, Turbine First Stage (STM DUMP) 3.3.3 PLACE the Condenser Steam Dump controller 1HFC-484 on Pressure Indicator reads 0 psig C03 in AUTO as follows, unless directed by Shift Management:
Expected Communications: a. LOWER the controller AUTO set point to 50 psig above IF and AO is dispatched to locally investigate the current Main Steam header pressure.
1PT-486, Turbine First Stage Pressure b. PLACE the controller in AUTO.
Transmitter, wait two minutes and THEN report c. RETURN the controller to the original AUTO set point.
that locally there doesnt seem to anything out of 3.4 REFERENCE AOP-6C, Uncontrolled Motion of RCCAs normal.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria: OS1 Implements AOP-24, Response to Instrument Malfunctions Once the crew has taken action per ARP and /or BOP 1. Identify Failed Instrument AOP-24 to address CSDs and addressed Technical 2 Check If Failed Instrument Is A Controlling Channel Specifications, or at the discretion of the Lead 3. Establish Manual Control As Required Examiner, continue with the next event. 4. Return Affected Parameter(s) To Desired Value(s)
- 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT An Input To RTO
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE
- 7. Return Controls To Automatic If Desired
- 8. Check Failure For Technical Specification Or TRM Applicability
- 9. Return To Procedure And Step In Effect OS1 Reference Technical Specifications Technical Specifications:
RPS LCO 3.3.1 is not met (3.3.1 item 17b-2)
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Enter the Condition Immediately Functions with one referenced in Table or more required 3.3.1-1 for the channels or trains channel(s) or inoperable. train(s).
S. One or more S.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel(s) required state for inoperable. existing conditions.
OR S.2 Be in MODE 2 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5: Trigger 5 [MAL1RCP001B, RCP#1 SEAL OATC Acknowledges alarms and identifies that 1P-1B, RCP is the affected 1P-1B, Reactor FAILURE PUMP B, RAMP = 00 :05 :00, pump based on alarms and available indications.
Coolant Pump VALUE = 5]
seal leak develops OS1 Implements AOP-1B, Reactor Coolant Pump Malfunction After the crew has stabilized the plant and has exited the applicable AOPs, insert Trigger 5 to OATC/BOP Monitors Fold out Page Start: __________ ramp in a ~5 gpm #1 seal leak on 1P-1B, Reactor 1. Check Annunciator P-1A&B RP VIBRATION ALARM - CLEAR Coolant Pump. 1C04 1C 1-5
- 2. Check Annunciator 1TR-2001 TEMPERATURE MONITOR ALARM Plant Response: - CLEAR Leak off flow will increase. Alarms for RCP No. 1 1C04 1C 3-10 Seal Water Flow High or Low, Lab Seal P Low, 3. Check Annunciator 1P-1A OER B RCP UPPER OR LOWER SUMP RCP Lab Seal Water or Bearing Temperature High OIL LEVEL HIGH OR LOW - CLEAR and RCP #1 RCP Seal Water Outlet Temperature 1C04 1D 3-11 High. The affected RCP seal and bearing 4. Check RCP No. 1 Seal Leakage - GREATER THAN 0.8 gpm temperatures increase. The seal outlet 5. Check RCP No. 1 Seal Leakage - LESS THAN 6 gpm temperatures increase. The seal P lowers or is 1FR-177 negative. RNO IF seal outlet temperature is rising, THEN go to Step 18.
o 1TI-182 for RCP B Cues: IF RCP No. 2 seal leakage greater than 2 gpm, THEN go to 1C03 1D 2-1, 1P-1A or B RCP Labyr Seal Delta Step 18.
P low o RCDT level change greater than 2% in 3 1/2 minutes.
1C03 1D 3-3, 1P-1B RCP No. 1 Seal Water Flow o Standpipe level high alarm High or Low o 1C03 1D 1-3 for RCP B
- 6. Verify RCP Seal Cooling:
- 1) Adjust seal injection throttle valves and charging flow control valve as necessary to establish a positive labyrinth seal P o 1CV-300B for RCP B o 1HC-142
- 2) IF positive labyrinth seal P can NOT be established AND component cooling water can NOT be maintained greater than 21 gpm, THEN go to Step 18.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: BOP b. Component cooling RCP thermal barrier - NORMAL IF the PAB AO is dispatched to monitor Unit 1 1) Thermal barrier outlet AOV - OPEN Reactor Coolant Drain Tank level; call up Instructor 1CC-761B for RCP B Station Drawing 1WPS1 and THEN report as 2) RCP Cooling water flow low alarm - CLEAR indicated. The change in RCDT level should 1C03 1D 1-5 for RCP B indicate a <1% change in 5 minutes. c. RCP component cooling return temperature alarm - CLEAR 1C03 1D 2-4 IF the PAB AO is directed to throttle 1CV-300B,
- 8. Check RCP No 2 Seal Indications - NORMAL coordinate with the Control Room and THEN make Annunciator 1P-1B RCP STANDPIPE LEVEL HIGH - CLEAR adjustments using LOA1CVC048, 1-CV-300B P-1B RCP SEAL INJ THROTTLE as directed. 1C03 1D 1-3 RCP No. 2 seal leakage - LESS THAN OR EQUAL TO 0.5 Continuation Criteria: gpm When the crew has completed Step 9 of AOP-1B RCP No. 1 seal leakage flow has remained stable Unit 1, Reactor Coolant Pump Malfunction, or at the o 1FR-175 discretion of the Lead Examiner continue with the o 1FR-177 next event. 9. Check RCP Seal Injection Temperatures - NORMAL Annunciator VCT TEMPERATURE HIGH - CLEAR 1C04 1C 3-7 VCT outlet temperature - LESS THAN 130°F 1TI-140
- 10. Determine RCP Seal Status:
RCP No. 1 and No. 2 combined seal leakage - BETWEEN 0.8 gpm AND 6 gpm RCP No. 2 seal leakage - LESS THAN 1.1 gpm RNO Perform the following
- a. Shutdown per OP-3A, POWER OPERATION TO HOT STANDBY Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5a: Trigger 7 [MAL1RCP001B, RCP#1 SEAL OATC/OS1 Recognizes degrading plant conditions and AOP-1B Unit 1, Foldout 1P-1B, Reactor FAILURE PUMP B, RAMP = 00 :05 :00, Page RCP trip criteria and goes to Step 18.
Coolant Pump seal VALUE = 300] o RCP No. 1 Seal leakage leak degrades o Greater than 6 gpm with seal water outlet temperature rising requiring a reactor Trigger 9 [MAL1RCS003F, RTD BYPASS LINE LEAK o Less than 0.8 gpm with seal water outlet temperature rising trip LOOP B COMMON, Value = 75]
OATC 18. Secure Affected RCP Start: _________ After the crew has completed Step 9 of AOP-1B a. Trip the reactor Unit 1, Reactor Coolant Pump Malfunction, insert Trigger 7 such that the seal leak degrades requiring NOTE: The pending ATWS will interrupt performance of Step 18 Event 6: Small a reactor trip. Trigger 9 will insert a RTD Bypass and should not be completed until exit of CSP-S.1 Unit 1, Break LOCA line leak (Small Break LOCA) when the reactor trip Response to Nuclear Power Generation / ATWS and return pushbuttons are depressed. to EOP-0 Unit 1, Reactor Trip or Safety Injection.
Plant Response: OATC/BOP b. Stabilize the plant using EOPs while continuing with this The affected RCP seal and bearing temperatures procedure increase. The seal outlet temperatures increase. c. Trip affected RCP The seal P lowers or is negative. Pressurizer d. Check at least one RCP running pressure and level begin to lower. e. Shut associated PZR normal spray valve Cues: o 1RC-431B for RCP B 1C03 1D 1-1, 1P-1A or B RCP Labyr Seal Water f. Check affected RCP has been tripped for 3 minutes Inlet or Bearing Temp High g. Shut affected RCP No. 1 seal water return MOV 1C03 1D 3-1, 1P-1A or B RCP No. 1 Seal Water o 1CV-270B for RCP B Outlet Temperature High h. Check RCP seal water bypass control valve shut 1C03 1D 4-1, 1P-1B RCP No. 1 Seal Delta P 1CV-386 Low 19. Return to Procedure And Step In Effect Rising 1P-1B, RCP seal inlet, outlet and bearing temperatures as indicated on 1TI-125 and 1TI-182.
Indications of a Small Break LOCA Expected Communications:
None Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE PRELOAD: [MAL1PPL001A, REACTOR TRIP Event 7: OS1 DIRECT a reactor trip BREAKER 52/RTA FAILURE, VALUE =
IMPLEMENTS EOP-0 Unit 1, Reactor Trip or Safety Injection Fails to Open]
Reactor fails to OATC 1. Verify Reactor Trip trip (ATWS) [MAL1PPL001B, REACTOR TRIP RNO: Manually trip reactor:
BREAKER 52/RTB FAILURE, VALUE = Train A Start: __________ Fails to Open]
Train B IF reactor power is greater than or equal to 5% OR Plant Response:
intermediate range SUR is positive, THEN Go to CSP-S.1 The reactor will not trip from the control room. The UNIT 1, RESPONSE TO NUCLEAR POWER GENERATION crew will have to take actions IAW CSP-S.1,
/ ATWS.
Subcriticality procedure and open the RTBs locally.
OS1 ENTER CSP-S.1, Response to Nuclear Power Generation / ATWS Cues:
RTBs NOT open OATC CT-52 Insert negative reactivity into the core PR NIs greater than 5%
- 1. Verify Reactor Trip Expected Communications: RNO: Manually trip reactor FOLLOWING the PA announcement for ATWS or IF reactor will NOT trip, THEN allow control rods to insert when directed to locally open the reactor trip automatically until rod speed is less than 36 breakers, allow 2 minutes for travel to the Rod Drive STEPS/MINUTE, THEN manually insert control rods Room and THEN report to the control room. WHEN 2. Verify Turbine Trip directed to open the Unit 1 reactor trip breakers change MAL1PPL001A and MAL1PPL001B to Trip Monitor Foldout Page Criteria:
and THEN report the reactor trip breakers are open
- 3. Verify AFW Pumps - RUNNING
- a. Motor-Driven Pump - RUNNING RNO: WHEN SI sequence is complete, THEN manually start motor-driven AFW pump.
- b. Turbine-Driven Pump - RUINNING RNO: Open both steam supply valves to turbine-driven AFW pump 1MS-2020 1MS-2019 Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP 4. Initiate Emergency Boration of RCS:
- 5. Check if the Following Trips have Occurred:
- a. Reactor - TRIPPED RNO: Dispatch operator to locally open trip and bypass breakers in rod control room.
- b. Turbine - TRIPPED
- 6. Check If Reactor is Subcritical:
- a. Power range channels - Less than 5%;
RNO: OBSERVE CAUTIONS PRIOR TO STEP 7. Go to Step 7
- b. Intermediate range channels - NEGATIVE STARTUP RATE RNO: OBSERVE CAUTIONS PRIOR TO STEP 7. Go to Step 7
- c. OBSERVE CAUTION PRIOR TO STEP 15. Go to Step 15 CAUTION: Boration should continue to obtain adequate OATC shutdown margin during subsequent actions.
- 15. Ensure Emergency Boration Is Proper For Current Plant Conditions
- 16. Return To Procedure And Step In Effect BOP Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 8: PRELOAD: [MOT1SIS001, 1-P15A SAFETY OS1 Implements EOP-0, Unit 1 Reactor Trip or Safety Injection Safety Injection INJECTION PUMP, Winding Ground] OATC 1. Verify Reactor Trip Pump failures: [BKR1SIS002, 1-A5285 P-15B 2. Verify Turbine Trip 1P-15A, Safety SAFETY INJ PUMP CKTBKR, 3. Verify Power to AC Safeguards Buses Injection pump Failautocl] 4. Check if SI is Actuated trips upon a. Any SI annunciators LIT starting and 1P- b. Both trains of SI - Actuated 15B, Safety Expected Communications: RNO: Manually actuate both trains of SI and CI Injection pump IF an AO is dispatched to locally investigate 1P- BOP fails to auto start 15A, Safety Injection pump, wait 2 minutes and NOTE: Following immediate actions, CREW may manually start a THEN report that the motor is hot to the touch Safety Injection Pump in accordance with OM 3.7, AOP and there is a faint acrid smell in the area. There And EOP Procedure Usage For Response To Plant is no fire. Transients.
IF an AO is dispatched to locally investigate NOTE: The ATWS interrupted performance of AOP-1B Unit 1.
breaker 1A52-59, Pwr to 1P-15A, Safety Step 18 and should now be completed upon the return to Injection Pump, wait 2 minutes and THEN report EOP-0 Unit 1, Reactor Trip or Safety Injection.
the breaker has tripped.
Monitor Foldout Page Criteria: RCP Trip Criteria IF both conditions listed below occur, THEN trip both RCPs:
RCS subcooling - LESS THAN [36 ºF] 26 ºF SI Pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW BOP 5. Perform ATTACHMENT A, Automatic Action Verification while OATC continuing with this procedure
- 6. Verify AFW pumps - Running
- 7. Check RCP Seal Cooling
- 8. Check RCS Temperatures
- 9. Check PZR PORVs and Spray Valves
- 10. Check if RCPs should be stopped
- 11. Check if SGs are NOT Faulted
- 12. Check if SG Tubes are NOT Ruptured
- 13. Check if RCS is Intact RNO: Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service Water valves, LW-61 and 62, THEN report both CT-6, Establish flow from at least one high-head SI pump valves are closed.
WHEN directed to locally check CW pump house A3 Verify ECCS Pumps RUNNING temperature <105 ºF, wait 3 minutes and THEN a. SI Pumps - BOTH RUNNING report the temperature is 72 ºF and stable. RNO WHEN SI sequence is complete, THEN manually start WHEN directed to locally check G03/G04 SI pumps Switchgear Room temperature <95 ºF, wait 3 b. RHR Pumps - BOTH RUNNING minutes and THEN report the temperature is 75 ºF A4 Verify Service Water Pumps RUNNING and stable. A5 Verify Containment Accident Cooling Units RUNNING IF directed to periodically check the status of A6 Verify Component Cooling Water Pumps - ONLY ONE RUNNING spent fuel cooling, wait 5 minutes and THEN A7 Check If Main Steam Lines Can Remain Open A8 Verify Containment Spray Not required report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable. a. Containment pressure recorder - HAS REMAINED LESS THAN 25 psig A9 Verify ECCS Flow A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 Verify Proper ECCS Valve Alignment A12 Check Containment Spray NOT ACTUATED A13 Stop any boration via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OS1 Implements EOP-1 Unit 1, Loss of Reactor or Secondary Coolant BOP 1. Check If RCPs Should Be Stopped Termination Criteria: 2. Check If SGs Are NOT Faulted Terminate the scenario when crew has completed 3. Check Intact SG Level Step 13 of EOP-1 Unit 1, Loss of Reactor or 4. Check Secondary Radiation Secondary Coolant or at the discretion of the Lead 5. Check PZR PORV and Block Valves Examiner. 6. Reset SI
- 7. Reset Isolation and Lockout Signals
- 8. Establish Instrument Air to Containment
- b. Open instrument air containment isolation valves one at a time 1IA-2047 1IA-3048
- 9. Check Power Supply To Charging Pumps
- 10. Check If Charging Flow Has Been Established
- 11. Check If ECCS Flow Should Be Terminated RNO: Go to Step 12.
- 12. Check If Containment Spray Should Be Stopped
- 13. Check If RHR Pumps Should Be Stopped
- a. Check RCS pressure
- 1) Pressure - GREATER THAN [450 PSIG] 325 PSIG
- 2) Pressure - STABLE OR RISING RNO: Go to Step 14
- END OF SCENARIO ***
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
- 1PT-486, Turbine First Stage Pressure Transmitter fails low
Small Break LOCA from RTD By-pass Line Reactor fails to trip (ATWS)
Safety Injection Pump failures 1P-15A, Safety Injection pump trips upon starting 1P-15B, Safety Injection pump fails to auto start Abnormal Events:
- 1PT-486, Turbine First Stage Pressure Transmitter fails low
- 1P-1A, Reactor Coolant Pump seal leak Major Transients:
Small Break LOCA ATWS Critical Tasks:
- 1. CT-6 Establish flow from at least one high-head SI pump
- 2. CT-52 Insert negative reactivity into the core Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG CT-6 Establish flow from at least one high-head SI pump Applicable ERG LP Version Applicable ERG E-0, ECA-0.2 Critical Task:
Establish flow from at least one Safety Injection pump before transition out of E-0 Plant Conditions:
Reactor trip SI Small-break LOCA RCS pressure below high-head ECCS pumps shutoff head LP Plants:
- Both Safety Injection pumps fail to start automatically
- At least one SI pump can be started provided that manual action is taken as necessary Cues:
Indication and/or annunciation that SI pump injection is required
- SI actuation
- RCS pressure below the shutoff head of the SI pump AND Indication and/or annunciation that no SI pump is injecting into the core
- Control switch indication that the circuit breaker or contactors for both SI pumps are open
- All SI pump discharge pressure reads zero
- All flow rate indicators for SI pump injection read zero Performance Indicator:
Manipulation of controls as required to establish flow from at least one SI pump Control switch indication that the circuit breaker or contactor for at least one SI pump Flow rate indication of injection from at least one SI pump Feedback:
Indication and/or annunciation that at least one SI pump is injecting Flow rate indication of injection from at least one SI pump Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 35
PBN LOI NRC 16E, 2017 NRC Exam Scenario 2, Rev. 0 SEG CT-52 Insert negative reactivity into the core Applicable ERG LP Version Applicable ERG FR-S.1 Critical Task:
Insert negative reactivity into the core by inserting control rods prior to completion of immediate actions.
Plant Conditions:
ATWS (Indication exists that the reactor is not tripped and that a manual reactor trip is not effective.)
Cues:
Indication of ATWS AND Indication that the reactor is not tripped and that a manual reactor trip is not effective Performance Indicator:
Manipulation of controls in the control room as required to initiate the insertion of negative reactivity into the core For scenarios in which it is possible for the crew to insert control rods:
- Group and individual rod position indication systems show control rods moving inward
- Control rod banks sequentially reach core bottom (unless RTBs opened locally)
Feedback:
Indication of a negative SUR on the intermediate range of the excore NIS Indication of less than 5% power on the power range of the excore NIS Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 35
TURNOVER INFORMATION SEG 1.0 Plant Conditions:
Unit 1 Unit 2 Time in Core Life (MWD/MTU): 1005 Reactor Power: 28%
Boron Concentration: 1874 ppm Rod Height: CBD @ 151 2.0 Equipment Out of Service:
1PT-950, Loop B Containment Pressure has been removed from service. Repairs are expected to be complete during the upcoming refueling outage.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:
LCO NOT Met TSAC Required Actions Completion Time 3.3.2 A. One or more Functions with one A.1 Enter the Condition referenced in Immediately or more channels or trains Table 3.3.2-1 for the channel(s) or inoperable. train(s).
D. One channel inoperable D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 4.0 Planned Evolutions:
Normal Shift routine will be to bump main feed and condensate pumps for iron flushing and raise power to 50% utilizing OP-1C Unit 1, Startup to Power Operation Unit 1.
5.0 Common
Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.
Filename: NRC Scenario 2 draft.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 35
SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 17E LMS Rev. Date:
SEG TITLE: 2017 NRC Exam Scenario 3 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner (Line) Date Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _3___________ Op-Test No.: _2017____
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Unit 1 was lowered to approximately 75% at the request of MISO/ATC due to grid stability issues. Grid stability has been restored and the unit is ready to be returned to full power in__
accordance with OP 1C, Startup to Power Operations. 1P-2B, Charging Pump is OOS and isolated _
per OI 50, Charging Pump Isolation for pump repairs. 1W-3B, Control Rod Shroud Fan is OOS due_
to imminent motor failure. 1PT-950, Loop B Containment Pressure has been removed from service._
Repairs are expected to be complete during the upcoming refueling outage. ____________________
Turnover: Commence raising power to 100% _
Event Malf. No. Event Event No. Type* Description C-BOP C-SRO P-32A, Service Water Pump trip with reduced head capacity on two 1 BKR1SWS001 running SW pumps TS-SRO C-BOP 1RE-219, SG Blowdown Monitor fails high off scale 2 XMT1RMS076A C-SRO 1MS-2083, HX-1A SG Sample Isolation Control Valve fails open R-RO N-BOP 3 MAL1RCS008A SG A Tube Leak approximately 10 gpm (rapid down power)
R-SRO TS-SRO C-BOP C-SRO Running CCW Pump seal leak, lowering surge tank 4 MAL1CCW002A (Pumps need to be shifted)
TS-SRO 5 MAL1GEN006 M-ALL Voltage Regulator Trouble leading to a Main Generator Lockout MALCRF001-B6 MALCRF001-B8 6 MALCRF001-C5 C-RO Multiple (4) Stuck Rods post trip MALCRF001-E11 7 MAL1RCS008A C-RO SGTL turns into SGTR CNH1PCS007B 8 CNH1PCS008B C-RO Spray valves fail causing use of the PORV for RCS depressurization
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to the failures listed below in accordance with plant procedures:
P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D.
1HX-1A, SG tube leak of approximately 10 gpm.
1RE-219, SG Blowdown Monitors fails high off-scale with no change in leak rate of 1HX-1A SG.
1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close.
The mechanical pump seal for 1P-11A, Component Cooling Water Pump begins leaking at an increased rate that causes a lowering CCW Surge Tank level.
Main Turbine Generator Voltage Regulator Trouble results in Main Generator Lockout and reactor trip Multiple stuck rods post trip 1HX-1A SG tube leak increases in size to a steam generator tube rupture 1RC-431A and B, PZR Spray Valves fail closed.
Embedded within these events is the expectation to properly utilize Technical Specifications.
Enabling None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG
References:
- 1. AOP-3 Unit 1, Steam Generator Tube Leak
- 2. AOP-9A, Service Water System Malfunction
- 3. AOP-9B Unit 1, Component Cooling System Malfunction
- 4. AOP-17A Unit 1, Rapid Power Reduction
- 6. EOP-0 Unit 1, Reactor Trip Or Safety Injection
- 7. EOP-0.1 Unit 1, Reactor Trip Response
- 8. EOP-3 Unit 1, Steam Generator Tube Rupture
- 9. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients
- 10. OP 1C, Startup To Power Operation Unit 1
- 11. RMSARB CI 1RE-219
- 12. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021 Rev. 9.
Operating N/A Experience:
Risk Significant HEP-ODC-EOP3-21, Operator fails to cooldown and depressurized the Operator Actions: intact SG (SGTR). [FV: 7.19E-05]
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Insert brief description of what will occur during this simulator exercise.
1P-2B, Charging Pump, is out of service for mechanical seal replacement. Work is expected to take another 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1PT-950, Loop B Containment Pressure has been removed from service. Repairs are expected to be complete during the upcoming refueling outage.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
Unit 1 was lowered to approximately 75% at the request of MISO/ATC due to grid stability issues. Grid stability has been restored and the unit is ready to be returned to full power in accordance with OP 1C, Startup to Power Operations.
Commence raising power to 100%.
Events P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D.
1RE-219, SG Blowdown Monitors fails high off-scale with no change in leak rate of 1HX-1A SG.
1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close.
1HX-1A, SG tube leak of approximately 10 gpm.
The mechanical pump seal for 1P-11A, Component Cooling Water Pump begins leaking at an increased rate that causes a lowering CCW Surge Tank level.
Main Turbine Generator Voltage Regulator Trouble results in Main Generator Lockout and reactor trip Multiple stuck rods post trip 1HX-1A SG tube leak increases in size to a steam generator tube rupture 1RC-431A and B, PZR Spray Valves fail closed.
Insert brief description of termination criteria.
When the crew has stopped SI pumps and taken appropriate action(s) per step 30 of EOP-3 Unit 1, Steam Generator Tube Rupture, then verify with the Lead Evaluator, freeze the simulator, and take the shift.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description
- 1. P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D The crew may start an idle SW pump to clear the low flow alarm.
The crew should respond by implementing AOP-9A, Service Water System Malfunction and referring to Technical Specifications.
- 2. 1RE-219, SG Blowdown Monitor fails high off-scale with no change in leak rate of 1HX-1A SG. 1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close.
The crew should reference the RMSARB CI RE219 and take actions to align equipment that did not automatically reposition.
The crew should implement AOP-3 Unit 1, Steam Generator Tube Rupture, determine a leak rate and reference Technical Specifications.
The crew should make preparations to reduce load in accordance with OP 3A Unit 1, Power Operation to Hot Standby Unit 1 or AOP-17A Unit 1, Rapid Power Reduction.
- 4. The mechanical pump seal for 1P-11A, Component Cooling Water Pump begins leaking at an increased rate that causes a lowering CCW Surge Tank level.
The crew should manually start 1P-11B, Component Cooling Water Pump, secure 1P-11A, implement AOP-9B Unit 1, Component Cooling System Malfunction and refer to Technical Specifications
- 5. Main Turbine Generator Voltage Regulator Trouble results in Main Generator Lockout and reactor trip Initially the crew should dispatch an Auxiliary Operator to investigate local alarms.
Once the unit has tripped the crew should respond by implementing EOP-0 Unit 1, Reactor Trip or Safety Injection and EOP-0.1 Unit 1, Reactor Trip Response.
- 6. Multiple stuck rods post trip The crew should borate in accordance with EOP-0.1 Unit 1, Reactor Trip Response.
- 7. 1HX-1A SG tube leak increases in size to a steam generator tube rupture After addressing the stuck rods EOP-0.1 Unit 1, plant conditions degrade necessitating a safety injection and return to EOP-0 Unit 1, Step 4 per the Foldout Page Criteria in EOP-0.1 Unit 1.
The crew will then transition for EOP-0 Unit 1 to EOP-3 Unit 1, Steam Generator Tube Rupture to isolate the ruptured generator and cooldown/depressurize the unit to minimize primary to secondary coolant leakage.
- 8. 1RC-431A and B, PZR Spray Valves fail closed.
Unavailable normal spray will require the crew to use a PORV during the depressurization phase of EOP-3 Unit 1 in order to effectively reduce RCS pressure.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG STOP Terminate the scenario when the crew has stopped SI pumps and taken appropriate action(s) per step 30 of EOP-3 Unit 1,Steam Generator Tube Rupture.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
General Instructions Simulator Setup Instructions:
Load IC-4 and go to run Open the saved Event and Schedule files from the secure drive:
Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)
Reposition bistable switches for: 1PT-950, Loop B Containment Pressure Transmitter Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:
Load saved IC and go to run Open the saved Event and Schedule files:
Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:
SETUP Unit 1 was lowered to approximately 75%, ready to be returned to full power. OOS: 1P-2B, 1W-3B, 1PT-950 MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-B5213B P-2B Fail BKR1CVC006 CHARGING - - - `- - Cont Preload PUMP CKTBKR Fuse 1-PT950 LOOP B CONT XMT1CNM017A PRESSURE 00 :00 :00 - 90 Preload XMTR FIXED OUTPUT Simulator set-up:
- 2. OOS-Maint magnet om 1P-2B
- 3. Orange Guarded magnets on 1P-2A and C
- 4. Place OOS magnet at PT-950, Containment Pressure
- 5. Place a RED dot on C01 B 1-5, U1 Containment Pressure Channel Alert
- 7. Install an orange Guarded magnet at 1W-3A.
SIMULATOR MALFUNCTIONS:
Event 1: P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-B5210C P-32A SERVICE BKR1SWS001 00 :00 :00 - 1 00 :00 :00 - Trip PLE WATER PUMP CKTBKR 0-P32B SERVICE PMP1SWS002C WATER PUMP B 00 :00 :00 - 1 00 :00 :00 - 90 PLE HEAD CAPACITY 0-P32D SERVICE PMP1SWS004C WATER PUMP D 00 :00 :00 - 1 00 :00 :00 - 90 PLE HEAD CAPACITY SW-10 P32A SW When directed by the LOA1SWS001 00 :00 :00 00 :00 :30 3 00 :00 :00 1.0 0 PUMP DISCH crew 1C-068A/C-068B When directed by the LOA1CWS023 LOCAL PANEL 00 :00 :00 - 5 00 :00 :00 FALSE TRUE crew ALARM RESET 2C-069A/C-069B When directed by the LOA2CWS023 LOCAL PANEL 00 :00 :05 - 5 00 :00 :00 FALSE TRUE crew ALARM RESET Expected field communications:
- 1. IF an AO is dispatched to locally investigate P-32A, Service Water Pump, wait two minutes and THEN report that the pump is not running and the motor is hot to the touch.
- 2. IF an AO is dispatched to locally investigate breaker 1B52-10C, Power to P-32A Service Water Pump, wait two minutes and THEN report that breaker has tripped on overcurrent.
- 3. WHEN directed to locally shut SW-10, P-32A Service Water Discharge Isolation, insert Trigger 3 and THEN report when the valve has repositioned.
- 4. IF directed to reset the local control panel alarms for Circ Pumps Cooling Water Flow Low, THEN insert Trigger 5 and report when the panel alarms have been reset.
- 5. IF directed to check power to RK31 and RK32, THEN report power is available to RK31 and RK32.
- 6. IF asked, report SW zurn strainer D/P is normal.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Event 2: 1RE-219, SG Blowdown Monitors fails high off-scale with no change in leak rate of 1HX-1A SG. 1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close.
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-RE219 SG BLOWDOWN XMT1RMS076A 00 :00 :00 00 :00 :05 11 00 :00 :00 400 1.0E+006 PLE LIQUID RM FIXED OUTPUT 1-MS-2083 STM GEN 1A SAMP VLV1NSS001 00:00 :00 - - 00 :00 :00 - Open PRELOAD ISOL VLV 1-V2083 1-MS-2083 STM When 1MS-2083 is taken GEN 1A SAMP 13 Delete VLV1NSS001 00 :00 :00 - - Closed to close ISOL VLV 1- Cond. Malf Cond. = [x01i126c==1]
V2083 Expected field communications:
- 1. IF RP is directed to take Unit 1 main steam line surveys, wait 5 minutes and THEN report that both Unit 1A and B main steam lines read background.
Event 3: 1HX-1A, SG tube leak of approximately 10 gpm MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE STEAM MAL1RCS008A GENERATOR A 00 :00 :00 00 :00 :00 7 00 :00 :00 0 0.035 PLE TUBE RUPTURE 1-P99A SFP SEAL WATER When directed by the LOA1CFW083 00 :00 :00 - 9 00 :00 :00 AUTO ON INJECT PUMP crew C.S.
1-P99B SGFP SEAL WATER When directed by the LOA1CFW084 00 :00 :05 - 9 00 :00 :05 AUTO ON INJECT PUMP crew C.S.
Expected field communications:
- 1. IF RP is requested to perform steam line surveys, THEN wait 5 minutes and report:
'A' main steam line is 5 mrem above background.
'B' main steam line is at background.
- 2. WHEN directed to start 1P-99A and 1P-99B SGFP Seal Water Injection Pumps, insert Trigger 9 and THEN report when they are started.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Event 4: The mechanical pump seal for 1P-11A, Component Cooling Water Pump begins leaking at an increased rate that causes a lowering CCW Surge Tank level.
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE MAL1CCW002A CCW PUMP 11A 00 :00 :00 00 :00 :00 15 00 :00 :00 - 1 PLE SEAL FAILURE 1C03 1D 3-6: 1T-12 CC Surge Tank Level High or Low 20 gal/%
LOA1CCW031 1-CC-773 T-12 00 :00 :00 00 :00 :30 17 00 :00 :00 - OPEN When directed by the CC SURGE TNK crew.
DEMN WTR INLT CLOSE when directed by the crew or adequate level.
LOA1CCW002 1-CC-723A CC 00 :01 :00 00 :00 :30 19 00 :00 :00 - 0 When directed by the P-11A SUCTION crew.
VALVE LOA1CCW004 1-CC-725A CC 00 :01 :30 00: 01:00 19 00 :00 :00 - 0 When directed by the P-11A crew.
DISCHARGE VALVE Expected field communications:
- 1. WHEN an AO is dispatched to locally investigate, THEN wait two minutes and report that there is excessive seal leakage coming from 1P-11A, CCW pump recommends immediately securing the pump. RP is in the area controlling the leakage.
- 2. IF an AO is directed to locally makeup to 1T-12 CC Surge Tank by cycling 1CC-773, Component Cooling Surge Tank Demin Water Inlet, THEN cycle open/close 1CC-773 to maintain tank level between 20% and 60%.
- 3. IF the crew directs the AO to locally isolate 1P-11A, Component Cooling Water Pump, THEN insert TRIGGER 19 and report when the valves are repositioned and the seal leak has subsided.
Event 5: Main Turbine Generator Voltage Regulator trouble results in Main Generator Lockout and reactor trip MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE VOLTAGE MAL1GEN006 REGULATOR 00 :00 :00 00 :15 :00 21 00 :00 :00 19.499 25 PLE FAILURE U1 VRC RG AUTO POSITON UNIT 1 OVR-GEN045C 00 :00 :01 - 21 00 :00 :00 - TRUE VOLTAGE REGULATOR CS U1 VRC RG MAN POSITON UNIT 1 OVR-GEN045A - - - - - FALSE PRELOAD VOLTAGE REGULATOR CS Expected field communications:
- 1. IF an AO is dispatched to 1E02 to check local annunciator panel ANN2 (on Voltage Regulator Panel), wait two minutes and THEN report that the alarm is HXL is Limiting.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Event 6: Multiple stuck rods post trip MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE Non-MAL1CRF001-B6 STUCK ROD B6 00 :00 :00 - - 00 :00 :00 - Trippable PRELOAD Non-MAL1CRF001-B8 STUCK ROD B8 00 :00 :00 - - 00 :00 :00 - Trippable PRELOAD MAL1CRF001- Non-STUCK ROD C5 00 :00 :00 - - 00 :00 :00 - Trippable PRELOAD C5 MAL1CRF001- STUCK ROD Non-00 :00 :00 - 00 :00 :00 - Trippable PRELOAD E11 E11 Expected field communications:
- 1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.
- 2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.
- 3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.
- 4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.
Event 7: 1HX-1A SG tube leak increases in size to a steam generator tube rupture MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE STEAM MAL1RCS008A GENERATOR A 00 :00 :00 00 :00 :00 23 00 :00 :00 0 0.4 PLE TUBE RUPTURE 1-MS-235 P-29 AFP & When directed by the LOA1SGN023 00 :00 :00 00 :00 :00 25 00 :00 :00 1.0 0 RADWASTE crew.
STM ISOL Expected field communications:
- 1. WHEN directed to shut 1MS-235, AFP Radwaste Steam Isolation and 1MS-228, Main Steam Trap Header Isolation, wait 5 minutes THEN insert Trigger 25 and report when the valves are closed.
Event 8: 1RC-431B, PZR Spray Valve B Loop fails closed.
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-HC431H 1-PCV431B SPRAY VALVE CNH1PCS008B 00 :00 :00 00 :00 :00 23 00 :00 :00 - 0 PLE HAND CTLR FIXED AUTO/MAN 1-HC431C 1-PCV431A SPRAY VALVE CNH1PCS007B 00 :00 :00 00 :00 :00 23 00 :00 :00 - 0 PLE HAND CTLR FIXED AUTO/MAN Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Expected field communications:
- 1. None Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.
Crew Shift Turnover Information: See Attached Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Commence Unit 1 was lowered to approximately 75% at the CREW Implements OP 1C, Startup to Power Operation Unit 1, at Step 5.44, raising power to request of MISO/ATC due to grid stability issues. Power Level At Between 75% And 85% Requirements 100% Grid stability has been restored and the unit is ready to be returned to full power in accordance Start: ________ with OP 1C, Startup to Power Operations.
Commence raising power to 100%.
Expected Communications:
None Note: The crew should take action to prepare the power ascension, but they may not actually initiate the power change.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 1: Trigger 1 [BKR1SWS001, 1-B5210C P-32A SERVICE BOP Identifies the event by low SW header pressure, loss of P-32A SW P-32A, Service WATER PUMP CKTBKR, VALUE = TRIP] Pump. Starts additional SW pumps to restore pressure to >50 psig.
Water Pump trips [PMP1SWS002C, 0-P32B SERVICE WATER Dispatches operators to walk down the system for potential leaks.
with reduced head PUMP B HEAD CAPACITY, VALUE = 90]
[PMP1SWS004C, 0-P32D SERVICE WATER capacity on P-32B OS1 Implements AOP-9A, Service Water System Malfunction PUMP D HEAD CAPACITY, VALUE = 90]
and P-32D BOP 1. Check Forebay Level - GREATER THAN -11.5 FEET
- 2. Check Pumpbay Level - GREATER THAN -11.5 FEET After completion of crew turnover and the examinees have assumed the watch, insert Trigger 3. Check Annunciator Traveling Screen Differential Level High Alarm -
Start: _________ CLEAR 1 to cause P-32A, Service Water Pump to trip with
- 4. Check North or South Service Water Header Pressure Low Alarm -
reduced head capacity on P-32B and P-32D.
Clear Plant Response: a. Start service water pumps - MAINTAIN PRESSURE BETWEEN 50 PSIG AND 90 PSIG This malfunction causes indicated North and South
- d. IF Any Service Water Pumps Tripped OR Recently Stopped, Service Water pressures to lower and brings in the THEN ensure affected pump is in pullout and locally shut corresponding North or South Service Water associated pump discharge valve Header Pressure Low Alarm.
o SW-10 for P-32A Cues: e. Go to Step 9
- 9. Notify Duty Station Manager and Enters Applicable TSACs Indicated North and South Service Water 10. Check if Emergency Plan Should be Implemented per EPIP 1.2, pressures lower Emergency Classification Annunciators include: 11. Check Supply Header Integrity C01A 3-5, North or South Service Water 12. Check Zurn Strainer - Normal header Pressure Low 13. Ensure Service Water Header Valves - OPEN
- 14. Check Component Alarms - Clear C01 B 3-4, U1 Motor Breaker Trip
- 15. OBSERVE NOTE PRIOR TO STEP 1 and Return to Step 1 Repeat steps 1-4
- 5. Check Zurn Strainer - NORMAL
- 6. Check component alarms - CLEAR
- 7. Check Service Water System - INTACT
- 8. Return to Procedure And Step In Effect Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: Reference Technical Specifications IF an AO is dispatched to locally investigate P- Technical Specifications:
32A, Service Water Pump, wait two minutes and THEN report that the pump is not running and the SW System TLCO 3.7.7.D is not met - one SW pump inoperable and motor is hot to the touch. requirements of Table 3.7.7-2 not met.
IF an AO is dispatched to locally investigate breaker 1B52-10C, Power to P-32A Service Water LCO 3.7.8, Service Water System is not met.
Pump, wait two minutes and THEN report that CONDITION REQURIED ACTION COMPLETION TIME breaker has tripped on overcurrent.
WHEN directed to locally shut SW-10, P-32A Service Water Discharge Isolation, insert Trigger A. One SW pump A.1 Restore SW 7 days 3 and THEN report when the valve has inoperable pump to OPERABLE AND repositioned. AND IF directed to check power to RK31 and RK32, status. 14 days from THEN report power is available to RK31 and Both units in discovery of failure to RK32. MODE 1, 2, meet the LCO IF asked, report SW zurn strainer D/P is normal. 3, or 4.
IF directed to reset the local control panel alarms for Circ Pumps Cooling Water Flow Low, THEN insert Trigger 5 and report when the panel alarms have been reset.
Continuation Criteria:
Once the crew has completed the actions of AOP-9A, Service Water Malfunction and addressed Technical Specifications, or at the discretion of the Lead Examiner, continue with the next event.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 2: Trigger 11 [XMT1RMS076A, 1-RE219 SG OATC Acknowledges annunciator 1C20 C 3-2, Unit 1 SG Blowdown Radiation 1RE-219, SG BLOWDOWN LIQUID RM FIXED OUTPUT, High, references applicable ARB and RMSASRB CI 1RE-219.
Blowdown VALUE =1.0e+006, RAMP = 5 SEC]
Monitors fails OS1 Implements ARB 1C20 C 3-2, Unit 1 SG Blowdown Radiation High high off-scale. Insert Trigger 11 to cause 1RE-219, SG Blowdown OATC/BOP 6.1 Follow actions specified in the Radiation Monitoring System Alarm Sample Isolation Monitors to fail high off-scale with no change in leak Setpoint and Response Book (RMSARB) for SG blowdown monitor Control Valve fails rate of 1HX-1A SG. 1MS-2083, 1HX-1A SG Sample 1RE-219.
to auto close. Isolation Control Valve will fail to auto close. 6.2 Refer to EPIPs for potential classification issues.
7.1 High alarm automatically shuts Plant Response: 7.1.1 MS-5958, A SG blowdown isolation Start: __________ High Alarm 1C20 C 3-2, Unit 1 SG Blowdown 7.1.2 MS-5959, B SG blowdown isolation Radiation High automatically shuts. 7.1.3 MS-2040, SG blowdown tank outlet MS-5958, A SG blowdown isolation 7.1.4 MS-2083, A SG sample isolation MS-5959, B SG blowdown isolation 7.1.5 MS-2084, B SG sample isolation MS-2083, A SG sample isolation (fails) OS1/OATC Implements RMSARB CI 1RE-219 MS-2084, B SG sample isolation 1. Ensure the following valves are shut MS-2040, Blowdown Tank Outlet Cont Vlv a) MS-5958, 1HX-1A SG Blowdown Isolation b) MS-5959, 1HX-1B SG Blowdown Isolation Cues: c) MS-2040, SG Blowdown Tank Outlet Control 1C20 C-3-2, Unit 1 SG Blowdown Radiation d) MS-2083, 1HX-1A SG Sample Isolation Control High e) MS-2084, 1HX-1B SG Sample Isolation Control
- 2. Compare channel to available redundant indication:
Expected Communications: a) 1RE-222, Unit 1 steam generator blowdown tank radiation alarm b) 1RE-215, Unit 1 air ejector radiation alarm IF RP is directed to take Unit 1 main steam line c) RE-225, Combined air ejector radiation alarm surveys, wait 5 minutes and THEN report that d) 1RE-231, Unit 1 steam line A radiation alarm both Unit 1A and B main steam lines read e) 1RE-232, Unit 1 steam line B radiation alarm background.
f) 1RE-229, Unit 1 service water overboard radiation alarm.
- 3. Refer to appropriate AOP:
a) AOP-1A Unit 1, Reactor Coolant Leak b) AOP-3 Unit 1, Steam Generator Tube Leak c) AOP-4A Unit 1, High Effluent Activity
- 4. Refer to CTS 15.3.1.D.4 {ITS 3.4.13}
- 5. IF the High Alarm is received, AND the cause is other than known testing or know movements of radioactive materials through the area, THEN NOTIFY RP Supervision (Duty & Cal, if off normal hours).
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Failure Alarm (Minimum operable channels per RECM Table 3-1, Operator Response:
Radioactive Liquid Effluent Monitoring Instrumentation Refer to generic response section. If this channel becomes inoperable, are met.) refer to the Radiological Effluent Control Manual (RECM)
Continuation Criteria: IF this channel becomes INOPERABLE, AND redundant RMS channels Once 1MS-2083, 1HX-1A SG Sample Isolation are OOS (i.e., RE-225, RE-215, or RE-231/232), THEN a Priority 2 work Control Valve is shut and the crew has addressed order shall be written to restore RMS for primary to secondary leakage the ARB and RMSASRB actions for 1RE-219, or at monitoring AND NP 3.2.4 referenced.
the discretion of the Lead Examiner, continue with the next event. Generic RMS Alarm Response Guidelines 2.1 Check on system Server, SS, to see if the alarm is HIGH or FAIL. If alarm is HIGH:
2.1.1 IF the HIGH Alarm is received, AND the cause is other than known testing or known movements of radioactive materials through the area, THEN NOTIFY RP supervision (Duty & Call, if off normal hours).
2.1.2 See alert responses.
2.1.3 If HiGH alarm is from an area monitor, ensure that affected areas are properly posted per RP procedures.
2.1.4 If HIGH alarm is from a process monitor with a control function:
a) Check that the control function has actuated, e.g.,
discharge valve shuts, ventilation dampers shifts, etc.
b) If control function has not actuated, initiate the control function manually. Identify the problem and correct it prior to attempting to return the channel to normal operation.
2.1.5 If the HIGH alarm is from a process monitor without a control function: identify the cause of the alarm.
2.1.6 Effluent pathways that have a monitor above its Alert alarm setpoint for at least one ten minute period should be sampled to determine Emergency Plan initiation/classification based on NUUREG 1022 reporting requirements. Ensure samples are collected at the time of the event.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 7 [MAL1RCS008A, STEAM GENERATOR OATC Identifies lowering pressurizer level, increased auto charging pump 1HX-1A, SG tube A TUBE RUPTURE, VALUE = 0.035] speed and increasing RMS.
leak of approximately 10 Once, insert Trigger 7 to cause a 1HX-1A, SG tube OS1 Implements AOP-3 Unit 1, Steam Generator Tube Leak gpm leak of approximately 10 gpm OATC 1. Check Safety Injection Not Required
- 2. Check Reactor Trip Not Required Plant Response: 3. Check PZR Level - STABLE AT OR TRENDING TO PROGRAM Start: __________ RMS alarms coincident with lowering RCS RNO: IF PZR level trending lower, THEN perform the following:
inventory. a. Control charging and letdown to maintain PZR level
- b. IF PZR level continues to lower, THEN isolate letdown.
Cues: 4. Check PZR Pressure - STABLE AT OR TRENDING TO DESIRED 1C20C 1-2 U1 Stm Line A Radiation High PRESSURE Lowering PZR level 5. Check Reactor Makeup Control Rising Secondary Radiation / Alarms: 6. Notify DSM, Chemistry, And Implement The Emergency Plan Stm Line Radiation 7. Identify Leaking SG Air Ejector exhaust 8. Determine Leak Rate (~10 gpm)
- 9. Check Reactor Shutdown Required Expected Communications: 10. Determine Action Response Based on SG Leakage:
IF RP is requested to perform steam line surveys, Reduce Power to < 50% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Mode 3 in the next two THEN wait 5 minutes and report: hours.
- 11. Place the Unit In MODE 3
'A' main steam line is 5 mrem above 12. Notify Chemistry Of Leak Rate And Rate Of Change background.
- 13. Monitor Leakage Every 15 Minutes
'B' main steam line is at background. 14. Direct Radiation Protection To Perform Exposure And Contamination Evaluations BOP 15. Check Leaking SG - IDENTIFIED
- 17. Isolate Blowdown on Affected Steam Generator A SG 1MS-5958 1MS-2042 Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE
- 18. Shut Affected Steam Generator Sample Isolation Valve 1MS-2083 for A SG
- 19. Ensure Condensate Storage Tank Isolated from Condenser Hotwell
- a. Ensure condenser reject isolation valve SHUT 1CS-113
- 20. Locally Align Low Pressure Trap Header to Condenser ...
Expected Communications: OS1 IMPLEMENT AOP-17A Unit 1, Rapid Power Reduction WHEN directed by crew to start 1P-99A and 1P- OATC 1. Check Power - GREATER THAN 100%
99B, MFP Seal Water Injection Pumps, wait 1 RNO Go To Step 3 minute THEN insert Trigger 9, and report the 3. Determine Desired Power Level or Condition to Be Met pumps started. 4. Commence Boration As Necessary To Target Load.
- 5. Select Rate Reduction Rate And Reduce Load:
BOP 6. Notify Power System Supervisor (PSS) Of Load Reduction Continuation Criteria: 7. Check Rod Control System - IN AUTO Once the crew has reduced load by 3% to 5%, or at OATC 8. Energize pressurizer backup heaters.
the discretion of the Lead Examiner, continue to the 9. Check PZR Pressure Controlling - IN AUTO next event. 10. Check PZR Level Controlling - IN AUTO
- 11. Check Steam Generator Level Controlling - IN AUTO
- 12. Ensure Main Feed Pump Seal Water Pump - RUNNING
- 13. Maintain RCS Tavg:
- 14. Check AFD - WITHIN LIMITS OF ROD 1.2, HFP EQUIL DELTA FLUX.
- 15. Determine Desired End-Point - LESS THAN 50% TURBINE LOAD Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 15 [MAL1CCW002A, CCW PUMP 11A BOP Identifies lowering 1T-12 CC Surge Tank level and references ARB 1C03 The mechanical SEAL FAILURE, VALUE = 1] 1D 3-6, 1T-12 CC Surge Tank Level High or Low pump seal for 1P-11A, Component Insert Trigger 15 to cause 1P-11A, Component OS1 Implements AOP-9B Unit 1, Component Cooling System Malfunction Cooling Water Cooling Water Pump seal failure BOP 1. Check Component Cooling Pumps - AT LEAST ONE RUNNING Pump begins 2. Maintain Surge Tank Level leaking at an Plant Response: a. Check surge tank level - LOWERING increased rate that Inventory is lost (out of) the CCW System resulting b. Start reactor makeup water pump aligned for RMW services causes a lowering in lowering 1T-12 CC Surge Tank. Indicated level c. Ensure component cooling surge tank vent - OPEN CCW Surge Tank on 1LI-618B lowers and annunciator 1C03 1D 3-6, d. Cycle emergency makeup valve to maintain level - BETWEEN level. 1T-12 CC Surge Tank Level High or Low alarms at 20% AND 60%
45% level lowering. Aux Building Sump -19 Ft. P- f. Identify and isolate leak per ATTACHMENT A, LEAK ISOLATION 40A and P-40B Run Time Meters will begin to indicate FOR LOWERING SURGE TANK LEVEL, while continuing with Start: _________ as they cycle on and off to accommodate the CCW this procedure.
leakage draining to the -19 FT sump. g. Check component cooling surge tank level - STABLE RNO WHEN leak isolated, THEN:
Cues: a) Shut surge tank makeup valve.
Lowering CC Surge Tank level as indicated on b) Stop reactor makeup water pump.
indicator 1LI-618B 3. Check Surge Tank Level - GREATER THAN 10%
- 4. Check Component Cooling System For Inleakage Annunciator 1C03 1D 3-6, 1T-12 CC Surge Tank 5. Check Reactor Trip - NOT REQUIRED Level High or Low
- 6. Check RHR Status
- 7. Request Chemistry Analyze Component Cooling Water Expected Communications:
- 8. Notify DSM And Implement Emergency Plan WHEN an AO is dispatched to locally investigate, 9. Return To Procedure And Step In Effect THEN wait two minutes and report that there is excessive seal leakage coming from 1P-11A, Attachment A CCW pump and recommends immediately A1 Isolate Leakage Out Of Component Cooling System Using One Of securing the pump. RP is in the area controlling The Following: (Step A2) the leakage. A2 System Leakage To Atmosphere IF an AO is directed to locally makeup to 1T-12 a. Inspect system piping to identify the source of the leak.
CC Surge Tank by cycling 1CC-773, Component b. Isolate the leak Cooling Surge Tank Demin Water Inlet, THEN c. Return to 2.g (main body).
cycle open/close 1CC-773 to maintain tank level between 20% and 60%. (Trigger 17 opens 1CC-773)
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Communications (cont.) CREW Reference Technical Specifications IF the crew directs the AO to locally isolate Technical Specifications:
1P-11A, Component Cooling Water Pump, THEN insert TRIGGER 19 and report when the valves CCW LCO 3.7.7 is not met.
are repositioned and the seal leak has subsided. CONDITION REQURIED ACTION COMPLETION TIME Instructor Note: If the crew starts to implement A. One CC pump A.1 Restore CC 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AOP-12A, the SM should notify the crew that inoperable pump to OPERABLE AND the Unit 2 OS will be implementing AOP-12A.
status. 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> from discovery of failure to meet the LCO Continuation Criteria:
After 1P-11B, Component Cooling Water Pump has been started, 1P-11A secured and Technical Specifications addressed, or at the discretion of the Lead Examiner, continue with the next event.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Trigger 21 [MAL1GEN006, VOLTAGE Event 5: BOP Identifies rising generator volts and outward vars. References ARP C01 REGULATOR FAILURE, VALUE = 25, Main Turbine A 1-3, Unit 1 Voltage Regulator Alert and dispatches an AO to RAMP = 15 min.]
Generator Voltage investigate.
Regulator Trouble Insert Trigger 21 to cause a voltage regulator results in Main OS1 May direct a reactor trip.
failure which results in a generator lockout and Generator reactor trip. OATC Lockout and Implements EOP-0 Unit 1, Reactor Trip or Safety Injection reactor trip Plant Response: 1. Verify Reactor Trip The regulator failure will cause vars to increase. Identifies stuck rods B6, B8, C5, E11 by IRPI and non-lit rod bottom Operators may recognize the failure and select lights.
Start: __________ RNO Manually trip reactor manual voltage control. Unit operations can continue in manual. In Automatic Control the If the Train A malfunction severity is set for a high voltage then an Train B over excitation trip will occur. Over excitation and 2. Verify Turbine Trip voltage regulator trouble and alert will alarm. The 3. Verify Power to AC Safeguards Buses turbine generator and reactor trip. Turbine speed 4. Check if SI is Actuated increases to 1900 rpm as crossover steam dumps a. Any SI annunciators LIT open to limit speed. RNO IF SI is NOT required, THEN go to EOP-0.1 Unit 1, Reactor Trip Response.
Cues:
C01 1A 1-3, Unit 1 Voltage Regulator Alert C01 1A 3-1, Unit 1 TG-01 or X-01 Over-Excitation C01 1A 4-4, Unit 1 Voltage Regulator Trouble.
Expected Communications: OS1 IF an AO is dispatched to 1E02 to check local annunciator panel ANN2 (on Voltage Regulator Panel),
wait two minutes and THEN report that the alarm is HXL is Limiting.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 6: PRELOAD: [MAL1CRF001-B6, B8, C5, E11, OATC Implements EOP-0.1 Unit 1, Reactor Trip Response Multiple stuck STUCK ROD B6, B8, C5, E11, VALUE = 1. Check RCS Temperatures:
rods post trip Non-Trippable] a. Condenser Steam Dumps - AVAILABLE Place Steam Dump Mode Selector in MANUAL
- b. RCS Temperature Plant Response:
o With any RCP running:
Non-Trippable rods will not move under any RCS average temperature - STABLE AT OR circumstance BOP TRENDING TO 547°F OR Cues:
o With No RCP running Rods B6, B8, C5 and E11 will remain at their RCS wide range cold leg temperatures - STABLE AT original position and rod bottom lights will not be lit OR TRENDING TO 547°F upon reactor trip.
- 2. Check Feedwater Status Expected Communications: a. Main feedwater regulating control valves - BOTH SHUT None 1FIC-466A 1FIC-476A Continuation Criteria: b. Transfer feedwater control to bypass regulating valves:
Once the crew has addressed the stuck rods by 1) Check main feedwater pumps - AT LEAST ONE initiating a boration, or at the discretion of the Lead RUNNING Examiner, continue with the next event. 2) Control feedwater flow using regulating bypass valves 1CS-480 1CS-481 BOP 3) Maintain both SG levels - BETWEEN 32% AND 63%
OATC 4) Reset Loss of Feedwater Turbine Trip
- 5) Stop any running AFW pumps.
- 3. Verify All Control Rods - FULLY INSERTED RNO IF two or more control rods are NOT fully inserted, THEN initiate emergency boration:
- a. Record initial level for in service BAST
- b. Perform the following to adjust charging flow:
- 1) Control charging pump speed as necessary to maintain flow GREATER THAN OR EQUAL TO 60 GPM.
- 2) Control charging line flow controller as necessary to maintain labyrinth seal P GREATER THAN 20 inches Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 7: Trigger 23 [MAL1RCS008A, STEAM GENERATOR OATC/BOP c. Start one boric acid transfer pump:
1HX-1A SG tube A TUBE RUPTURE, VALUE = 0.4] o 1P-4A leak increases in o 1P-4B size to a steam Inset Trigger 23 to increase steam generator tube d. Open emergency borate valve:
generator tube leak to a tube rupture. 1CV-350 rupture e. Borate 2825 gallons for each control rod not fully inserted.
Plant Response: Use TLB-5, BORIC ACID STORAGE TANKS to Start: _________ RCS inventory will rapidly lower, RCS pressure and determine BAST level change subcooling lower. f. WHEN emergency boration is complete, THEN control charging as necessary to establish desired charging Cues: flow.
Rapidly Lowering PZR level g. IF emergency boration can NOT be established, THEN perform boration per OP 5B, BLENDER OPERATION /
DILUTION / BORATION, while continuing with this procedure.
OS1 Plant conditions degrade; exercises EOP-0.1 Unit 1 Foldout Page criteria and returns to EOP-0 Unit 1, Reactor Trip or Safety Injection Step 4.
OATC EOP-0 Unit 1, Reactor Trip or Safety Injection BOP 4. Check If SI Is Actuated
- 5. Perform ATTACHMENT A, Automatic Action Verification while continuing with this procedure
- 6. Verify AFW pumps - Running
- 7. Check RCP Seal Cooling
- 8. Check RCS Temperatures
- 9. Check PZR PORVs and Spray Valves
- 10. Check if RCPs should be stopped
- 11. Check if SGs are NOT Faulted
- 12. Check if SG Tubes are NOT Ruptured RNO Go to EOP-3 UNIT 1, STEAM GENERATOR TUBE RUPTURE Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service A3 Verify ECCS Pumps RUNNING Water valves, LW-61 and 62, THEN report both A4 Verify Service Water Pumps RUNNING valves are closed. A5 Verify Containment Accident Cooling Units RUNNING WHEN directed to locally check CW pump house A6 Verify Component Cooling Water Pumps - ONLY ONE RUNNING temperature <105 ºF, wait 3 minutes and THEN A7 Check If Main Steam Lines Can Remain Open report the temperature is 72 ºF and stable. A8 Verify Containment Spray Not required WHEN directed to locally check G03/G04 a. Containment pressure recorder - HAS REMAINED LESS Switchgear Room temperature <95 ºF, wait 3 THAN 25 psig minutes and THEN report the temperature is 75 ºF A9 Verify ECCS Flow and stable. A10 Verify AFW valve alignment - PROPER EMERGENCY IF directed to periodically check the status of ALIGNMENT spent fuel cooling, wait 5 minutes and THEN A11 Verify Proper ECCS Valve Alignment A12 Check Containment Spray NOT ACTUATED report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable. A13 Stop any boration via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: OS1 Implements EOP-3, Unit 1 Steam Generator Tube Rupture BOP 1. Check If RCPs Should Be Stopped WHEN directed to shut 1MS-235, AFP Radwaste 2. Identify Ruptured SG(s)
Steam Isolation and 1MS-228, Main Steam Trap Header Isolation, wait 5 minutes THEN insert CT-18 Isolate feedwater flow into and steam flow from the ruptured SG Trigger 25 and report when the valves are closed. before a transition to ECA-3.1 occurs.
- 3. Isolate Flow From Ruptured SG
- 3) Ensure 1MS-2016 - SHUT
- 4) Ensure 1HC-468 A ADV Controller - SET TO 1050 psig
- 5) Shut 1MS-2020, TDAFWP Steam supply
- 7) Locally shut the following:
o 1MS-235 1P-29/Radwaste Isolation o 1MS-228 Main Steam Trap Isolation
- 4. Check Ruptured SG(s) Level:
- a. Level - GREATER THAN [51%] 32%
RNO: Maintain feed flow to ruptured SG(s) unit level is greater than [51%] 32%
Continue with Step 5.
- 1) Place in manual and shut 1AF-4074A
- 3) Ensure AF-4023 SSG supply valve - SHUT
- 5. Check Ruptured SG(s) Pressure - GREATER THAN 590 PSIG Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP 6. Initiate RCS cooldown
- a. Check SI signal status:
- 2) Reset SI
- b. Determine required core exit temperature:
- c. Dump steam to condenser from intact SG at maximum rate
- d. Check core exit TCs - LESS THAN REQUIRED TEMPERATURE
- e. Stop RCS cooldown
- f. Maintain core exit TCs - LESS THAN REQUIRED TEMPERATURE
- 7. Check Intact SG Level
- 8. Check PZR PORVs And Block Valves
- 9. Check SI Signal Status
- 10. Reset Isolation And Lockout Signals
- 11. Establish Instrument Air To Containment
- 12. Check If RHR Pumps Should Be Stopped:
- b. RCS pressure - GREATER THAN [450 PSIG] 325 psig
- c. Stop both RHR pumps and place in auto
- 13. Establish Charging Flow
- a. Charging Pumps - AT LEAST ONE RUNNING
- b. Align charging pump suction to RWST
- c. Establish maximum charging flow
- 14. Check If RCS Cooldown Should Be Stopped
- 16. Check RCS Subcooling Based On core Exit Thermocouples -
GREATER THAN [94ºF] 55 ºF Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Event 8: Trigger 23 [CNH1PCS008B, 1-HC431H 1- OATC 17. Depressurize RCS To Minimize Break Flow And Refill PZR 1RC-431A and B, PCV431B SPRAY VALVE HAND CTLR a. Normal PZR spray - AVAILABLE PZR Spray Valves FIXED AUTO/MAN, VALUE = 0] RNO- OBSERVE CAUTIONS AN NOTE PRIOR TO STEP 18 fail closed. and go to Step 18.
[CNH1PCS007B, 1-HC431C 1- 18. Depressurize RCS Using PZR PORV To Minimize Break Flow and PCV431A SPRAY VALVE HAND CTLR Refill PZR:
FIXED AUTO/MAN, VALUE = 0] a. At least one PZR PORV - AVAILABLE
- b. Open one PORV until any of the following conditions satisfied:
o Both of the following:
Trigger 23 (inserted for the SGTR) causes 1PCV- 1) RCS pressure - LESS THAN RUPTURED SG 431A and B, Spray valves to fail closed in auto and PRESSURE manual. 2) PZR level - GREATER THAN [32%] 13%
OR o Both of the following
- 1) RCS PRESSURE - WITHIN 300 psid OF RUPTURED SG PRESSURE 2 PZR level greater than OR o PZR level - GREATER THAN [50%] 43%
OR o RCS subcooling based on core exit TCs - LESS THAN
[74ºF] 35ºF
- c. Shut PZR PORV
- d. Go to Step 20
- e. OBSERVE CAUTION PRIOR TO STEP 21 and go to Step 21.
- 20. Check RCS Pressure - RISING:
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG CT-21 Terminate SI before the SG goes water solid (simulator out of limits alarm) and control RCS pressure and makeup flow so that primary and secondary inventory are stable before the end of the scenario.
- 21. Check If ECCS Flow Should Be Terminated
- a. RCS subcooling based on core exit thermocouples - GREATER THAN [74ºF] 35ºF
- b. Secondary Heat Sink:
o Intact SG level - GREATER THAN [51%] 32%
OR o Total feed flow to SGs - GREATER THAN OR EQUAL TO 230 GPM AVAILABLE
- d. PZR level - GREATER THAN [32%] 13%
BOP/OATC 22. Stop Both SI Pumps And Place In Auto
- 23. Establish Charging Flow
- 24. Ensure Adequate RCS Depressurization
- a. Check normal spray - AVAILABLE RNO - Go to Step 25
- 25. Verify SI flow is Not Required:
- a. RCS subcooling based on core exit thermocouples - GREATER THAN [74º F] 35º F.
- b. PZR level - GREATER THAN [32%] 13%
- 26. Check Reactor Makeup Control:
- b. Makeup set for greater than 2800 ppm
- c. VCT level - GREATER THAN 17%
- d. Ensure makeup armed and in auto Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG OATC 27. Check if Letdown can be established
- a. PZR level - GREATER THAN [44%] 24%
- b. Establish Letdown
- 1) Open letdown line containment isolation valves:
1CV-371A 1CV-371
- 2) Open RCS loop B cold leg letdown isolation valve:
- 3) Ensure component cooling flow to non-regenerative heat exchanger - ESTABLISHED 1HC-130
- 4) Ensure charging flow - AT LEAST 21 GPM
- 5) Adjust backpressure as necessary and open letdown isolation valves to establish letdown flow:
o 1CV-200A o 1CV-200B o 1CV-200C
- 28. Align Charging Pump Suction To VCT:
- a. VCT level - GREATER THAN 17%
- b. Open VCT outlet to charging pump suction MOV:
- c. Shut RWST to charging pump suction MOV:
- 29. Check If SI Accumulators Should Be Isolated:
- a. RCS pressure - LESS THAN 1075 psig RNO: WHEN RCS pressure is less than 1075 psig THEN do Steps 29.b, 29.c, 29.d, and 29.e.
Observe CAUTION prior to Step 30 and continue with Step 30 Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Termination Criteria: 30. Control RCS Pressure And Charging To Minimize Leakage End: ______ OS1 Terminate the scenario when the crew has stopped a. Perform appropriate action(s) from table below and use SI pumps and taken appropriate action(s) per step ATTACHMENT B handout as desired:
30 of EOP-3 Unit 1, or at the discretion of the Lead Evaluator. . RUPTURED SG LEVEL PZR LEVEL RISING LOWERING OFF SCALE HIGH Raise charging LESS THAN Raise charging flow flow Raise charging Maintain RCS and OR EQUAL Depressurize flow ruptured SG TO [44%] 24% RCS using Step pressures equal 29.b BETWEEN Depressurize Maintain RCS and Turn on PZR
[44%] 24% RCS using Step heaters ruptured SG AND 50% 29.b pressures equal Depressurize BETWEEN RCS using Step Maintain RCS and Turn on PZR 50% AND 29.b heaters ruptured SG
[62%] 68% Reduce pressures equal charging flow GREATER Maintain RCS and THAN OR Reduce Turn on PZR ruptured SG EQUAL TO charging flow heaters pressures equal
[62%] 68%
- b. Use normal PZR spray as necessary to depressurize RCS per table in Step 30a.
RNO: IF letdown is in service THEN use auxiliary spray
- END OF SCENARIO ***
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D 1HX-1A, SG tube leak 1RE-219, SG Blowdown Monitors fails high 1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close.
1P-11A, Component Cooling Water Pump mechanical seal leak Main Generator Lockout (Voltage Regulator Trouble)
After EOP Entry:
Multiple stuck rods (4) post trip 1HX-1A SG steam generator tube rupture 1RC-431A and B, PZR Spray Valves fail closed Abnormal Events:
P-32A, Service Water Pump trips with reduced head capacity on P-32B and P-32D 1HX-1A, SG tube leak of approximately 10 gpm 1RE-219, SG Blowdown Monitors fails high off-scale 1MS-2083, 1HX-1A SG Sample Isolation Control Valve fails to auto close 1P-11A, Component Cooling Water Pump mechanical seal leak Major Transients:
1HX-1A SG steam generator tube rupture Critical Tasks:
- 1. CT-18 Isolate ruptured SG
- 2. CT-21 Terminate SI/control RCS pressure and makeup Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG CT-18 Isolate ruptured SG Applicable ERG LP Version Applicable ERG E-3 Critical Task:
Isolate feedwater flow into and steam flow from ruptured SG before a transition to ECA-3.1 Plant Conditions:
SGTR Reactor trip SI Cues:
Indication and/or annunciation of SGTR in one SG
- Increasing SG water level
- radiation AND Indication and/or annunciation of reactor trip AND Indication and/or annunciation of SI Performance Indicator:
Manipulation of controls as required to isolate the ruptured SG Main steam isolation valve position lamps indicate closed Main steam isolation bypass valve position lamps indicate closed PORV setpoint adjusted to ERG Footnote O.03 Blowdown isolation valve position lamps indicate closed Steam isolation valve to TDAFW pump position lamps indicate closed AFW valve position lamps and/or indicators indicate closed Feedwater isolation valve position lamps indicated closed Feedback:
Indication of stable or increasing pressure in the ruptured SG Indication of decreasing or zero feedwater flow rate in the ruptured SG Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 36 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG CT-21 Terminate SI/control RCS pressure and makeup Applicable ERG LP Version Applicable ERG E-3, ES-3.1, ES-3.2, ES-3.3, ECA-3.3 Critical Task:
CT-21 Terminate SI before the SG goes water solid (simulator out of limits alarm) and control RCS pressure and makeup flow so that primary and secondary inventory are stable before the end of the scenario.
Plant Conditions:
SGTR SI Ruptured SG identified and isolated RCS cooldown to target temperature completed RCS depressurization completed SI termination criteria met Cues:
Indication and/or annunciation of SGTR in one SG
- Increasing SG water level
- Radiation AND Indication and/or annunciation of reactor trip and SI AND Indication that RCS is cooldown to the target temperature AND Indication that RCS depressurization is completed AND Indication that SI termination criteria met Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 37 of 40
PBN LOI NRC 17E, 2017 NRC Exam Scenario 3, Rev. 0 SEG Performance Indicator:
Manipulation of controls as required to Terminate SI
- All high-head ECCS pumps breaker position lamps indicate open Control RCS pressure and makeup flow
- Indication that the charging flow control valve is at the appropriate position (open, closed, or throttled)
- Indication that charging pump speed is increasing or decreasing as appropriate OR
- PRZR heater beaker position lamp(s) or current indicator shows appropriate position/current change (open or close/increase or decrease OR
- PRZR spray valve(s) position lamp(s)/indicator shows appropriate change (open or close)
Feedback:
Indication of high-head ECCS flow rate decreasing or zero Indication of increasing or decreasing RCS pressure Indication of increasing or decreasing makeup flow to the RCS Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 38 of 40
TURNOVER INFORMATION SEG 1.0 Plant Conditions:
Unit 1 Unit 2 Time in Core Life (MWD/MTU): 9005 Reactor Power: 75%
Boron Concentration: 1179 ppm Rod Height: CBD @ 175 2.0 Equipment Out of Service:
1P-2B, Charging Pump, is out of service for mechanical seal replacement. Work is expected to take another 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1PT-950, Loop B Containment Pressure has been removed from service. Repairs are expected to be complete during the upcoming refueling outage.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:
LCO NOT Met TSAC Required Actions Completion Time 3.3.2 A. One or more Functions with one A.1 Enter the Condition referenced in Immediately or more channels or trains Table 3.3.2-1 for the channel(s) or inoperable. train(s).
D. One channel inoperable D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 4.0 Planned Evolutions:
Unit 1 was lowered to approximately 74% (1339 MWT) at the request of MISO/ATC due to grid stability issues. Grid stability has been restored and the unit is ready to be returned to full power in accordance with OP 1C, Startup to Power Operations.
Commence raising power to 100%.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 39 of 40
TURNOVER INFORMATION SEG
5.0 Common
Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.
Filename: NRC Scenario 3 draft.doc TR-AA-230-1003-F06 Revision 0 Page 40 of 40
SIMULATOR EXERCISE GUIDE SEG SITE: Point Beach Revision #: 0 LMS ID: PBN LOI NRC 18E LMS Rev. Date:
SEG TITLE: 2017 NRC Exam Scenario 4 SEG TYPE: Training Evaluation PROGRAM: LOCT LOIT Other:
DURATION: 90 minutes Developed by:
Instructor/Developer Date Reviewed by:
Instructor (Instructional Review) Date Validated by:
SME (Technical Review) Date Approved by:
Training Supervision Date Approved by:
Training Program Owner (Line) Date Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 1 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG Facility: _Point Beach_____ Scenario No.: _4___________ Op-Test No.: _2017____
Examiners: ___________________________ Operators: _____________________________
Initial Conditions: _Unit 1 is at approximately 100%. 1LT-112 VCT Level Transmitter has failed low, _
I&C expect repairs to be completed within the hour and returned to service by the end of shift. 1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure._______________________________
Turnover: Start 1P-27A, Heater Drain Tank Pump, and secure 1P-27C Heater Drain Tank Pump____
per OP 2A, Normal Power Operations, Attachment M, in preparations for maintenance. Lower power utilizing OP 3A, Power Operation to Hot Standby, in preparation for TS 3, Main Turbine Stop and Governor Valve with Turbine Trip_(Biannual)
Event Malf. No. Event Event No. Type* Description N-BOP 1 Shift Heater Drain Tank Pumps, start 1P-27A, secure 1P-27C N-SRO R-RO 2 N-BOP Down Power for TS-3 R-SRO I-RO I-SRO NI-43, PR NI fails low fast enough to cause outward rod motion near 3 MAL1NIS007C 12-15 steps/min.
TS-SRO I-BOP I-SRO 1LT-471, SG Level fails low slowly 4 XMT1SGN012A (Manual SG level control)
TS-SRO I-RO 1LT-141, VCT Level Transmitter fails low, causing an auto shift to XMT1CVC020A I-SRO the RWST. (Manual reactor trip required) 5 See SEG The first set of Reactor Trip push buttons fails to cause a reactor trip, TS-SRO but the second set used is successful 6 MAL1SGN003B M-ALL Steam Generator Fault in Containment on Reactor Trip 1P-53, Motor Driven Auxiliary Feedwater Pump sheared shaft and PMP1AFW004 C-BOP 1P-29, Turbine Driven Auxiliary Feedwater Pump trips on over 7 PMP1AFW002 speed (CSP-H.1, Response to Loss of Secondary Heat Sink)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 2 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given specific plant conditions, the students will be able to respond to plant evolution and failures listed below in accordance with plant procedures:
- 1. Shift Heater Drain Pumps
- 2. Lower Power utilizing OP 3A Unit 1, Power Operation to Hot Standby Unit 1 for TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Biannual) Unit 1
- 3. 1N-43, Power Range Nuclear Instrument fails low
- 6. 1HX-1B SG faults to containment upon reactor trip
- 7. Reactor trip breakers fails to auto open; reactor trip push buttons on 1C04 do not work
- 8. Auxiliary Feedwater malfunctions 1P-53, Motor-Driven AFW Pump - sheared shaft 1P-29, Turbine-Driven AFW Pump - trips on overspeed Embedded within these events is the expectation to properly utilize Technical Specifications.
Enabling None Objectives:
Prerequisites: 1. Simulator available
- 2. Students enrolled in Initial License Program Training 1. Floor Instructor as Shift Manager / Shift Technical Advisor Resources: 2. Simulator Booth Operator
- 3. Communicator
- 4. NRC Evaluators Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 3 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG
References:
- 1. 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels
- 2. 0-SOP-IC-001 Yellow, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Yellow Channels
- 3. 0-SOP-IC-002, Technical Specifications LCO - Instrument Cross Reference
- 4. AOP-1D Unit 1, Chemical And Volume Control System Malfunction
- 6. AOP-6C, Uncontrolled Motion of RCCAs
- 7. AOP-24, Response to Instrument Malfunctions
- 8. CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink
- 9. EOP-0 Unit 1, Reactor Trip Or Safety Injection
- 10. EOP-1 Unit 1, Loss Of Reactor Or Secondary Coolant
- 12. EOP-2 Unit 1, Faulted Steam Generator Isolation
- 13. OM 3.7, AOP And EOP Procedure Usage For Response To Plant Transients
- 14. OP 2A UNIT 1, Normal Power Operation Unit 1
- 15. OP 3A Unit 1, Power Operation to Hot Standby Unit 1
- 16. Technical Specifications Protected Content: None Evaluation Method: Simulator performance will be evaluated in accordance with NUREG 1021 Operating N/A Experience:
Risk Significant HEP-COG CSPH1, OPERATORS FAIL TO DIAGNOSE LOSS OF Operator Actions: SECONDARY HEAT SINK. [Fv = 6.59E-02]
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 4 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.
PREPARER DATE
- DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR#
REVIEWER DATE Rev. 0 Developed for 2017 NRC ILT Exam.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 5 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG OVERVIEW / SEQUENCE OF EVENTS OVERVIEW Insert brief description of what will occur during this simulator exercise.
Unit 1 is at approximately 100% EOL.
1W-3B, Control Rod Shroud Fan is OOS due to imminent motor failure.
1LT-112, VCT Level Transmitter has failed low 1CV-112A is in TO VCT position and VCT level is being manually controlled between 17% and 78% per AOP-1D I&C expect repairs to be completed within the hour and returned to service by the end of the shift.
Start 1P-27A, Heater Drain Tank Pump and secure 1P-27C, Heater Drain Tank Pump per OP-2A Attachment M, in preparation for maintenance.
Lower Power utilizing OP 3A Unit 1, Power Operation to Hot Standby Unit 1 for TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Biannual) Unit 1 Malfunctions 1N-43, Power Range Nuclear Instrument fails low 1LT-471, SG Level Transmitter fails low 1LT-141, VCT Level Transmitter fails low Reactor trip breakers fails to auto open; first set of reactor trip push buttons attempted do not work 1HX-1B SG faults to containment upon reactor trip Auxiliary Feedwater malfunctions 1P-53, Motor-Driven AFW Pump - sheared shaft 1P-29, Turbine-Driven AFW Pump - trips on overspeed Termination criteria.
Terminate the scenario when crew has completed Step 5 of EOP-1.1 Unit 1, SI Termination.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 6 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SEQUENCE OF EVENTS ALL TIMES IN THIS SCENARIO ARE APPROXIMATE Event # Description
- 1. Start 1P-27A, Heater Drain Tank Pump and secure 1P-27C, Heater Drain Tank Pump per OP-2A Attachment M, in preparation for maintenance
- 2. Lower Power utilizing OP 3A Unit 1, Power Operation to Hot Standby Unit 1 for TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Biannual) Unit 1
- 3. 1NI-43, Power Range Nuclear Instrument fails low (outward rod motion at or near 12-15 steps/min)
The crew should respond by taking rods to manual to stop unwanted outward rod motion.
The crew should implement AOP-24, Response to Instrument Malfunctions and 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Blue Channels to shift to a new controlling channel and take the nuclear instrument out of service.
Take 1FIC-476A to Manual or shift the controller to single element.
Implement AOP-2B Unit 1, Feedwater System Malfunction, AOP-24, Response to Instrument Malfunction and 0-SOP-IC-001 Yellow, Routine Maintenance Procedure Removal of Safeguards or Protection Sensor from Service - Yellow Channels take the channel out of service.
Refer to Technical Specifications for the failed channel
- 5. 1LT-141, VCT Level Transmitter fails low The crew should implement AOP-1D Unit 1, Chemical and Volume Control System Malfunctions, and trip the unit per the Foldout page criteria in response to the CVC system aligning the RWST and the charging pump suction source.
When the manual reactor trip is attempted the first set of pushbuttons will not work, the reactor will trip when the second set of pushbuttons are depressed.
- 6. 1HX-1B SG faults to containment upon reactor trip The should I transition from EOP-0 Unit 1, Reactor Trip or Safety Injection to EOP-2 Unit 1, Faulted Steam Generator Isolation to isolate the faulted 1HX-1B Steam Generator.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 7 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG
- 7. Auxiliary Feedwater malfunctions 1P-53, Motor-Driven AFW Pump - sheared shaft 1P-29, Turbine-Driven AFW Pump - trips on overspeed The crew should respond to the loss of auxiliary feedwater by transitioning form EOP-0 Unit 1, Reactor Trip or Safety Injection to CSP-H.1 Unit 1, Response to Loss of Secondary Heat Sink.
Restoration of AFW will be from 2P-53, Motor-Driven AFW Pump through cross connects Unit 1 and Unit 2 AF-192 and by resetting the OS trip of 1P-29, Turbine Driven AFW Pump.
STOP Terminate the scenario when the crew has completed Step 5 of EOP-1.1 Unit 1, SI Termination.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 8 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR SET UP INSTRUCTIONS Perform simulator set up per the site specific Simulator Setup Checklist.
General Instructions Simulator Setup Instructions:
Load IC-2 and go to run Open the saved Event and Schedule files from the secure drive:
Verify all commands listed in table below are contained in the Schedule File Insert the setup malfunction(s)
Reposition bistable switches for:
Make any necessary adjustments or corrections Freeze the simulator and save to scenario specific IC Re-initialize into saved IC and go to run Open and start the Event and Schedule files Open and start InSight and Alarm files for data collection Run the scenario real time Save InSight, Event, Alarm, Schedule Files to the secure drive and collect procedure markups for SBT Complete TR-AA-23001008-F01 Scenario Based Testing (SBT) Checklist Multiple Use:
Load saved IC and go to run Open the saved Event and Schedule files:
Start the Schedule File Walk down the control boards to ensure plant conditions accurately reflect the scenarios initial conditions Make any necessary adjustments or corrections Update documentation if required Resave if required Turnover to the crew Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 9 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR - SCENARIO SETUP:
Setup: 1LT-112, VCT Level Transmitter failed low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-LT112 VCT XMT1CVC019A LEVEL FIXED 00 :00 :00 00 :00 :00 00 :00 :00 - 0 SETUP OUTPUT Simulator Setup:
- 2. Take auto makeup to STOP
- 5. Install an orange Guarded magnet at 1W-3A.
SIMULATOR MALFUNCTIONS:
Event 1: Start 1P-27A, Heater Drain Tank Pump and secure 1P-27C, Heater Drain Tank Pump per OP-2A Attachment M, in preparation for maintenance MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE Expected field communications:
- 1. IF asked about pre-start checks for 1P-27A, Heater Drain Tank Pump, THEN report that they were completed satisfactorily and the pump is ready for start.
- 2. REPORT that 1P-27A, Heater Drain Tank Pump start was normal.
- 3. REPORT that 1P-27C, Heater Drain Tank Pump coast down was normal, the pump is stopped and is not rotating backwards.
Event 2: Lower Power utilizing OP 3A Unit 1, Power Operation to Hot Standby Unit 1 for TS-3 MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-P99A SFP SEAL WATER When directed by the LOA1CFW083 00 :00 :00 - 1 00 :00 :00 AUTO ON INJECT PUMP crew C.S.
1-P99B SGFP SEAL WATER When directed by the LOA1CFW084 00 :00 :05 - 1 00 :00 :05 AUTO ON INJECT PUMP crew C.S.
Expected field communications:
- 1. WHEN directed to start 1P-99A and 1P-99B SGFP Seal Water Injection Pumps, insert Trigger 1 and THEN report when they are started.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 10 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG Event 3: 1NI-43, Power Range Nuclear Instrument fails low (outward rod motion at or near 12-15 steps/min)
MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE P.R. CHANNEL N43 HIGH MAL1NIS007C 00 :00 :00 00 :00 :27 3 00 :00 :00 - 300 PLE VOLTAGE FAILURE Expected field communications:
- 2. None Event 4: 1LT-471, SG Level fails low MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-LT471 STM GEN B NR XMT1SGN012A 00 :00 :00 00 :01 :30 5 00 :00 :00 64 19 PLE LEVEL FIXED OUTPUT Expected field communications:
- 1. None Event 5: 1LT-141, VCT Level Transmitter fails low, reactor trip with failed pushbuttons MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE 1-LT141 VCT XMT1CVC020A LEVEL FIXED 00 :00 :00 00 :00 :05 7 00 :00 :00 - 0 PLE OUTPUT REACTOR TRIP Fails_To_
MAL1PPL001A BREAKER 00 :00 :00 - - 00 :00 :00 - Open PRELOAD 52/RTA FAILURE REACTOR TRIP Fails_To_
MAL1PPL001B BREAKER 00 :00 :00 - - 00 :00 :00 - Open PRELOAD 52/RTB FAILURE REACTOR TRIP 15 MAL1PPL001B BREAKER Trip et_array(16) & et_array(17)
Cond 52/RTB FAILURE REACTOR TRIP 15 MAL1PPL001A BREAKER Trip et_array(16) & et_array(17)
Cond 52/RTA FAILURE 1C04 REACTOR 16 x14i057a == 1 l x14i055a TRIP A OR B Cond == 1 PUSHBUTTON C01 REACTOR 17 x01i142a == 1 l x01i141a TRIP A OR B Cond == 1 PUSHBUTTON Expected field communications:
- 1. IF an AO is dispatched to locally investigate LT-141, VCT Level Transmitter, wait two minutes and THEN report that locally there doesnt seem to anything out of normal.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 11 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG Event 6: 1HX-1B SG faults to containment upon reactor trip MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE SG B MAIN STEAM LINE 9 PRELOAD MAL1SGN003B 00 :00 :00 00 :01 :00 00 :00 :00 - 5.0E5 BREAK INSIDE Cond. Cond. = Reactor Trip CNMT 1-MS-237 P-29 AFP & When directed by the LOA1SGN025 00:00:00 00 :00 :00 17 00 :00 :00 - 0 RADWASTE crew STEM ISOL Expected field communications:
- 1. WHEN directed to locally check RW Service Water valves, LW-61 and 62, THEN report both valves are shut.
- 2. WHEN directed to locally check CW pump house temperature <105 ºF, wait 3 minutes and THEN report the temperature is 72 ºF and stable.
- 3. WHEN directed to locally check G03/G04 Switchgear Room temperature <95 ºF, wait 3 minutes and THEN report the temperature is 75 ºF and stable.
- 4. IF directed to periodically check the status of spent fuel cooling, wait 5 minutes and THEN report Spent Fuel Pool level is 63 feet, pool temperature is 67 ºF and both are stable.
- 5. WHEN directed to locally shut 1MS-237, 1P-29 AFP/Radwaste Steam Isolation and 1MS-238, Main Steam Trap Isolation, insert Trigger 17 and THEN report completed when the valve has repositioned.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 12 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG Event 8: Auxiliary Feedwater malfunctions: 1P-53, Motor-Driven AFW Pump - sheared shaft and 1P-29, Turbine-Driven AFW Pump -
trips on overspeed MALFUNCTION MALFUNCTION DELETE INITIAL FINAL DELAY RAMP ET NOTES No. TITLE IN VALUE VALUE AUX FWP MAL1AFW001 TURBINE 00 :00 :00 - 9 00 :03 :00 - - PRELOAD OVERSPEED 1-P53 AUXILIARY Shaft PMP1AFW004 00 :00 :00 - - 00 :00 :00 - PRELOAD FEEDWATER Break PUMP 1-B5212C P-38A BKR1AFW001 AUX SG FEED 00 :00 :00 - - 00 :00 :00 - Failasis PRELOAD PUMP CKTBKR 0-P38B AUXILIARY Shaft PMP1AFW002 00 :00 :00 - - 00 :00 :00 - PRELOAD FEEDWATER Seizure PUMP 1-AF-192 U1 When directed by the LOA1AFW051 AFW CROSS 00 :00 :00 - 11 00 :00 :00 - 1.0 crew CONNECT 2-AF-192 U2 When directed by the LOA2AFW016 AFW CROSS 00 :00 :00 - 11 00 :00 :00 - 1.0 crew CONNECT 1-TV-2082R 2082 When directed by the LOA1SGN033 00 :00 :00 - 13 00 :00 :00 - RESET OVERSPEED crew TRIP RESET Expected field communications:
Note: The intended sequence for the restoration of feed is first from 2P-53 via unit cross-connect valves then second from 1P-29 by resetting the OS trip mechanism.
- 1. IF an AO is dispatched to locally investigate 1P-29, Turbine-Driven AFW Pump, wait two minutes and THEN report that the pump has tripped on overspeed and the overspeed trip mechanism is intact.
- 2. WHEN directed by the crew to reset 1P-29 OS trip mechanism, THEN report that while attempting to reset the mechanism will not latch and that you are going to continue to try to get it reset.
- 2. IF an AO is dispatched to locally investigate 1P-53, Motor-Driven AFW Pump, wait two minutes and THEN report that the motor is turning, but is no longer connected to the pump (shaft break). He recommends securing the pump motor.
- 3. WHEN directed by the crew, insert Trigger 11, wait two minutes and THEN report that Unit 1 and Unit 2 AF-192, AFW Cross-connect Valves are open.
- 4. AFTER the crew has commenced feeding from U2 AFW, Insert TRIGGER 13, THEN report the OS trip reset. (verify MAL1AFW001 is deleted)
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 13 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG BRIEF / TURNOVER INFORMATION Conduct simulator crew pre-scenario brief using TR-AA-230-1007-F06, Simulator Instructor Pre-Exercise Checklist.
Brief the scenario evaluators Brief surrogates using TR-AA-230-1007-F11, Surrogate Brief Checklist, if necessary.
Crew Shift Turnover Information: See Attached Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 14 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 1: Start 1P-27A, Heater Drain Tank Pump and secure OS1 Implements OP 2A Unit 1, Normal Operation, ATTACHMENT M, 1P-27C, Heater Drain Tank Pump per OP-2A BOP 4.1 START a Heater Drain Tank Pump as follows:
Start 1P-27A, Attachment M, in preparation for maintenance. 4.1.1 SELECT a HDT Pump to be STARTED and CHECK applicable Heater Drain Tank box below.
Pump and secure Expected Communications: 4.1.2 ENSURE the following Prestart Checks for Pump selected in 1P-27C IF asked about pre-start checks for 1P-27A, Heater Attachment M, Step 4.1.1 have been COMPLETED IN Drain Tank Pump, THEN report that they were ACCORDANCE with OP 13A Unit 1, Secondary Systems completed satisfactorily and the pump is ready for Startup Unit 1:
start. 4.1.3 START Pump selected in Attachment M, Step 4.1.1 and Start: __________ REPORT that 1P-27A, Heater Drain Tank Pump CHECK applicable box below:
start was normal. 4.2 STOP a Heater Drain Tank Pump as follows:
REPORT that 1P-27C, Heater Drain Tank Pump 4.2.1 SELECT HDT Pump to be SECURED and CHECK applicable coast down was normal, is stopped and is not box below.
rotating backwards. 4.2.2 STOP HDT Pump selected in Attachment M Step 4.21.
4.2.3 IF indications exist that HDT Pump is rotating backward, THEN SHUT the associated Pump Discharge Valve and CHECK applicable box below:
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 15 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 2: Lower Power utilizing OP 3A Unit 1, Power OS1 Implements OP 3A Unit 1, Power Operation to Hot Standby Unit 1 Lower Power Operation to Hot Standby Unit 1 for TS-3 5.1.9 MAKE notification of load reduction in accordance with NP utilizing OP 3A 2.1.5, Electrical Communications, Switchyard Access and Work Unit 1, Power Expected Communications: Planning Operation to Hot None 5.1.10 NOTIFY Auxiliary Operators (AOs) to monitor the following Standby Unit 1 for during load reduction TS-3 Continuation Criteria: 5.1.11 IF returning to full load THEN RECORD positon of Valve After the crew has reduced power 3% to 5%, or at Position Limiter (VPL AND Governor Valves for subsequent the discretion of the Lead Examiner, continue to the return to full load Start: _________ next event. 5.1.12 IF load reduction is to take turbine off line, THEN RUN a review of points Scan Removed, Alarm Check Removed, and Limit Check Removed on PPCS, AND MAINTAIN in Control Operators notebook.
5.1.13 SET PPCS trends as desired 5.1.14 REDUCE PPCS constants for SG Blowdown Flow by 5 klb/hr 5.1.15 IF desired, THEN PLACE an additional LETDOWN Orifice in service 5.1.6 ENERGIZE backup heaters to recirc Pressurizer for born, as required.
5.2 Beginning Load Reduction 5.2.1 ESTIMATE amount of boron/rod motion needed for desired load change, and REFER to PPCS Xenon program for timing estimates Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 16 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP 5.2.2 PERFORM the following to be being reducing load:
- a. RECORD time in Narrative Log Expected Communications: b. ENSURE EH Control in OPER AUTO WHEN directed to start 1P-99A and 1P-99B SGFP c. IF Turbine control is on Valve Positon Limiter (VPL), THEN Seal Water Injection Pumps, insert Trigger 1 and TRANSFER turbine control from VPL as follows:
st THEN report when they are started. d. IF Turbine control is in 1 STG OUT mode, AND is st required to go to 1 STG IN, AND Reactor power is less st than 97%, THEN PRESS 1 STG IN pushbutton to shift st Turbine control to 1 STG IN mode
- e. PRESS Reference Control (lower) pushbutton to set terminal load (SETTER) consistent with target load in accordance with Step 5.1.1
- f. SET desired ramp rate (Consistent with Step 5.1.7), using thumbwheel
- g. PRESS GO pushbutton AND CHECK REFERENCE display indicates a controlled load reduction at selected rate 5.2.3 START SG Feed Pump Seal Water Pumps as required 5.2.4 IF unit is to be shutdown or operated at less than or equal to 10% load for greater than 15 minutes, THEN THROTTLE SHUT MSR Control Valves using manual operation of controller 1HC-2085, AND INITIATE Crossover temperature reduction at a rate of less than or equal to 25°F per 30 minutes 5.2.5 IF unit is to remain on line at greater than 10% load, THEN THROTTLE SHUT MSR Control valves using manual operation of controller 1HC-2085, MSR Steam Supply Controller (1C03) AND MAINTAIN crossover temperature less than 500°F Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 17 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE OATC/BOP 5.3 Performance Requirements During Load Reduction 5.3.1 MAINTAIN controls in auto as practicable 5.3.2 MAINTAIN Axial Flux Difference (AFD) within limits specified in COLR.
5.3.3 MAINTAIN Control banks within the insertion, sequence and overlap limit specified in the COLR 5.3.4 REFER to PPCS Xenon program for Xenon follow information 5.3.5 MAINTAIN Tavg within 1.5°F of Tref 5.3.6 ADJUST Power Range NIS as directed by 1-TS-RE-001, Power Level Determination Unit 1, if required 5.3.7 MAINTAIN 345 KV voltage in accordance with OP 2B, 345 KV Transmission System Impacts Upon PBNP Station Operations, section 345 KV Voltage Control 5.3.8 MAINTAIN controller setpoint for LP Feedwater Heater Bypass Valve (1CS-2273) at 25 psig below SG Feed Pump suction pressure (except when singling up feed trains in accordance with Step 5.5.2.b 5.3.9 MONITOR Ice Melt operations as necessary Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 18 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 3: Trigger 3 [MAL1NIS007C, P.R. CHANNEL N43 OATC Identifies failing 1NI-43 Power Range Nuclear Instrument and 1NI-43, Power HIGH VOLTAGE FAILURE, RAMP = 27, unexpected / unwanted outward rod motion. OATC may take rods to Range Nuclear VALUE = 300] manual after reporting malfunction and attempting to or obtaining Instrument fails concurrence from OS1.
low (outward rod Insert Trigger 3 to cause 1NI-43, Power Range motion at or near Nuclear Instrument to fail low (outward rod motion at OS1 Implements AOP-6C, Uncontrolled Motion Of RCCA(s) 12-15 steps/min) or near 12-15 steps/min) If practical, start this event 1. Check Rod Motion - Required with rod control in automatic. RNO Place rod control bank selector switch to - MANUAL Start: __________ 2. Maintain RCS Tavg:
Plant Response: 3. Check RCS Tavg - AT OR TRENDING TO Tref The voltage fails to the selected value. The detector RNO IF fuel has been conditioned, THEN move control rods in operates in the ion chamber region. The normal manual or adjust turbine load to restore Tavg.
value is 800 volts. At 700 volts decreasing the loss 4. Check Control Rods - ABOVE MINIMUM INSERTION LIMIT of detector voltage alarms. Alarms for low failure 5. Verify AFD - WITHIN LIMIT include Power Range Channel Deviation, Power 6. Check Rod Motion Due To Instrument Failure Range Loss Of Detector voltage and Power Range 7. Go to AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS Rod Drop.
Cues:
1C04 1A 1-7, Automatic Rod Motion Implements AOP-24, Response to Instrument Malfunctions 1C04 1A 3-2, 1N-41, 42, 43, or 44 Power Range 1. Identify Failed Instrument Loss of Det Voltage 2 Check If Failed Instrument Is A Controlling Channel 1C04 1A 3-3, Power Range Channel Deviation 3. Establish Manual Control As Required 1C04 1A 4-5, Power Range Rod Drop 4. Return Affected Parameter(s) To Desired Value(s) 1N-43B, 1N-43Power Range Power indicating at 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE a lower value REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT Outward Rod Motion An Input To RTO
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, ROUTINE MAINTENANCE PROCEDURE REMOVAL OF SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE
- 7. Return Controls To Automatic If Desired
- 8. Check Failure For Technical Specification Or TRM Applicability
- 9. Return To Procedure And Step In Effect Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 19 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: None Prepares to implement 0-SOP-IC-001 Blue, Routine Maintenance Procedure Removal Of Safeguards Or Protection Sensor From Service - Blue Channels Continuation Criteria:
Once the crew has addressed Technical Specifications or at the discretion of the Lead Examiner, continue with the next event.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 20 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Reference Technical Specifications Technical Specifications:
3.2.4 (SR 3.2.4.1, Verify QPTR is In accordance with the Surveillance 3.2.4.2) Quad. Power within limit by Frequency Program Tilt Ratio calculation Verify QPTR is within limit using the moveable incore detectors Table 3.3.1-1 item 2a D. One channel D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Power Range inoperable OR Neutron Flux-High D.2 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Table 3.3.1-1 item 2b Power range Neutron Flux-Low Table 3.3.1-1 item 5 OverTemp Delta T Table 3.3.1-1 item S. One or more S.1 Verify interlock is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 17b-1 PR Neutron channel(s) in required state Flux P-7 inoperable for existing conditions.
Table 3.3.1-1 item OR 17c PR Neutron Flux S.2 Be in MODE 2 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> P-8 Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 21 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 4: Trigger 5 [XMT1SGN012A, 1-LT471 STM GEN B BOP Identifies the failing channel and takes 1FIC-476A, 1HX-1B SG 1LT-471, SG Level NR LEVEL FIXED OUTPUT, VALUE = Feedwater Regulating Valve Controller to manual, matches feed flow to fails low 19, RAMP = 90 sec] steam flow and controls actual level at or near program.
OS1 Insert Trigger 5 to cause 1LT-471, 1HX-1B SG Implements AOP-2B Unit 1, Feedwater System Malfunction Start: __________ Narrow Range Level Transmitter to fail low. Monitor Foldout Page BOP 1. Maintain Reactor Power Less Than or Equal to 100%
Plant Response: 2. Determine the Secondary System Malfunction AND go to the The controlling channel lowers to 19%. The SGWLC appropriate step (12) system responds by modulating open the affect 12. Perform The Following For The Feed Regulating Valves:
SGs feedwater regulating valve to restore level to a. Check Feed Regulating Valve Response - NORMAL program. Actual level rises to the 78% lockout. 1FIC-476A RNO Perform the following:
Cues: 1) Place affected feedwater regulating valve controller 1C03 1E2 1-5, Steam Generator B Level to manual or single element control Setpoint Deviation/Trouble o 1FIC-476A 1C03 1E2 4-4, Seam Generator B Low-Low 2) Match feed flow to steam flow Level Channel Alert 3) Stabilize steam generator level at programmed 1LI-471 SG B Level (controlling channel lowers level.
to 19% 4) IF transient caused by instrument failure, THEN defeat failed instrument per AOP-24, RESPONSE TO INSTRUMENT MALFUNCTIONS
- 5) Direct I&C to identify and correct cause of failure
- b. Return to Step 2
- 3. Check Plant Conditions - STABLE
- 4. Check Secondary System Alignment - NORMAL
- 5. Check Change in Reactor Power - LESS THAN 15% IN ANY ONE HOUR
- 6. Notify the DSM
- 7. Return To Procedure And Step In Effect Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 22 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE The crew should implement AOP-2B Unit 1, OS1 Implements AOP-24, Response to Instrument Malfunctions Feedwater System Malfunction, AOP-24, Response to Instrument Malfunctions, and address Technical BOP 1. Identify Failed Instrument Specifications 2 Check If Failed Instrument Is A Controlling Channel
- 3. Establish Manual Control As Required Expected Communications: 4. Return Affected Parameter(s) To Desired Value(s)
None 5. Using Attachment A, PPCS PARAMETERS USED TO CALCULATE REACTOR THERMAL OUTPUT, Verify That Failed Instrument Is NOT Continuation Criteria: An Input To RTO
- 6. Remove Failed Instrument Channel From Service Per 0-SOP-IC-001, After the crew has taken manual control or shifted ROUTINE MAINTENANCE PROCEDURE REMOVAL OF the controller to single element, stabilized the unit SAFEGUARDS OR PROTECTION SENSOR FROM SERVICE and addressed Technical Specifications, or at the 7. Return Controls To Automatic If Desired discretion of the Lead Examine, continue on with the 8. Check Failure For Technical Specification Or TRM Applicability next event. 9. Return To Procedure And Step In Effect BOP Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 23 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE CREW Reference Technical Specifications Technical Specifications:
RPS LCO 3.3.1 is not met (3.3.1-1 item 13)
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Enter the Condition Immediately Functions with one referenced in Table or more required 3.3.1-1 for the channels or trains channel(s) or inoperable. train(s).
D. One channel D.1 Place channel in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. trip OR 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> D.2 Be in MODE 3 RPS LCO 3.3.2 is not met (3.3.2-1 item 5b and 6b)
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Enter the Condition Immediately Functions with one referenced in Table or more required 3.3.1-1 for the channels or trains channel(s) or inoperable. train(s).
D. One or more D.1 Place channel in trip 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel(s) OR inoperable. D.2.1 Be in MODE 3 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND D.2.2 Be in MODE 4 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 24 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 5: Trigger 7 [XMT1CVC020A, 1-LT141 VCT LEVEL OATC Identifies failed channel and references ARB 1C04 1C 1-7, 1T-4 Volume 1LT-141, VCT FIXED OUTPUT, VALUE = 0, RAMP = 5 Control Tank Level High Or Low Level Transmitter sec]
fails low OS1 Implements AOP-1D Unit 1, Chemical and Volume Control System Insert Trigger 7 to cause 1LT-141, VCT Level Malfunctions Reactor trip Transmitter to fail low. 1. Check RCS Leak - NOT IN PROGRESS breakers fail to auto open; first Plant Response: OS1 Monitor Foldout Page reactor trip push Charging pump suction shifts from the VCT to the CHARGING PUMP SUCTION SUPPLY CRITERIA:
buttons do not RWST. IF charging pump suction is from VCT and VCT level can NOT be work, reactor maintained greater than 8%, THEN shift charging pump suction to manually trips on The reactor trip breakers will not open on an auto RWST:
second signal; the first set of reactor trip push buttons a. Open RWST to Charging Pump Suction MOV pushbuttons attempted do not work when depressed. The reactor 1CV-112B can be tripped from the control room using the b. Shut VCT Outlet to Charging Pump Suction MOV second set of reactor trip pushbuttons. 1CV-112C
- c. Manually trip reactor Start: __________ Cues: d. Stabilize plant using EOPs while continuing with this procedure 1C04 1C 1-7, 1T-4 Volume Control Tank Level High Or Low OS1 Orders a manual reactor trip.
1LI-141 on 1LR-112 indicates 0%
1CV-112C, 1T-4 VCT Outlet to Charging Pump CT-1, Manually Trip The Reactor Suction MOV indicates closed 1CV-112B, 1T-13 RWST to Charging Pump Suction MOV indicates Open Reactor remains at power until the reactor is tripped.
52/RTB AND 52/RTB indicate closed until the reactor is tripped.
Expected Communications:
IF an AO is dispatched to locally investigate LT-141, VCT Level Transmitter, wait two minutes and THEN report that locally there doesnt seem to anything out of normal.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 25 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Continuation Criteria:
If the crew decides to NOT manually trip the reactor, THEN with Lead Examiner concurrence, initiate the faulted SG event. (The faulted SG will result in an auto SI; the reactor will not automatically trip. A manual reactor trip will still be required, CT-1)
Event 6: Trigger 9 [MAL1SGN003B, SG B MAIN SEAM OS1 Implements EOP-0 Unit 1, Reactor Trip or Safety Injection 1HX-1B SG faults LINE BEAK INSIDE CNMT, VALUE 1. Verify Reactor Trip to containment 5.0E5, RAMP = 60 sec] RNO Manually trip reactor upon reactor trip 2. Verify Turbine Trip Trigger 9 is conditional upon a reactor trip. 1HX-1B 3. Verify Power to AC Safeguards Buses SG faults to containment. Reactor trip breakers fail 4. Check if SI is Actuated to auto open; reactor trip push buttons on 1C04 do OATC not work. Monitor Foldout Page Criteria:
Faulted SG Isolation Criteria Start: _________ Plant Response: IF any SG pressure trending lower in an uncontrolled manner OR any Containment humidity, temperature, pressure and SG completely depressurized, THEN the following may be performed:
sump level will increase and alarm. Safety Injection a. Isolate feed flow to faulted SG and Containment Isolation actuate. Condensate, b. Maintain total feed flow greater than or equal to 230 gpm until feedwater and Heater Drain Pumps trip. Main narrow range level in at least one SG is greater than [51%] 32%.
Steam Isolation valves close. Containment Spray actuates. The steam generator will blow dry.
Operator action is necessary to secure feedwater to the faulted SG.
Cues:
Indicated steam flow on 1HX-1B Steam Generator Degrading containment conditions; containment humidity, temperature, pressure and sump level will increase and alarm.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 26 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Event 7: BOP 5. Perform ATTACHMENT A, Automatic Action Verification while Auxiliary Plant Response: continuing with the procedure Feedwater Loss of main and auxiliary feedwater results in 6. Verify AFW Pumps - RUNNING malfunctions: 1P- lowering steam generator levels. a. Motor-driven pump - RUNNING 53, Motor-Driven b. Turbine-driven pump - RUNNING AFW Pump - Cues: RNO: Manually open both steam supply valves to turbine-sheared shaft and 1MS-2082 1P-29 AFP LOW SU/OVRSPD TRIP driven pump 1P-29, Turbine- VALVE PLOSITON - Amber Light - ON IF AFW flow NOT established, THEN perform the Driven AFW Pump 1FI-4002, 1P-29 AFP DISCHARGE FLOW following:
- trips on indicates zero 1) Place Stripping Logic Override Switch to the overspeed 1PI-4005, 1P-29 AFP DISCH PRESS indicates OVERRIDE position.
zero 2) Start Standby Steam Generator feed pump (s):
1FI-4073, 1P-53 AFP TOTAL DISCHARGE 3) Verify valve alignment:
FLOW indicates zero a) Open Unit 1 valve(s):
1PI-4071, 1P-53 AFP DISCH PRESSURE AF-4023, train A indicates zero AF-4021, train B b) Ensure Unit 2 valves - SHUT AF-4022, train A AF-4020, train B c) Manually align valve(s) as necessary to establish flow greater than or equal to 230 gpm.
AF-4012, train A AF-4019, train B
- c. Verify total AFW - GREATER THAN 230 gpm RNO IF SG level is less than [51%] 32% in both SGs, THEN perform the following:
- 1) Manually align valve(s) as necessary to establish flow greater than or equal to 230 gpm.
- 2) IF AFW flow greater than or equal to 230 gpm can NOT be established, THEN go to CSP-H.1 Unit 1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 27 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: OS1 IMPLEMENT CSP-H.1 Unit 1, Loss of Heat Sink
- 1. Check If Secondary Heat Sink Is Required:
- 2. Check If RCS Bleed And Feed Is Required:
Note: The intended sequence for the restoration RNO: Perform the following:
of feed is first from 2P-53 via unit cross-connect 1) Monitor bleed and feed conditions valves, then second from 1P-29 by resetting the 2) If any bleed and feed condition occurs, then do steps 2.b OS trip mechanism. and 2.c
- 3) Observe the caution prior to Step 3 and continue with For 1P-29: Step 3 IF an AO is dispatched to locally investigate 1P- BOP 3. Establish Feed Flow From TDAFW Pump 29, Turbine-Driven AFW Pump, wait until the a. Check TDAFW Pump available:
crew has entered CSP-H.1 and THEN report that 1) Suction pressure trip - NOT ACTUATED the pump has tripped on overspeed and the 2) Overspeed trip - NOT ACTUATED overspeed trip mechanism is intact. RNO: Go to Attachment A, RESET/OVER-RIDE AFW PUMP WHEN directed by the crew to reset 1P-29 OS TRIPS, to reset trips AND continue with Step 4.
trip mechanism, THEN report that while 4. Establish Feed Flow From MDAFP attempting to reset the mechanism will not latch a. Check MDAFP available and that you are going to continue to try to get it 1) Suction pressure trip not actuated reset. 2) 1A06 available AFTER the crew has commenced feeding from b. Start 1P-53 U2 AFW, Insert TRIGGER 13, THEN report the c. Ensure MDAFP valves - PROPERLY ALIGNED OS trip reset. (verify MAL1AFW001 is deleted) d. Check total feed flow - GREATER THAN 230 gpm RNO: Go to Step 5 IF an AO is dispatched to locally investigate 1P- 5. Establish Feed Flow From Standby SSG Pumps 53, Motor-Driven AFW Pump, wait two minutes a. Check SSG Pumps available and THEN report that the motor is turning, but is b. Place stripping override switches to override no longer connected to the pump (shaft break). c. Start SSG Pumps He recommends securing the pump motor. RNO: Go to Step 6
- 6. Establish Feed Flow From Unit 2 MDAFP WHEN directed by the crew, insert Trigger 11, 1) Locally open MDAFP cross connects wait two minutes and THEN report that Unit 1 2) Start 2P-53 and Unit 2 AF-192, AFW Cross-connect Valves 3) Ensure Unit 1 MDAFP valves - PROPERLY ALIGNED are open. 4) Check total feed flow - GREATER THAN 230 gpm.
- 5) Go to Step 7 Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 28 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE BOP 7. Check S/G Blowdown And Sample Isolation:
- 8. Check Total Feed Flow to S/Gs - GREATER THAN OR EQUAL TO 230 gpm
- 9. Determine Procedure Transition:
o IF Feed and Bleed is NOT in progress, THEN return to procedure and step in effect CT-43: Establish feedwater flow to at least one SGs before bleed and feed is required EOP-0 continued BOP
- 7. Check RCP Seal Cooling
- 8. Check RCS Temperatures
- 9. Check PZR PORVs and Spray Valves
- 10. Check if RCPs should be stopped
- 11. Check if SGs are NOT Faulted RNO Go to EOP-2 UNIT 1, FAULTED STEAM GENERATOR ISOLATION OS1 Implement EOP-2 Unit 1, Faulted Steam Generator Isolation CAUTIONS:
One SG must be maintained available for RCS cooldown.
If any faulted SG is not needed for RCS cooldown, it should remain isolated during subsequent recovery actions.
- 1. Check Main Steam Isolation
- a. Any MSIV valve - OPEN
- b. Check Main Steamline Isolation Signal - NOT ACTUATED
- 2. Check If Any SG Is Not Faulted
- 3. Identify Faulted SG Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 29 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Expected Communications: 4. Isolate Faulted SG WHEN directed to locally shut 1MS-237, 1P-29 a. Ensure feedwater isolation valves - SHUT AFP/Radwaste Steam Isolation and 1MS-238, o 1CS-3125 for SG B Main Steam Trap Isolation, insert Trigger 17 and BOP b. Ensure MDAFW valve - SHUT THEN report completed when the valve has o SG B repositioned.
- d. SSG supply valve - SHUT o SG B AF-4021
- e. Isolate flow from faulted SG:
- 5) Locally shut main steam trap isolation o 1MS-238 for SG B Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 30 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE
- a. Request Chemistry to periodically sample both SGs for activity
- b. Request local surveys of main steam lines
- c. Secondary system radiation monitor levels - NORMAL Condenser Air Ejector 1RE-215 RE-225 SG Blowdown 1RE-219 1RE-222 Main Steam Lines 1RE-232 for SG B
- d. Secondary activity samples and surveys - Normal (When available)
- 7. Go to EOP-1 UNIT 1, LOSS OF REACTOR OR SECONDARY COOLANT Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 31 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE EOP-0 Unit 1, Attachment A BOP EOP-0 Unit 1, Attachment A, Automatic Action Verification Expected Communications: A1 Verify Feedwater isolation A2 Verify Containment Isolation WHEN directed to locally check shut RW Service A3 Verify ECCS Pumps RUNNING Water valves, LW-61 and 62, THEN report both A4 Verify Service Water Pumps RUNNING valves are closed. A5 Verify Containment Accident Cooling Units RUNNING WHEN directed to locally check CW pump house A6 Verify Component Cooling Water Pumps - ONLY ONE RUNNING temperature <105 ºF, wait 3 minutes and THEN A7 Check If Main Steam Lines Can Remain Open report the temperature is 72 ºF and stable. A8 Verify Containment Spray Not required WHEN directed to locally check G03/G04 a. Containment pressure recorder - HAS REMAINED LESS Switchgear Room temperature <95 ºF, wait 3 THAN 25 psig minutes and THEN report the temperature is 75 ºF RNO Perform the following:
and stable. 1) Check containment spray actuated:
IF directed to periodically check the status of Annunciator {C01 B 2-6}, CONTAINMENT spent fuel cooling, wait 5 minutes and THEN SPRAY, lit report Spent Fuel Pool level is 63 feet, pool IF containment spray has NOT actuated, THEN temperature is 67 ºF and both are stable. manually actuate containment spray.
A9 Verify ECCS Flow A10 Verify AFW valve alignment - PROPER EMERGENCY ALIGNMENT A11 Verify Proper ECCS Valve Alignment A12 Check Containment Spray NOT ACTUATED via the blender in progress A14 Ensure the Auxiliary Building Filter/Exhaust Fans - OPERATING A15 Verify Service Water System Alignment A16 Check Miscellaneous Valves - SHUT A17 Check Control Room Ventilation A18 Check Cable Spreading Room Ventilation System - OPERATING A19 Check Computer Room Ventilation System - OPERATING A20 Check AFW Recirc fans - ONE RUNNING A21 Check Circulating Water Pump House Temperature Less Than 105°F A22 Check G03/G04 Switchgear Room Temperature less than 95°F A23 Periodically check status of spent fuel cooling Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 32 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY POSITION EXPECTED STUDENT RESPONSE Implements EOP-1 Unit 1, Loss of Reactor or Secondary Coolant Termination Criteria: OS1 Terminate the scenario when crew has completed Monitor Foldout Page Criteria:
End: ______ Step 5 of EOP-1.1 Unit 1, SI Termination or at the SI Termination Criteria discretion of the Lead Examiner. IF all conditions below occur, THEN go to EOP-1.1, SI TERMINATION:
RCS Subcooling based on core exit thermocouples - GREATER THAN [74 ºF] 35 ºF Secondary heat sink available:
o Any Intact SG level - GREATER THAN [51%] 32%
OR o Total feed flow to intact SGs - GREATER THAN OR EQUAL TO 230 GPM RCS pressure - GREATER THAN [1850 PSIG] 1725 PSIG RCS pressure - STABLE OR RISING PZR Level - GREATER THAN [32%] 13%
OS1 Implements EOP-1.1 Unit 1, SI Termination BOP 1. Reset SI
- 2. Reset Isolation And Lockout Signals
- 3. Establish Instrument Air To Containment
- 4. Check If Charging Flow Has Been Established
- 5. Stop ECCS Pumps And Place In Standby:
- a. Stop both SI pumps and place in auto:
1P-15A 1P-15B
- c. Stop both RHR pumps and place in auto:
1P-10A 1P-10B
- END OF SCENARIO ***
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 33 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG QUANTITATIVE ATTRIBUTES (Use this form for NRC/INPO Evaluations only as required to document associated quantitative information.)
Malfunctions:
Before EOP Entry:
1N-43, Power Range Nuclear Instrument fails low 1LT-471, SG Level Transmitter fails low 1LT-141, VCT Level Transmitter fails low After EOP Entry:
1HX-1B SG faults to containment upon reactor trip Reactor trip breakers fails to auto open; reactor trip push buttons on 1C04 or C01 do not work Auxiliary Feedwater malfunctions 1P-53, Motor-Driven AFW Pump - sheared shaft 1P-29, Turbine-Driven AFW Pump - trips on overspeed Abnormal Events:
1N-43, Power Range Nuclear Instrument fails low 1LT-471, SG Level Transmitter fails low 1LT-141, VCT Level Transmitter fails low Major Transients:
1HX-1B SG faults to containment upon reactor trip Auxiliary Feedwater malfunctions (Loss of Heat Sink) 1P-53, Motor-Driven AFW Pump - sheared shaft 1P-29, Turbine-Driven AFW Pump - trips on overspeed Critical Tasks:
- 1. CT-1 Manually trip the reactor
- 2. CT-43 Establish feedwater flow to at least one SGs before bleed and feed is required Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 34 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG CT-1 Manually trip the reactor Applicable ERG LP Version Applicable ERG Critical Task:
Manually trip the reactor from the control room before completing immediate actions in EOP-0 Plant Conditions:
Reactor greater than 5% power Plant parameters exist that should result in automatic reactor trip but reactor does not automatically trip o RCPs tripped Reactor can be tripped manually from control room Cues:
Indication and/or annunciation that plant parameter exist that should result in automatic reactor trip but reactor does not automatically trip Performance Indicator:
Manipulation of control room reactor trip switches as required to trip the reactor o Reactor trip and bypass breakers indicate open Feedback:
Indications of reactor trip Control rods at bottom of core Neutron flux decreasing Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 35 of 37
PBN LOI NRC 18E, 2017 NRC Exam Scenario 4, Rev. 0 SEG CT-43 Establish feedwater flow to SGs before bleed and feed is required Applicable ERG HP, LP Version Applicable ERG FR-H.1 Critical Task:
Establish feedwater flow to at least one SGs before bleed and feed is required.
Plant Conditions:
Extreme (RED path) challenge to the heat sink CSF Plant conditions require SGs as heat sinks AFW flow is not sufficient and cannot be increased Feedwater flow is available but not established from any of the following:
- Main feedwater pumps
- Condensate pumps
- Plant-specific alternate source (Unit 2 AFW)
Indication that RCS bleed and feed is not required Reactor trip and SI Cues:
Extreme (RED path) challenge to the heat sink CSF AND Indication that RCS pressure remains above the pressure of all SGs AND Indication that RCS temperature is above the temperature for placing the RHR system in service AND Indication and/or annunciation that no AFW flow is available after repeated attempts to establish AND Indication that RCS bleed and feed is not required Performance Indicator:
Manipulation of controls as required to establish feedwater flow into at least one SG Feedback:
Indication of feedwater flow into at least one SG Indication of increasing water level in at least one SG Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 36 of 37
TURNOVER INFORMATION SEG 1.0 Plant Conditions:
Unit 1 Unit 2 Time in Core Life (MWD/MTU): 9005 Reactor Power: 100%
Boron Concentration: 1078 ppm Rod Height: CBD @ 220 2.0 Equipment Out of Service:
1LT-112 VCT Level Transmitter 1W-3B, Control Rod Shroud Fan 3.0 Technical Specification LCOs NOT Met and Action Conditions in Effect:
None 4.0 Planned Evolutions:
Unit 1 is at approximately 100% EOL.
1LT-112, VCT Level Transmitter has failed low 1CV-112A is in TO VCT position and VCT level is being manually controlled between 17% and 78% per AOP-1D I&C expect repairs to be completed within the hour and returned to service by the end of the shift.
Start 1P-27A, Heater Drain Tank Pump and secure 1P-27C, Heater Drain Tank Pump per OP-2A Attachment M, in preparation for maintenance.
Lower Power utilizing OP 3A Unit 1, Power Operation to Hot Standby Unit 1 for TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Biannual) Unit 1
5.0 Common
Safety Monitor is Green Today is Sunday, clock time is real time and you have a normal shift complement.
Filename: NRC Scenario 4 draft.doc TR-AA-230-1003-F06 Revision 0 Page 37 of 37