ML22243A214
| ML22243A214 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/26/2022 |
| From: | Jim Nance NRC/RGN-III/DRS/OLB |
| To: | Xcel Energy |
| Nance J | |
| Shared Package | |
| ML21188A222 | List: |
| References | |
| Download: ML22243A214 (26) | |
Text
Form 2.3-3 Operating Test Review Worksheet (JPMs)
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL GENERAL COMMENTS E
S o Please provide use history of JPMs (i.e.,
When were they used on any NRC exam, IF applicable). (Complete) o Please provide all marked-up procedures to be given to examinees in the appropriate JPM packages.
(Complete) o Administrative JPMs are very short -
average <6 minutes (Ref. NUREG 1021, Rev 12, ES-3.2, Page 4 of 18). (Noted) o JPMs reference FP-T-SAT-73, Licensed Operator Requalification Program Examinations. Is this appropriate?
(Addressed at OSV)
Response
Complete for applicable JPMs Complete Noted Addressed at OSV SIM a Restore RCS Tave and Respond to Dropped Rod RD-6SF-2:
S Y
2 S
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SIM b SP1130B Train B CNTMT Vacuum Breaker Qtr Test ZC-3S-1 S
N 2
E S
NRC: 1) Include original JPM and how it was modified. 2) Add to terminating cue that the examinee has completed steps 7.4 through
7.5.6. Response
- 1) Outline changed to bank JPM. Facility believes this JPM does not meet the NUREG 1021 criteria for significantly modified. 2) Incorporated SIM c Periodic Rotation of Charging Pumps and Respond to Fire in 1K1 RC-26SF-1 EARLY SUBMITTAL S
Y 3
X E
NRC: 1) In the third step, the examinee places 12 Charging Pump speed control to AUTOMATIC - this is a critical step that is required to accomplish the task standard. 3)
K/A mismatch (RCPs not CCPs). 4) Revision 1 should be noted on cover sheet. 5) The alternate path is unrelated to CCPs (Ref.
NUREG 1021, Rev 12, page ES-3.2, Page 9 of 18, Paragraph E) 6) Second performance step (top of page 4) Add to end of Standard statement, (while maintaining seal injection flow) 7) Page 5 of 10, there are 2 performance steps in one box. 8) In order for this to be an alternate path JPM, that is new or modified, which is required, there needs to be steps where the charging pump or its auto circuit is the cause of the fire and charging comp actions are a result.
Response: 1-8) JPM replaced based on Comment 8.
NRC: See replacement JPM below
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SIM c Periodic Rotation of Charging Pumps with Charging Pump Trip and Restoration of Seal Injection RC-26SF-2 S
Y 3
E S
NRC: Add clarifying statements to Evaluator Notes on status of 12 Charging Pump and expected seal injection flow following the start of 13 Charging Pump Response: Completed SIM d 12 MDAFWP Monthly Test with 12 MDAFWP Overload AF-22SF S
Y 3
X U
S NRC: 1) Clearly specify when and where the overload alarm is received. 2) Performance Step SP1100, step 7.9 - Is marked not critical. Starting the pump is part of the Task Standard starts 12 MD AFWP, and is therefore a critical step. 3) Step 7.3, add (Hold for 5 seconds after green indication),
to Standard.
Response: 1) Incorporated as Evaluator Note. 2) Corrected. 3) Added to steps 7.3 AND 7.4, however, facility believes that portion would not be considered critical. This will be documented in an evaluator note.
Facility believes if this step were not completed satisfactorily, a small amount of water may flow into the SG which would be accounted for by SGWLC. The difference is trivial.
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SIM e Raise PRT Pressure RC-27S S
N 2
E S
NRC: 1) The K/A catalog has the referenced K/A as being SF 5 (versus SF 3 per the outline - Form 3.2-2). 2) Remove ERCS from Task Standard on page 3 of 8. 3)
Initiating Cue says between 5 and 6 psig and performance steps say 6 +/- 1, please reconcile.
Response: 1) Changed KA to 007 A2.02, which is SF5. Outline updated. 2) Agree.
- 3) Aligned all cues to say 6 +/- 1 SIM f Remote Start of D2 With Lookout, Rev 0 EG-22SF (SIM f)
S Y
3 E
S NRC: 1) Clearly indicate where the D2 Emergency Generator Lock Out alarm is received. 2) How does the candidate verify that the diesel generator is locked out? 3)
This is not a complete KA match - Ability to manually operate and/or monitor in the control room: Manual starting, loading, and stopping of the EDG Suggest continuing the JPM through step 5.2.2 H and then locking out the DG.
Response: 1) Added as an Evaluator Note.
- 2) Added as an Evaluator Note. 3) Changed KA to 064 A1.10 based on mutual agreement with NRC at OSV.
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SIM g Secure R11/12 in the Control Room RM-5S S
N 3
E S
NRC: The cue and the Task Standard states removing 1R11 and 1R12 from service. If it is desired to only remove only 1R11 from service, designate that, and adjust the procedures, cues, and Task Standard accordingly. 2) Performance Step C11 step 6.4.8.C.6: Standard: Examinee enters the pumps status change subroutine. Add the term (flashes)to the end of the Standard.
Response: 1) Turning the pump off removes both R11 and R12 from service. No changes made. 2) Added as an evaluator note.
Licensee believes that adding it to the standard may have unintended grading consequences.
SIM h SP1112 Steam Exclusion Monthly Damper Test ZD-1S:
S N
3 E
S NRC: 1) The K/A catalog has the referenced K/A as being SF 2 (versus SF 8 per the outline - Form 3.2-2). 2) Performance Step SP 1112, step 7.1.5 page 6 of 10 is not a critical step.
Response: 1) Mutual agreement reached with NRC to change KA to 050 A4.03, which is SF 9. Outline updated. 2) Comment will be incorporated. Comment was incorporated into the task standard and terminating cue.
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL IP i Investigate Containment Condensate High Leak Rate CL-19 Unit 1 P
N 2
E S
NRC: 1) Please provide the original JPM and pedigree for M JPM. 2) Where is the equipment located - since the applicant must go there. 3) Verify outline lettering.
Response: 1) Outline changed to new JPM.
Upon further review, facility determined this JPM is new rather than modified. A sig mod version does not exist in bank. 2)
Locations added. 3) Complete IP j Restore 121 & 123 IA Compressors F5-19 P
N 3
E S
NRC: 1) Where is the equipment located -
since the applicant must go there. 2) Verify outline lettering.
Response: 1) Locations added. 2) Complete
IP k RADIOACTIVE Gas Release with High RAD Alarm WG-5F P
Y 2
E S
NRC: 1) Where is the equipment located -
since the applicant must go there. 2) The applicant needs to inform the Control Room of the failure and subsequent actions. 3)
Verify outline lettering. 4) Why is this considered to be an Alternate Path JPM?
(Ref. ES-3.2, p. 9; Success Path) 5)
Shouldnt this be reported to the MCR?
Response: 1) Locations added.
- 2) Not incorporated. R30/R37 causes CR alarms, thus facility believes notifying the CR is a non-critical step. Previous NRC examiner feedback has been to not include non-critical steps after the task standard is complete This would be a non-critical step that occurs after the terminating cue. Facility believes this does not add discriminatory value to the JPM. 3) Complete. 4) The operator is required to use a different procedure to mitigate conditions related to the task that arise during the course of actions taken. If examinee does nothing, the CV does not return to normally closed, as such they would fail that step. The alarm automatic action is to close the CV, which in this case, does not happen due to fault. The examinee must then use a different procedure and take manual action to accomplish the task. Exam already has 4 alternate path JPMs which meets the minimum requirement. 5) See number 2.
RO A.1.1 Determine Initial Deborating In-Service Time Admin-125 A
N 2
E S
NRC: 1) Explain how step 1 is determined in the JPM step - is there a data sheet that they could extract the appropriate data from instead of simply comparing 2 provided numbers? As a critical step, it needs to be more discriminating. (LOD=1). 2) Include the marked-up procedure for the steps.
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL Response: 1) There is no data sheet with this information. A chemist calls the control room and provides this information verbally. Changed initial cue to A Chemist is available to take boron samples and adding an evaluator cue to provide an attachment stating this information. This was verbally agreed to during phone discussion with CE.
- 2) Complete RO A.1.2 RIL Verification During A Loss of ERCS Admin-136 A
N 3
E S
NRC: 1) Attachment 4 gauges are difficult to read. Rescale to improve readability. 2)
Include the marked-up procedure and references. 3) Describe how step 1 is determined in the JPM step. 4) Revise Initiating Cue to: The Shift Supervisor directs you to evaluate 1C1.5, Operation Without Computer, step 6.1.6 and determine if Rod Insertion Limits (RIL) are being exceeded. and remove Y/N question.
Response: 1) Complete. 2) Complete. 3)
Complete. 4) Incorporated.
RO A.2 SP 1001B FOR HIGH CONTAINMENT PRESSURE Admin-133 A
N 3
E S
NRC: In Performance Step 2 under Standard, change narrow to wide.
Response: Complete
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL RO A.4 Determine Maximum RCS Venting Time ADMIN-86 EARLY SUBMITTAL A
N 3
E S
NRC: 1) Determine containment temperature is a critical step, it must be read somewhere, not simply provided. Have them call up the right point in ERCS and then provide them Attachment 4A with that information ONLY. 2) Determine RCS Pressure is a critical step, have them call up the right point in ERCS and then provide them Attachment 4B with that information ONLY. 3) Determine containment hydrogen concentration is a critical step, have them call up the right point in ERCS and then provide them Attachment 4C with that information ONLY. 4) The task standard must be made more precise, so that intermediate CS completion is needed.
Response: 1) Made step NOT critical.
Update cue and standard. Verbal agreement from CE. 2) Made step NOT critical. Update cue and standard. Verbal agreement from CE. 3) Made step NOT critical. Update cue and standard. Verbal agreement from CE.
- 4) Complete
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SRO A.1.1 Initiation of a Tech Spec Required Shutdown Notification, Rev 1 Admin-131 A
N 2
E S
NRC: 1) A more discriminating evaluation tool could include written notification requirements and/or the notification requirements if the TS requirement(s) were met prior to completing the shutdown. 2) Use the original CUE and delete questions 1 & 2.
Response: 1) Not incorporated based on OSV comments. 2) Incorporated.
SRO A.1.2 Determine Heat Sink CSFST Color with ERCS OOS - Red, Rev 1 Admin-121 A
N 2
U NRC: This not a Conduct of Operations Administrative JPM. (Ref. ES-3.2, p.2) This JPM was replaced.
Response: Replaced with ADMIN-88 NRC: See replacement JPM below SRO A.1.2 Assess Shift Staffing Levels, Rev 2 Admin-88 A
N 3
E S
NRC: 1) Revise the CUE to: If Minimum Shift Staffing requirements are currently met AND can the STAs request be granted. and delete questions 1 & 2. 2) Replace family dinner plans with attend an after-hours class. 3) Change the arrival time to one and one half hours.
Response: 1) Changed cue. 2) After verbal discussion with CE, comment was not incorporated. 3) Incorporated.
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SRO A.2 Determine SFP Protected Equipment Requirements, Rev 0 Admin-130 A
N 2
E U
NRC: 1) Before Performance Step FIG C1-34 Spent Fuel Pool Heatup Curves, add a non-critical step where the examinee determines that time to 200F in the spent fuel pool is between 43.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 44.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (the standard). 2) Change Performance Step FIG C1-34 Spent Fuel Pool Heatup Curves to a Critical Step. 3)
Upon discussion about addressing the earlier enhancements, it was determined that due to changes in equipment and procedures, the JPM had only one critical step. The JPM was then determined to be UNSAT and required to be either modified or replaced.
Response: The JPM was replaced based on comments above.
NRC: See the replacement JPM below SRO A.2 Authorize the Installation of a Bypass, Rev 3 Admin-89 A
N 3
S
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SRO A.3 Authorize Emergency Radiation Exposure, Rev 6 Admin-37 A
N 3
E S
NRC: For the initial conditions, make the following changes: 1) Bullet #4, A 41 year old male Operator. 2) Bullet #5, A 57 year old male Radiation Protection Technician.
- 3) Dose rates in Unit 1 Auxiliary Building are as shown on the given radiation survey map (Provide a suitable survey map and update Evaluator Notes and Evaluator Cues in Performance Steps as necessary). 4) Steps 4.4, 4.5, 4.6, Delete Evaluator Cues as the information is given in the Initial Conditions or on the previous signed PINGP 600 forms provided to the examinee. 5) Performance Step PINGP 600 Step 5 - For Standard give either a reasonable band, or an absolute of 30 rem and the justification for why the final number or band was chosen. Change Mike Smith to John Jones, as Mike Smith is ineligible due to previous emergency expose.
Response: 1) Complete. 2) Complete. 3)
Complete. 4) Complete. 5) Mike smith changed to John Jones
Facility: Prairie Island Exam Date: August 8, 2022 1
JPM # or title 2
Type (S/P/A) 3 ALT (Y/N) 4 LOD (1-5) 5 JPM Errors 6
U/E/S 7
Explanation LOD REF IC TSK CUE CS TL SRO A.4 Determine Type of Evacuation and Assembly Point FOE SAE, Rev 0 Admin-132 A
N 3
E S
NRC: 1) Initial Conditions, 3rd bullet, typographical error (Site Are Emergency).
- 2) The change agreed to at OSV was not incorporated. The post OSV resubmittal was revised without NRC input. Revise the Initiating Cue to: The Shift Manager directs you to determine if an evacuation is REQUIRED, and if so, what type of evacuation is REQUIRED and what the associated assembly point is, using guidance of PINGP 1125, Control Room Shift Manager/Shift Supervisor Emergency Director Checklist.
Response: 1) Incorporated. 2) Incorporated.
Form 2.3-3 Instructions for Completing the JPM Table
- 1. Enter the JPM number and/or title.
- 2. Enter the type of JPM(S)imulator, (P)lant, or (A)dministrative.
- 3. Enter (Y)es or (N)o for an Alternate Path JPM.
- 4. Rate the level of difficulty (LOD) of each JPM using a scale of 1-5 (easy-difficult). A JPM containing less than two critical steps, a JPM that tests solely for recall or memorization, or a JPM that involves directly looking up a single correct answer is likely LOD = 1 (too easy). Conversely, a JPM with over 30 steps or a JPM that takes more than 45 minutes to complete is likely LOD = 5 (too difficult).
- 5. Check the appropriate block for each JPM error type, using the following criteria:
LOD = 1 or 5 is unsatisfactory (U).
REF: The JPM lacks required references, tools, or procedures (U).
IC: The JPM initial conditions are missing or the JPM lacks an adequate initial cue (U).
CUE: The JPM lacks adequate evaluator cues to allow the applicant to complete the task, or the evaluator cues are subjective or leading (U).
TSK: The JPM lacks a task standard or lacks completion criteria for a task standard (U).
CS: The JPM contains errors in designating critical steps, or the JPM lacks an adequate performance standard for a critical step (U).
TL: The JPM validation times are unreasonable, or a time-critical JPM lacks a completion time (U).
- 6. Mark the JPM as unsatisfactory (U), satisfactory (S), or needs enhancements (E). A JPM is (U) if it has one or more (U) errors as determined in step 5. Examples of enhancements include formatting, spelling, or other minor changes.
- 7. Briefly describe any JPM determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound JPM is marked by a satisfactory (S) resolution on this form.
Form 2.3-3 Operating Test Review Worksheet (Scenarios)
Facility: Prairie Island Scenario: PI-ILT-NRC-2201S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2201S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS EARLY SUBMITTAL X
E S
NRC: General comments: 1) Critical Tasks on p. 3 states PI-CT-18: Trip Reactor Coolant Pumps within 5 minutes of RCP trip criteria being met, but Critical Task Sheet # PI-CT-18 states Trip Reactor Coolant Pumps within 8 minutes of RCP trip criteria being met. Please indicate only the correct value (8 minutes). 2) Please add Form 3.3-1 to the front of the scenario guide (formerly ES-D.1). 3) Evaluate TS overlap issues at OV.
Response: 1) Complete. 2) Complete.
- 3) Addressed at OSV.
Event-1 Energize all PRZR Backup Heaters E
S NRC: Specify the procedure steps the applicants are using to accomplish tasks.
Response: Completed Event-2 Flexible Power Operations to 485 MW E
S NRC: Specify the procedure steps the applicants are using to accomplish tasks.
Response: Completed Event-3 PRZR PORV 1PCV-431 Leakage E
S NRC: 1) Specify the procedure steps the applicants are using to accomplish tasks. 2) The leakage (specify the approximate size of the leak) is identified leakage per the TS definition. Optional
Facility: Prairie Island Scenario: PI-ILT-NRC-2201S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2201S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS EARLY SUBMITTAL TS are inappropriate. 3) Tech Specs not consistent within the Scenario Guide nor between the Scenario Guide and the submitted Outline Response: 1) Complete. 2) 2 GPM Added. 3) Will update events 3 and 4 to be consistent across all locations.
Event-4 1PT-486 Blue Channel First Stage Pressure Fails Low E
S NRC: Specify the procedure steps the applicants are using to accomplish tasks.
Response: Complete.
Event-5 Loss of Gap/Support Cooling E
S NRC: Specify the procedure steps the applicants are using to accomplish the tasks.
Response: Complete.
Event-6 Small Break LOCA X
E S
NRC: 1) Specify the procedure steps the applicants are using to accomplish tasks. 2) CT-18 has a different definition in Events 6,7,8 (need to address the timing once RCP Trip criteria is met).
Response: 1) Complete. 2) Complete.
Event-7 Component Cooling pumps fails to start automatically E
S NRC: Specify the procedure steps the applicants are using to accomplish tasks.
Response: Complete.
Event-8 12 DD Cooling Water Pump Fails to Start Automatically E
S NRC: When does the crew secure RHR pumps? The guide should indicate when and by who (per what procedure).
Response: Modified SEG to allow terminating scenario regardless of RHR pump status. RHR pumps MAY be stopped by either ATC or BOP during 1E-1(depending on the speed that RO and SRO completes the EOPs vs the speed the BOP completes attachment L) if RCS pressure meets the requirements when crew reaches this step.
RHR pumps may NOT be stopped during this scenario if RCS pressure is continuing to lower throughout the scenario.
Facility: Prairie Island Scenario: PI-ILT-NRC-2202S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2202S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS General Comment E
S NRC: Evaluate TS overlap issues at OV.
Response: Resolved during OSV.
Initial Conditions S
NRC: 1) Changed initial rod height from 221 steps to 225 steps, why? 2) The initial conditions in the submitted outline (221 steps) is not consistent with the scenario guide (225 steps).
Response: 1) Feedback from licensed operators that control rods would be withdrawn to 225 for CDC. 2) Updated outline.
Event-1 Swap Auto HDT Pump per 1C28.4 S
Event-2 Thot Yellow Channel Fails High E
S NRC: 1) During OSV received 47013-0107 B and D Rod withdrawal Hi Limit alarm as an expected alarm. This alarm is not listed in the revised scenario guide. 2) Under return the following to Auto the bulleted items were reordered. Why was this change made?
Response: 1) Will add to expected alarms. 2) CE verbally agreed that no additional changes were necessary.
Event-3 1PT-478, 12 SG Pressure Blue E
S NRC: For Booth Operator 1., delete After the crew has assumed the duty and /or
Facility: Prairie Island Scenario: PI-ILT-NRC-2202S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2202S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS Channel Fails Low Response: Incorporated.
Event-4 11 Circ. Water Pump High Temp S
NRC: What is the reason 1C12.5, Unit 1 Boron Concentration Control, Step 5.10 is performed before Step 5.9?
Response: The last step of 5.10 directs performance of 5.9. The SEG reflects the order in which the sections are performed.
Event-5 Rapid Power Reduction S
Event-6 Turbine Trip /
ATWS E
S NRC: Under 1FR-S.1, Response to Nuclear Power Generation/ATWS, fourth major bullet down, second sub-bullet, revise to read, Open in-service BAST recirc valve to 50% - MV-32086 if that is the correct number.
Response: 1) The valve was left out of that step to match the procedure.
Updated to CV-31195. MV-32086 should be the valve for the next bullet. Will update that as well.
Event-7 12 MDAFWP Fails to Start S
Event-8 Normal Boration Fails S
Facility: Prairie Island (SPARE)
Scenario: PI-ILT-NRC-2203S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2203S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS
Facility: Prairie Island (SPARE)
Scenario: PI-ILT-NRC-2204S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2204S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS
Facility: Prairie Island (SPARE)
Scenario: PI-ILT-NRC-2204S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2204S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS
Facility: Prairie Island Scenario: PI-ILT-NRC-2205S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2205S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS Scenario General Comment E
S NRC: Verify that all instrument and valve nomenclature and alphanumeric descriptions are the same throughout the event and scenario.
Response: Complete.
General Comment E
S NRC: Evaluate TS overlap issues at OV.
Response: Addressed at OSV Event-1 Swap RX make up pumps S
Event-2 Lower reactor power to 90%
E S
NRC: The outline and the initial conditions indicate that Event 1 is a power reduction from 100% to 90%.
The Sequence of Events under Plant Response states Reactor Power rises, Generator Load rises, and RCS Tavg rises. The Expected Student Responses are for an increase in power. Please clarify if this is intended to be a power reduction or a power increase.
Response: Complete.
Event-3 11 SG Steam Flow Red channel fails high S
Event-4 PRZR Level Blue channel (controlling) fails high S
Facility: Prairie Island Scenario: PI-ILT-NRC-2205S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2205S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS Event-5 B Condenser Air In-Leakage S
Event-6 12 SG faulted to CTMT E
S NRC: 1) On page 16 of 32, under 1E-0 Attachment L: SI Alignment Verification, 5th bullet, Check If Main Steamlines Are required to be isolated. ADD (Examiner note: Close B MSL if not already closed.) 2) 11 Containment Spray Pump and Containment Fan Coolers will only start if Containment pressure exceeds 23 psig. What is the status 11 Containment Spray Pump and 11CFCU, 13 CFCU and D1 EDG if containment never gets to 23 psig?
Response: 1) Examiner note added.
- 2)
- previously added to indicate that 11 spray pump will only be manually started if pressure exceeds 23 lbs.
11 CS pump will not start due to malfunction regardless of containment pressure. 11 and 13 CFCUs would normally restart in SLOW on SI, but do not due to malfunction. They will need to be put in slow, at which point, they will start. THIS IS NOT RELATED TO CONTAINMENT PRESSURE. D1 would normally start on SI but does not due to
Facility: Prairie Island Scenario: PI-ILT-NRC-2205S Rev 0 Exam Date: August 8, 2022 1
Scenario Event ID/Name:
2 Scenario event errors 3
U/E/S 4
Explanation PI-ILT-NRC-2205S Realism/
Credibility Performance Standards Verifiable Actions Critical Task TS malfunction. The operator will manually start D1. THIS IS NOT RELATED TO CONTAINMENT PRESSURE.
Event-7 D1 fails to automatically start S
Event-8 BKR 8H-16 fails to open S
Form 2.3-3 Instructions for Completing the Scenario Table
- 1. For each scenario, enter the scenario event names and descriptions.
- 2. Review the individual events contained in each scenario, and identify and mark event errors:
The scenario guide event description is not realistic/credibleunsatisfactory (U).
The scenario guide event description lacks adequate crew/operator performance standardsneeds enhancement (E).
The scenario guide event description lacks verifiable actions for a credited normal event, reactivity event instrument/component malfunction, or technical specification (TS) event (or a combination of these) (U).
The scenario guide event description incorrectly designates an event as a critical task (i.e., a noncritical task labeled as critical or a critical task labeled as noncritical). This includes critical tasks that do not meet the critical task criteria (i.e., the critical task does not have a measurable performance standard) (U).
The scenario guide event description incorrectly designates entry into TS actions when not required or does not designate entry into TS actions when required (U).
- 3. Based on the outcome in step 2, mark the scenario event as unsatisfactory (U), satisfactory (S), or needs enhancements (E). An event is (U) if it has one or more (U) errors as determined in step 2. Examples of enhancements include formatting, spelling, or other minor changes.
- 4. Briefly describe any scenario event determined to be unsatisfactory (U) or needing enhancement (E). Save initial review comments and detail subsequent comment resolution so that each exam-bound scenario event is marked by a satisfactory (S) resolution on this form.