ML22250A699
| ML22250A699 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/30/2022 |
| From: | Ted Wingfield NRC/RGN-III/DRS/OLB |
| To: | Indiana Michigan Power Co |
| Wingfield T | |
| Shared Package | |
| ML21263A039 | List: |
| References | |
| Download: ML22250A699 (96) | |
Text
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A1.a-RO Task
Title:
Boron Volume Determination Task No.: 0050080101 Borate the RCS System: 004 SF1 CVCS Chemical and Volume Control System Knowledge/Ability Reference and Rating:
2.1.43 Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion.
RO: 4.1 / SRO: 4.3 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 15 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: The Candidate determines that boric acid must be added to restore Tave to Tref and determines the amount of boric acid required within an allowed range of 22 to 28 gallons.
Required Materials (procedures, equipment):
Copy of 2-OHP-4021-005-002 Attachment 9 Boron or Dilution Volume Determination Copy of Unit 2 Technical Data Book curves (Sections 4, 5, 6, and 7)
A color copy of Tech Data Book Figure 2-Figure 7.5.1 will be required because the lines for different PPM concentrations are in different colors.
Use the actual Tech Data Book from the Unit 2 Simulator if available Copy of the Unit 2 RO or BOP Turnover Checklist included with this JPM Calculator General
References:
2-OHP-4021-005-002 Attachment 9 Boron or Dilution Volume Determination, Revision 15 Technical Data Book Figures for Unit 2 Cycle 26
2 Notes to Examiner:
Simulator Requirements: N/A The NERDS computer program referenced by the procedure is installed on Control Room computers but is not installed by default on other computers outside the Control Room.
Required data from NERDS will be provided as a cue when requested by the Candidate.
During the Task Briefing, provide the candidate with the Unit 2 RO or BOP Turnover Checklist included with this JPM, the Copy of 2-OHP-4021-005-002 Attachment 9 Boron or Dilution Volume Determination, the Copy of Unit 2 Technical Data Book curves (Sections 4, 5, 6, and 7),
and the calculator.
Simulator Requirements: N/A Initial Conditions:
You are the Reactor Operator on Unit 2.
Current plant conditions are as listed on the provided RO/BOP Turnover Checklist with the following additional items:
Tave 574.2°F Tref 573°F The NERDS computer program is not available at your location. Reactor Engineering is available to provide data from the NERDS computer that is not available using Technical Data Book figures.
Initiating Cues:
The Unit Supervisor has directed you to calculate the required Boration or Dilution to restore Tave to program using 2-OHP-4021-005-002, Attachment 9, Boron or Dilution Volume Determination. Use Technical Data Book figures when an option exists for NERDS data or Technical Data Book figures. Submit completed Attachment 9 when task is complete.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Candidate determines that section 4.1.1 is not applicable SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Candidate determines that section 4.1.2 is applicable SAT:
UNSAT:
STANDARD: Candidate determines that 1.2°F temperature change is required (574.2 - 573 = 1.2)
SAT:
UNSAT:
STANDARD: Candidate determines 8000 MWD/MTU is Core Burnup value from Turnover Checklist.
SAT:
UNSAT:
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Candidate determines 1000 ppm is current RCS boron concentration from Turnover Checklist.
SAT:
UNSAT:
STANDARD: Candidate determines that MTC is -13.2 pcm/°F (Range -
13.0 to -13.4)
SAT:
UNSAT:
CUE: When requested as Reactor Engineering, provide Effective Fuel Temperature value of 1180.8°F.
STANDARD: Candidate determines that the Effective Fuel Temperature is 1180.8°F SAT:
UNSAT:
CUE: When requested as Reactor Engineering, provide Doppler Temperature Coefficient value of -2.114 pcm/°F.
STANDARD: Candidate determines that the DTC is -2.114 pcm/°F SAT:
UNSAT:
STANDARD: Candidate determines that TC is -15.314 pcm/°F (-13.2 + -
2.114) (Range -15.114 to -15.514)
SAT:
UNSAT:
STANDARD: Candidate determines that PCM change is -18.3768 pcm/°F x 1.2°F) ( Range (-18.1368 to -18.6168)
SAT:
UNSAT:
STANDARD: Candidate determines that DBW is -8.05 pcm/ppm (Range -8.0 to -8.1)
SAT:
UNSAT:
6 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Determines that Boron change is +2.28 ppm (-18.3768 pcm/-8.05 pcm/ppm) ( Range +2.24 to +2.33)
SAT:
UNSAT:
Evaluator Note: The boric acid required can be calculated using the formula given on Tech Data Book Figure 2-Figure 7.5.1. BAST PPM concentration, required for the calculation, can be determined using the Turnover Checklist. This calculation would result in a range limit of 25.99 to 27.04 gallons. Acceptable range to satisfy the Critical Step is based on graph reading from the lower limit line (22) and mid-scale (28) for the given boron concentration and required ppm change. The calculated limits of 25.99 to 27.04 are included within this range)
STANDARD (CS): Determines that 26.46 gallons of Boric Acid is required (Range 22 - 28 gallons)
SAT:
UNSAT:
STANDARD (CS): Determines that Boration is required (circle Boric Acid)
SAT:
UNSAT:
STANDARD: Determines that section 4.2 is not applicable SAT:
UNSAT:
TERMINATION CUE: When Attachment 9 is submitted for review, JPM is complete.
7 Task Briefing Initial Conditions:
You are the Reactor Operator on Unit 2.
Current plant conditions are as listed on the provided RO/BOP Turnover Checklist with the following additional items:
Tave 574.2°F Tref 573°F The NERDS computer program is not available at your location. Reactor Engineering is available to provide data from the NERDS computer that is not available using Technical Data Book figures.
Initiating Cues:
The Unit Supervisor has directed you to calculate the required Boration or Dilution to restore Tave to program using 2-OHP-4021-005-002, Attachment 9, Boron or Dilution Volume Determination. Use Technical Data Book figures when an option exists for NERDS data or Technical Data Book figures. Submit completed Attachment 9 when task is complete.
8
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A1.b-RO Task
Title:
Perform a 1/M Plot from Reactor Start up Task No.: 0130050101 Perform 1/M plot using the Scaler Timer.
System: 015 SF7 NI Nuclear Instrumentation System Knowledge/Ability Reference and Rating:
2.1.07 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
RO / SRO: 4.4 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 14 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: Calculate the Inverse Count Rate and plot ICRR for each of the four rod withdrawals such that the first three withdrawals predict criticality between greater than the
-1000 pcm limit and the last rod withdrawal predicts criticality below the rod insertion limit.
Based on 1/M plot data, inform US that rod withdrawal should be stopped.
Required Materials (procedures, equipment):
Copy of 2-OHP-4021-013-005 Attachment #2, ICRR Plotting Using Scaler Timer, Pages 10&11 of 19 Copy of 2-OHP-4021-013-005 Data Sheet 1, ICRR Data Sheet - Control Banks, with information completed as follows:
ECP -1000 PCM: 67 CBD ECP:
160 CBD ECP +500 PCM: 211 CBD Base Count Rate: 100 CPS Check boxes for first 4 withdrawals using N31 and Count Restarted checked Data for Rod Withdrawals:
o Rod Height Display Counts Time Period o BANK A @ 50 steps:
6318 60 sec o BANK A @ 100 steps:
7056 60 sec o BANK B @ 22 steps:
7998 60 sec o BANK B @ 72 steps:
10908 60 sec Copy of Tech Spec 3.1.6 Copy of Unit 2 Core Operating Limits Report (COLR)
Calculator and Ruler General
References:
2-OHP-4021-013-005 Visual Audio Count Rate Channel (NIS), Revision 20.
2 Notes to Examiner:
Simulator Requirements: N/A During the Task Briefing, provide the candidate with a calculator, a ruler, the copy of 2-OHP-4021-013-005 Attachment #2 Page 11 of 19, ICRR Plotting Using Scaler Timer, and the copy of 2-OHP-4021-013-005 Data Sheet 1, ICRR Data Sheet - Control Banks. Provide the copy of Tech Spec 3.1.6 and the copy of the Unit 2 COLR when requested.
Initial Conditions:
Unit 2 is performing a Reactor Startup per OHP-4021-001-002, Reactor Start up.
Boron is at the Estimated Critical Boron Concentration.
Shutdown Control Rod Banks are fully withdrawn.
Control Rods have been withdrawn four times in increments of 50 steps with current rod position of Bank B at 72 steps.
The Unit Supervisor wants to re-perform the Inverse Count Rate Ratio Calculations and re-plot the four points on an ICRR Data Sheet to re-verify Predicted Critical Rod Height after each of the four withdrawals.
Initiating Cues:
The Unit Supervisor directs you to perform the following:
Determine the Inverse Count Rate Ratio (ICRR) calculation for ALL FOUR rod withdrawals shown on 2-OHP-4021-013-005 Data Sheet 1, ICRR Data Sheet - Control Banks per 2-OHP-4021-013-005 Attachment 2 Steps 4.5.5.c and 4.5.6.
Plot the calculated ICRR values for ALL FOUR rod withdrawals on the ICRR plot on Data Sheet 1 per 2-OHP-4021-013-005 Attachment 2 Steps 4.5.7 and 4.5.8.
Record any required action per 2-OHP-4021-013-005 Attachment 2 based on 1/M Data obtained in the comments section of 2-OHP-4021-013-005 Data Sheet 1.
When task is complete, submit completed Data Sheet 1 for review.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: This page included as candidate may reference while completing ICRR plot.
DISPLAY COUNTS have been recorded for the four 50 step withdrawals previously completed.
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: Copies of Data Sheet 1 showing the expected plot and expected table completion are included on subsequent pages of this JPM for evaluator reference.
STANDARD (CS): For the first rod withdrawal (A-50), calculate count rate, calculate ICRR, and plot ICRR predicting criticality greater than the -1000 pcm limit. (Evaluator Note: Expected Count Rate is 105.3; expected ICRR is 0.95)
SAT:
UNSAT:
STANDARD (CS): For the second rod withdrawal (A-100), calculate count rate, calculate ICRR, and plot ICRR predicting criticality greater than the -1000 pcm limit.
(Evaluator Note: Expected Count Rate is 117.6; expected ICRR is 0.85)
SAT:
UNSAT:
STANDARD (CS): For the third rod withdrawal (B-22), calculate count rate, calculate ICRR, and plot ICRR predicting criticality greater than the -1000 pcm limit.
(Evaluator Note: Expected Count Rate is 133.3; expected ICRR is 0.75)
SAT:
UNSAT:
Evaluator Note: If the Candidate requests a copy of T.S. 3.1.6 or the Core Operating Limits Report, provide them as requested.
STANDARD (CS): For the fourth rod withdrawal (B-72), calculate count rate, calculate ICRR, and plot ICRR predicting criticality less than the rod insertion limit of CBD at zero steps. (Evaluator Note: Expected Count Rate is 181.8; expected ICRR is 0.55)
SAT:
UNSAT:
STANDARD (CS): Documents required action to stop rod withdrawal on Data Sheet 1 or verbally informs the evaluator as US of the listed requirements.
SAT:
UNSAT:
TERMINATION CUE: When the Candidate has submitted the completed Data Sheet 1 for review, JPM is complete
5 Expected ICRR plot.
Included for evaluator reference.
6 Expected ICRR plot.
Included for evaluator reference.
Items in RED are given as initial conditions, items in BLUE are expected candidate entries 100 67 CBD 160 CBD 211 CBD X
X X
X X
X X
X X
6318 7056 7998 10908 60 sec 60 sec 60 sec 60 sec 105.3 117.6 133.3 181.8 0.95 0.85 0.75 0.55
7 Task Briefing Initial Conditions:
Unit 2 is performing a Reactor Startup per OHP-4021-001-002, Reactor Start up.
Boron is at the Estimated Critical Boron Concentration.
Shutdown Control Rod Banks are fully withdrawn.
Control Rods have been withdrawn four times in increments of 50 steps with current rod position of Bank B at 72 steps.
The Unit Supervisor wants to re-perform the Inverse Count Rate Ratio Calculations and re-plot the four points on an ICRR Data Sheet to re-verify Predicted Critical Rod Height after each of the four withdrawals.
Initiating Cues:
The Unit Supervisor directs you to perform the following:
Determine the Inverse Count Rate Ratio (ICRR) calculation for ALL FOUR rod withdrawals shown on 2-OHP-4021-013-005 Data Sheet 1, ICRR Data Sheet - Control Banks per 2-OHP-4021-013-005 Attachment 2 Steps 4.5.5.c and 4.5.6.
Plot the calculated ICRR values for ALL FOUR rod withdrawals on the ICRR plot on Data Sheet 1 per 2-OHP-4021-013-005 Attachment 2 Steps 4.5.7 and 4.5.8.
Record any required action per 2-OHP-4021-013-005 Attachment 2 based on 1/M Data obtained in the comments section of 2-OHP-4021-013-005 Data Sheet 1.
When task is complete, submit completed Data Sheet 1 for review.
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A2-RO Task
Title:
Determine the requirements for isolating a Plant Air Compressor Cooler NESW leak Task No.: 3000040101 Prepare a Clearance Permit.
System: 076 SF4S SW Service Water System Knowledge/Ability Reference and Rating:
2.2.13 Knowledge of tagging and clearance procedures RO: 4.1 / SRO: 4.3 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 15 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: Candidate identifies all valves that must be tagged closed to isolate 2-WRV-950, Candidate identifies required vent and drain paths, and Candidate marks valves on drawing OP-2-5114 per 12-OHP-2110-CPS-001 Figure 2, Clearance Preparation Checklist.
Required Materials (procedures, equipment):
12-OHP-2110-CPS-001 Figure 2, Clearance Preparation Checklist Drawing OP-2-5114 Non-essential Service Water Unit 2 12-OHP-2110-CPS-001, Clearance Permit System, QDR Search Results for OP-2-5114 Highlight markers: Orange, Blue, Green, Pink, Purple, Yellow General
References:
Drawing OP-2-5114 Non-essential Service Water Unit 2 12-OHP-2110-CPS-001, Clearance Permit System, Revision 63
2 Notes to Examiner:
Simulator Requirements: N/A During the Task Briefing, provide the candidate with the six highlighter markers, Drawing OP 5114 Non-essential Service Water Unit 2 and 12-OHP-2110-CPS-001 Figure 2, Clearance Preparation Checklist. If at any time during the JPM the candidate requests a copy of the entire procedure 12-OHP-2110-CPS-001, Clearance Permit System, provide the copy as requested.
JPM Attachment 1, QDR Search Results for OP-2-5114, will be provided per the Evaluator Note in the JPM body.
Initial Conditions:
The Unit 2 Turbine AEO reported that 2-WRV-950, Unit 2 NESW Supply to the Plant Air Compressor (PAC) Valve, has a crack in the valve body The PAC was removed from service and NESW was isolated to stop the leak.
A work package is being prepared to perform repairs on 2-WRV-950.
Initiating Cues:
The Unit Supervisor directs you to complete only the Clearance Drawings section of 12-OHP-2110-CPS-001 Figure 2, Clearance Preparation Checklist, using the provided drawing OP 5114. Identify the valves closest to the leak that will isolate 2-WRV-950 from the rest of the NESW system and a required vent/drain path. Return the completed drawing and checklist to the US when task is complete.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: When Candidate states intention to review information for drawing OP-2-5114 in the Quick Data Retrieval (QDR) Web application, provide the Candidate with the screen shot included with this JPM as.
STANDARD: Determines that the drawing is the current revision and no Temp Mods Pending Changes apply by checking the drawing in QDR SAT:
UNSAT:
STANDARD: Determines that the drawing is adequately legible SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: A completed drawing is shown on the next page for Evaluator reference. Tagging additional valves, such as instrument isolations or extra drain valves, within the isolation boundary outlined in yellow is not required, but would not be a cause for JPM failure STANDARD (CS): Determines that the following valves must be closed to isolate WRV-950 and highlights the valves in Blue on the drawing:
NSW-119 NSW-120 NSW-126 NSW-127 NSW-129 NSW-130 NSW-132 NSW-133 NSW-135 SAT:
UNSAT:
STANDARD: (CS) Highlights WRV-950 in Green on the drawing SAT:
UNSAT:
STANDARD (CS): Determines that the following valves must be opened to provide a vent & drain path and highlights the valves in Pink on the drawing:
NSW-124 At least one of the following: NSW-302, NSW-373, NSW-876, NSW-877, NSW-113 SAT:
UNSAT:
STANDARD: (CS) Highlights areas of the system within the clearance boundary in Yellow on the drawing SAT:
UNSAT:
TERMINATION CUE: When the Candidate returns the completed drawing to the Evaluator, JPM is complete.
5 Positioned CLOSED for Isolation (Critical) Positioned Open for vent/drain path System within clearance boundary Component to be worked X
X X
X X
X X X
X X
6
, QDR Search Results for OP-2-5114
7 Task Briefing Initial Conditions:
The Unit 2 Turbine AEO reported that 2-WRV-950, Unit 2 NESW Supply to the Plant Air Compressor (PAC) Valve, has a crack in the valve body The PAC was removed from service and NESW was isolated to stop the leak.
A work package is being prepared to perform repairs on 2-WRV-950.
Initiating Cues:
The Unit Supervisor directs you to complete only the Clearance Drawings section of 12-OHP-2110-CPS-001 Figure 2, Clearance Preparation Checklist, using the provided drawing OP 5114. Identify the valves closest to the leak that will isolate 2-WRV-950 from the rest of the NESW system and a required vent/drain path. Return the completed drawing and checklist to the US when task is complete.
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A3-RO Task
Title:
Determine Locked High Radiation Area (LHRA) Entry Requirements Task No.: GE-V-002 Radiation Worker System: N/A Knowledge/Ability Reference and Rating:
2.3.12 Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters RO: 3.2 / SRO: 3.7 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 15 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: The operator uses the ATOMs software system to locate the survey map for the U1 VCT room and identifies the U1 VCT room is a Locked high Radiation Area and determines the highest general area radiation dose in the room. The candidate then uses the RWP software to locate and review RWP-221001 to determine that a specific LHRA RP brief for the Locked High Radiation Area, an alarming / vibrating Self reading dosimeter shall be worn, and continuous RP coverage are required.
Required Materials (procedures, equipment):
Computer with LAN access General
References:
Radiation Work Permit 221001 U1 VCT Radiation Area Map from ATOMS
2 Notes to Examiner:
Simulator Requirements: N/A On the day of JPM administration, the Survey Map in ATOMS and the RWP should be checked to verify it matches the illustrations in this JPM. If data has changed, current data should be used.
Each Candidate should log into the network using his/her own password and log out when the JPM is complete. This will preclude use of the Browser History from previous candidates for subsequent JPM administration.
Initial Conditions: A worker exiting the plant reports that seepage was observed on the Unit 1 Volume Control Tank (VCT)
Initiating Cues: You are an Extra RO. The Shift Manager directs you to determine the Entry Requirements for Unit 1 VCT Room (the Room/area directly surrounding the VCT) per the applicable Radiation Work Permit for Operations personnel using a Plant LAN computer. You are also directed to identify the highest general area radiation dose in the Unit 1 VCT room.
Report this information to the Shift Manager when complete.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: The Candidate may be aware of how to access the ATOMS software without referencing this page.
STANDARD: Selects Departments option from the Cook Home page screen by clicking Departments SAT:
UNSAT:
STANDARD: Selects Radiation Protection option from the Departments page by clicking Radiation Protection SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
NOTE: The Candidate may be aware of how to access the ATOMS software without referencing this page.
STANDARD: Notes the ATOMS Status Board Viewer is in CNP APPS folder on the desktop.
SAT:
UNSAT:
Note: Survey Map Key may be referenced later, from page 7 of this JPM.
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): Returns to computer desktop screen and opens CNP APPS folder by double clicking folder.
SAT:
UNSAT:
STANDARD (CS): When CNP APPS opens candidate selects ATOMS shortcut folder and opens by double clicking folder.
SAT:
UNSAT:
STANDARD (CS): When ATOMS shortcut folder opens candidate selects ATOMS Production folder and opens by double clicking folder.
SAT:
UNSAT:
STANDARD (CS): When ATOMS Production folder opens candidate selects ATOMS Status board Viewer - Shortcut and opens by double clicking.
SAT:
UNSAT:
6 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): In Status board Viewer selects Unit 1 VCT Room under the 609 drop down menu SAT:
UNSAT:
7 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): Identifies the VCT room in posted as Locked High Radiation Area (LHRA)
SAT:
UNSAT:
NOTE: Survey Map Key is located on page 4 of this JPM on screen shot of RP Homepage STANDARD (CS): Identifies the highest General Area Radiation reading by noting the highest underlined reading.
SAT:
UNSAT:
Note: Candidate must now return to the RP Homepage to view the Radiation Work Permit (RWP) to determine entry requirements to the LHRA VCT room.
8 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: There are several ways to access the RWP application page. The method highlighted below or any other method would be acceptable.
STANDARD: On the RP Homepage Radiation work Permits (RWP) is selected SAT:
UNSAT:
STANDARD (CS): On the Radiation work Permits (RWP) page the drop down menu is used to locate 221001-01 (which is the Permit assigned to Operations for Auxiliary Building entrance).
SAT:
UNSAT:
9 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): Identifies LHRA entry requires:
a) LHRA Briefing with RP b) Wearing of an Alarming / vibrating self-reading dosimeter c) Continuous RP coverage SAT:
UNSAT:
TERMINATION CUE: When the examinee has completed report of highest General Area radiation reading and entry requirements for VCT room and completion of task to the Shift Manager, JPM is complete.
10 Task Briefing Initial Conditions: A worker exiting the plant reports that seepage was observed on the Unit 1 Volume Control Tank (VCT)
Initiating Cues: You are an Extra RO. The Shift Manager directs you to determine the Entry Requirements for Unit 1 VCT Room (the Room/area directly surrounding the VCT) per the applicable Radiation Work Permit for Operations personnel using a Plant LAN computer. You are also directed to identify the highest general area radiation dose in the Unit 1 VCT room.
Report this information to the Shift Manager when complete.
1 Facility: DC Cook Job Performance Measure No.: RO33 -A1.a-SRO Task
Title:
Review Reactor Vessel Void Vent Time Task No.: EOP1090512 Mitigate the effects of voids in the reactor System: 028 SF5 HRPS Hydrogen Recombiner and Purge Control System Knowledge/Ability Reference and Rating:
KA 2.1.25 Ability to interpret reference materials, such as graphs, curves, and tables (reference potential)
RO 3.9/SRO 4.2 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 12 MINUTES Method of Testing: Simulated Performance _____ Actual Performance ____
Location: Classroom X Simulator ___
Plant ___
Task Standard: Identifies wrong Hydrogen concentration used in the completed calculation and determines correct Reactor Vessel Void time by completing calculation using correct values (within given range of 931 - 1012 minutes).
Required Materials (procedures, equipment):
Copy of completed 1-OHP-4023-FR-I.3 Response to Voids in Reactor Vessel, Attachment A, Instructions for Determining Venting Time.
Copy of Containment Temperature Recorder SG-18 indications included with this JPM Copy of 1-OHP-4023-FR-I.3 Response to Voids in Reactor Vessel, Figure 1, Hydrogen Flow Rate versus RCS Pressure.
Calculator General
References:
1-OHP-4023-FR-I.3 Response to Voids in Reactor Vessel
2 Notes to Examiner:
Simulator Requirements: N/A Provide the Candidate with all required materials when giving the Task Briefing Initial Conditions:
You are an extra SRO.
The Unit One Control room team is responding to a SBLOCA and is currently implementing 1-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.
There has been significant voiding in the RCS. The Unit Supervisor has implemented 1-OHP-4023-FR-I-3, response to Voids in Reactor Vessel.
RCS pressure is 1050 psig Containment Hydrogen concentration is 0.7%
Initiating Cues: The Unit Supervisor directs you to review the vent time for the reactor Vessel on the completed Attachment A of FR-I.3. Identify any errors and submit a corrected Attachment A as required.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines Average temp of 143 ºF is correct. (Using points 2, 4, & 10 as per note at bottom of page)
SAT:
UNSAT:
Standard: Determines 603 ºR is correct.
SAT:
UNSAT:
Standard: Determines 1.012 x 106 ft3 is correct.
SAT:
UNSAT:
Standard (CS): Determines actual value for containment hydrogen concentration should be 0.7% based on Task Briefing (Wrong Hydrogen concentration used).
SAT:
UNSAT:
Standard (CS): Determines actual value should be 2.3276 x 104 ft3 (Error carried forward from previous line).
SAT:
UNSAT:
Standard: Determines 2400 is correct within +/- 100 scfm SAT:
UNSAT:
Standard (CS): Determines actual value should be 9.7 minutes (range of 9.3 - 10.12 minutes)
SAT:
UNSAT:
(Error carried forward from 3.c)
Termination Cue: When Candidate returns corrected Attachment A, JPM is Complete 603 1.012 x 106 7.084 x 103 1.012 x 106 2.3 143 2400 7.084 x 103 2400 29.52 603
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines Average temp of 143 ºF is correct. (Using points 2, 4, & 10 as per note at bottom of page)
SAT:
UNSAT:
Standard: Determines 603 ºR is correct.
SAT:
UNSAT:
Standard: Determines 1.012 x 106 ft3 is correct.
SAT:
UNSAT:
Standard (CS): Determines actual value for containment hydrogen concentration should be 0.7% based on Task Briefing (Wrong Hydrogen concentration used).
SAT:
UNSAT:
Standard (CS): Determines actual value should be 2.3276 x 104 ft3 (Error carried forward from previous line).
SAT:
UNSAT:
Standard: Determines 2400 is correct within +/- 100 scfm SAT:
UNSAT:
Standard (CS): Determines actual value should be 9.7 minutes (range of 9.3 - 10.12 minutes) (Error carried forward from 3.c)
SAT:
UNSAT:
Termination Cue: When Candidate returns corrected Attachment A, JPM is Complete
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Included for Evaluator reference
6 Task Briefing Initial Conditions:
You are an extra SRO.
The Unit One Control room team is responding to a SBLOCA and is currently implementing 1-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization.
There has been significant voiding in the RCS. The Unit Supervisor has implemented 1-OHP-4023-FR-I-3, response to Voids in Reactor Vessel.
RCS pressure is 1050 psig Containment Hydrogen concentration is 0.7%
Initiating Cues: The Unit Supervisor directs you to review the vent time for the reactor Vessel on the completed Attachment A of FR-I.3. Identify any errors and submit a corrected Attachment A as required
7 Containment Air Temperature Recorder SG-18 Indications Point #
Point ID Noun Name Temperature (Deg F) 1 ETR-11 Upper Cont. 090 110 2
ETR-12 Upper Cont.180 134 3
ETR-13 Upper Cont.270 101 4
ETR-14 Upper Cont. 0 128 5
ETR-15 Lower Cont. Q1 173 6
ETR-16 Lower Cont. Q2 139 7
ETR-17 Lower Cont. Q3 129 8
ETR-18 Lower Cont. Q4 168 9
ETR-19 HV-CLV-1-4 Room 151 10 ETR-20 HV-CEQ-2-Room 167 11 ETR-21 HV-CLV-2-3 Room 146 12 ETR-22 INST Room 190 13 ETR-23 PZR Doghouse 197
8 143 603 1.012 x 106 1.012 x 106 2.3 7.084 x 103 2400 7.084 x 103 2400 2.95
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A1.b-SRO Task
Title:
Determine if Core Alterations Can Continue Task No.: 0340260202 Verify Containment Penetration Integrity Checks prior to Core Alterations (STP.041).
System: 13 SF5 CNT Containment System Knowledge/Ability Reference and Rating:
2.1.40 Knowledge of refueling administrative requirements SRO: 3.9 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 14 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: Review a completed shiftly surveillance to continue Core Alterations using 2-OHP-4030-227-037 Data Sheet 3. Identifies the errors made by the performer:
Check of Trip Block switches for RMS cannot be N/Ad, The Residual Heat Removal flow too low for the instrument selected for use RHR Return temperature too low for the instrument selected for use.
Based on these discrepancies the candidate determines Acceptance Criteria are NOT met.
Required Materials (procedures, equipment):
Copy of completed 2-OHP-4030-227-037, Data Sheet 3, Shiftly Surveillance requirements to Continue Core Alterations included with this JPM General
References:
2-OHP-4030-227-037, Data Sheet 3, Shiftly Surveillance requirements to Continue Core Alterations, Revision 32
2 Notes to Examiner:
Simulator Requirements: N/A During the Task Briefing, provide the candidate with the copy of completed 2-OHP-4030-227-037, Data Sheet 3, Shiftly Surveillance requirements to Continue Core Alterations.
Initial Conditions:
You are an extra SRO.
Fuel is currently being off loaded from the core in containment and being placed in the SFP.
The BOP has completed the shiftly surveillance for continuing Core Alterations using 2-OHP-4030-227-037 Data Sheet 3, Shiftly Surveillance requirements to Continue Core Alterations.
Another operator has completed the Department Review in Section 10.2.
The current date is 7/19/22. The current time is 0300.
Initiating Cues: The US directs you to perform the SRO Review and Acceptance Section 10.3.
If errors are found, document the errors in the Comments of Section 10.3. Return the completed Data Sheet to the US when task is complete.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: All mistakes are circled in red.
CUE: If requested, report all recorded data is as reported from chemistry.
Standard: Determines shutdown margin requirements are met and properly documented SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines Nuclear Instrumentation requirements are met and properly documented.
SAT:
UNSAT:
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines requirements are met and properly documented.
SAT:
UNSAT:
6 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines requirements are met and properly documented.
SAT:
UNSAT:
7 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines requirements are met and properly documented.
SAT:
UNSAT:
Standard (CS): Determines step 2.7 CANNOT Be NA since Fuel Movement is in Containment.
SAT:
UNSAT:
CUE: If Candidate stops review after recognizing error in step 2.7 and informs the Evaluator as US that requirements are not satisfied per Section 10.3, inform the Candidate to complete the review of the surveillance to determine if additional errors exist.
Standard: Determines requirements are met and properly documented.
SAT:
UNSAT:
8 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines requirements are met and properly documented.
SAT:
UNSAT:
Standard (CS): Identifies requirements are NOT met with flow <3100 GPM on IFI-335.
SAT:
UNSAT:
CUE: If Candidate stops review after recognizing error in step 4.2 and informs the Evaluator as US that requirements are not satisfied per Section 10.3, inform the Candidate to complete the review of the surveillance to determine if additional errors exist.
Standard: Determines requirements are met and properly documented.
(This Step Could be NA since >23 Feet while moving fuel)
SAT:
UNSAT:
9 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard (CS): Identifies requirements are NOT met with temperature
<78ºF using ITR-311.
SAT:
UNSAT:
CUE: If Candidate stops review after recognizing error in step 4.4 and informs the Evaluator as US that requirements are not satisfied per Section 10.3, inform the Candidate to complete the review of the surveillance to determine if additional errors exist.
Standard: Determines Section 5 requirements are met and properly documented.
SAT:
UNSAT:
10 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines Section 6 requirements are met and properly documented.
SAT:
UNSAT:
Standard: Determines Section 7 requirements are met and properly documented.
SAT:
UNSAT:
11 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Determines Section 8 requirements are met and properly documented.
SAT:
UNSAT:
Standard: Determines Section 9 requirements are met and properly documented.
SAT:
UNSAT:
12 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Standard: Identifies Department Review improperly indicated Acceptance Criteria were met.
SAT:
UNSAT:
Standard (CS): Identifies not all acceptance criteria were met.
SAT:
UNSAT:
TERMINATION CUE: When the Candidate returns the completed Data Sheet 3, JPM is complete
13 TASK BRIEFING Initial Conditions:
You are an extra SRO.
Fuel is currently being off loaded from the core in containment and being placed in the SFP.
The BOP has completed the shiftly surveillance for continuing Core Alterations using 2-OHP-4030-227-037 Data Sheet 3, Shiftly Surveillance requirements to Continue Core Alterations.
Another operator has completed the Department Review in Section 10.2.
The current date is 7/19/22. The current time is 0300.
Initiating Cues: The US directs you to perform the SRO Review and Acceptance Section 10.3.
If errors are found, document the errors in the Comments of Section 10.3. Return the completed Data Sheet to the US when task is complete.
14 GH 2495 2492 2495 7-19-22/0005 GH GH GH O
7-19-22/0005 7-19-22/0005
15 O
GH GH GH GH GH 482 495 488 502
16 GH GH GH GH
17 GH GH GH GH GH O
18 GH GH GH N/A GH GH GH GH 7/19/22
19 O
O GH GH GH 2650 X
X X
20 O
O 74.5 644 9 7-19-22/0030 GH GH X
21 X
GH GH GH
22 GH GH GH GH KB
23 0001 0045 7 19 22 Glenn Harding X
X 0145 Richard Shaver 7 19 22 7 19 22
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A2-SRO Task
Title:
Review Unit 2 LTOP Verification Task No.: STP0390201 Perform Shiftly Surveillance checks for MODE 5 & 6 System:
Knowledge/Ability Reference and Rating:
2.2.42 Ability to recognize system parameters that are entry-level conditions for TS RO: / SRO: 4.0 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 15 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: Candidate performs the SRO review of the completed LTOP Verification and determines LTOP Requirements for Unit 2 are not met per 2-OHP-4030-214-030, Daily and Shiftly Surveillance Checks, Data Sheet 20. Candidate identifies the following errors by the performer:
Annunciator 208 Drop 28 is lit so NRV-153 is not operable.
Identifies that there is no Pressure Relief Capability Operable.
Identifies LTOP Requirements are NOT met Required Materials (procedures, equipment):
Copy of Completed 2-OHP-4030-214-030, Data Sheet 20 (Included with this JPM)
Copy of Completed 2-OHP-4030-214-030, Data Sheet 20A (Included with this JPM)
Copy of Equipment Availability Table (Included with this JPM)
Copy of Unit 2 Open Items Summary (Included with this JPM)
TS 3.4.12 and Bases General
References:
2-OHP-4030-214-030, Data Sheet 20 / 20A, Revision 33 TS 3.4.12 and Bases
2 Notes to Examiner:
Simulator Requirements: N/A During the Task Briefing, provide the Candidate with the following:
Copy of Completed 2-OHP-4030-214-030, Data Sheet 20 (Included with this JPM)
Copy of Completed 2-OHP-4030-214-030, Data Sheet 20A (Included with this JPM)
Copy of Equipment Availability Table (Included with this JPM)
Copy of Unit 2 Open Items Summary (Included with this JPM)
Provide the copy of T.S. 3.4.12 and 3.4.12 Bases as requested during performance of the JPM.
Initial Conditions:
Unit 2 is in Mode 5 Equipment status is as indicated in the Equipment Availability Table and the Unit 2 Open Items Summary 2-OHP-4030-214-030 Data Sheet 20, LTOP Verification, has been completed and requires an SRO review.
The current Date is 7/19/22. The current time is 0700.
You are an extra SRO.
Initiating Cues: The Shift Manager directs you to perform section 4.3, Senior Reactor Operator (SRO) Review and Acceptance, of the completed 2-OHP-4030-214-030, Data Sheet 20. Return the completed Data Sheet 20 to the Shift Manager when the review is complete.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Included for Evaluator Reference
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Identifies correct entries using Equipment Availability Table and Open Items log (Correct items are un-circled Xs.
SAT:
UNSAT:
Evaluator Note: Annunciator Panel 208 Drop 28 is LIT (not Clear) (See Open Items Log - page 2).
STANDARD (CS): Identifies that the lower box in the Both PORVS OPERABLE box should not be checked, and that the YES box for the Both PORVS OPERABLE box should not be checked.
SAT:
UNSAT:
Evaluator Note: After the Candidate identifies an error, prompt the candidate to correct Data Sheet 20A after determining the error.
STANDARD: Identifies unchecked items that should be checked (required items indicated by red circles with no X)
SAT:
UNSAT:
STANDARD (CS): Determines that LTOP Requirements are NOT Met (YES box should not be checked, NO box should be checked).
SAT:
UNSAT:
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Identifies Acceptance Criteria met YES box was incorrectly checked.
SAT:
UNSAT:
STANDARD (CS): Checks box to indicate Acceptance Criteria are not met.
SAT:
UNSAT:
STANDARD: Signs and returns completed Data Sheet 20 to the Evaluator as Shift Manager or verbally informs Shift Manager that LTOP Requirements are NOT met.
SAT:
UNSAT:
Termination Cue: When the candidate returns the completed Data Sheet 20 to the evaluator as Shift Manager, JPM is Complete
6 Task Briefing Initial Conditions:
Unit 2 is in Mode 5 Equipment status is as indicated in the Equipment Availability Table and the Unit 2 Open Items Summary 2-OHP-4030-214-030 Data Sheet 20, LTOP Verification, has been completed and requires an SRO review.
The current Date is 7/19/22. The current time is 0700.
You are an extra SRO.
Initiating Cues: The Shift Manager directs you to perform section 4.3, Senior Reactor Operator (SRO) Review and Acceptance, of the completed 2-OHP-4030-214-030, Data Sheet 20. Return the completed Data Sheet 20 to the Shift Manager when the review is complete.
7 Unit 2 Open Items Summary Open Item #
Component Noun System Open Item Entered 2-2022-0594 2-VTR-300 Control Room Air Temperature VCRAC Tuesday, June 28, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.7.11 2022-13357 Condition Description Notes 12-IHP-5021-IMP-001 (55384995-01) Temperature Instrument Calibration Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0600 2-NTR-12 CORE EXIT THERMOCOUPLE LOCATION F-15 NI Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.3.3 A
Modes 1, 2, 3, and 4 Condition Description Notes Failed TC Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0601 2-NRV-153 PRESSURIZER PORV NRV-153 PZR Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 F
N/A Modes 5 & 6 3.4.12 E
N/A Mode 4 3.4.11 A
N/A Modes 1, 2, and 3 Condition Description Notes Emergency Air Tank is depressurized and Isolated due to air leak at pressure connection Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0602 2-IMO-110 Safety Injection Accumulator Discharge Valve ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B
A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Page 1 of 3
8 Open Item #
Component Noun System Open Item Entered 2-2022-0603 2-IMO-120 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B
A Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0604 2-IMO-130 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B
B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0605 2-IMO-140 SAFETY INJECTION ACCUMULATOR DISCHARGE VALVE ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.1 B
B Modes 1, 2 and 3 > 1000 psig Condition Description Notes Valve is tagged closed to prevent Injection Required for SR 3.4.12.3 Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0606 2-PP-26N NORTH SAFETY INJECTION PUMP ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A
A Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Page 2 of 3
9 Open Item #
Component Noun System Open Item Entered 2-2022-0607 2-PP-26S SOUTH SAFETY INJECTION PUMP ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A
B Modes 1, 2, and 3 Condition Description Notes SI Pumps Tagged to Prevent Injection Required for SR 3.4.12.1 Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0608 2-SV-103 RHR Suction Line Relief Valve RHR Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.4.12 E
N/A MODE 4 when any RCS cold leg temperature is 299°F 3.4.12 F
N/A Modes 5 and 6, when the vessel head is on 5.5.6 Condition Description Notes RHR Suction Line Relief Valve failed to lift at required setpoint Valve did not Open Until 460 psig.
Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0609 2-PP-50E East CCP ECCS Monday, July 19, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 3.5.2 A
A Modes 1, 2, 3 Condition Description Notes CCP Tagged Out to Prevent Injection Required for SR 3.4.12.2 Procedure Title Drop Dead Date Open Item #
Component Noun System Open Item Entered 2-2022-0610 2-SRA-2900 SJAE Radiation Monitor RMS Saturday, June 25, 2022 LCO/TRO/ODCM Condition/Action Train Applicability Action Work Order Clearance Work Request EIS Events 8.3.8 C
Condition Description Notes RP has not completed Operability recommendation checks following I & C board replacement under WOT 55403403 Procedure Title Drop Dead Date Page 3 of 3
10 Equipment Availability Table COMPONENT I.D.:
DESCRIPTION:
STATUS:
2-NMO-152 PORV Block Valve Open & Energized 2-NMO-153 PORV Block Valve Open & Energized 2-NRV-152 Control Selector Cold Over-Pressure Block for 2-NRV-152 Cold Over Press 2-NRV-153 Control Selector Cold Over-Pressure Block for 2-NRV-153 Cold Over Press 2-IMO-128 Return from Hot Leg 2 Open & Energized 2-ICM-129 Return from Hot Leg 2 Open & Energized Annunciator Panel 208 Drop 27 2-NRV-152 EMER AIR TANK PRESSURE LOW NOT Lit Annunciator Panel 208 Drop 28 2-NRV-153 EMER AIR TANK PRESSURE LOW Lit 2-PP-50E East Centrifugal Charging Pump PTL (Racked Out) 2-PP-50W West Centrifugal Charging Pump Running (Racked In)
Loop 2 WR Cold Leg Temp RCS Lowest Cold Leg Temperature 185o F RCS WR Pressure 2-NPS-121 RCS Highest Reading Pressure 230 psig 2-PP-26N North Safety Injection Pump PTL (Racked Out) 2-PP-26S South Safety Injection Pump PTL (Racked Out) 2-NTA-251 Pressurizer Liquid Temp 400o F 2-IMO-110, 120, 130, 140 SI Accumulator Isolation Valves Closed & De-Energized
11 KJ KJ KJ KJ N/A KJ 7/19/22 X
X X
X O
O O
O O
O O
12 0600 0630 07 19 22 07 19 22 Kelson Johansen X
X 0645 Brad Bowhuis X
44556 07 19 22
13
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A3-SRO Task
Title:
Review and Authorize a Waste Gas Release Permit Task No.: 0230140103 Authorize a gaseous radioactive waste release.
System: 071 SF9 WGS Waste Gas Disposal System Knowledge/Ability Reference and Rating:
K/A 2.3.6 Ability to approve liquid or gaseous release permits SRO: 3.8 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 10 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard:
Identify the following conditions that would prevent authorization of a gaseous release:
Approval signature from Environmental cannot be N/A
>72 hours have elapsed from time of Waste Gas Decay Tank Sample Required Materials (procedures, equipment):
Copy of 12-OHP-4021-023-002, Attachment 2 completed through step 4.4 Copy of 12-OHP-4021-023-002, Data Sheet 1 completed up to Section 3 with errors (Included with this JPM Copy of corrected 12-OHP-4021-023-002, Data Sheet 1 Page 47 with Environmental approval signature General
References:
12-OHP-4021-023-002, Rev. 31; PMP-6010-OSD-001, Rev. 24
2 Notes to Examiner:
Simulator Requirements: N/A During the Task Briefing, provide the candidate with the copy of 12-OHP-4021-023-002, Data Sheet 1 completed up to Section 3 with errors.
If requested at any time during the JPM, provide the candidate with the Copy of 12-OHP-4021-023-002, Attachment 2 completed through step 4.4.
Initial Conditions:
Both units are operating at 100% power Radiation Monitors 1-VRS-1500 and 2-VRS-2500 are OPERABLE Meteorological instrumentation is OPERABLE Gas Decay Tank # 6 is ready to be released.
The current date is July 15, 2022. The time is 13:30.
Initiating Cues:
You are directed to perform SECTION 3 RELEASE AUTHORIZATION for the Gas Decay Tank Release Permit, 12-OHP-4021-023-002 Data Sheet 1 for gas decay tank release (G-22-14).
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: If requested at any time during the JPM, provide the candidate with the Copy of 12-OHP-4021-023-002, Attachment 2 completed through step 4.4.
STANDARD: Candidate verifies isolation data in SECTION 1 filled in.
SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: (CS) Candidate initiates review of Data Sheet 1 and determines Environmental Signature CANNOT be N/A.
SAT:
UNSAT:
CUE: If the Candidate determines that the release cannot be authorized and stops the review at this point, provide the candidate with the Copy of corrected 12-OHP-4021-023-002, Data Sheet 1 Page 47 with Environmental approval signature included with this and direct the Candidate to continue the review.
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Evaluator Note: The approval steps are bulleted and can be completed in any order. If the candidate identifies that >72 hours have elapsed since the sample was taken and determines the release cannot be authorized before conducting a review of approval signatures in section 2, direct the candidate to complete the review and identify any other errors.
CUE: If candidate asks, the current date/time is as given in the Task Brief STANDARD: (CS) Identifies that greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> has elapsed since time of sample analysis.
SAT:
UNSAT:
STANDARD: (CS) Candidate states the release cannot be approved or states he will not sign for approval SAT:
UNSAT:
Termination Cue: JPM is complete when examinee states release is not approved.
6 Task Briefing Initial Conditions:
Both units are operating at 100% power Radiation Monitors 1-VRS-1500 and 2-VRS-2500 are OPERABLE Meteorological instrumentation is OPERABLE Gas Decay Tank # 6 is ready to be released.
The current date is July 15, 2022. The time is 13:30.
Initiating Cues:
You are directed to perform SECTION 3 RELEASE AUTHORIZATION for the Gas Decay Tank Release Permit, 12-OHP-4021-023-002 Data Sheet 1 for gas decay tank release (G-22-14).
7 6
20 MAY 2022/0912 99 Phil Miller
8 X
X G-22-31 7/12/2022 0510 6
125 G-22-14 Kaitlin Kohn 7 14 22 KK 7/14/22 N/A 1920
9
10
1 Facility: DC Cook Job Performance Measure No.: NRC-RO33-A4-SRO Task
Title:
Determine if PAR required and determine PAR Task No.: EPP0120703 Develop a Protective Action Recommendation System: N/A Knowledge/Ability Reference and Rating:
2.4.44 Knowledge of emergency plan protective action recommendations.
SRO: 4.4 Time-Critical Task: (Yes/No)
Alternate Path: (Yes/No)
Validated Time: 12 MINUTES Method of Testing: Simulated Performance Actual Performance Location: Classroom X Simulator ___
Plant ___
Task Standard: The task is satisfactorily met when Candidate has identified a Protective Action Recommendation (PAR) using PMP-2080-EPP-100 Attachment 1 to evacuate Area 1 and Area 3 and to clear lake area 6 in 12 minutes from the start of the JPM.
Required Materials (procedures, equipment):
PMP-2080-EPP-100, Emergency Response Additional copy of PMP-2080-EPP-100 Attachment 1 Protective Action Recommendations PMP-2080-EPP-101, Emergency Plan Classification, MIDAS Accident Calcs Dose Assessment Results, MIDAS Summary, Radioactive Release Radiation Monitors General
References:
PMP-2080-EPP-100, Emergency Response PMP-2080-EPP-101, Emergency Plan Classification
2 Notes to Examiner:
Simulator Requirements: N/A The Time Critical limit of 12 minutes is based upon the 15 minute notification requirement for a PAR. If the PAR is identified in 12 minutes, this will allow for a 2 minute notification completion using the Vaporstream application.
During the Task Briefing, provide the candidate with PMP-2080-EPP-100, Emergency Response, the additional copy of PMP-2080-EPP-100 Attachment 1 Protective Action Recommendations, PMP-2080-EPP-101, Emergency Plan Classification, and Attachment 1, MIDAS Accident Calcs Dose Assessment Results.
Provide Meteorological data as requested from Attachment 2, MIDAS Summary.
Provide Radiation Monitor data as requested from Attachment 3, Radioactive Release Radiation Monitors Initial Conditions:
Unit 2 was operating at 80% power.
A plant shut down was in progress due to failed fuel.
21 SG PORV failed open and could not be isolated manually or locally.
The Crew tripped the reactor and performed actions of E-0 and E-2.
A steam generator tube rupture subsequently occurred on 21 Steam Generator and the Crew transitioned to E-3.
The Shift Manager classified a Site Area Emergency (FS1.1) based on Loss of the RCS barrier and Loss of the Containment Barrier.
Containment radiation subsequently rose to the following values:
VRA-2310, U2 UPPER CONTAINMENT AREA MONITOR - HIGH RANGE = 1300 R/hr.
VRA-2410, U2 LOWER CONTAINMENT AREA MONITOR - HIGH RANGE = 900 R/hr.
The Shift Manager has upgraded to a General Emergency based on Loss of All Three Fission Product barriers (FG1.1).
Quick Dose Projection has been performed per PMP-2080-EPP-108, Initial Dose Assessment.
You are an extra SRO.
Initiating Cues:
The Shift Manager directs you to complete PMP-2080-EPP-100 Attachment 1 Protective Action Recommendations, and submit the completed attachment to the Shift Manager for approval.
This is a Time Critical JPM.
3 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
EVALUATOR NOTE: The Time Critical requirement is that the Candidate completes Attachment 1 and submits it for approval in 12 minutes.
JPM Start Time:.
STANDARD (CS): Candidate determines PAR is required and continues with the attachment.
SAT:
UNSAT:
STANDARD: (CS) Candidate determines the PAR is concurrent with the GE classification and utilizes the Initial PAR flowchart.
SAT:
UNSAT:
4 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD (CS): Candidate determines a General Emergency has been declared based on the Task Briefing.
SAT:
UNSAT:
Evaluator Note: A Rapidly Progressing Severe Accident is not occurring due to Containment Radiation monitors read less than the limit and conditions not met for RG1.1, RG1.2, or RG1.3 (Based on Radiological Release Radiation Monitor readings and Dose Assessment do not indicate exceeding Protective Action Guidelines).
CUE: If requested, provide the candidate with Radiological Release Radiation Monitor readings from Attachment 3. Candidate should state that this data can be found on the PPC or the RMS displays in the Control Room. If asked, Field Monitoring Team data is not available.
STANDARD (CS): Candidate determines a Rapidly Progressing Severe Accident is not occurring.
SAT:
UNSAT:
CUE: If requested, inform the Candidate that a Hostile Action has not been reported by the Security Shift Supervisor STANDARD (CS): Candidate determines a Hostile Action has not been reported by the Security Shift Supervisor.
SAT:
UNSAT:
STANDARD (CS): Candidate determines PAR to evacuate Area 1 and Area 3 and to clear lake area 6, with no action for other areas.
SAT:
UNSAT:
5 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
STANDARD: Candidate completes the Table in Step 2 as follows and submits completed Attachment for review in 12 minutes:
(CS) Candidate checks boxes for evacuation of Areas 1 and 3 only (CS) Candidate checks box for Clear Lake Area 6 only Candidate checks No box for PARs based on Dose Calculations Candidate checks No box for PARs beyond 10 Miles SAT:
UNSAT:
EVALUATOR NOTE: The Time Critical requirement is that the Candidate completes Attachment 1 and submits it for approval in 12 minutes.
JPM Completion Time:.
Termination Cue: When completed Attachment 1 and submitted it to the Evaluator as Shift Manager, JPM is complete.
6 EXPECTED ACTIONS CUES/STANDARDS (CS Indicates Critical Standard)
Included for Evaluator Reference
7
, MIDAS Accident Calcs Dose Assessment Results
8
, MIDAS Summary
9
, Radioactive Release Radiation Monitors
10 Task Briefing Initial Conditions:
Unit 2 was operating at 80% power A plant shut down was in progress due to failed fuel 21 SG PORV failed open and could not be isolated manually or locally The Crew tripped the reactor and performed actions of E-0 and E-2 A steam generator tube rupture subsequently occurred on 21 Steam Generator and the Crew transitioned to E-3.
The Shift Manager classified a Site Area Emergency (FS1.1) based on Loss of the RCS barrier and Loss of the Containment Barrier Containment radiation subsequently rose to the following values:
VRA-2310, U2 UPPER CONTAINMENT AREA MONITOR - HIGH RANGE = 1300 R/hr.
VRA-2410, U2 LOWER CONTAINMENT AREA MONITOR - HIGH RANGE = 900 R/hr.
The Shift Manager has now upgraded to a General Emergency based on Loss of All Three Fission Product barriers (FG1.1)
Quick Dose Projection has been performed per PMP-2080-EPP-108, Initial Dose Assessment You are an extra SRO Initiating Cues:
The Shift Manager directs you to complete PMP-2080-EPP-100 Attachment 1 Protective Action Recommendations, and submit the completed attachment to the Shift Manager for approval.
This is a Time Critical JPM.