ML23038A142
| ML23038A142 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/12/2023 |
| From: | NRC/RGN-III/DORS/OB |
| To: | |
| Greg Roach | |
| Shared Package | |
| ML21188A238 | List: |
| References | |
| Download: ML23038A142 (47) | |
Text
OT-3701-ADM_031_SRO Rev C 1
JOB PERFORMANCE MEASURE SETUP SHEET System:
Admin Time Critical:
No Alternate Path:
No Setting:
Classroom Applicability:
SRO only Admin Topic:
Conduct of Operations Validated Time:
30 Minutes
References:
NOP-OP-1002 Rev 16 Required Material NOP-OP-1002-Conduct of Operations 10CFR50.54 Conditions of licenses Task:
343-598-03-02 Contact an Individual in Situations that Require Being Called-in During Non-Scheduled Work Hours 343-501-03-03 Verify that the Shift is Manned Properly Task Standard:
Identify positions that are not staffed properly for the on-coming shift. Determines EP staffing requirements for Shift Manager, Unit Supervisor and Shift Engineer cannot all be met. And, that minimum staffing requirements for Reactor Operator and Fire Brigade Leader cannot be met. And, that minimum staffing requirements for Non-Licensed Operator and Fire Brigade Member cannot be met.
K/A:
2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations (reference potential). Importance: SRO 3.9.
1.
Setup Instructions: Print pages 8 & 9 on yellow paper.
2.
Location / Method: Classroom / Performance 3.
Initial Condition: Plant is in Cold Shutdown for a forced outage. A severe snow storm has made travel to the plant difficult. Attached is a list of the oncoming crew personnel that are currently on site. The report was developed from Career Map. The Security Shift Supervisor reports that Site Protection is fully staffed.
4.
Initiating Cue: As the off going Shift Manager, determine if the oncoming crew has sufficient personnel to meet all minimum Perry shift staffing requirements. Document the results of your determination on the JPM CUE SHEET.
Start Time End Time Operator
OT-3701-ADM_031_SRO Rev C 2
JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Step 1 NOP-OP-1002 Conduct of Operations 4.1.12 Fire Brigade
- 1. Site specific staffing requirements are contained in Attachment 4.
4.1.13 Shift Staffing
- 1. A summary of Operations staffing requirements at each site is contained in Attachment 4.
With information provided, candidate reviews NOP-OP-1002 and/or 10CFR50.54 to determine if minimum Perry staffing requirements are met.
Standard:
Operator reviews NOP-OP-1002 and the Career Map printout to determine if sufficient personnel on site to man the shift.
Instructor Cue:
If requested, provide copies of NOP-OP-1002 and/or 10CFR50.54.
If asked about the Column Names, Complete means Qualified.
Notes:
Perry Shift Staffing Requirements are contained on Attachment 4 of NOP-OP-1002, page 100.
Minimum Safe Shutdown staffing in Mode 4 is 3 people. However, Minimum EP staffing is 20.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_031_SRO Rev C 3
Step 2 With information provided, determine if minimum Perry staffing requirements are met for Shift Manager, Unit Supervisor and Shift Engineer.
Critical Step:
Candidate determines that minimum EP (Normal) staffing requirements for Shift Manager, Unit Supervisor and Shift Engineer cannot all be met.
One of the three will not be filled.
Instructor Cue:
After Candidate determines that all positions cannot be filled, ask for explanation of which spots cant be filled.
Notes:
Safe Shutdown requirements can be met, but not EP Staffing requirements. (EP and Normal staffing are identical)
Only Tony E. can fill the Shift Manager spot.
Only Adam C. can fill the Shift Engineer spot.
Either Tony E or Adam C can fill the US spot.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 With information provided, determine if minimum Perry staffing requirements are met for Reactor Operator and Fire Brigade Leader.
Critical Step:
Candidate determines that minimum staffing requirements for Reactor Operator and Fire Brigade Leader cannot be met. Either one RO or the Fire Brigade Leader cannot be filled.
Instructor Cue:
None Notes:
Safe Shutdown requirements can be met, but not EP Staffing requirements.
ROs or SROs can be qualified Fire Brigade Leaders.
Only Henry J. and Jacob E. can fill the 2 RO spots.
Only Henry J. can fill the FBL spot SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_031_SRO Rev C 4
Step 4 With information provided, determine if minimum Perry staffing requirements are met for Non-Licensed Operator and Fire Brigade Member.
Critical Step:
Candidate determines that minimum staffing requirements for Non-Licensed Operator and Fire Brigade Member cannot be met. Either one NLO or one Fire Brigade member cannot be filled.
Instructor Cue:
None Notes:
Safe Shutdown requirements can be met, but not EP Staffing requirements.
POs or PPAs can be qualified Fire Brigade Members.
Only Amanda L., Andrew J., Brian J., and David P. can fill the 2 NLO spots.
Only Amanda L., Andrew J., Colin J. and David P. can fill the 4 Fire Brigade Member spots.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 5 With information provided, determine if minimum Perry staffing requirements are met for Radwaste Technician.
Standard:
Candidate determines that minimum staffing requirements for Radwaste Technician are met.
Instructor Cue:
None Notes:
Radwaste Operations Supervisor is the Radwaste Technician.
Radwaste Technician can be filled by either Alan K. or Robert J.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_031_SRO Rev C 5
Step 6 With information provided, determine if minimum Perry staffing requirements are met for Health Physics Technician.
Standard:
Candidate determines that minimum staffing requirements for Health Physics Technician are met.
Instructor Cue:
None Notes:
The RP Shift Tech is the Health Physics Technician Health Physics Technician positions (2) are filled by both Alan D. and Nick A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 7 With information provided, determine if minimum Perry staffing requirements are met for Chemistry Technician.
Standard:
Candidate determines that minimum staffing requirements for Chemistry Technician are met.
Instructor Cue:
None Notes:
Chemistry Technician can only be filled by Elizabeth A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_031_SRO Rev C 6
Step 8 With information provided, determine if minimum Perry staffing requirements are met for I&C Technician.
Standard:
Candidate determines that minimum staffing requirements for I&C Technician are met.
Instructor Cue:
None Notes:
I&C Technician can be filled by either Bret B., David R., or Mason M.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 9 With information provided, determine if minimum Perry staffing requirements are met for NRC Phone Talker.
Standard:
Candidate determines that minimum staffing requirements for NRC Phone Talker are met.
Instructor Cue:
None Notes:
Even though Michael C is not qualified as Rx operator, he is licensed and has requisite knowledge to fill this position. NRC Phone Talker can only be filled by Michael C. unless an additional RO, NLO or FBM position is left open.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: Three positions in the oncoming shift staffing are identified as not being filled.
Evaluation Results: SAT_____
UNSAT_____
End time
OT-3701-ADM_031_SRO Rev C 7
OT-3701-ADM_031_SRO Rev C 8
Personnel qualification report from Career Map (partial)
First Name Last Name Title Complete Days Remaining Item Completion Status Description Elizabeth A Chemistry Technician Yes 65 Credit Gary L Chemistry Technician No Adam C Field Supervisor Yes 123 Credit Henry J Field Supervisor Yes 5
Credit Jacob E Field Supervisor Yes 265 Credit Michael C Field Supervisor No Tony E Field Supervisor Yes 44 Credit Adam J Fire Brigade Member No Amanda L Fire Brigade Member Yes 67 Credit Andrew J Fire Brigade Member Yes 152 Credit Brian J Fire Brigade Member No Colin J Fire Brigade Member Yes 301 Credit David P Fire Brigade Member Yes 28 Credit Henry J Fire Brigade Member Yes 92 Credit Michael C Fire Brigade Member No Bret B I & C Technician Yes 31 Credit Chaz A I & C Technician No David R I & C Technician Yes 4
Credit Mason M I & C Technician Yes 166 Credit Henry J Perry Fire Brigade Leader Yes 92 Credit Michael C Perry Fire Brigade Leader No Adam J Perry Plant Attendant Yes 101 Credit Amanda L Perry Plant Attendant Yes 109 Credit Andrew J Perry Plant Attendant Yes 84 Credit Brian J Perry Plant Attendant Yes 94 Credit Colin J Perry Plant Attendant Yes 154 Credit David P Perry Plant Attendant Yes 108 Credit Adam J Plant Operator No Amanda L Plant Operator Yes 109 Credit Andrew J Plant Operator Yes 152 Credit Brian J Plant Operator Yes 94 Credit Colin J Plant Operator No David P Plant Operator Yes 108 Credit Alan K Radwaste Operations Supervisor Yes 154 Credit Robert J Radwaste Operations Supervisor Yes 154 Credit
OT-3701-ADM_031_SRO Rev C 9
First Name Last Name Title Complete Days Remaining Item Completion Status Description Henry J Reactor Operator Yes 138 Credit Jacob E Reactor Operator Yes 260 Credit Michael C Reactor Operator No Alan D RP Shift Tech Yes 154 Credit Nick A RP Shift Tech Yes 93 Credit Adam C Shift Engineer Yes 120 Credit Michael C Shift Engineer No Adam C Shift Manager No Tony E Shift Manager Yes 104 Credit Adam C Unit Supervisor Yes 120 Credit Jacob E Unit Supervisor N0 Tony E Unit Supervisor Yes 104 Credit
OT-3701-ADM_031_SRO Rev C 10 JPM CUE SHEET INITIAL CONDITIONS:
Plant is in Cold Shutdown for a forced outage.
A severe snow storm has made travel to the plant difficult.
Attached is a list of the oncoming crew personnel that are currently on site.
The report was developed from Career Map.
The Security Shift Supervisor reports that Site Protection is fully staffed.
INITIATING CUE:
As the off going Shift Manager, determine if the oncoming crew has sufficient personnel to meet all minimum Perry shift staffing requirements.
Document the results of your determination on the JPM CUE SHEET.
OT-3701-ADM_025SRO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
No Alternate Path:
No Setting:
Classroom / Simulator Applicability:
SRO only Administrative Topic: N/A - Refueling Validated Time:
References:
Required Material:
Tasks:
Task Standard:
K/A Data:
28 minutes FTI-D09 Rev. 19 & SOI-F15 Rev 27 FTI-D09 - Use of the Fuel Movement Checklist & JPM Support Material 341-029-03-02 Supervise Refueling Operations as Refueling Supervisor 341-624-01-02 Verify Compliance with Technical Specifications, Procedures, and Instructions During Refueling and Fuel Handling Verify proper placement of in-core components during Refuel Operations IAW the Fuel Movement Checklist. Determines that bundles 12P400 and 12P499 are in incorrect locations and bundle 13P911 has the incorrect orientation and FBG is misoriented.
2.1.35 Knowledge of the fuel-handling responsibilities of SROs.
Importance Rating: SRO 3.9.
2.1.42 Knowledge of new and spent fuel movement procedures.
Importance Rating: SRO 3.4 1.
Instructions: None 2.
Location / Method: Simulator or Control Room / Administrative performance.
3.
Initial Condition: Plant is in Mode 5 with refueling operations in progress. The ROV cameras had been out of service for the past several hours but are now back in service.
You are the on-coming Refuel Bridge SRO. The off-going Refuel Bridge SRO asks you to verify Page 65 of the attached Fuel Movement Checklist. The Fuel Movement Checklist Cover Sheets, Core Map, and ROV pictures of the applicable core cells are available.
4.
Initiating Cue: As the Refueling SRO, verify the in-core placement of all components on Page 65 of the attached Fuel Movement Checklist.
Start Time End Time Operator
OT-3701-ADM_025SRO Rev A JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Step 1 Determine INCORRECT loading of Cell 54-15.
The operator reviews the Fuel Movement Checklist and compares the cell pictures to the FMC.
Critical Step:
The Operator reviews the FMC Page 65 Step 295 and determines that bundle 12P400 is in the incorrect location. Additionally, bundle 12P499 for Step 296 is in the incorrect location.
Instructor Cue:
Acknowledge errors and advise to continue to perform peer check.
Notes:
Provide a copy of FTI-D09.
Bundle 12P400 should be in location 53-16 and bundle 12P499 should be in location 55-14.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_025SRO Rev A Step 2 Determine CORRECT loading of Cell 46-35.
Standard:
The Operator reviews the FMC Page 65 Steps 306 & 307 and determines that they were performed correctly.
Instructor Cue:
Advise to continue to perform peer check.
If asked about Step 306.5, tell Operator to review Initiating Cue.
Notes:
Step 306.5 is not a verification of in-core components as instructed on Initiating Cue.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 Determine INCORRECT loading of Cell 42-19.
Standard:
The Operator reviews the FMC Page 65 Step 311 and determines that bundle 13P907 is in the correct location and correct orientation.
Critical Step:
The Operator reviews the FMC Step 312 and determines bundle 13P911 has the incorrect orientation in the correct location.
Instructor Cue:
If Operator has not referenced FTI-D009, question operator on what is required when an error is discovered.
Acknowledge errors and advise to continue to perform peer check.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_025SRO Rev A Step 4 Determine INCORRECT orientation (loading) of Cell 38-55.
Critical Step:
The Operator reviews the FMC Page 65 Step 315 and determines that the Full Blade Guide was placed in the incorrect locations.
Instructor Cue:
Ask Operator if this is a fuel movement error. He should respond no.
If asked about Step 316, tell Operator to review Initiating Cue.
Notes:
FBG is in locations 39-56 & 37-54.
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: Operator determines that bundles 12P400 and 12P499 are in the incorrect locations and bundle 13P911 has the incorrect orientation in the correct location.
Evaluation Results:
SAT_____
UNSAT_____
End Time
OT-3701-ADM_025SRO Rev A JPM CUE SHEET INITIAL CONDITIONS:
- Plant is in Mode 5 with refueling operations in progress.
- The ROV cameras had been out of service for the past several hours but are now back in service.
- You are the on-coming Refuel Bridge SRO.
- The off-going Refuel Bridge SRO asks you to verify Page 65 of the attached Fuel Movement Checklist.
- The Fuel Movement Checklist Cover Sheets, Core Map, and ROV pictures of the applicable core cells are available.
INITIATING CUE:
As the Refueling SRO, verify the in-core placement of all components on Page 65 of the attached Fuel Movement Checklist.
OT-3701-ADM_025SRO Rev A FUEL MOVEMENT CHECKLIST REFUEL FLOOR CHECKLIST PAGES 1
TO 182 STEPS 2
TO 1860 14-MAR-2017 15:01 The purpose of this FMC is to support refueling activities in 1R16. It shall be executed in accordance with FTI-D0009, SOI-F0015, SOI-F0042, and 101-0009.
The Maintenance Window for control rod blades and drive mechanisms, and SRM and IRM visual inspections is reached when Step 495 is completed and stays open through Step 1071.
Steps 1072 through 1074 (which move only single blade guides) may be completed any time after the SRM and IRM dry tube inspections have been completed but must be completed before the LPRM dry tube replacements begin.
Phase 2 commences with Step 1075 and ends with Step 1845.
Steps 1854 through 1860 configure the half blade guides in RPI. Since these half blade guides are not used during the outage, these steps may be completed at any convenient time.
In Phase 1, if any SRM becomes inoperable, contact Reactor Engineering to determine if fuel moves may be continued in another quadrant, and any limitations to changing quadrants. No changes are permitted in Phase 2.
Phase 2 peripheral camera inspections for uncontrolled bundle seating are noted on the FMC. Seating checks are performed after step has been completed.
The quadrants for I RI 3 are defined by the North/South line along coordinate 30 and the East/West line along coordinate 31. This makes control rod 30-3 1 the center of the core. This is a change from 1 RI 2.
If a planned location in the containment pool (RP1) is not usable, any unused location in RP1 rows C through F, columns -01 through -03, may be used for a FREE MOVE. Note that the furthest East column is designated 00 (not 01).
Page 1 of 2
OT-3701-ADM_025SRO Rev A FUEL MOVEMENT CHECKLIST REFUEL FLOOR CHECKLIST PAGES 1
TO 182 STEPS 2
TO 1860 14-MAR-2017 15:01 Notify Reactor Engineering any time a Free Move is used and cleared.
Orientation in RP1 is in accordance with the direction of the bridge supervisor.
Transfer Tube steps may be performed any time the appropriate component is loaded in the carriage.
Fuel movement does not involve invessel fuel moves.
Fuel movement only removes fuel from core.
Fuel movement only reloads core to BOC pattern.
Fuel movement involves a shuffle through intermediate loading patterns.
Minimum SDM = _1.0__% dk/k Reference Tech Spec SR 3.1.1.1 concerning the above requirements.
PREPARED BY:
Chuck R. Enginer REVIEWED BY:
Pat B. Peer APPROVED BY:
P. J. Supe DATE: 2 days ago FMC COMPLETE: ______________________________ DATE: __________
CHANGE HISTORY:
Page 2 of 2
OT-3701-ADM_025SRO Rev A FENOC - - PNPP NUCLEAR FUEL ACCOUNTING FUEL MOVEMENT CHECKLIST - Refuel Floor FMC 14-Mar-2017 15:01 Page 65 STEP COMPONENT FROM LOCATION FREE MOVE INIT/DATE TO LOCATION ORIENT INIT DATE 295 12P400 RX1 31-30 RX1 53-16 SE HD LEFT - EZ RIGHT
/
LBJ /
Today 296 12P499 RX1 05-14 RX1 55-14 NW EZ LEFT - EZ RIGHT
/
LBJ /
Today 306 14P046 FTT U1-E RX1 45-36 SE
/
LBJ /
Today 306.5 TRANSFER FUEL CARRIAGE DOWN TO FHB LBJ /
Today 307 14P038 RP1 B-01 RX1 47-34 NW
/
LBJ /
Today 311 13P907 RX1 43-30 RX1 43-20 SW HD LEFT - EZ RIGHT
/
LBJ /
Today 312 13P911 RX1 49-30 RX1 41-18 NE EZ LEFT - EZ LEFT
/
LBJ /
Today 315 FBG RX1 41-20 RX1 37-56 RX1 43-18 RX1 39-54 LBJ /
Today 316 14P051 RX1 59-24 FTT U1-W
/
LBJ /
Today 317 14P049 FTT U1-E RX1 47-48 SE
/
/
OT-3701-ADM_025SRO Rev A
Control Cell 54-15 N
Control Cell 46-35 N
Control Cell 42-19 N
Control Cell 38-55 N
OT-3701-ADM_036SRO Rev C JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
No Alternate Path:
No Setting:
Classroom Applicability:
SRO Only Admin Topic:
Equipment Control Validated Time:
18 Minutes
References:
PDB-G001 Rev. 6, Tech Specs, Drawings 302-641 Rev. KKK, 302-642, Rev.
PP., & 302-705 Rev. HH Required Material:
Drawings 302-641, 302-642, 302-705 included on drawing stick and laptop with Filenet Lite loaded Task:
341-591-01-02 Apply Technical Specifications, ORM, ODCM, the Operating License, Holtec Hi Storm Technical Specifications, and FLEX Specifications as required, during all Modes of plant operation.
Task Standard:
Determine that 1E12-F609 is a PCIV and TS 3.6.1.3 Required Actions and Completion Time for a failed PCIV apply. And, that 1E12-F610 must be closed and down-powered to comply with Tech Spec 3.6.1.3 Required Action A.1.
K/A:
2.2.22 Knowledge of limiting conditions for operation and safety limits IR SRO 4.7 1.
Setup Instructions: Provide set of 302 drawings and all Tech Spec Books and FileNet lite computer. Have a copy of PDB-G001 available. Have Picture of Isolation Matrix available.
2.
Location / Method: Classroom / Administrative Performance 3.
Initial Condition: Plant is in Mode 3. Water was being transferred from the Suppression Pool to the CST using SPCU. While the transfer was being terminated, 1E12-F609, SPCU TO RHR SECOND OTBD ISOL got stuck in the open position and cannot be closed.
4.
Initiating Cue: As the Unit Supervisor, determine any current Tech Spec implications for this stuck valve.
Start:
Stop:
Candidate:
OT-3701-ADM_036SRO Rev C JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Step 1 Standard:
Candidate reviews drawings, procedures, etc. to ascertain purpose/location of valve 1E12-F609.
Instructor Cue:
None Notes:
302 series drawings are provided as well as computer loaded with all procedures from FileNet.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 2 Critical Step:
Candidate determines that 1E12-F609 is a Primary Containment Isolation valve.
Standard Candidate refers to PDB-G001, Containment Isolation Valve Table, (page
Instructor Cue:
If Applicant says they are looking for a PBD (Plant Data Book), provide them a copy of PDB-G001 If Applicant asks for a picture of the Isolation Matrix, provide them with Isolation Matrix picture.
Notes:
Candidate may recall from memory or refer to other documents or drawings to determine that 1E12-F609 is a PCIV SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_036SRO Rev C Step 3 Critical Step:
Candidate determine that 1E12-F609 is an inoperable PCIV and LCO 3.6.1.3 Condition A is not met.
Standard Candidate reviews Tech Spec 3.6.1.3.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 4 Critical Step:
Candidate determine that Tech Spec 3.6.1.3 Required Action A.1 must be performed with a completion time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and Required Action A.2 must be performed with a Completion time of Once per 31 days.
Standard Candidate reviews Tech Spec 3.6.1.3.
Instructor Cue:
Ask Candidate how specifically, Required Action A.1 would be accomplished for this Inoperable PCIV.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_036SRO Rev C Step 5 Critical Step:
Candidate determines that 1E12-F610, SPCU TO RHR FIRST OTBD ISOL, must be closed and down-powered to comply with Tech Spec 3.6.1.3 Required Action A.1.
Standard Candidate reviews Tech Spec 3.6.1.3 Bases (page B 3.6-20). When a PCIV becomes inoperable within a line. and the Required Action directs the operator to "isolate the affected penetration flowpath." the intent is to isolate only the line with the inoperable PCIV. It is not the intent to close off other lines that are unaffected by the inoperable PCIV.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
Candidate determined that 1E12-F609 is an Inoperable PCIV IAW TS 3.6.1.3 Condition A and that it must be isolated by closing and deactivating 1E12-F610 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-ADM_036SRO Rev C
OT-3701-ADM_036SRO Rev C JPM CUE SHEET INITIAL CONDITIONS:
Plant is in Mode 3.
Water was being transferred from the Suppression Pool to the CST using SPCU.
While the transfer was being terminated, 1E12-F609, SPCU TO RHR SECOND OTBD ISOL got stuck in the open position and cannot be closed.
INITIATING CUE:
As the Unit Supervisor, determine any current Tech Spec implications for this stuck valve.
OT-3701-ADM_035_SRO Rev B System:
Administrative Time Critical:
No Alternate Path:
No Setting:
Classroom Applicability:
SRO only Admin Topic:
Radiation Control Validated Time:
16 Minutes
References:
OAI-1703 Rev. 42 EPI-B13 Rev. 16 EOP-01-1 Rev. 0 EOP-02 Rev. 6 EAL Matrix TSG-2 Rev. 0 Required Material:
OAI_1703 Attachment 6 SDS Printouts EOP-01-1 Chart EOP-02 Chart EPI-B13 EAL Matrix TSG-2 Or FileNet Lite Task:
344-539-05-02 Utilize the core damage occurring hardcard to determine if core damage is occurring.
Task Standard:
The candidate determines that core damage has occurred based on DW and Containment radiation levels and determines the Core Damage Category is MELT.
K/A:
2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures, or analysis and interpretation of coolant activity, including comparison to emergency plan or regulatory limits (SRO Only)
IR SRO 3.8
- 1.
Setup Instructions: None
- 2.
Location / Method: Classroom / Administrative Performance
- 3.
Initial Condition: The plant entered EOP-01-1, Alternate Level/Pressure Control one hour ago. The RPV has been Rapidly Depressurized IAW EOP-01-1, resulting in rising radiation levels in the DW and Containment. Hydrogen Analyzers are in-service. Drywell H2 is 2% and rising. Containment H2 is 4% and rising. The TSC is not yet activated. Chemistry is analyzing a Containment Atmospheric Sample and will have results in 20 minutes.
- 4.
Initiating Cue: As an off-shift SRO, determine if core damage is occurring.
Start:
Stop:
Candidate:
OT-3701-ADM_035_SRO Rev B JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Step 1 Review information and determine the appropriate procedure to use to determine if core damage has occurred.
Standard:
The candidate evaluates the SPDS information and the cue information and determines that core damage evaluation can be determined by using:
- OAI-1703, Hardcards - Attachment 6 - Core Damage Occurring Hardcard
- EPI-B13 Determination of Core Damage Under Accident Conditions
- TSG-2.2.2.g Primary Containment Radiation Level Instructor Cue:
None Notes:
These three procedures may be used to determine if core damage has occurred. Each will lead to the determination of core damage.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_035_SRO Rev B Step 2 OAI-1703, Hardcards - Attachment 6 - Core Damage Occurring Hardcard OAI-1703 Hardcard Revision 2 Core Damage Occurring Use a combination of several of the following items Use multiple and diverse indications Yes supports Core Damage Condition Trend Condition Met Greater than 10% Clad Failure (Requires ERO assessment support)
YES NO Drywell greater than 1x104 R/hr and rising UP STABLE DOWN YES NO Containment greater than 1x104 R/hr and rising UP STABLE DOWN YES NO Off Site Dose Release rates greater than those requiring a General Emergency UP STABLE DOWN YES NO Vessel injection NOT available prior to losing RPV level indication YES NO HPCS Pump NOT injecting greater than 6200 gpm YES NO LPCS Pump NOT injecting greater than 6200 gpm YES NO Hydrogen levels Greater than HDOL YES NO Adequate core cooling lost for greater than 30 minutes YES NO Standard:
The candidate evaluates OAI-1703, Att. 6, Core Damage Occurring, Hardcard.
Critical Step:
The candidate determines that core damage has occurred.
Instructor Cue:
If the candidate determines that core damage has occurred, ask the candidate the following:
What Core Damage Category has been met?
GO TO Step 5.
Notes:
This step is only Critical if the candidate utilizes OAI-1703 for determining core damage, otherwise this step may not be applicable.
If the Candidate determines that Core Damage has NOT occurred, this constitutes a failure of the Critical Step and terminate the JPM.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_035_SRO Rev B Step 3 EPI-B13 Determination of Core Damage Under Accident Conditions 4.2.1 Assessment of Core Damage Based on Drywell/Containment Dose Rate NOTE This is a quick and rough estimate of core damage.
Core damage may be estimated by the use of Attachment 1, Core Condition Determination flow chart. The flow chart utilizes the Drywell and Containment Post Accident Monitor readings to estimate the core damage. Initially this estimate will be used to determine the source term input into the Unified RASCAL Interface (URI)
Dose Assessment Software. URI uses an isotopic mixture associated with the source term in conjunction with effluent monitor readings, time of reactor trip, meteorological data and release duration to provide offsite dose projections for the purpose of protecting the public.
NOTE RPV water level and core cooling strategy are described I the EOP-Bases Document.
- 1. Obtain the D19N100A/D19N100B Drywell Radiation Monitor and D19N200A/D19N200B Containment Radiation Monitor reading(s).
- 2. Perform core damage determination using Attachment 1, Source Term Determination Flow Chart.
OT-3701-ADM_035_SRO Rev B Step 3 (Continued)
EPI-B13 Determination of Core Damage Under Accident Conditions, Core Damage Categories:
- Normal Coolant is the source term used in URI when there is either no significant damage to fuel cladding or there is minor clad damage such that fission products normally present in the fuel rod gap region can be released into the Reactor Coolant System (RCS).
- Clad is the source term used in URI with a loss of both the Fuel Clad Barrier and the RCS Barrier, corresponding to an approximate range of 2% to 5% fuel clad damage. The radiation threshold represents an instantaneous release of all reactor coolant mass into the containment, assuming reactor coolant activity equals 300
µCi/gm dose equivalent I-131. Reactor coolant activity above this level is greater than that expected for iodine spikes. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier.
- Melt is the source term used in URI with a loss of both the Fuel Clad Barrier and the RCS Barrier, assuming that 20% of the fuel cladding has failed. The radiation threshold represents an instantaneous release of all reactor coolant mass into the containment.
OT-3701-ADM_035_SRO Rev B Step 3 (Continued)
EPI-B13 Determination of Core Damage Under Accident Conditions, Att. 1 Core Condition Determination.
OT-3701-ADM_035_SRO Rev B Step 3 (Continued)
Standard:
The candidate evaluates for core damage IAW EPI-B13 Att. 1 Critical Step:
The candidate determines that core damage has occurred.
Instructor Cue:
If the candidate determines that core damage has occurred, ask the candidate the following:
What Core Damage Category has been met?
GO TO Step 5.
Notes:
This step is only Critical if the candidate utilizes EPI-B13 for determining core damage, otherwise this step may not be applicable.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_035_SRO Rev B Step 4 TSG-2, Technical Support Guidelines Control Parameter Assessment, Section 2.2.2.g, Primary Containment Radiation Level.
Primary Containment radiation level can be determined from:
- Containment radiation monitoring instruments installed to monitor drywell or containment radiation level
- Portable instruments which measure radiation outside containment can be used to extrapolate radiation levels inside containment Curves correlating decay of radiation readings for different fuel failure conditions may be very helpful in confirming whether or not the indication is reliable. Figure 2.8 is an example illustrating drywell radiation readings and various states of fuel damage. Refer to EPI-B13, Determination Of Core Damage Under Accident Conditions for further information on determination of Core Damage.
Figure 2.8 - Drywell Radiation Rates for Various Fuel Failure Conditions
OT-3701-ADM_035_SRO Rev B Step 4 (Continued)
Standard:
The candidate evaluates for core damage IAW TSG-, Section 2.2.2.g and Figure 2.8 Critical Step:
The candidate determines that core damage has occurred.
Instructor Cue:
If the candidate determines that core damage has occurred, ask the candidate the following:
What Core Damage Category has been met?
GO TO Step 5.
Notes:
This step is only Critical if the candidate utilizes TSG-2 for determining core damage, otherwise this step may not be applicable.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_035_SRO Rev B Step 5 Critical Step:
The candidate determines that Core Damage Category is MELT.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
Determined Core Damage has occurred, and the Core Damage Category is MELT.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-ADM_035_SRO Rev B JPM CUE SHEET INITIAL CONDITIONS:
- The plant entered EOP-01-1, Alternate Level/Pressure Control one hour ago.
- The RPV has been Rapidly Depressurized IAW EOP-01-1, resulting in rising radiation levels in the DW and Containment.
- Hydrogen Analyzers are in-service.
- Drywell H2 is 2% and rising.
- Containment H2 is 4% and rising.
- The TSC is not yet activated.
- Chemistry is analyzing a Containment Atmospheric Sample and will have results in 20 minutes.
INITIATING CUE:
As an off-shift SRO, determine if core damage is occurring.
OT-3701-ADM_323SRO Rev B JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
Yes Alternate Path:
No Setting:
Classroom/Simulator Applicability:
SRO only Admin Topic:
Emergency Procedures / Plan Validated Time:
8 Minutes
References:
NOP-LP-5502 Rev. 00, NOP-LP-5003 Rev. 00 Required Material:
NOP-LP-5502, Event Classification, NOP-LP-5003 Emergency Notification Form NOBP-LP-5509 - Attachment 1 Form NOP-LP-5503 Perry ERO Notification Messages Form Perry Emergency Notification Cover Sheet Form PNPP Initial Notification Form Task:
344-532-05-02 Prepare emergency plan initial notification form.
451-654-05-50 Upon declaration of any Emergency Action Level, notify offsite authorities of the event.
Task Standard:
Perform a peer check of E-plan forms and identify incorrect EAL recorded and incorrect PAR determination and make communications to the state and local counties.
K/A:
2.4.43 Knowledge of emergency communications systems and techniques. Importance SRO 3.8
- 1.
Setup Instructions: Insert JPM material into binders with dividers. Place placard near E-Plan Phone. Place U1 Plant Vent rad monitor picture over rad monitor. Simulator Driver may act as State and Counties on 5-way. Make simulator 5-way phone marking match control room. Use analog clock for JPM administration. Evaluator:
Give Candidate material from Tab-2.
- 2.
Location / Method: Simulator / Administrative Performance
- 3.
Initial Condition: A transient occurred. The Emergency Plan has been entered. You as the Shift Engineer have already peer checked the Shift Managers EAL classification of FS1.1 with a non-routine release in progress. The time of the Emergency Declaration was 3 minutes ago. The Notification Messages form has been broadcast; The Shift Manager completed the Initial Notification Form. (Maybe reverse these two I/Cs.)
- 4.
Initiating Cue: Shift Manager directs you the Shift Engineer to perform a peer check of the Initial Notification Form. This JPM is Time Critical.
Start:
Stop:
Candidate:
NOTE: Record Start Time once Candidate Acknowledges the I/Cs are understood.
OT-3701-ADM_323SRO Rev B JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Step 1 Perform a peer check of the Emergency Plan paperwork.
Critical Step Standard:
Candidate Reviews the Initial Notification Form and determines an EAL of FG1.1 was recorded vs. FS1.1.
Instructor Cue:
I will correct the EAL Notes:
If Candidate doesnt identify the second error (PAR not required), hand them the alternate corrected Notification Form from Tab-3.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 2 Perform a peer check of the Emergency Plan paperwork.
Critical Step Standard:
Candidate Reviews the Initial Notification Form and determines a PAR was incorrectly included on form.
Instructor Cue:
I will delete the PAR Notes:
After Candidate identifies EAL & PAR errors, hand them a corrected Initial Notification Form from Tab-4.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_323SRO Rev B Step 3 Perform a peer check of the Emergency Plan paperwork.
Standard:
Candidate Reviews the corrected Initial Notification Form and determines it is completed correctly.
Instructor Cue:
After the corrected form is reviewed, hand the Candidate the material from Tab-5 with partially completed CR Shift Manager/Emergency Coordinator Checklist and inform the Candidate that he/she has now been directed by the Shift Manager to continue with E-plan duties.
Notes:
Candidate may review the CR Shift Manager/Emergency Coordinator Checklist to determine remaining actions.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_323SRO Rev B Step 4 Make notification to the state and local counties.
Critical Step Standard:
Candidate pickups the 5-way and communicates the content of the Initial Notification Form to the State of Ohio and Lake, Geauga, & Ashtabula counties.
Instructor Cue:
If Candidate pages the Shift Communicator, inform him the Communicator is stuck in the plant and unable to come to the Control Room When Candidate picks up the Training 5-way phone and presses the red bar (on the lower part of the phone), inform him that State of Ohio and Lake, Geauga, & Ashtabula counties are all on the line.
NOTE:
Once Candidate Acknowledges the cue that all parties are on the line mark the End Time below for completion of the Time Critical portion of the JPM. [End Time - Start Time < or = 12 min; SAT]
The following is from the PY Notification Cover Sheet:
- 4. Direct parties to obtain Initial Notification Form. - Respond all parties have the form.
- 5. Pause 10 seconds to allow parties to obtain a form.
- 6. Transmit Notification Form Data - Respond all parties have the data.
(The State of Ohio phone is answered by the Ohio Highway Patrol office in Columbus.)
Notes:
After Candidate makes notifications, terminate the JPM.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
Initial Notification Form has been corrected and notification to the state and local counties is complete.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-ADM_323SRO Rev B JPM CUE SHEET INITIAL CONDITIONS:
- A transient occurred.
- The Emergency Plan has been entered.
- You as the Shift Engineer have already peer checked the Shift Managers EAL classification of FS1.1 with a non-routine release in progress.
- The time of the Emergency Declaration was 3 minutes ago.
- The Notification Messages form has been broadcast.
- The Shift Manager completed the Initial Notification Form.
INITIATING CUE:
Shift Manager directs you the Shift Engineer to perform a peer check of the Initial Notification Form.
This JPM is Time Critical.
PERRY NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM NOP-LP-5503-07 Rev. 00 USE FOR:
INITIAL CLASSIFICATIONS, CHANGES IN CLASSIFICATIONS, CHANGES IN PROTECTIVE ACTION RECOMMENDATIONS.
EVENT TERMINATION STATE / COUNTY USE ONLY DATE:
TIME:
MESSAGE NO:
- 1. This is the:
Perry Nuclear Power Plant
- 2. This is:
An Actual Emergency A Drill
- 3.
- a. A(n)
GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT was declared at: 1500 on Today based on EAL:
FS1.1 (TIME)
(DATE)
- b. The Emergency situation has been terminated at:
on (TIME)
(DATE)
- c. The Protective Action Recommendation is being changed at:
on (TIME)
(DATE)
- 4. The radiological conditions are:
- a. A non-routine release of radioactive material, as a result of this event, is in progress.
- b. The release of radioactive material associated with this event has been terminated.
- c. NO Radiological Release in progress as a result of this event.
- 5. Utility Protective Action Recommendations (PARs):
- a. Evacuation:
(check applicable subareas) 1 2
3 4
5 6
7 LAKE AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.
- b. Sheltering:
(check applicable subareas) 1 2
3 AND Evacuate the Lake AND that potassium iodide (KI) be administered to the general public in accordance with State procedures.
The general public in unaffected areas should be advised to go indoors and monitor EAS broadcasts.
- c. None For Utility Use Only Approved: Shiff T. Major
Page 2 of 2 INSTRUCTIONS FOR COMPLETION PY INITIAL NOTIFICATION FORM (INF)
NOP-LP-5503-05, Rev 0 This form is to be used for:
- Initial Classifications
- Changes in Classification
- Changes in PAR
- Event Termination Complete Sections 2 through 5 using the following guidance:
Section 2
- 1. Check the appropriate box.
Section 3
- 1. IF this is an Initial or change is classification, THEN check box a.
1.1.
Check the applicable classification box.
1.2 Enter the Time and Date that the Classification was declared.
1.3.
Enter the applicable EAL alpha/numeric characters from the Wallboard.
- 2. IF this is an Event Termination notification, THEN check box b.
2.1 Enter the Time and Date that the event was terminated.
- 3. IF this is a PAR Change notification, THEN check box c.
3.1 Enter the Time and Date of the PAR change.
Section 4
- 1. Check the appropriate box IAW guidance in NOP-LP-5501, Attachment B AND/OR C.
Section 5.
- 1. Check the appropriate boxes IAW guidance in NOP-LP-5504, Protective Measures, Attachment F.