ML19239A411
| ML19239A411 | |
| Person / Time | |
|---|---|
| Site: | Perry |
| Issue date: | 08/23/2019 |
| From: | Joseph Demarshall FirstEnergy Nuclear Operating Co |
| To: | NRC/RGN-III/DRS/OLB |
| demarshall j | |
| Shared Package | |
| ML17215A922 | List: |
| References | |
| Download: ML19239A411 (40) | |
Text
OT3701ADM_033SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
No Applicability:
SRO Administrative Topic: Conduct of Operations Validated Time:
15 minutes
References:
NOBP-TR-1271, Rev. 7 & PYBP-POS 1-5, Rev. 3 Required Material:
NOBP-TR-1271, Operator License Administration PYBP-POS 1-5, Operations Training Guidelines NOP-LP-4011, FENOC Work Hour Control NUREG-1021, Operator Licensing Examination Standards For Power Reactors Tasks:
299-831-03-01 Perform licensed duties only if your license is Current and Active Task Standard:
Review proposed work schedules to determine appropriate schedule(s) to reactivate SRO license per NOBP-TR-1271, Operator License Administration K / A Data:
2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. RO 3.3 SRO 3.8
- 1. Setup Instructions: N/A
- 2. Location / Method: Classroom / Perform
- 3. Initial Condition: It is June 26 and you have an Inactive SRO license. Operations Manager wants you to activate your SRO license. I will provide you with 6 proposed schedules to re-activate your SRO license.
- 4. Initiating Cue:
Evaluate the proposed schedules to determine if each/any of the schedules meet the requirements to reactivate your SRO License.
If a schedule does not meet the requirements, EXPLAIN why it does not.
Start Time:
End Time:
Candidate:
OT3701ADM_033SRO Rev 0 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 NOBP-TR-1271, Operator License Administration 4.5 Maintaining an Active NRC License 4.5.1 Operations Manager
- 1.
Ensure that only individuals with an active, valid, NRC Reactor Operator or Senior Reactor Operator License (or individuals in an approved Licensed Operator Training Program and directly supervised by a Licensed Operator) are permitted to perform Licensed Duties as specified in Technical Specifications and Plant Operating Procedures.
- 3.
Initiate an Inactive License Retraining Program (Attachment 2) for the individual that specifies the following minimum requirements for reinstatement to Licensed Duties:
- b.
Stand a minimum of forty (40) hours of on-shift functions (within the same calendar quarter), including at least one complete on-coming shift turnover and one complete offgoing shift turnover, under the direction of a Licensed Operator or Licensed Senior Operator watchstander (as appropriate) in the position to which the individual will be assigned.
PYBP-POS-1-5, Operations Training Guidelines 4.1 Tracking Of Proficiency Watches 4.1.1 Discussion of Maintenance and Reactivation Requirements If the time-on-shift requirement is not met within a calendar quarter, the active license becomes inactive. The license holder is not permitted to resume watchstanding duties until the license is reactivated through a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of under instruction watch-standing and the completion of other reactivation activities..
Step 1 continued next page
OT3701ADM_033SRO Rev 0 Step 1 continued Standard:
Operator reviews the following for reactivation requirements:
- NOBP-TR-1271, Operator License Administration
- PYBP-POS-1-5, Operations Training Guidelines Instructor Cue:
None Notes:
Candidate may want to review NOP-LP-4011 for Fatigue Rule.
Reactivation of a License does not require standing full shifts to fulfill the 40-hour under instruction requirement. (Ref. NUREG 1021, ES-605 C.2.f)
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 2 Evaluate Schedule 1.
Critical Step:
Operator determines Schedule 1 does not meet:
- 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in a calendar quarter in a qualifying position (NOT Shift Engineer)
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT3701ADM_033SRO Rev 0 Step 3 Evaluate Schedule 2 Critical Step:
Operator determines Schedule 2 does not meet:
- 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in a calendar quarter in a qualifying position (NOT Shift Engineer)
- No On-coming turnover Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 4 Evaluate Schedule 3 Critical Step:
Operator determines Schedule 3 meets all requirements.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT3701ADM_033SRO Rev 0 Step 5 Evaluate Schedule 4 Critical Step:
Operator determines Schedule 4 does not meet:
- 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in a calendar quarter Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 6 Evaluate Schedule 5 Critical Step:
Operator determines Schedule 5 meets all requirements.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT3701ADM_033SRO Rev 0 Step 7 Evaluate Schedule 6 Critical Step:
Operator determines Schedule 6 does not meet:
- 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in a calendar quarter in a qualifying position (NOT Shift Engineer)
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
Operator has determined that schedules 1, 2, 4, & 6 do not meet the requirements for SRO license reactivation and has selected either schedule 3 or 5 to reactivate SRO license.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT3701ADM_033SRO Rev 0 Proposed Schedules Schedules 27-Jun 28-Jun 29-Jun 30-Jun 1-Jul 2-Jul 3-Jul 4-Jul 5-Jul 1
Hours 8 hrs.
12 hrs.
12 hrs.
12 hrs.
12 hrs.
4 hrs.
Position SE US US SE SM US Turnovers On-coming Off-going Off-going On-coming 2
Hours 12 hrs.
12 hrs.
12 hrs.
12 hrs.
Position US US US SE Turnovers Off-going Off-going Off-going 3
Hours 12 hrs.
6 hrs.
12 hrs.
12 hrs.
8 hrs.
6 hrs.
Position SE US US US US US Turnovers On-coming Off-going 4
Hours 8 hrs.
8 hrs.
8 hrs.
8 hrs.
8 hrs.
Position SM SM US US SE Turnovers On-coming On-coming Off-going Off-going 5
Hours 12 hrs.
12 hrs.
8 hrs.
8 hrs.
8 hrs.
Position US US US US SE Turnovers On-coming Off-going Off-going 6
Hours 12 hrs.
8 hrs.
12 hrs.
8 hrs.
12 hrs.
8 hrs.
7 hrs.
Position SE SM US US US SE SE Turnovers Off-going On-coming On-coming SE - Shift Engineer SM = Shift Manager US = Unit Supervisor
OT3701ADM_033SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
It is June 26 and you have an Inactive SRO license.
Operations Manager wants you to activate your SRO license.
I will provide you with 6 proposed schedules to re-activate your SRO license.
INITIATING CUE:
- Evaluate the proposed schedules to determine if each/any of the schedules meet the requirements to reactivate your SRO License.
- If a schedule does not meet the requirements, EXPLAIN why it does not.
OT-3701-ADM_034SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
No Alternate Path:
No Applicability:
SRO Safety Function:
Conduct of Operations Validated Time:
14 Minutes
References:
SVI-P50-T2001 Rev 7, NOP-WM-2003 Rev 9 Required Material:
SVI-P50-T2001, CVCW Isolation Valves Operability Test NOP-WM-2003, Work Management Surveillance Process Task:
342-564-03-02 Determine Operability of Plant Equipment Based on Surveillance Test Results and Other Plant Conditions.
342-566-03-02 Complete the Requirements for a Final Review of a Surveillance Data Package Task Standard:
Review surveillance to determine if isolation valves are operable.
K/A:
2.1.2 Knowledge of operator responsibilities during all modes of plant operation. Importance: SRO 4.4 1.
Setup: None 2.
Location / Method: Class Room / Administrative performance.
3.
Initial Condition: Reactor power is currently at 95%. SVI-P50-T2001, CVCW Isolation Valves Operability Test was performed but not reviewed last shift per the PWIS for the 2-Year (24-month) performance.
4.
Initiating Cue: As the Unit Supervisor, perform SRO review of the attached SVI-P50-T2001, CVCW Isolation Valves Operability Test. Document the results of your review on the Data Package Cover Sheet.
Start:
Stop:
Operator:
OT-3701-ADM_034SRO Rev 0 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 surveillance.
SVI-P50-T2001, CVCW Isolation Valves Operability Test 4.0 PREREQUISITES 2
Have the Unit Supervisor determine PI Verification requirements from the Functional Location associated with this instruction and, check YES or NO.
PI Verification Required:
YES
NO.
Standard:
Operator reviews the SVI and determine that PREREQUISITE Step 2 was inappropriately checked NO.
Instructor Cue:
If asked, direct Operator to continue review.
Notes:
Per the Initial Conditions, the 2-year performance of this surveillance is required. The position indication verification is required every 2 years for the Inservice Testing Program (T.S. 5.5.6) and T.S. 3.3.3.1, Post Accident Monitoring (PAM) Instrumentation, SR 3.3.3.1.3 SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_034SRO Rev 0 Step 2 Review surveillance.
Critical Step:
Operator determines in Step 5.1.2.c, the recorded closed stroke time exceeds the Acceptable Range.
Instructor Cue:
None Notes:
Step is marked SAT with an excessive stroke time.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 Review surveillance.
Standard:
Operator determines all other items checked in this surveillance were performed satisfactorily.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_034SRO Rev 0 Step 4 Review surveillance.
Critical Step:
Reviews Acceptance Criteria (Step 5.3) and determines that Step 5.3.1 was inappropriately signed.
Instructor Cue:
None Notes:
Step 5.3.2 was correctly signed off.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 5 Review surveillance Data Package Cover Sheet.
Critical Step:
Reviews Data Package Cover Sheet and determines that TECHNICAL SPECIFICATION DATA block should be checked UNACCEPTABLE.
Instructor Cue:
None Notes:
Valve P50-F140 exceeded the Acceptable Range for stroke time to close.
Therefore, Acceptance Criteria 5.3.1 was not met.
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: Review of SVI-P50-T2001 is complete and problems have been documented on the Data Package Cover Sheet.
Evaluation Results:
SAT_____
UNSAT_____
End Time
OT-3701-ADM_034SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
Reactor power is currently at 95%. SVI-P50-T2001, CVCW Isolation Valves Operability Test was performed but not reviewed last shift per the PWIS for the 2-Year (24-month) performance.
INITIATING CUE:
As the Unit Supervisor, perform SRO review of the attached SVI-P50-T2001, CVCW Isolation Valves Operability Test.
Document the results of your review on the Data Package Cover Sheet.
OT-3701-ADM_026SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
P54, Fire Protection System - Water Time Critical:
No Alternate Path:
No Setting:
Classroom Applicability:
SRO only Admin Topic:
Equipment Control Validated Time:
22 Minutes
References:
SOI-P54(WTR) Rev 24, PAP-1910 Rev 39, & Dwg 914-001 Rev RR Required Material:
SOI-P54(WTR), PAP-1910, & Dwg 914-001 Task:
286-505-01-01 Analyze System Problems 286-506-03-01 Inform Unit Supervisor of Inoperable Fire Protection Systems 343-684-03-02 Determine Required Actions for an Unplanned Fire Impairment / Barrier Removal When the P54 RSE is not Available Task Standard:
Identify boundary for leaking fire protection system component and determine Required Actions for an Unplanned Fire Impairment.
K/A Data:
2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance SRO 3.9 2.2.38 - Knowledge of conditions and limitations in the facility license.
Importance SRO 4.5
- 1.
Setup Instructions: If administered in classroom, have package of all 914 drawings available.
- 2.
Location / Method: Simulator / Classroom - Administrative Performance
- 3.
Initial Condition: The Plant is at rated power. Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture.
The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54(WTR).
- 4.
Initiating Cue: As the Unit Supervisor, determine:
- 1)
How P54-F3554 can be isolated.
- 2)
What Fire Protection Functional Specification(s) is the plant currently in per PAP-1910?
Start:
Stop:
Candidate:
OT-3701-ADM_026SRO Rev 0 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 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step:
Candidate obtains drawing and determines that closing P54-F3552 is necessary to isolate P54F3554.
Instructor Cue:
When the Candidate determines the correct 914 drawing to use, then provide the drawing to the Candidate if required Notes:
JPM Steps 1, 2, & 3 can be performed in any order.
P54-F3554 coordinates are F-4 and P54-F3552 coordinates are H-2.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_026SRO Rev 0 Step 2 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step:
Candidate obtains drawing and determines that closing P54-F6371 is necessary to isolate P54F3554.
Instructor Cue:
None Notes:
JPM Steps 1, 2, & 3 can be performed in any order.
P54-F3554 coordinates are F-4 and P54-F6371 coordinates are C-3.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 Evaluate Leak Isolation, Drawing 914-0001-0000, Fire Service Yard Area Critical Step:
Candidate obtains drawing and determines that closing P54-F3555 is necessary to isolate P54F3554.
Instructor Cue:
None Notes:
JPM Steps 1, 2, & 3 can be performed in any order.
P54-F3554 coordinates are F-4 and P54-F3555 coordinates are F-4.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_026SRO Rev 0 Step 4 PAP-1910 Fire Protection Program
, Section 3.A Fire Suppression Water Supply (Motor/Diesel Pumps)
D. ACTIONS FOR NOT FUNCTIONAL:
IF Both Fire Pumps are not functional, THEN:
24 HOURS a.(1) Establish a backup fire suppression water system.
OR 1 HOUR a.(2) If a backup system cannot be established, implement the requirements of LCO 3.0.3. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. Where corrective measures are completed that permit operation, LCO 3.0.3 is not required. LCO 3.0.3 is only applicable in MODES 1, 2, and 3.
Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:
Critical Step:
Candidate determines that both fire pumps are not functional and determines Actions for Not Functional are:
(1) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to establish backup system or (2) Enter LCO 3.0.3.
Instructor Cue:
Plant is in Mode 1 Notes:
PAP 1910 pages 66-67, with both pumps in secured status, pumps are not capable of auto starting, therefore, not functional.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_026SRO Rev 0 Step 5
, Section 4.A Fire Mains and Headers D. ACTIONS FOR NOT FUNCTIONAL:
IF:
- 1) Any portion of the fire main distribution piping is out of service, THEN:
24 HRS b. Establish back-up fire suppression water supply to the affected system/areas through temporary jumpers.
NOTE During the time period between the determination of loss of fire suppression water supply to a system/area and the establishment of a temporary supply, or if a temporary supply cannot be provided, all impaired systems shall be properly compensated for per the individual systems requirements of this attachment.
Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:
Standard:
Candidate determines that the Fire Header located between isolation valves P54-F3552, P54-F3555, and P54-F6371 is not functional.
Candidate applies NOTE above Action 4.D.1)b. which states, During the time period between the determination of loss of fire suppression water supply to a system/area and the establishment of a temporary supply, or if a temporary supply cannot be provided, all impaired systems shall be properly compensated for per the individual systems requirements of this attachment. Candidate determines that a temporary supply cannot be provided to the isolated piping due to the pipe rupture.
Candidate refers to PAP-1910, Attachment 3, Section 6.A, Yard Fire Hydrants and Hydrant Hose Houses to determine required actions.
Instructor Cue:
None Notes:
PAP-1910, Attachment 3, Section 6.A, Yard Fire Hydrants and Hydrant Hose Houses required actions are covered under Step 6.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_026SRO Rev 0 Step 6
, Section 6.A Yard Fire Hydrants and Hydrants Hose Houses D. ACTIONS FOR NOT FUNCTIONAL:
IF:
- 2) Any other hydrant or hose house is not functional, THEN:
NONE a. Ensure that the fire brigade is aware of the status.
Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:
Critical Step:
Candidate determines that Yard Hydrant # 25 is not functional and determines Actions for Not Functional are:
(2).a Ensure that the fire brigade is aware of the status.
Instructor Cue:
Understand Fire Brigade is aware of the status.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: The valves needed to isolate the leak have been correctly identified and the correct Functional Specifications for the loss of Fire Suppression Equipment have been identified.
Evaluation Results:
SAT_____
UNSAT_____
End Time
OT-3701-ADM_026_SRO Rev 0 Leaking valve Isolation valve Isolation valve Drawing 914-0001 Rev RR Answer Key
OT-3701-ADM_026_SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
- The Plant is at rated power.
- Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture.
- The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.
INITIATING CUE:
As the Unit Supervisor, determine:
- 1) How P54-F3554 can be isolated.
- 2) What Fire Protection Functional Specification(s) is the plant currently in per PAP-1910?
OT-3701-ADM_019SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
Administrative Time Critical:
No Alternate Path:
No Setting:
Classroom Applicability:
SRO only Admin Topic:
Radiation Control Validated Time:
22 Minutes
References:
HPI-B0003 Rev 28 Form 10136 Rev 7/26/01 Required Material:
HPI-B0003, Processing of Personnel Dosimetry EPI Book, NOP-OP-4200 series book Form PNPP 10136, Emergency Dose Authorization Calculator Task:
344-511-05-03 Request and Authorize increased exposure limits for emergency responders during emergency events.
451-656-05-50 Discuss TSC or CR EC responsibilities for authorization plans personnel to receive dose in excess of 10CFR20 limits under emergency situations.
Task Standard:
Determine if an Operator can perform an emergency evolution due to radiation levels and complete an Emergency Dose Authorization if evolution can be performed.
K/A:
2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. Importance: SRO 3.7
OT-3701-ADM_019SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET Cont
- 1.
Setup: Ensure Required Material available at JPM site.
- 2.
Location / Method: Class Room / Administrative performance.
- 3.
Initial Condition: The plant is in an Unusual Event due to lowering Spent Fuel Pool level.
No facilities are currently activated, and Emergency Coordinator duties remain in the Control Room. While investigating a leak in the FPCC Heat Exchanger Room, an NLO (Roberts) became pinned against the east wall near the A HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move but is shielded. He has suffered potentially life-threatening injuries and must be rescued. RP Supervision informs you that travel path dose rates are 3 REM/hr to NLO Roberts and 60 REM/hr where NLO Roberts is located. It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&1/2 minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.
The four operators available for this assignment are Bob Smith, Bill Johnson, Ray Jones, and Tom Bell Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mRem. Bob has not volunteered for this assignment.
Bill Johnson is 34 years old and has had 2 planned special exposures with a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mRem. Bill has volunteered for this assignment.
Ray Jones is 28 years old and has received a previous emergency exposure with a life time dose of 27.9 Rem. Ray has a year to date dose of 100 mRem. Ray has volunteered for this assignment.
Tom Bell is 21 years old and has a lifetime dose of 128 mRem. Tom has a year to date dose of 23 mRem. Tom has not volunteered for this assignment.
- 4.
Initiating Cue: As the Shift Manager: 1) Determine which, if any operator(s) can perform the evolution to rescue the NLO Roberts. 2) If the evolution can be performed, complete and approve the Perry Emergency Dose Authorization form PNPP 10136 Start:
Stop:
Candidate:
OT-3701-ADM_019SRO Rev 0 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 the radiation dose that will be received.
Critical Step:
Determine dose to be received by the rescue operators.
Instructor Cue:
None Notes:
3 REM/60 min*5 min=0.25 REM.
60 REM/60 min* 30 min =30 REM Total dose = 30.25 REM per rescuer SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_019SRO Rev 0 Step 2 Determine that the rescuers may receive greater than 25 REM for lifesaving if he is a volunteer.
Critical Step:
Determines that only Bill Johnson and Ray Jones can rescue the NLO Roberts.
Instructor Cue:
Only one of the two cues below will be provided. This is dependent on the number of operators the applicant has identified.
- If the applicant identifies only one operator then direct applicant to complete and approve the Perry Emergency Dose Authorization form.
- If applicant identifies that 2 or more operators can perform the task, then say, Due to the weight of the lead blankets it will require two operators to perform the rescue. After providing the cue direct applicant to complete and approve Perry Emergency Dose Authorization form for the two operators.
Notes:
Do not give Dose Authorization Form to Candidate until after he determines who can perform rescue.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_019SRO Rev 0 Step 3 Complete Emergency Dose Authorization (Form # - PNPP 10136)
Critical Step:
Fill in NAME, CURRENT YEAR DOSE, LIFETIME DOSE, & LEVEL APPROVED on form PNPP 10136.
Instructor Cue:
If asked, Operator-1 SSN is 555-55-5551 and Operator-2 SSN is 555 5552 If asked, acting as Operator-1 & Operator-2, sign for Operator-1 &
Operator-2. (Use actual names of the Operators being selected)
Notes:
Level approved needs to be 30.25 and 30.5 Rem.
No signatures are required in the REQUEST block, but if requested, sign as RP supervisor.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 4 Approve Emergency Dose Authorization (Form # - PNPP 10136) as Shift Manager acting as Emergency Coordinator.
Critical Step:
Approve the Emergency Dose Authorization form PNPP 10136 in the APPROVAL Section Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: Assigns one or more operators to rescue the NLO Roberts and approve the Emergency Dose Authorization.
Evaluation Results:
SAT_____
UNSAT_____
End Time
OT-3701-ADM_019SRO Answer Key Rev 0 EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 R
E Q
U E
S T
INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:
Rescue NLO Roberts from FPCC HX Room Name SSN Current Year - All Facilities Lifetime required to exceed 5 rem Signature Required to exceed 5 rem Level Approved Ray Jones 555-55-5551 100 mRem 27.9 Rem 30.25 to 30.5 Rem Bill Johnson 555-55-5552 200 mRem 16.5 Rem 30.25 to 30.5 Rem OSC Support Supervisor/Operations Shift Manager:
N/A Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor:
N/A Print / Signature Date LIMITS TEDE:
10CFR20 - 5 rem Services - 5 rem Valuable Property - 10 rem Large Pop. or Lifesaving - 25 rem*
- If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.
Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.
A P
P R
O V
A L
TSC Operations Manager/Operations Shift Manager:
Print / Signature Date Radiation Protection Coordinator/Supervision, RP:
Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.
OT-3701-ADM_019SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
- The plant is in an Unusual Event due to lowering Spent Fuel Pool level.
- No facilities are currently activated, and Emergency Coordinator duties remain in the Control Room.
- While investigating a leak in the FPCC Heat Exchanger Room, an NLO (Roberts) became pinned against the east wall near the A HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move but is shielded. He has suffered potentially life-threatening injuries and must be rescued.
- RP Supervision informs you that travel path dose rates are 3 Rem/hr to NLO Roberts and 60 Rem/hr where NLO Roberts is located. It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&1/2 minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.
- The four operators available for this assignment are Bob Smith, Bill Johnson, Ray Jones, and Tom Bell o Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mrem. Bob has not volunteered for this assignment.
o Bill Johnson is 34 years old and has had 2 planned special exposures with a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mrem. Bill has volunteered for this assignment.
o Ray Jones is 28 years old and has received a previous emergency exposure with a life time dose of 27.9 Rem. Ray has a year to date dose of 100 mrem. Ray has volunteered for this assignment.
o Tom Bell is 21 years old and has a lifetime dose of 128 mrem. Tom has a year to date dose of 23 mrem. Tom has not volunteered for this assignment.
INITIATING CUE:
As the Shift Manager:
- 1) Determine which, if any operator(s) can perform the evolution to rescue the NLO Roberts.
- 2) If the evolution can be performed, complete and approve the Perry Emergency Dose Authorization form PNPP 10136
OT-3701-ADM_019SRO Rev 0 EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 R
E Q
U E
S T
INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:
Name SSN Current Year - All Facilities Lifetime required to exceed 5 rem Signature Required to exceed 5 rem Level Approved OSC Support Supervisor/Operations Shift Manager:
Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor:
Print / Signature Date LIMITS TEDE:
10CFR20 - 5 rem Services - 5 rem Valuable Property - 10 rem Large Pop. or Lifesaving - 25 rem*
- If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.
Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.
A P
P R
O V
A L
TSC Operations Manager/Operations Shift Manager:
Print / Signature Date Radiation Protection Coordinator/Supervision, RP:
Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.
NOTE: Normally, planned doses during an emergency should be controlled to within <10CFR20> limits. However, under emergency circumstances these limits may be waived by TSC Operations Manager along with the Radiation Protection Coordinator, or the Operations Shift Manager, acting as Emergency Coordinator, if the TSC is not activated, to allow personnel to perform valuable emergency actions. Due to the urgent nature of emergency dose requirements, completion of the Emergency Dose Authorization can be accomplished subsequent to receiving dose if situations warrant. The doses received should be voluntary and commensurate with the significance of the objective and held to the lowest practicable level that the emergency permits.
OT-3701-ADM_322SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
Admin Time Critical:
Yes Alternate Path:
No Applicability:
SRO only Admin Topic:
Emergency Procedures/Plan Validated Time:
15 Minutes
References:
10565 Rev. 1/3/17, EPI-A1 Rev. 28, EPI-A2 Rev. 23, EPI-B1 Rev. 28, NORM-LP-5001 Rev. 6, PSI-19 Rev. 20 Required Material 10565 - EAL Classification Matrix EPI-A1 - Emergency Action Levels EPI-A2 - Emergency Actions Based On Event Classification EPI-B1 - Emergency Notification System NORM-LP-5001 - FENOC Position on Release in Progress for Emergency Response Organization PSI-19, Emergency Action Level (EAL) Bases Document Event Classification Forms packet Task:
451-654-05-50 Upon declaration of any Emergency Action Level, notify offsite authorities of the event.
344-532-05-02 Prepare Emergency Plan Initial Notification Form Task Standard:
Declare the emergency action level (RA1.1), complete initial notifications within 15 minutes and ensure communicator has notification form within the following 10 minutes.
K/A:
2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
Importance: SRO 4.4.
OT-3701-ADM_322SRO Rev 0
- 1.
Setup Instructions: Provide EAL Matrix and EPI book from simulator and PSI-19, Emergency Action Level (EAL) Bases Document and Event Classification Forms packet for candidate use.
- 2.
Location / Method: Admin / Performance
- 3.
Initial Condition: The plant was operating at 100% power. A steam leak occurred in the turbine building. A manual reactor scram was inserted.
All rods are indicating 00, full-in. Review the attached TB/HB Vent Radiation Monitor picture for current stable conditions. A MIDAS report has been requested but is not yet available. Steam is visible on the cameras in the Offgas Holdup Line area of the Turbine Building. RP estimates it will take at least an hour to enter the Turbine Building to identify the exact leak location and isolate the leak.
- 4.
Initiating Cue: You are the Shift Manager and I am the Control Room Communicator. You are to: Evaluate the Emergency Plan and complete required paperwork.
Task is Time Critical Start Time:
End Time:
Candidate:
OT-3701-ADM_322SRO Rev 0 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 EPI-A1, Emergency Action Levels 5.1 Event Assessment and Event Classification 5.1 Classify the emergency as follows:
- 1. Using form PNPP No. 10565, EAL Classification Matrix Pages 1 through 3, identify the emergency by event and determine the most appropriate EAL.
- 2. Declare an emergency class when all the conditions listed for an EAL have been met, and implement <EPI-A2>.
- a. When several EALs are met, declare the most severe emergency class.
- 3. Complete the Event Classification Checklist (PNPP No. 7983A), contained in <EPI-A2>.
OT-3701-ADM_322SRO Rev 0 Critical Step:
Classifies RA1.1, 15 minutes to classify.
Instructor Cue:
Notify that time critical action starts after first read of initial conditions and he is given initiating cue.
Notes:
The current rad levels on the TB/ HB Gas Channel rad monitor are more than 2X the HIGH alarm set point.
Based on not being able to enter the area to isolate the leak for more than 60 minutes at this current release rate, NOTE 1 states the Shift Manager should classify the event if the release will not be isolated within 60 minutes but should not wait the 60 minutes if this information is known.
EAL RA1.2-DOES NOT Apply based on not having a MIDAS printout.
Start Time ________
Classification Time __________
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_322SRO Rev 0 Step 2 Event Classification Checklist Checklist completed through line A.6.
Standard:
Uses Event Classification Checklist to assist with required actions.
Instructor Cue:
None Notes:
Refer to Answer Key for EC Checklist.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 Event Classification Checklist
- 4.
Complete an Initial Notification form (PNPP No. 7794), approve, and forward to communicators within 10 minutes of decision to classify event or revise Protective Action Recommendations (PARs).
Critical Step:
Initial Notification Completed within 10 minutes of Classification and forwarded to the Communicator.
Block 3.a is checked for ALERT RA1.1.
Instructor Cue:
None Notes:
Time Given to Communicator ______________
Refer to Answer Key (highlighted items) for minimum required items on Notification Form.
See PSI-019, Rev. 20 p 227 for an unisolable pathway to environment.
If Candidate uses Fission Product Barrier Matrix, will only get a Loss of Containment, which does not have entry into Fission Product Barrier Degradation EAL SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-ADM_322SRO Rev 0 Step 4
- 6.
Complete the Notification Messages form (PNPP No. 9100), approve, and forward to the FCMS within 10 minutes of decision to classify event or revise PARs.
Standard:
Pager Message completed, scenario ID No. 2 Instructor Cue:
None Notes:
Completion of Reactor Plant Event Notification Worksheet form (NOP OP 1015 01) not required.
Refer to Answer Key for Pager Messages Terminate JPM SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: RA1.1 Classified within 15 minutes and Initial Notification given to Communicator within 10 minutes.
Evaluation Results: SAT_____
UNSAT_____
End Time:
OT-3701-ADM_322SRO Rev 0 EVENT CLASSIFICATION CHECKLIST PNPP No. 7983A Rev. 2/26/18 Page 1 of 2 EPI-A2 Event classified as a/an:
General Emergency Site Area Emergency Alert Unusual Event At Within 15 minutes of Cue on Todays Date.
Time Date Checklist completed by:
(Shift Manager/TSC Operations Manager/ EOF Emergency Coordinator)
A. IMMEDIATE ACTIONS INITIAL TIME
- 1.
Announce event classification and reason for declaring emergency over the Plant PA System.
- 2.
Sound Plant Emergency Alarm. (Request Control Room to initiate Alarm)
- 3.
[CONTROL ROOM ONLY] Call the shift I&C technician to the Control Room as a communicator.
NOTE: For a GENERAL EMERGENCY, ensure that PAR is included using EPI-B8,, PAR Decision Flowchart.
- 4.
Complete an Initial Notification form (PNPP No. 7794), approve, and forward to communicators within 10 minutes of decision to classify event or revise Protective Action Recommendations (PARs).
5a. Determine facilities to be activated using table below: (R-required; O-optional)
Classification/Facility OSC TSC PIRT EOF JIC Unusual Event O
O O
O O
Alert R
R R
O O
Site Area Emergency R
R R
R R
General Emergency R
R R
R R
5b. Announce facilities to be activated over the Plant PA System.
NOTE: (1) Completion of form is delegated to the Security Coordinator once TSC is operational. (2) Activation of ERO communication devices is NOT needed if required facilities have already been/are being mobilized.
- 6.
Complete the Notification Messages form (PNPP No. 9100), approve, and forward to the FCMS within 10 minutes of decision to classify event or revise PARs.
- 7.
Complete an Reactor Plant Event Notification Worksheet form (NOP-OP-1015-01),
approve, and forward to communicators immediately following notification of the State of Ohio and local counties, but within 50 minutes of event classification.
NOTE: It may be prudent to delay implementation of accountability in situations where personnel safety could be jeopardized, such as a security event or severe weather.
- 8.
[SITE AREA EMERGENCY or above] Initiate personnel accountability per EPI-B5, if not yet implemented:
Not Required 8a. Direct Shift Manager, or designee, to initiate appropriate Emergency message over the Exclusion Area Paging System and use PA feature to provide further guidance on offsite assembly if required.
8b. The Shift Manager, or designee, is to manually repeat the accountability message approximately every 5 minutes until accountability is completed, if the automated message is not working
- 9.
Verify that notifications and/or requests for offsite support were completed by the FCMS:
- a.
Fire Department (911)
Not Required
- b.
Ambulance (911)
Not Required
- c. Hospital: Primary - TriPoint; Backup - Lake West Not Required
- 10. If the NRC requests that the ENS circuit remains open then verify that an individual knowledgeable in system operations is assigned to the NRC ENS Circuit to answer questions and inquiries.
REFER TO page 2 of 2 FOR LISTING OF FOLLOW-UP ACTIONS
OT-3701-ADM_322SRO Rev 0 FENOC NUCLEAR POWER PLANT INITIAL NOTIFICATION FORM Perry PNPP No. 7794 Rev. 1/9/18 EPI-B1 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 SITE AREA EMERGENCY ALERT UNUSUAL EVENT was declared at:
Time on Todays based on EAL: RA1.1______
(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: Signature________________________
OT-3701-ADM_322SRO Rev 0 NOTIFICATION MESSAGES PNPP No. 9100 Rev. 8/22/18 Page 1 of 1 EPI-B1 CONTROL ROOM/TSC SECURITY COORDINATOR INSTRUCTIONS:
- 1.
Select appropriate Scenario ID number.
- 2.
Initiate the notification by forwarding to FCMS or by forwarding the information contained within the form to an ERS representative.
TSC SECURITY COORDINATOR/FCMS OPERATOR INSTRUCTIONS:
Using the information on this form, initiate the notification of the Emergency Response Organization per PYBP-ERS-0037.
()
Scenario ID No.
Event Code Message Narrative 1
1111 Unusual Event - No facility activation.
2 2222 Alert - OSC, TSC, and PIRT to be activated.
3 3333 Site Area Emergency - OSC, TSC, EOF, PIRT, and JIC to be activated.
4 4444 General Emergency - OSC, TSC, EOF, and JIC to be activated.
51 5555 Event Termination 52 5555 OSC to be staffed.
53 5555 TSC to be staffed.
54 5555 PIRT to be staffed.
55 5555 OSC, TSC and PIRT to be staffed.
56 5555 EOF to be staffed.
57 5555 JIC to be staffed.
61 6666 ERO Teams respond to your offsite facility.
62 6666 Site Inaccessible, ERO Teams respond to your offsite facility.
81 8888 Drive-In Drill - OSC, TSC & EOF to be activated.
91 9999 Weekly Notification Device Test (Shift Manager/EC approval not required) 92 9999 Unannounced Notification Device Test (Shift Manager/EC approval not required) 93 9999 Security Notification Device Test (Shift Manager/EC approval not required) 95 1111 Drill Unusual Event - No facility activation.
96 2222 Drill Alert - OSC, TSC, and PIRT to be activated.
97 3333 Drill Site Area Emergency - OSC, TSC, EOF, PIRT, and JIC to be activated.
98 4444 Drill General Emergency - OSC, TSC, EOF, and JIC to be activated.
Approved by:
Today
/ Time
/ Signature Date Time Emergency Coordinator Delivered to:
/
/
Date Time Name Activated by:
/
/
OT-3701-ADM_322SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
- The plant was operating at 100% power.
- A steam leak occurred in the turbine building.
- A manual reactor scram was inserted.
- All rods are indicating 00, full-in.
- Review the attached TB/HB Vent Radiation Monitor picture for current stable conditions.
- A MIDAS report has been requested but is not yet available.
- Steam is visible on the cameras in the Offgas Holdup Line area of the Turbine Building.
- RP estimates it will take at least an hour to enter the Turbine Building to identify the exact leak location and isolate the leak.
INITIATING CUE:
You are the Shift Manager and I am the Control Room Communicator.
You are to:
- Evaluate the Emergency Plan
- Complete required paperwork.
Task is Time Critical
OT-3701-ADM_322SRO Rev 0