ML20140H017
| ML20140H017 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/01/1997 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20140G761 | List:
|
| References | |
| TRCR-86.0, NUDOCS 9705120285 | |
| Download: ML20140H017 (24) | |
Text
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s POINT BEACH NUCLEAR PLANT TRAINING COURSE COVER SHEET j
TITLE: TRCR 86.0, ADMINISTRATIVE Revision: 12 Date:
MAY I 1997 Describe changes (step / change / reason)-
(for Revision 0, describe purpose; provide summary review)
TOTAL REWRITE.
COURSE REVISED TO REFLECT IMPLEMENTATION OF SELF DIRECTED LEARNING MODULES.
ASTERISK ITEMS TO BE INCLUDED PER NPM97-Ol90," ADMINISTRATIVE PROCEDURE TRAINING FOR OPERATIONS PERSONNEL" REFEPINCE RESTART COMMITMENT #75. NRC ENTORCEMENT CONFERENCE ACTION NUMBER 20.
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Temporary Change No Date Performed:
Prepared by:
Date: April 30,1997 Optional Reviews: (Check those desiredf ACCR:
Date:
4f-%)
Group Head:
Date:
((J9 /
Reviewed by:
Date:
j[97 Approved By:
Date:
v TR-7.3.1 Rev. 0 (06/10/91)
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9705120285 970505 PDR ADOCK 05000301 P
FDR
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE l
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1.0
- GOAL, i
The intent of the Administrative course is provide trainees with direction for self study of i
materials pertaining to watch standing duties, plant operating procedures, and administrative procedures.
2.0 DESCRIPTION
2.1 Prereauisites l
A trainee should be enrolled in one of the following programs:
TRPR 18.0, Control Operator TRPR 19.0, Senior Reactor Operator 1
TRPR 20.0, Duty Technical Advisor I
- TRPR 30.0, Senior Reactor Operator - Certification l
l 2.2 Leneth of Course The Administrative course is approximately 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of self-study and evaluation.
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2.3 Syllabus l
l The Administrative course includes the following Self-Directed Learning Modules:
Conduct of Operations (TRCR 86.1)
Equipment Control (TRCR 86.2)
Radiation Control (TRCR 86.3)
Emergency Plan (TRCR 86.4) j i
3.0 EVALUATION A written test measuring the objectives will be given upon completion of this course.
Activity code is T86.0 A grade of 280% will be considered passing. A failure will result i
in remedial actions outlined in TIP 8.6, of the PBNP Training Manual.
10 TASK MATRIX 1
A task matrix is attached.
Page 1 of 23 1
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12
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May 1,1997 ADMINISTRATIVE TOTAL REWRITE i
TRCR 86.1 - CONDUCT OF OPERATIONS i
1.0 TERMINAL OBJECTIVES l
l COT TASKS-l l
l C6501 COT T Assess Technical Specifications and procedural requiremerds to equipment l
necessary for safe operation of the plant.
l C6512 COT T Recognize abnormal parameters or conditions.
P2603 COT PA Respond to a loss of secondary coolant chemistry control.
P6501 COT T Assess Technical Specifications and procedural requirements to equipment necessary for safe operation of the plant.
i P6503 COT T Maintain required logs, records, charts, printouts, and status boards.
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SRO TASKS:
'C0307SRO T During all modes of operation and given Technical Specifications apply safety j
limits, settings and operating conditions that are addressed by Technical Specifications.
P030lSRO T During plant refueling and given OM 3.10 supervise refueling operations in accordance with OM 3.10, " Operations Personnel Assignments and Scheduling."
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I P0302SRO T During all modes of operation and given OM 3.9 conduct shift tumover in accordance with OM 3.9, " Guidelines for Watch Standing Logbooks, Records and Status Control."
P0303SRO T During all modes of operation and given OM 3.9 maintain required logs, records and status boards in accordance with OM 3.0, " Guidelines for Watch Standing, Logbooks, Records & Status Control."
P0308SRO T During all modes of operation and given OM 3.2 coordinate load changes with the systems control supervisor in accordance with OM 3.2, " System Control Center - and WE Energy Marketing Group Communications."
l P0310SRO T During all modes of operation and given OM 3.9 review operating logs for i
trends and out-of-specification conditions in accordance with OM 3.9,
" Guidelines for Watch Standing, Logbooks, Records & Status Control."
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE.
TOTAL REWRITE P0314SRO T During all modes of operation and given DCS 2.1.1, perform required notifications in accordance with DCS 2.1.1.
P0315SRO T During plant evolutions direct personnel actions. Satisfactory direction would accomplish the evolution in a timely manner without damage to equipment or personnelinjury.
P0323SRO T During all modes of operation review completed procedures.
i P0324SRO T During all modes of operation given Technical Specifications and normal i
operating procedures review chemistry data to ensure conformance to specifications in Technical Specifications and normal operating procedures.
P0330SRO T At all times implement the plant Security Manual.
P0403SRO T During all modes of operation and given the Fire Protection manual direct actions of the fire brigade in accordance with the Fire Protection Manual.
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P0507SRO T During all modes of operation and given the Fire Protection Manual conduct on-shift fire brigade training in accordance with the Fire Protection Manual.
P0508SRO T Given the Fire Protection Manual, conduct a fire drill in accordance with the Fire Protection Manual.
P071ISRO T During all modes of operation and given the OM 3.1 control personnel access and conduct in the control room in accordance with OM 3.1, " Main Control Rwm Environment, Conduct and Access."
P0910SRO T During shutdown condition and given RP-1 A, establish initial conditions for refueling in accordance with RP-1 A, " Preparation for Refueling."
P0918SRO I During shutdown conditions and given RP-1B, recover from refueling in accordance with RP-1 B, " Recovery from Refueling."
P1014SRO T During all modes of operation. utilize effective communications. Satisfactory effective communication would incorporate different kinds of feedback and open loop versus closed loop communication.
C0304SRO T During all modes of operation, determine priority for on-shift assignments.
Satisfactory categorization would consider; task frequency, its Technical Specifications implications, possible load reductions, and interference with other tasks.
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 t
TRAINING COURSES Revision 12 l~
May 1,1997 ADMINISTRATIVE TOTAL REWRITE P0703SRO T During all modes of operation and given NP 1.2.2 prepare a temporary procedure change in accordance with NP 1.2.2, " Technical Procedure Classification, Review and Approval."
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i P0707SRO T During all modes of operation and given NP 1.4.3 prepare a DCN in accordance with NP 1.4.3.
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P1004SRO P During all modes of operation and given TS 15.6.11 and HP 2.6 maintain l
positive control of assigned keys in accordance with TS 15.6.11, " Radiation Protection Program," and HP 2.6, "High Radiation Area and Radioactive Source Key Control."
C0402SRO T During abnormal / emergency condition and given AOPs, CSPs and EOPs recognize procedures which are required by an emergency / abnormal event in accordance with the AOPs, CSPs and EOPs.
C0404SRO T During abnormal / emergency condition and given AOPs, CSPs and EOPs analyze indications to determine that an emergency / abnormal plant event is in progress in accordance with AOPs, CSPs and EOPs.
.C0405SRO T During abnormal / emergency condition and given AOPs, CSPs and EOPs recognize plant conditions that require a manual reactor trip in accordance with the AOPs, CSPs and EOPs.
C0702SRO T Following plant trips or other significant incidents, synthesize information during post-incident reviews in accordance with OM 4.1.1, " Post-Trip Review," and NP 5.3.3, " Post-Incident Critique and Investigation."
C080lSRO T During all modes of operation and given the EOPs and AOPs, diagnose the cause, severity, and location of the emergency / abnormal event in accordance with EOPs and AOPs.
C0805SRO T During abnonnal/ emergency condition and given AOPs, CSPs and EOPs i
analyze and verify that all plant emergency systems function properly in accordance with the AOPs, CSPs and EOPs.
C0807SRO T During abnormal / emergency condition and given AOPs, CSPs and EOPs evaluate the adequacy of responses of personnel involved in emergency evolutions. Satisfactory evaluation would consider how well the procedures were used, the teamwork and communications between personnel and the level of excitement / confusion.
1 C1005SRO T During all modes of operation and given OM 4.1.7 recognize a nonscheduled radioactive release in accordance with OM 4.1.7,"RMS Alarm Setpoint and Response Book."
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 i
l' May 1,1997 i
ADMINISTRATIVE.
TOTAL REWRITE P0404SRO T During abnormal / emergency condition and given AOPs, CSPs and EOPs f
direct personnel to mitigate emergency /abnomial event in accordance with the AOPs, CSPs and EOPs.
j P0706SRO T Following a reactor trip or other significant incident, collect information and iavestigate the cause(s) of plant trips and/or other significant incidents in accordance with NP 5.3.3 and OM 4.1.1.
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P1003SRO T During all modes of operation and given OM 4.1.7 evaluate RMS l
alarms / abnormalities in accordance with OM 4.1.7,"RMS Alarm Setpoint and l
Response Book."
l DTA TASKS:
C0210DTA T Given an off-normal plant condition, apply the incident reporting requiremet:: of 10 CFR 50 as interpreted by PBNP to the off-normal plant condition or event.
C0219DTA T When off-normal plant conditions exist, assess the Technical Specification requirements of the condition to determine any required plant actions.
1 P0213DTA P When taking over or being relieved from duty, perform a DTA duty turnover to ensure that no pertinent information is lost and to be sure of the condition of
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the plant.
P0401DTA T Following a reactor trip or other significant incident, collect information and investigate the cause(s) of plant trips and/or other significant incidents in accordance with NP 5.3.3 and OM 4.1.1.
P3336DTA N Given an alarm at the SBCC alarm panel or RMS cabinet, respond to the alarm in accordance with PB 85-292.
P5401DTA T When directed under abnormal plant conditions or for the DTA communications check, operate the PBNP pager system to contact the desired individual (s).
2.0 DESCRIPTION
2.1 Prereauisites None Page 5 of 23
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE 2.2 Lessons LP2558, Shill Turnover i
- OM 3.9, Watchstander Status Checks and Watchstander Turnover Guides (PBNP 4.16) i LP2559, Shift Staffing Requirements
- OM 3.1, Operations Shift Staffing Requirements (PBNP 4.4)
OM 3.10, Operations Personnel Assignments and Scheduling (PBNP 4.3)
OM 3.26, Use of Dedicated Operators (PBNP 4.12.4 &4.12.54)
- TS 15.6.2, Organization NP 1.6.6, Work Duration Restrictions (PBNP 3.4.4)
- NOM DCS - Duty and Call Supervisor
- NOM DTA - Duty Technical Advisor
- NOM MSS - Manager Supervisory Staff
- NOM OPS - Operations
- FSAR 12.2 - Organization Fire Protection Manual LP2560, Temporary Modification to Procedures NP 1.2.2, Technical Procedure Classification Review and Approval (PBNP 2.1.1)
NP 1.2.3, Temporary changes (PBNP 2.1.13)
NP 1.2.6, Infrequently Performed Tests or Evolutions (IPTES) (PBNP 3.4.19)
OM 5.4.6, Instructions for Making Changes in the Electrical Master Data Book (PBNP 4.29)
OM 5.4.7, Drawing Revisions (PBNP 4.12.12)
NP 1.4.3, Drawing Change Notice Procedure (QP 6-4)
LP2561, Reactor Plant Startup Requirements OP-1B, Reactor Startup i
OP-1B Appendix A, Estimated Rate Position Calculation CL-1 A, Criticality Checklist LP2562, Mode Changes CL-1 A, Criticality Checklist CL-1B, Containment Integrity CL-1C, Main Turbine Loading and Unloading Limitations (For Startup, Shutdown, and Significant Load Change Operations)
CL-1D, Heatup CL-lE, Containment Closure Checklist OM 3.2, System Control Center and WE Energy Marketing Group Communications (PBNP 4.15)
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NUCLEAR POWER BUSINESS U~ NIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997
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ADMINISTRATIVE TOTAL REWRITE LP2563, Plant Parameter Verification OP-1B Appendix A, Estimated Rate Position Calculation l
OP-3B Appendix A, Shutdown Margin Calculation REI 1.0, Power Level Determination and Guidelines REI 2.0, Power Range Detector Power Level Adjustment REI 13.0, Quadrant Power Tilt l
OM 3.19, Reactor Coolant System Leakage Determination (PBNP 4.11) 01-35, Primary Leak Rate Calculation 01-96, Steam Generator Tube Leakage Calculation and Evaluation
LP2564, Short Term Information Operations Notebook
- OM 3.13, Operations Notebook OM 3.14, Operations Group Special Orders (PBNP 4.14)
OM 3.15, Operations Group Standing Orders (PBNP 4.12)
LP2565, Key Control HP 2.6, High Radiation Area and Radioactive Source Key Control LP2566, Security NP 1.7.1, Security Expectations (PbMP 3.8.9)
NP 1.7.5, Fitness for Duty Policy and Procedure (PBNP 3.8.5)
NP 1.7.10, Bomb and Overt Threats (PBNP 3.8.6) i LP2567, Fuel Handling RP 1 A, Preparation for Refueling RP-1B, Recovery From Refueling RP IC, Refueling RP 2A, Receipt of New Fuel Assemblies 01-3, Thimble Plug Handling Tool 01-4, Spent fuel Assembly Handling Tool 01-5, Irradiation Capsule Handling Tool OI-6, Guide tube Insert Handling Tool 01-7, Burnable Poison Rod Assembly (BPRA)/ Plug Device Handling tools j
(Z-100 old/new) 01-8, Portable Load Cell Instrument l
01-19, Spent Fuel Pit Demineralizer Resin Flush and Recharge, U6 OI-22C, Changing Spent Fuel Pool Filter 01-23, Containment Fuel Transfer Equipment OI-23A, containment Refueling Cavity Filtration System (Z-467) 01-51, Spent Fuel Pool / Transfer Canal Doors 01-52, Spent Fuel Pool Skimmer Suction Strainer Changeout.
01-53, Positioning of the Fuel Transfer Cart Page 7 of 23
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE i
01-56, Draining and Refilling the Transfer Canal 01-74, Spent fuel Rack Poison Handling Tool 01-75 RCC Change Tool (Z-02311) 01-91, SFP Bridge Hoists 01-94, Fuel Assembly Loading Guides (Z-701 and Z-702)
LP2568, Miscellaneous
- OM 3.4, Operations Self-Checking Expectations OM 3.18, Operations Administrative Limits OM 3.23, Operations Response to Alarms, and Abnormal Indications CANCELED. Renumbered to OM 1.1, Conduct of Plant Operations OM 3.29, Pre-Job and Post-Job Briefings OM 4.1.6, alarm Response (PBNP 4.5.6)
OM 6.1, Performance Assessment Program NP 1.1.4, Procedure Use and Adherence NP 1.6.4, Verbal Communication Procedure (PBNP 3.4.24)
NP 1.2.4, Procedure Documentation Requirements (PBNP 2.1.4)
NP 2.3.3, Work Control Center l
- NP 5.3.1, Condition Reporting system (QP 15-3)
OM 4.1.1, Post Trip Review (PBNP 3.4.10)
OM 4.1.7, RMS Alarm Setpoint and Response Book (RMSARB)(PBNP 4.5.11) j NP 3.2.2, Primary Water Chemistry Monitoring Program (PBNP 8.4.2)
NP 3.2.3, Secondary Water Chemistry Monitoring Program (PBNP 8.4.1)
NP 5.3.3, Post Incident Critique and Investigation (PBNP 2.3.2)
DCS 2.1.1, Requirements and Guidance for immediate Notification to i
NRC/ EPA of"Significant Events" at PBNP.
3.0 EVALUATION Indvidual lesson enabling objectives may be evaluated by classroom assignments, written quizes, or other means as determined appropriate by the instructor, i
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE l
TRCR 86.2 - EQUIPMENT CONTROL l
1.0 TERMINAL OBJECTIVES COT TASKS:
C6401 COT T Assess the consequences of safety related equipment not meeting operability criteria.
P6405 COT T Perform pump / valve operability test.
SROT TASKS:
C010lSRO T During all modes of operation analyze overall plant status to determine whether maintenance is permissible. Satisfactory coordination would ensure plant system lineups to support maintenance met Technical Specifications and did not cause plant automatic protective actions to occur.
C0103SRO T During all modes of operation and given OM 4.2.2 determine required post-maintenance testing is in accordance with OM 4.2.2, " Inservice Testing."
C0105SRO T During all modes of operation and given OM 4.2.2 analyze the results of post-maintenance tests to determine equipment or system operability in -
accordance with OM 4.2.2, " Inservice Testing."
C0106SRO T During all modes of operation and given NP 8.1.1 determine the need for an unforeseen MWR in accordance with NP 8.1.1, " Work Order Process."
C0107SRO T During all modes of operation and given NP 1.9.15 analyze a red tag series to be adequate to maintain personnel safety and system protection in accordance with NP 1.9.15," Danger Tag Procedure."
C0110SRO T During all modes of operation and given NP 7.3.1 analyze temporary modifications for their impact on operation in accordance with NP 7.3.1,
C0202SRO T During all modes of operation and given OM 4.2.2 analyze the results of the data on surveillance / periodic tests to verify plant / equipment operability in accordance with OM 4.2.2, " Inservice Testing."
l C0203SRO T During all modes of operation and given Technical Specifications recognize Technical Specification limits imposed by existing plant conditions prior to testing.
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE C0205SRO T During all modes of operation analyze the effect that testing has on plant operations. Satisfactory analysis would ensure procedures were being followed and no automatic protective actions are necessary.
C030lSRO T During all modes of operation and given PCs, CLs, and OM 3.17 determine j
equipment requiring locking (red lock, padlocks, etc.) and/or independent l
verification in accordance with PCs, CLs and OM 3.17.
P0104SRO T During all modes of operation and given NP 1.9.15 authorize hanging and clearing of red tags on plant equipment in accordance with NP 1.9.15,
" Danger Tag Procedure."
1 P0107SRO T During all modes of operatien and given NP 8.1.1 and NP 1.9.15 authorize j
performance of maintenance in accordance with NP 8.1.1, " Work Order Process" and NP 1.9.15, " Danger Tag Procedure." -
P0109SRO T During all modes of operation and given NP 8.1.1 perform post-maintenance inspections in accordance with NP 8.1.1, " Work Order Process."
P0115SRO T During all modes of operation and given NP 1.9.13 approve ignition control permits in accordance with NP 1.9.13, " Ignition Control Procedure."
i P0116SRO T During all modes of operation and given NP 1.9.9 approve transient combustible control permi's in accordance with NP 1.9.9, " Transient Combustible Control."
P0118SRO T During all modes of operation and given NP 7.3.1 approve temporary
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modifications in accordance with NP 7.3.1, " Temporary Modifications."
P0119SRO P Given a copy of NP 8.1.1, " Work Order Process," prepare an unforeseen MWR.
P0120SRO P Given a copy of OM 5.4.4, " Control of Posted Plant Information," prepare a temporary information sheet.
P0121SRO P Given a copy of NP 8.4.8, " Requirements for Scaffold Near Safety-Related Equipment," authorize temporary scaffolding permits.
P0122SRO P Given a copy of NP 8.4.11, " Penetrating Barriers", and PBF-0034, " Fire l
Barrier Penetration Permit," authorize a fire barrier penetration permit.
l P0123SRO T Determine the applicability of 10 CFR 50.59 to a proposed modification, change, test or experiment.
Page 10 of 23 i-
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 l
TRAINING COURSES Revision 12
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May 1,1997 i
ADMINISTRATIVE TOTAL REWRITE P0202SRO T During all modes of operation and given OM 4.2.2 authorize performance of surveillance / tests assigned on shift in accordance with OM 4.2.2, " Inservice Testing."
P0331SRO P Given a plant surveillance, perform the surveillance as per the inspection program.
P0917SRO T During refueling and given the operational refueling test procedure, participate in ORT 3, " Safety Injection Actuation with Loss of Engineered Safeguards AC" in accordance with the procedure.
2.0 DESCRIPTION
2.1 Prereauisites None 2.2 Lessons LP2569, Surveillance Requirements OM 4.2.1, Technical Specification Tests (PBNP 4.5.7)
OM 4.2.2, inservice Tests (PBNP 4.5.8)
OM 4.2.3, Periodic Callups (PBNP 4.5.9)
OM 4.2.4, Operations Refueling Tests (PBNP 4.5.10)
OM 4.2.5, Documentation of Technical Specification Surveillance Requirements (PBNP 4.12.48)
OM 5.4.1, Operating Group Periodic Testing and Surveillance (PBNP 4.10)
NP 5.1.5, implementation of TS/ Safety-Related Sur,eillance Testing Requirements (PBNP 3.2.1)
LP2570, Maintenance OM 3.12, Control of Equipment and Equipment Status OM 3.20, MOV/AOV Operation and Maintenance Guidelines OM 3.27, Control of Fire Protection & Appendix R Safe Shutdown Equipment (4.12.7)
OM 3.28, Valve and Equipment Operation (PBNP 4.12.4)
- NP 8.1.3, Post Maintenance Testing (PBNP 3.2.6)
NP 8.1.1, Work Order Processing (PBNP 3.1.3)
LP2571, Tagging and Clearances OM 3.17, independent Check Guidelines (PBNP 4.12.18)
NP 1.9.15, Danger Tag Procedure Page11of23
NUCLEAR POWER BUSINESS UNIT
.TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE 1
LP2572, Temporary Modification of Systems NP 7.3.1, Temporary Modifications (QP 3-12)
LP2573, Familiarity with and use of Piping and Instrument Drawings LP2574, Miscellaneous
- NP 1.9.4, Confined Spaces Procedures (PBNP 3.5.4)
- NP 1.9.5, Industrial Safety Equipment (PBNP 3.5.5)
- NP 1.9.13, Ignition Control Procedure (PBNP 3.4.1)
- NP 2.3.4, System Restoration
- NP 10.3.1, Authorization of Changes, Tests, and Experiments (10 CFR 50.59 and 72.48 Reviews)(QP 3-3)
NP 1.9.9, Transient Combustible Control (PBNP 3.4.8)
NP 8.4.11, Penetrating Barriers (PBNP 3.4.11)
NP 8.4.8, Requirements for Scaffolding Near Safety-Related Equipment (PBNP 3.4.16)
OM 5.4.4, Control of Posted Plant Information (PBNP 4.20) 3.0 EVALUATION Individual lesson enabling objectives may be evaluated by classroom assignments, written j
quizzes, or other means as determined appropriate by the instructor.
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Page 12 of 23
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12
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May 1,1997 ADMINISTRATIVE TOTAL REWRITE TRCR 86.3 - RADI ATION CONTROL 1.0 TERMINAL OBJECTIVES SRO TASKS:
C0108SRO T During all modes of operation determine if changes in plant conditions affect the applicability of an RWP. Satisfactory assessment would include areas and conditions which would change levels.
P0113SRO T During all modes of operation and given NP 4.2.20 authorize an RWP in accordance with NP 4.2.20 and the RWP form itself.
P0312SRO P During all modes of operation, approve radioactive waste discharge permits in accordance with radioactive liquid waste discharge permits.
P0313SRO P During all modes of operation and given NP 4.2.14 approve extension of personnel dose limits for operations personnel in accordance with NP 4.2.14,
" Administrative Dose Levels / Dose Level Extension Procedure."
2.0 DESCRIPTION
2.1 Prereauisites None 2.2 Lesson LP2575, The Use and Function of Portable Radiation and Contamination Survey Instruments and Personnel Monitoring Equipment.
NP 4.2.27, Personnel Exposure Monitoring Device Minimum Requirements and General Use (HP 1.7)
HP 1.11, Portal Monitor Use and Alarm Response HP 1.11.1, Personnel contamination Monitor PCM-1B Contamination Alarm Response Procedure HP 2.1.2, Personnel Monitoring Requirements for Radioactive Contamination HPIP 2.4, Use of RO-2 Portable Survey Instrument HPIP 2.5, Use of RO-2A Portable Survey Instrument HPIP 2.8, Use of RO-5 Portable Survey Instrument HPIP 2.11, Use of Teletector 6112 Portable Survey Instrument HP 2.16, Portable Survey Instrument and Exposure Monitoring Device Control Program HPIP 2.26, Use of Victoreen 410 Portable Survey Instrument HPIP 2.27, Use of RSO-50 Portable Survey Instrument Page 13 of 23 i
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 l_
i May 1,1997 l
ADMINISTRATIVE TOTAL REWRITE l
l LP2576, Knowledge of Significant Radiation Hazards i
HP 3.2, Radiological Posting and Labeling Requirements LP2577, The Ability to Perform Procedures to Reduce Excessive Levels of Radiation and to Guard Against Personnel Exposure.
NP 4.2.1 ALARA Policy (PBNP 3.7.1)
NP 4.2.3, 4 LARA Review Procedure (PBNP 3.7.4)
NP 4.2.10, ALARA Program (PBNP 11.2)
LP2578, Radiation Exposure Limits and Contamination Control, Including Permissible Levels in Excess of Those Authorized.
HP 2.15, Control of Personnel Exposure to High Level Contamination, Hot Particles, and Activated or Fission Product Debris NP 4.2.13, Maximum Permissible Dose Limits (HP 1.3)
NP 4.2.14, Administrative Dose Levels / Dose Level Extension Procedure (HP 1.4)
NP 4.2.15, Fetal Protection Implementation Policy (HP 1.4.1)
NP 4.2.16, Visitor Access to a Radiologically Controlled Area (HP 1.5)
NP 4.2.18, Planned Special Exposure (HP 1.13)
- NP 4.2.19, General Rules For Work in a Radiologically Controlled Area (HP 1.5)
NP 4.2.23, Routine Use Protective Clothing Requirements (HP 2.7.2)
NP 4.2.24, Non-Routine Use Protective Clothing Requirements (HP 2.7.3)
LP2578, Radiation Work Permits HP 2.5.6, Radiologically Controlled Area Entry Permit NP 4.2.20, Radiation work Permit (HP 2.5)
NP 4.2.21, Standing Radiation Work Permit (HP 2.5.1)
LP2580, Control of Radiation Releases i
HP 2.12, Containment Entry / Exit Procedure OP-9A, Liquid Waste Process System Operation OP-9C, Containment Venting and Purging OP-9D, Discharge of Gas Decay Tank (s)
OP-10E, Discharge of B CVCS HUT 3.0 EVALUATION 1
Individual lesson enabling objectives may be evaluated by classroom assignments, written i
quizzes, or other means as determined appropriate by the instructor.
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE j
TRCR 86,4 - EMERGENCY PLAN 1.0 TERMINAL OBJECTIVES DTA TASKS:
C0210DTA T Given an off-normal plant condition, apply the incident reporting requirements of 10 CFR 50 as interpreted by PBNP to the off-normal plant condition or event.
I102EMR T When offsite notifications are required. apply procedural requirements as they pertain to notifications, in accordance with EPIP 2.1 and 2.2.
1107EMR T When emergency action level requires activation of the TSC, operate emergency response facility communications equipment to provide accurate communications.
P5402DTA P Under abnormal plant conditions or for the DTA communications check, operate the portable radios to make the necessary communications.
'C3309DTA T During emergency plan activation, classify emergency events in terms of emergency action levels in accordance with EPIP 1.2.
C3310DTA T When emergency conditions warrant, determine protective action recommendations in accordance with applicable procedures.
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2.0 DESCRIPTION
2.1 Prereauisites
)
None 2.2 Lesson LP2581, Emergency Plan 3.0 EVALUATION Individual lesson enabling objectives may be evaluated by classroom assignments, written quizzes, or other means as determined appropriate by the instructor, Page 15 of 23
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2558 LP2559 LP2560 LP2561 LP2562 LP2563 LP2564 LP2565 LP2566 LP2567 LP2568 Shift Shift Temporary Reactor Mode Plant Short Term Key Security Fuel Miscellaneous TRCR 86.1 Turnover Starting Modificati Plant Changes Parameter Information Control Handling Require on to Startup Verification Conduct of
-ments Procedures Require-Operations ments C6501 COT X
C6512 COT X
P2603 COT X
P6501 COT X
P6503 COT X
C03075RO X
1930lSRO X
P0302SRO X
3 P0303SRO X
i P0308SRO
.X P0310SRO X
f IN314SRO X
IN315SRO X
IN323SRO X
l Page 16 of 23
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2558 LP2559 LP2560 LP2561 LP2562 LP2563 LP2564 LP2565 LP2566 LP2567 LP2568 Shift Shift Temporary Reactor Mode Plant Short Term Key Security Fuel Miscellaneous TRG E6.1 Turnover Staffing Modificati Plant Changes Parameter Information Control llandiing Require on to Startup Verification Conduct of
-ments Procedures Require-Operations ments P0324SRO X
P0330SRO X
P0403SRO X
PO5075RO X
IT508SRO X
P0711SRO X
j i
P0910SRO X
l P0918SRO X
l PIO14SRO X
C0304SRO X
f P0703SRO X
P0707SRO X
r i
P1004SRO X
C0402SRO X
Page 17 of 23 L
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b NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2558 LP2559 LP2560 LP2561 LP2562 LP2563 LP2564 LP2565 LP2566 LP2567 LP2568 Shifi Shift Temporary Reactor Mode Plant Short Term Key Security Fuel Miscellaneous TRCR 86.1 Turnover Stafling Modificati Plant Changes Parameter Information Control
- Handlint, Require on to Startup Verification Conduct of
-ments Procedures Require-Operations ments C0404SRO X
C0405SRO X
C0702SRO X
C080lSRO X
C0805SRO X
C0807SRO X
C1005SRO X
PO404SRO X
i P0706SRO X
P1003SRO X
i CO219DTA X
P0213DTA X
P3336DTA X
5 P5401DTA X
t Page 18 of 23 L
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NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES
- Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2558 LP2559 LP2560 LP2561 LP2562 LP2563 LP2564 LP2565 LP2566 LP2567 LP2568 Shift Shill Temporary Reactor Mode -
Plant Short Term Key-Security Fuel Miscellaneous TRCR 86.1 Turnover StalTing Modificati Plant Changes Parameter Information Control llandling Require on to Startup Verification Conduct of
-ments Procedures Require-Operations ments CO210DTA X
I l
PO407DTA X
l t
t 3
F Page 19 of 23
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2569 LP2570 LP2571 LP2572 LP2573 LP2574 Surveillance Maintenance Tagging and Temporary Familiarity with and Miscellaneoas TRCR 86.2 Requirements Clearances Modification of use of Piping and Systems Instrument Equipment Control Drawings C640lCOT X
t P6405 COT X
P0917SRO X
C010lSRO X
C0103SRO X
i C0105SRO X
C0106SRO X
C0107SRO X
P0104SRO X
P0107SRO X
X P0109SRO X
P0115SRO X
19116SRO X
[9119SRO X
l Page 20 of 23
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2569 LP2570 LP2571 LP2572 LP2573 LP2574 Surveillance Maintenance Tagging and Temporary Familiarity with and Miscellaneous TRCR 86.2 Requirements Clearances Modification of use of Piping and l
Systems Instrument Equipment Control Drawings P0121SRO X
19122SRO X
C0110SRO X
CO202SRO X
CO203SRO X
t CO205SRO X
C030lSRO X
19118SRO X
19120SRO X
19123SRO X
P0202SRO X
19331SRO X
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Page 21 of 23
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE
-=
i Task Matrix LP2575 LP2576 LP2577 LP2578 LP2579 LP2580 The Use and Knowledge of The Ability to Radiation Exposure Radiation Work Control of Radiation TRCR 86.3 Function of Portable Signif' cant Perform Procedures Limits and Permits Releases Radiation and Radiation llazards to Reduce Excessive Contamination Radiation Control Contamination Levels of Radiation Control, including Survey Instruments and to Guard Permissible Levels and Personnel Against Personnel in Excess of1 hose Monitoring Exposure Authorized Equipment P0312SRO X
C0108SRO X
19113SRO X
P0313SRO X
L L
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1 Page 22 of 23 m
=
m..
2 m.
.m...
mmm. -
- a m
NUCLEAR POWER BUSINESS UNIT TRCR 86.0 TRAINING COURSES Revision 12 May 1,1997 ADMINISTRATIVE TOTAL REWRITE Task Matrix LP2581 Emergency Plan TRCR 86.4 Emergency Plan C0210DTA X
~
Il02EMR X
l107EMR X
P5402DTA X
C3309DTA X
C3310DTA X
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Page 23 of 23 l
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