Letter Sequence Other |
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Results
Other: A00938, Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program, A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted, A01551, Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities, A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737, A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl, B12611, Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements, ML19340E921, ML19344E073, ML19344E075, ML19344E083, ML19345E125, ML20004D414, ML20010A692, ML20028E427, ML20031F894, ML20041B060, ML20041B062, ML20041B064, ML20041B066, ML20041B069, ML20041B070, ML20050C507, ML20054E184, ML20077B854, ML20149L522, ML20214K567, ML20237D811, ML20244C864
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MONTHYEARIR 05000245/19790211979-10-30030 October 1979 IE Insp Repts 50-245/79-21 & 50-336/79-22 on 790804-0901.No Noncompliance Noted.Major Areas Inspected:Plant Tours, Physical Security,Exam of Feedwater Piping Per IE Bulletin 79-13,fire Protection & Surveillance Testing Project stage: Request ML19296B2941980-02-0808 February 1980 Submits Response to NRC 800201 Request for Addl Info Re Proposed long-term Emergency Operations Ctr,Required by NUREG-0578.Ctr Would Be Located 1.5 Miles from Plant. Preliminary Maps & Drawings Encl Project stage: Request ML19296B0471980-02-0808 February 1980 RCS Asymmetric Loads Evaluation Program;Interim Rept Project stage: Request ML19309B8431980-03-28028 March 1980 Submits Info Re Direct Indication of PORV & Safety Valve Positions.Recent Discussions W/Vendor Revealed Difficulty w/800401 Completion Date.Revised Date of Completion Is 810401 Project stage: Request ML19323B1601980-04-16016 April 1980 Forwards NRC Position Re Emergency Response Facilities. Primary Technical Support Ctr That Does Not Meet Habitability Requirements Acceptable,Provided That Secondary Ctr,Meeting Requirements,Available Project stage: Meeting A01024, Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted1980-06-10010 June 1980 Forwards Info Re Five Addl TMI-2 Related Requirements Applying to Operating Reactors Per 800507 Request.Integrated Assessment of Collective Impact of All Requirements Should Be Conducted Project stage: Other ML20041B0661980-07-22022 July 1980 Instructor Requalification Project stage: Other ML20041B0641980-07-23023 July 1980 To CT Yankee Reactor Operator Requalification Project stage: Other ML20041B0601980-07-23023 July 1980 To Licensed Reactor Operator Replacement Training Project stage: Other ML20041B0621980-07-23023 July 1980 To Licensed Senior Reactor Operator Replacement Training Project stage: Other ML19344E0751980-07-31031 July 1980 Operator Requalification Program Project stage: Other A00938, Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program1980-08-15015 August 1980 Forwards Haddam Neck Plant Reactor Operator Qualification & Requalification Programs & Millstone,Units 1 & 2,reactor Operator Qualification Program Project stage: Other ML20041B0701980-08-31031 August 1980 Requalification Program for Licensed Operators Project stage: Other ML19344E0731980-08-31031 August 1980 Qualification of Reactor Operators Project stage: Other ML19344E0831980-08-31031 August 1980 Qualification of Reactor Operators Project stage: Other ML20041B0691980-08-31031 August 1980 Operator License Program Project stage: Other B10111, Forwards Implementation Status of TMI Action Plan.Items Which Cannot Be Implemented by 810101 Identified1980-10-31031 October 1980 Forwards Implementation Status of TMI Action Plan.Items Which Cannot Be Implemented by 810101 Identified Project stage: Other ML19345E1251980-12-15015 December 1980 Forwards Response to NUREG-0737 Re Implementation Status of TMI-related Requirements Project stage: Other ML19340E9211980-12-31031 December 1980 Forwards Rept on post-TMI Requirements in Response to NUREG-0737 & NRC Project stage: Other B10200, Comments on Draft NUREG-0659 Re Human Engineering Guide to Control Room Evaluation.Consideration Should Be Given to Lengthening 1-yr Review Process Due to Increased Workload on Operators Requirements Such as TMI Action Plan Items1981-04-16016 April 1981 Comments on Draft NUREG-0659 Re Human Engineering Guide to Control Room Evaluation.Consideration Should Be Given to Lengthening 1-yr Review Process Due to Increased Workload on Operators Requirements Such as TMI Action Plan Items Project stage: Draft Other ML20004D4141981-05-22022 May 1981 Forwards Response to IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Mytilus Sp Is Salt Water Organism & Cannot Inhabit Freshwater Mo River Project stage: Other A01551, Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities1981-06-0303 June 1981 Provides Info & Appropriate Refs in Response to Generic Ltr 81-10 Re Emergency Response Facilities Project stage: Other ML20010A6921981-08-0606 August 1981 Advises of Intended Licensing Exam Requests for Facilities for 1982.Advance Notice for NRC Support Considered Necessary Due to Limited Simulator Availability to Meet New Regulations Project stage: Other A01845, Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request1981-08-10010 August 1981 Forwards Info Re NRC Orders Confirming Licensee Commitments on post-TMI Related Issues.Issues Have Been Addressed.If NRC Does Not Allow Util to Reserve Request for Hearing,Ltr Should Be Treated as Hearing Request Project stage: Request ML20031F8941981-10-14014 October 1981 Responds to NUREG-0737 Item II.K.3.5,automatic Reactor Coolant Pump Trip.Requirement for Installation of Automatic Trip Sys Is Neither Warranted Nor Desirable Project stage: Other ML20031H1491981-10-20020 October 1981 Advises That Cable Supplied for Requirements of NUREG-0737 Item II.F.1.3, Containment High-Range Radiation Monitor, Is Not Fully Environmentally Qualified.Cable Will Be Replaced During Next Outage Project stage: Other ML20033D2301981-11-30030 November 1981 Notifies That Stack Monitoring Sys Will Be Modified to Accomodate Installation of High Range Noble Gas Effluent Monitor Per Item II.F.1 NUREG-0737 Requirement.Compliance W/Tech Specs During Installation Will Be Maintained Project stage: Other ML20050C5071982-03-24024 March 1982 Ack Commitment in to Meet Reporting Requirement Provided in NRC Re Relief & Safety Valve Failures.Info Missing from 1981 Annual Rept.Requests That Rept Be Updated W/Errata Sheet to Correct Discrepancy Project stage: Other ML20054E1841982-04-16016 April 1982 Forwards Responses to Generic Ltr 82-05 Re post-TMI Requirements Implementation.Continued Safe Operation Assured W/Existing Implementation Status Project stage: Other A02376, Responds to 820318 Request for Addl Info Required to Complete Review of NUREG-0737,Item I.A.1.2 Re Upgraded Senior Reactor Operator & Reactor Operator Training & Item II.B.4 Re Training for Mitigating Core Damage1982-05-10010 May 1982 Responds to 820318 Request for Addl Info Required to Complete Review of NUREG-0737,Item I.A.1.2 Re Upgraded Senior Reactor Operator & Reactor Operator Training & Item II.B.4 Re Training for Mitigating Core Damage Project stage: Request A02477, Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-07371982-06-0404 June 1982 Forwards Response to Generic Ltr 82-10 Requesting Info Re Implementation Dates for Selected TMI Action Plan Items in NUREG-0737 Project stage: Other ML20028E4271982-08-17017 August 1982 Improvements in Training & Requalification Programs as Required by TMI Action Items,I.A.2.1 & II.B.4, Technical Evaluation Rept Project stage: Other ML20214K5671983-04-19019 April 1983 Advises That Reporting Period Began on 800401 for All PWR Licensees Committed to Providing NRC Prompt Notification of Porv/Sv Failures & Periodic Repts.Project Managers Should Have Info Available in Records Project stage: Other ML20077B8541983-07-20020 July 1983 Operating Reactor PORV Repts (F-37) TMI Action Plan Requirements:Generic Rept - B&W Designed Units, Technical Evaluation Rept Project stage: Other ML20244C8641984-02-16016 February 1984 Amends 95 & 92 to Licenses DPR-21 & DPR-65,respectively, Changing Tech Specs to Comply W/Final Rule on Licensed Operator Staffing Project stage: Other A05610, Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl1986-06-13013 June 1986 Responds to Generic Ltr 86-04 Re Policy Statement on Engineering Expertise on Shift.Comparison of INPO Shift Technical Advisor Guidelines W/Established Bachelors Degree Programs in Engineering Encl Project stage: Other B12611, Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements1987-08-0707 August 1987 Comments on NRC Evaluation of Util Program for Training & Qualifying Individuals for dual-role,senior Reactor Operator/Shift Technical Advisor Positions W/Specific Emphasis on Whether Program Meets NRC Requirements Project stage: Other ML20237D8111987-12-18018 December 1987 Informs That Util May Proceed Immediately W/Implementation of Organizational Structures Proposed in 871118 & 19 Ltrs Project stage: Other ML20149L4451988-02-17017 February 1988 Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Changing Table 6.2-1 of Tech Specs to Recognize Acceptability of Qualified Individuals in Dual Role of Senior Reactor Operator (SRO) & Shift Technical Advisor Project stage: Request ML20149L5221988-02-17017 February 1988 Proposed Tech Specs,Amending Table 6.2-1 Re Dual Role Senior Reactor Operator (SRO) & Shift Technical Advisor (STA) Project stage: Other 1981-04-16
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DOCKET NO. 50-213 HADDAM NECK PLANT OPERATOR REQUALIFICATION PROGRAM JULY, 1980 800826n o
1
CONNECTICUT YANKEE rrogram 1.o.,
or-aro nev. 1
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TRAINING PROGRAM
^veroved: 7V]44k Date:
TITLE Connecticut Yankee Reactor Operator Requalification OBJECTIVE Assure continued competence of Reactor Operators EVALUATION See Content, Section 4.0 CONTENT 1.0 LECTURES A lecture series, consisting of at least six lectures per year addressing the following topics, will be attended by all licensed personnel.
1.1 Reactor Theory 1.2 Operating Characteristics 1.3 Instrumentation and control System 1.4 Protection and Safety Systems 1.5 Normal and Emergency Procedures 1.6 Radiation Control and Safety 1.7 Fluid Flow and Pump Theory l
1.8 Thermodynamics
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l.9 Operation with a Damaged Core j
Technical Specifications will be included where applicable.
Video tapes or other commercially available training programs will be limited to less than 1
25 percent of the total lecture series.
s 2.0 On-Tl!L-JOL TRAINING On-the-job training consists of the following three categories.
2.1 Review of Changes All Licensed Reactor Operators will review pertinent changes to the following:
2.1.1 Operating License 2.1.2 Normal Operating Procedures 2.1.3 Emergency Procedures 2.1.4 Surveillance Procedures 2.1.5 Technical Specifications 2.1.6 Plant Design Review requirements will be established by the Plant Operations Review Comnittee.
2.2 Review of Emergency Procedures All Emergency Procedures will be scheduled for annual review.
2.3 Reactor Control Manipulations Reactor Control Manipulations, that demonstrate satisfactory understanding of reactor operation and provide for at least ten significant reactivity changes, must be experienced during each requalification period.
An effort will be made to insore a variety of reactivity changes will be experienced.
A power transient is any power change other than adjustments for burnup.
This portion of On the Job Training may be satisfied by an approved simulator program.
Significant reactivity changes are identified as:
- 2.3.1 Reactor critical approach during which neutron level is brought to the point of adding heat.
- 2.3.2 Orderly reactor shutdown.
- 2.3.5 Manual rod control during power transient.
- 2.3.6 Turbine control during phasing.
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- 2.3.7 Manual feedwater control during startup or shutdown.
- 2.3.8 Loss of coolant including:
1.
significant PWR steam generat ~ r leaks 2.
inside and outside primary containment 3.
large and small, including Icak-rate determination 4.
saturated Reactor Coolant response (PWR)
- 2.3.9 Loss of all feedwater (normal and emergen'cy).
2.3.11 Loss of condenser vacuum.
2.3.12 Loss of service water if required for safety.
2.3.13 Loss of shutdown cooling.
2.3.14 Loss of component cooling system or cooling to an individual component.
2.3.15 Loss of normal feedwater or normal feedwater system failure.
2.3.16 Loss of all feedwater (normal and emergency).
2.3.17 Loss of protective system channel.
2.3.18 Mispositioned control rod or rods (or rod drops).
2.3.19 Inability to drive control rods.
2.3.20 Conditions requiring use of emergency boration.
2.3.21 Fuel cladding failure or high activity in reactor coolant.
2.3.22 Turbine trip.
2.3.23 Malfunction of reactor coolant pressure / volume control system.
2.3.24 Reactor Trip.
2.3.25 Main steam line break (inside or outside containment).
2.3.26 Nuclear instrumentation failure (s).
- Indicates items that shall be experienced annually.
o 4
3.0 Simulator A simulator program, of at Icast three days duration, may be used to meet Section 2.3 of on the Job Training.
The simulator must meet the following criteria:
3.1 Nuclear Regulatory Commission approved.
3.2 Simulates Connecticut Yankee Operating Characteristics.
3.3 Provide the control manipulations required.
4.0 Evaluation 4.1 Exams A written exam, similar to the Nuclear Regulatory Commission License Exam, will be administered annually.
Exams will be evaluated to identify deficiencies which will be factored into future retraining lectures.
An overall score of less than 80 percent or less than 70 percent in each category on the annual exam will result in the individual being relieved of licensed duties and provided with acceleration training in the deficient areas.
4.2 Quizzes Quizzes will be administered to evaluate student progress in lecture material.
A score of less than 80 percent will be evaluated and specific training administered to upgrade the individual.
The lecture will be rescheduled if more than 50 percent of the attendees scored less than 80 percent.
4.3 Drills Drills will be conducted at 1 cast annually to provide a systematic review of the operator's ability to respond to emergency conditions.
4.4 Exemptions Instructors will be exempt from evaluation based on their participation in the preparation and administration of the evaluations.
.,u 5.0 Accelerated Programs Accelerated programs will be developed for individuals failing to meet the requirements of Section 4.0.
6.0 Records 6.1 Records will be maintained that document attendance and satisfactory performance of all phases of this
- program, 6.2 Masters and keys of all exams and quizzes will be maintained on file.
6.3 Copies of each operators response to exam and quiz questions will be maintained on file.
6.4 Drill evaluations will be maintained on file.
CONNECTICUT YANKEE r,oyrem 1.D.,
rC-rR 03 TRAINING ABSTRACT
^rvrovea d8A Dates h ) }h$
TITLE Instructor Requalification DEVELOPED FOR Connecticut Yankee Instreutors responsible for cle;; room instruction of plant systems or operation for licensed reactor operators, reactor operator license candidates or shift technical advisors.
OBJECTIVE Maintain the instructors knowledge of plant design and administrative controls current.
NOTE:
Satisfies requirement stated in Attachment One (Section 2e) of NRC (Denton) letter dated March 28, 1980,
Subject:
Qualifications of Reactor Operators.
LENGTH N/A SCHEDULE Continuous TYPE Self Study EVALUATION N/A CONTENT 1.0 Operating Experience 2,0 Plant Design 3.0 Changes I
l
CONNECTICUT YANKEE pre rem 1.o.,
TC-TR 03 TRAINING PROGRAM
^varovea: M A M / -
Dates } } } [/
TITLE INSTRUCTOR REQUALIFICATION OBJECTIVE Maintain instructors knowledge of operating history and changes to plant equiptent, systems and administrative controls.
EVALUATION N/A CONTENT 1.0 operating Experience 1.1 Monthly Review of " Operating Experiences Sumary" 1.2 Plant Information Reports 1.3 Plant Licensee Event Report 1.4 Morning Meeting Report 1.5 Plant Operation Review Comittee Minutas 1.6 Monthly Operating Report 2.0 Plant Design 2.1 Plant Design Change Request Review 3.0 Changes 3.1 Facility License 3.2 Plant Procedures Manual 3.3 Technical Specifications 3.4 Facility Description and Safety Analysis 3.5 Station Policies 3.6 Code of Federal Regulations
.