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
[Table View] |
Text
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i NNECO OPERATOR LICENSE PROGRAM
- 1. _
PURPOSE l
The purpose of this program is to_. provide a comprehensive training program which will prepare opera' tors for license examination.
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2.
REFERENCES
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'4 2.1 10 CFR 55 Operator's Licenses 2.2 H. Denton's letter on operator qualification dated 3/29/80 f
2.3 ANSI N 18.1 - 1971 2.4 WASH 1094, NRC Licensing Guide PB 255 664 l
3.
PROGRAM INDEX Subject Article Page flumber 1.
Applicabili ty 4.1 1
i i
2.
Prerequisites 4.2 2
i 3.-
Operator Program 4.3 2
4.3.2 2
A.
On Shift Training B.
Simulator Certification 4.3.2.2 2
C.
Review and Evaluation 4.3 3 3
4.
Senior Operator Program 4.4 3
i A.
On Shift Training 4.4.6 4
5.
Instructor Qualifications 5.
4 j
4.
PROGRAM DESCRIPTION 4.1 Applicability l
This program describes training for replacanent personnel.
It 1
applies to Hot License R0 and SRO candidates.
Millstone Unit 1 Docket 50-245
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" Millstone Unit 2 Docket 50-336 l
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. 4.2 Prercquisites License candidates are required to meet education and experience requi reaants of references 2.1, 2.2 and 2.3.
4.3 Reactor Operator Program The reactor operator program will be described in three phases.
4.3.1 Phase 1, Formal classroom Subject 1.
Mathema tics / Algebra 2.
Heat transfer and fluid flow 3.
Plant Performance 4.
Electrical / Instrumentation 5.
Understanding of CWD's and P&ID's 6.
Chanistry, Waste Treatment 7.
f uclear Physics 8.
Reactor Physics 9.
Plant System and Procedures 10.
Plant Transients and Accident Analysis 11.
Use of Systems to Control an Accident Uhen Severe Core Damage Exists
==
Description:==
This phase is approximately 24 weeks in length.
l 4.3.2 Phase 2, On-the-Job Training This phase provider the license candidate the oppor-tunity to perform and become familiar with plant operations.
This program is structured and provides progress evaluation.
4.3.2.1 Each candidate will be assigned as an extra person in the control room for 12 weeks.
4.3.2.2 Each candidate will attend an NRC approved simulator program for license demonstration certification.
' 4.3.3 Phase 3, Review and Evaluation 4.3.3.1 A review period of at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> will be structured after simulator certification program.
Each candidate will be required to satis-factorily complete a written and oral examination prior to taking the NRC exami-nation.
A.
Exan Criteria 1.
Written examination overall shall be greater than 80%.
2.
Each section shall be greater than 70%. Remedial study and test retake may be exercised to meet this criteria.
3.
Oral exam / walk-thru overall satis factory.
4.4 Senior Reactor Operator Program Operators advancing to the SR0 level will be provided upgrade training and evaluation by the Training Staff.
4.4.1 The program shall be a structured review to include self-study, fonnal presentations and review discussion.
A weekly progress evaluation is required.
Each candidate must complete the program with an overall score greater than 80%, with all test sections greater than 70%.
4.4.2 Remedial study and test retake is pennissable to
. meet the above criteria.
4.4.3 The fonnal review program shall be a minimum of six weeks in length.
4.4.4 The program shall include as a minimum, those areas listed in Reference 2.1 and 2.2.
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. 4.4.5 Applicants for an SR0 license shall have held an operators license for 1 year.
-(Effective for applications after December 1,1980) 4.4.6 Applicants for Senior license shall have 12 weeks of shift training as an extra man on shift.
(Effective for applications after August 1,1980).
4.5 Applicant Evaluation The Training Supervisor shall evaluate all candidates for licens e.
He shall review / recommend and forward applications to the Station Superintendent for Site approval.
All applications for license shall be forwarded to the Senior Vice President of NNECo, for final corporate approval.
5.
INSTRUCTOR QUA1.IFICATIONS 5.1 Instructors chosen to instruct. any phase of the operator program shall approved by the Training Supervisor.
5.2 An SR0 licensed instructor shall review and approve all programs presented in the license candidate program.
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