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 ML20041B0621980-07-23023 July 1980 To Licensed Senior Reactor Operator Replacement Training 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 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 ML20041B0691980-08-31031 August 1980 Operator License Program Project stage: Other ML20041B0701980-08-31031 August 1980 Requalification Program for Licensed Operators Project stage: Other ML19344E0831980-08-31031 August 1980 Qualification of Reactor Operators Project stage: Other ML19344E0731980-08-31031 August 1980 Qualification of Reactor Operators 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 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 1981-05-22
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RTF CONN *.CTICUT 06101 b'l?:;'!l?,7,"X',;'f"""
G03) 666-6911 L
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- n'.J:,"lll%7 October 14, 1981 Docket Nos. 50-213 g-m
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50-336 A01379 %,\\ "
Mr. Darrell G. Eisenhut, Director 00[] g 700/A
,h Division of Licensing Office of Nuclear Reactor Regulation D.s. g.,d N h re[
U. S. Nuclear Regulatory Commission 7
G sy Washington, D.C.
20555
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. A
Reference:
(1)
D. G. Eisenhut letter to All Operating Pla'nts;hkdf Applicants for Operating Licenses and Holders of' Construction Permits, dated October 31, 1980, Forwarding NUREG-0737.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station Unit No. 2 NUREG-0737 Item II.K.3.5, Automatic Reactor Coolant Pump Trip Item II.K.3.5 of Reference (1) requires licensees to propose modifica-tions to automatically trip the reactor coolant p2aps during a Loss-of-Coolant Accident. In Reference (1) the Staff admits that " tripping of the reactor coolant pumps is not an ideal solution" but requires that "in the meantime, until a better solution is found, the reactor coolant p'2mps should be tripped automatically in case of a small-break IOCA."
Connecticut Yankee Atomic Power Company (CYAPCO), on behalf of the Haddam Neck Plant, and Northeast Nuclear Energy Company (NNECO), on behalf of Millstone Unit No. 2, have determined that the requirement for installation of an automatic trip system is neither warranted nor desirable at this time, and may in fact degrade plant safety during certain con-ditions. The loss of forced coolant flow during power operation is a potentially severe event. Failure of an automatic trip system which results in a reactor coolant pump trip would cause an unnecessary challenge to the Reactor Protection System as well as the entire plant as a trip from full power would result.
In addition, automatically tripping the Reactor Coolant Pumps during certain transients similar to a IOCA will g
lead to more severe consequences.
Y g
3(
Reactor operators at the Haddam Neck Plant and at Millstone Unit No. 2 are required to manually trip the reactor coolant pumps on receipt of a safety injection signal. Analyses have been performed and docketed to demonstrate that the existing plant design and procedures are adequate.
Operators are trained to recognize conditions when a reactor coolant pump trip is warranted (e.g. - high vibration) and to act accordingly, 8110200521 011014 DR ADOCK 05000213 PDR
. CYAPCO and IMECO have concluded that. an automatic Reactor Coolant Pump trip system is not required to ensure safe operation of the Haddam Neck Plant and Millstone Unit No. 2, and that such a system could potentially degrade plant safety. Plant procedures and operator training are adequate to ensure that the Reactor Coolant Pumps will be tripped when required if the operator determines they are not re-quired for a safe plant shutdown. CYAPCO and IMECO intend to reevaluate this position in light of new data if and when they become available.
We trust the Staff will find the above information sufficient to concur with our position and resolve the concerns of Action Plan Item II.K.3.5.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY CC 7ANY
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A//ld?
W.'G. Counsil Senior Vice President