Letter Sequence Other |
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Results
Other: 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, A02589, Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.17, A03501, Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 831026, ML19210D037, ML19254F792, ML19256A718, ML19256F452, ML19262B985, ML19275A926, ML19310A971, ML19340E921, ML20004B640, ML20008E032, ML20008E564, ML20008F134, ML20054E184, ML20076A987, ML20078N847
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MONTHYEARML18078A4061978-11-11011 November 1978 Forwards Comments in the Form of Redraft of Commission Paper Re Proposed Fed Register Notice Abnormal Occurrence Event, Loss of Containment Integrity W/Encl Draft Notice of Issuance Project stage: Draft Other ML19256A7181979-01-0303 January 1979 Discusses Unlimited Purging Re Possible Failure of Automatic Isolation of Large Diameter Containment Purge Penetrations Used During Power Operations.Concludes That Bypass & Override Conditions Can Be Identified Project stage: Other ML20076A9871979-04-27027 April 1979 Forwards Proposed Revision to Tech Specs to Allow Unlimited Containment Purges.Revisions Deal W/Containment Isolation Valves Project stage: Other ML19254B3631979-08-29029 August 1979 Forwards Request for Addl Info Re Override of Containment Purge Isolation Project stage: RAI ML19275A9261979-10-18018 October 1979 Forwards Commitment to Meet Requirements of NUREG-0578. Intends to Meet Requirements & Schedules Set Forth in NRC Project stage: Other ML19250A7591979-10-18018 October 1979 Forwards Response to 790913 Request for Commitment to Comply W/Requirements of NUREG-0578.Optimum Method of Addressing Concern,In Recognition of plant-unique Features, Proposed Project stage: Request ML19254F7921979-10-30030 October 1979 Requests Util Commitment to Comply W/Encl Interim Position Re Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability.Commitment Needed within 45 Days Project stage: Other ML19210D0371979-11-13013 November 1979 Responds to NRC Re Containment Purging & Venting. Vent & Purge Valves at Three Units Qualify W/Nrc Guidelines to Extent Guidelines Apply Project stage: Other ML19211A4411979-11-19019 November 1979 Forwards Request for Addl Info to Complete Evaluation of Electrical Override/Bypass Aspects of Containment Purge Sys Project stage: RAI ML19256F4521979-11-19019 November 1979 Forwards Addl Info Required for Completion of NRC Evolution of Electrical Override/Bypass Aspects of Containment Isolation Matter.Criteria Encl Project stage: Other ML19260C2221979-12-11011 December 1979 Forwards Criteria Re Electrical Override/Bypass for Use in Review of Operating Reactors.Maintaining Purge Valves Closed Does Not Resolve NRC Concern W/Purge Valve Circuitry Project stage: Approval ML19310A9711979-12-27027 December 1979 Requests Preliminary Evaluation of Licensee Response to NRC 791023 Interim Position for Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability, Generic Item B-24.Evaluation Form Encl Project stage: Other ML19262B9851980-01-16016 January 1980 Responds to NRC 791211 Request Re Containment Purge Sys & Engineered Safety Equipment Component Design.Sys Design & Procedures Utilized for Operation Provide Acceptable Degree of Safety Project stage: Other 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 ML20008E0321980-10-0606 October 1980 Amend 61 to License DPR-65 Authorizing Cycle 4 Operation at 2,700 Mwt W/Mixed Core w/one-third Westinghouse Fuel & two- Thirds CE Fuel & Modified Guide Tubes for Control Element Assemblies Project stage: Other ML19340E9211980-12-31031 December 1980 Forwards Rept on post-TMI Requirements in Response to NUREG-0737 & NRC Project stage: Other ML20008E5641981-02-27027 February 1981 Provides Justification for Min Containment Pressure Used to Initiate Containment Isolation for Facility,Per NRC 801231 Request Re NUREG-0737.Present Containment Isolation Setpoint Is Adequate & No Reduction in Setpoint Is Warranted Project stage: Other ML20008F1341981-03-0404 March 1981 Forwards ECCS Outage Rept for Facilities for 1980,in Response to NUREG-0737,Item II.K.3.17.No Sys or Tech Spec Mods Are Required Project stage: Other ML20004B6401981-05-20020 May 1981 Advises That No Mods Will Be Made to TMI Action Plan Item II.E.4.2 Re Containment Isolation Dependability.Signals Used for Containment Isolation Are Redundant & Diverse & Adequate to Ensure Safe Operation 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 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 A02589, Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.171982-12-29029 December 1982 Forwards Addl Info Re safety-related ECCS Tank Outages, Provided Verbally on 821220 in Response to NUREG-0737, Item II.K.3.17 Project stage: Other A03035, Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment1983-03-28028 March 1983 Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment Project stage: Request A03501, Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 8310261983-10-12012 October 1983 Requests Addl Time to Provide Info Re 6-inch Containment Purge & Vent Valve Operability.Info Will Be Provided by 831026 Project stage: Other ML20078N8471983-10-27027 October 1983 Forwards Response to NRC 830902 Comments on Unresolved Items Re Containment Purge/Vent Review.No Addl Tech Specs or Equipment Mods Warranted.Operability Requirement Met W/Compliance W/Tmi Item II.E.4.2 Project stage: Other A03992, Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.71984-05-15015 May 1984 Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7 Project stage: Meeting 1980-10-06
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November 13, 1979 Docket Nos. 50-213 50-245 50-336 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
D. G. Eisenhut letter to All Light Water Reactors dated October 17, 1979.
(2)
W. G. Counsil letter to D. L. Ziemann dated January 3,1979.
(3)
W. G. Counsil letter to D. L. Ziemann dated January 2, 1979.
(4)
W. G. Counsil letter to D. L. Ziemann dated April 27, 1979, on Millstone Unit No. 1.
(5)
W. G. Counsil letter to R. W. Reid dated April 27, 1979, on Millstone Unit No. 2.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos. 1 and 2 Containment Purging and Venting Reference (1) provided operability and demonstration guidelines that addressed generic concerns about containment purging and ventilation valves. This letter responds to those guidelines, to the extent that they pertain to the Haddam Neck Plant, Millstone Unit No.1, and Millstone Unit No. 2.
Haddam Neck Plant Our Reference (2) letter stated that Technical Specifications prohibit purging with the 42-inch purge valves unless the plant is in cold shutdown or refueling.
Some containment venting, however, can be performed through the much smaller one-inch valve on the air particulate monitoring line during plant opertion.
Our evaluations of the large purge valves had already considered the new opera-bility guidelines in Reference (1), however, since the larger valves remain closed, the operability guidelines for valve closure are non-applicable. The smaller valve is a containment isolation valve that receives automatic closure signals during an accident.
For both valves, scaling integrity has been periodically demonstrated as part of the 10CFR50, Appendix J, testing requirements. Thus, the vent and purge valves at the Haddam Neck Plant are qualified to meet the guide-lines in Reference (1), to the extent those guidelines apply.
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. Millstone Unit No. 1 Unlimited containment purging was justified in References (3) and (4).
Our evaluations of the purge and vent valves had already considered the new guidelines in Reference (1). The sealing integrity has been periodically demon-strated as part of the 10CFR50, Appendix J, testing requirements. Thus, the valves are qualified to meet the guidelines in Reference (1), to the extent those guidelines apply.
Millstone Unit No. 2 Our Reference (5) letter proposed Technical Specification changes that would maintain the purge valves in a locked closed position in Modes 1 through 4.
Our evaluations of the purge valves had already considered the new operability guidelines in Reference (1), however, the operability guidelines are not applica-ble to locked-closed valves. The sealing integrity has been periodically demonstrated as part of the 10CFR50, Appendix J, testing requirements.
Reference (5) also committed to maintain the purge valves locked closed during the interim prior to Technical Specification change approval. Thus, the purge valves at Millstone Unit No. 2 are qualified to meet the guidelines in Reference (1), to the extent those guidelines apply.
Should you have any questions, please contact us.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY d
/Z W. G. Counsil Vice President h
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