Letter Sequence Other |
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Results
Other: A01657, Forwards Revised Pages for Inservice Insp & Testing Program Submitted in for 10-yr Interval 801228-901228. Revised Program for Pumps Will Continue to Be Implemented Unless Informed Otherwise, A02327, Forwards Revised Page 4 to 790625 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, in Response to NRC 820226 Request, B10202, Discusses Proposed Revision to Inservice Insp Program Whereby Exam of Primary Reactor Coolant Sys Piping Would Be Conducted Using Exam Techniques in ASME Code.Revision Found Necessary During 1980 Refueling Outage, ML19241B658, ML19246A684, ML19261E233, ML19261E236, ML19270F351, ML20002D636, ML20009B884, ML20009B885, ML20028A679, ML20040C965, ML20062B950, ML20062B955, ML20083K659
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MONTHYEARML20083K6591979-01-25025 January 1979 Forwards Updated Inservice Insp & Testing Program Describing Operational Readiness Testing for Essential Pumps & Valves & Program of Periodic Pressure Tests.Program Will Be Implemented on or About 790426 Project stage: Other ML19270F3511979-01-31031 January 1979 Forwards Page Accidentally Omitted from Recent Submittal on Inservice Insp Program Project stage: Other ML19246A6821979-05-11011 May 1979 Discusses Preliminary Review of 781026 & 790125 Submittals Re Proposed Inservice Insp & Testing Tech Specs & Request for Relief from Selected ASME Code Requirements.Notice of Relief Encl Project stage: Approval ML19246A6841979-05-11011 May 1979 Notice Granting Relief from ASME Section XI Inservice Insp & Testing Requirements Project stage: Other ML19241B6581979-06-0707 June 1979 Requests Addl Info on Inservice Insp Program Re Hydraulic Snubers,Closure Head Welds,Thread Roots & nozzle-to-vessel Welds of Shutdown Heat Exchangers Project stage: Other ML19261E2331979-06-25025 June 1979 Forwards Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, for 790426-801226 Project stage: Other ML19261E2361979-06-25025 June 1979 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, for 790426-801226 Project stage: Other ML20002D6361981-01-13013 January 1981 Ro:On 801209,inservice Insp Revealed That Required Valve Operability Tests Not Performed During Third Calendar Quarter 1980.Valves Successfully Tested.Action Taken to Assure Timely Review of Valve Test Data Project stage: Other B10202, Discusses Proposed Revision to Inservice Insp Program Whereby Exam of Primary Reactor Coolant Sys Piping Would Be Conducted Using Exam Techniques in ASME Code.Revision Found Necessary During 1980 Refueling Outage1981-05-0101 May 1981 Discusses Proposed Revision to Inservice Insp Program Whereby Exam of Primary Reactor Coolant Sys Piping Would Be Conducted Using Exam Techniques in ASME Code.Revision Found Necessary During 1980 Refueling Outage Project stage: Other ML20009B8851981-07-0101 July 1981 Notice of Issuance & Availability of Amend 70 to License DPR-65 Project stage: Other ML20009B8841981-07-0101 July 1981 Amend 70 to License DPR-65,revising Tech Specs to Incorporate Inservice Insp & Inservice Test Requirements & Remove Outmoded Requirements Project stage: Other A01615, Notifies That Util Will Submit Status of Compliance W/ NUREG-0313,Revision 1 Re BWR Coolant Pressure Boundary Piping & Necessary Tech Spec Change Requests by 811001,in Response to NRC1981-07-0101 July 1981 Notifies That Util Will Submit Status of Compliance W/ NUREG-0313,Revision 1 Re BWR Coolant Pressure Boundary Piping & Necessary Tech Spec Change Requests by 811001,in Response to NRC Project stage: Request A01657, Forwards Revised Pages for Inservice Insp & Testing Program Submitted in for 10-yr Interval 801228-901228. Revised Program for Pumps Will Continue to Be Implemented Unless Informed Otherwise1981-09-30030 September 1981 Forwards Revised Pages for Inservice Insp & Testing Program Submitted in for 10-yr Interval 801228-901228. Revised Program for Pumps Will Continue to Be Implemented Unless Informed Otherwise Project stage: Other ML20040C9651982-01-22022 January 1982 Forwards Revised Figures 1-4 Which Define Affected Areas of Steam Generator Tube Bundle to Which Util Proposed to Limit Cycle 5 Refueling Outage Steam Generator eddy-current Exams. Revised Figures Part of Proposal to Limit Inservice Insp Project stage: Other ML20041E8601982-02-26026 February 1982 Forwards Request for Addl Info Re Inservice Insp Program. Response Requested within 30 Days of Receipt of Ltr Project stage: RAI A02327, Forwards Revised Page 4 to 790625 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, in Response to NRC 820226 Request1982-04-14014 April 1982 Forwards Revised Page 4 to 790625 Inservice Insp & Test Program for Pumps,Valves & Pressure Tests, in Response to NRC 820226 Request Project stage: Other A02260, Forwards Response to NRC 820125 Request for Addl Info Required to Complete Evaluation of SEP Topic III-3.C, Inservice Insp of Water Control Structures1982-05-28028 May 1982 Forwards Response to NRC 820125 Request for Addl Info Required to Complete Evaluation of SEP Topic III-3.C, Inservice Insp of Water Control Structures Project stage: Request ML20062B9551982-06-0404 June 1982 Inservice Insp Rept IR-ISI-010, Fourth Refueling Outage Inservice Insp Rept for Northeast Utils Millstone Point, Unit 2. Class 1 Piping Inspected Project stage: Other ML20062B9501982-07-16016 July 1982 Forwards Inservice Insp Rept IR-ISI-010, Fourth Refueling Outage Inservice Insp Rept for Northeast Utils Millstone Point,Unit 2 Project stage: Other ML20028A6791982-11-0404 November 1982 Grants Relief from Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code.Grant Will Not Result in Significant Environ Impact.Ser & Fr Notice Encl Project stage: Other 1981-07-01
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7590-01 i
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1 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-336 NORTHEAST NUCLEAR ENERGY CCMPANY, ET. AL.
NOTICE OF GRANTING OF RELIEF FROM ASME SECTION XI INSERVICE INSPECTION AND TESTING REQUIREMENTS i
The U. S. Nuclear Regulatory Comission (the Commission) has i
granted relief from certain requirement; of the ASME Code,Section XI, " Rules for Inservice Inspection of Nudear Power Plant Components" l
to Northeast Nuclear Energy Company. The relief relates to the inservice inspection and testing program for the Millstone Nuclear Power Station, Unit No. 2 (the facility) located in Waterford, Connecticut. The ASME Code requirements are incorporated by reference into the Commission's rules and regulations in 10 CFR Part 50.
The relief is effective as of its date of issuance.
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Relief is granted, on an interim basis, pending completion of a more detailed review, from compliance with certain inservice inspection and testing requirements determined to be impractical for the facility because compliance would result in hardships and unusual 1
difficulties without a compensating increase in the level or quality of safety.
The request for relief complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Comissico has made appropriate findings as required by the Act and the Comission's 7 9 0 'w 6 o '? z em y V
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s 7590 01 i
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rules and regulations in 10 CFR Chapter I, which are set forth in the letter granting relief.
prior public notice of this action was not required since the granting of this relief from ASME Code re-quirements does not involve a significant hazards consideration.
j The Con 11ssion has determined that the granting of this relief i
will not resalt in any significant environmental impact and that i
pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with tnis action.
For further details with respect to this action, see (1) the l
licensee's proposed Technical Specifications dated October 26, 1978, (2) the program description and request for relief dated January 25, 1979, and (3) the Comr.Tission's letter to the licensee dated MAY 1 1 mg These items are available for public inspection at the Com-mission's public Document Room,1717 H Street, N.W., Washington, D.C.
and at the Waterford public Library, Rope Ferry Road, Route 156, Waterford, Connecticut. A copy of item (3) may be obtained upon request addressed to the U. S. Ne, sear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this lith day of May 1979.
FOR THE NUCLEAR REGULATORY COMMSSION 1} h I, ck Robert W. Reid, Chief 1h Operating Reactors Branch #4 Division of Operating Reactors
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