Letter Sequence Other |
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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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June 7, 1979
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Docket No. 50-336 Mr. W. G. Couns'1, Vice President Nuclear Engineering & Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101
Dear Mr. Counsii:
In the process of reviewing your proposed Inservice Inspection Program for the Millstone Unit No. 2, we find that additional information as detailed in the enclosure is needed to complete our review. The page references in the enclosure correspond to your January 25, 1979 submittal.
In order to complete our review in a timely manner, please provide the additional information by at least July 2,1979.
Sincerely,
.s! hfAJ nobert W. Reid, Chief Operating Reaccors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page v s.n hk sII r
J 10071.00727.,
Northeast Nuclear Energy Company cc:
William H. Cuddy. Esquire Day, Serry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Waterford Pu' lic Library o
Rope Ferry Road, Route 156 Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN:
Supp-:ntendent Millstone Plant Post Of fice Box 128 Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN:
Mr. James R. Himmelwright Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Anthony Z. Roisman, Esq.
Natural Resources Defense Council 91715th Street, N.W.
Washington, D.C.
20005 Mr. John T. Shedlosky Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406
Enclosure Millstone Unit 2 Inservice Inspection Program Request For Additional Inferration PAGE I-2 1.
Use of Appendix III of Section XI,1974 edition through winter 1975 is acceptable, hcwever, the recording of indications should be as folicws:
Record all indications which produce a response of 50% or greater of primary reference level.
Evaluate all indications producing a response of 100% or greater of primary reference level.
2.
Use of technical specifications for examination of hydraulic snubbers is acceptable if technical specification procedures meat or exceed code requi remen ts.
Please provide documentation that si a s the extent of technical specification examination requirements.
PAGE I-3 Class 1 Comoonents 1.
Can nozzle to vessel welds N-2, N-4 and N-6 be examined using surface methods ?
PAGE I-10 1.
Concerning your request for relief from examination of vessel cladding, will examination of the closure head welds also provide meaningful information about the condition of the cladding?
2.
In Note 10, you state that safety infection valve bonnet belting has spherical ends, thus precluding volumetric examination.
Since the probable point of crack initiation and growth is the thread root area, has an ultrasonic examination technique utilizing response from thread roots been considered? If this alternate volumetric examination is not possible, is a surface examination of these bolts possible?
Class 2 Comconents 1.
Examination of hydraulic snubbers to requirements of technical specifica-tions is acceptable only if technical specificaticns meet or exceed code requi remen ts.
Please ccmcare and state the differences.
2.
Note 2, Page II-5, states that volumetric examination of the shu ccwn heat excnangers is precluced due to weld design.
please provice details of che nozzle-00-vessel welcs tna; explain wny go volumetric examina icn can be done.
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