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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Text
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s IMHrl'Hi!A!iT UTII.ITII!!i l
HARTFORD CONNECTICUT 06101 g203) 666-6911
(
,i January 31, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn: Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Conmission Washington, D. C.
20555 Gentlemen:
Reference:
(1)
W. G. Counsil to R. Reid dated January 25, 1979.
Due to a collating error, the attached page was omitted from our recent submittal on the Inservice Inspection Program, Reference (1). Accordingly, 40 copies of the missing page are provided.
The subject page should be inserted before page P-1.
Please excuse any inconvenience caused by this omission.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMFANY I
M70'c W. G. Counsil Vice President Attactnent
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MILLSTONE UNIT 2 INSERVICE INSPECTION PROGRAM ASME SECTION III CLASS 3 COMPONENTS Class 3 components comprising the systems listed below will be tested and examined in accordance with IWA-5000, IWD-5000, and IWD-2600, by the expiration of each inspection interval.
Supports and hangers for components exceeding four inch nominal pipe size, whose structural integrity is relied upon to withstand design loads when the system function is. required, shall be visually examined to detect any loss of support capability and evidence of inadequate restraint.
In addition, 100 percent of the components shall have been examin2d in accordance with IWA-5240 and IWD-2600 while in operation or during system inservice testing by the expiration of every one-third of each inspection interval.
Class 3 component pressure tests are listed under the section on pressure tests, Table BCD-5000.
Service Water System
- screen well house
- to R"CCW heat exchangers
- to diesel cooling heat exchangers
- to chilled water heat ax change rs Reactor Building Closed Cooling Water
- to shutdown heat exchangers
- to containment air cooling
- to spent fuel cooling heat exchangers
- to engineered safeguards room cooler to seal coolers Chilled Water For Switchgear Room Cooling Main Steam Supply to Steam Generator Auxiliary Feedpump Turbine Spent Fuel Pool Cooling System Auxiliary Feedwater
- condensate storage tank through auxiliary feedpumps to isolation valves.
NOTE - System classifications are shown graphically on the attached boundary diagrams.
