Letter Sequence Other |
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Results
Other: ML19250B849, ML19256F834, ML19308D652, ML19308D751, ML19308D892, ML19317G522, ML19319D228, ML19327A382, ML19327A384, ML19341C948, ML19341C952, ML20010G595, ML20031E322, ML20150F069
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MONTHYEARIR 05000302/19760141976-09-22022 September 1976
IE Insp Rept 50-302/76-14 on 760817-19.No Noncompliance Noted.Major Areas Inspected:Followup on Previous IE Insp Findings,Gaseous Waste Sys Mods,Facility Status Affecting Plant Completion & Revision to SP-158
Project stage: Request
ML19308D6521976-12-15015 December 1976
Surveillance & Inservice Insp Program
Project stage: Other
ML19308D7511976-12-15015 December 1976
Submits Util Planned Surveillance & Inservice Insp Program & Requests First Year Relief from STS 4.0.5 Requirements
Project stage: Other
ML19308D8921977-02-0101 February 1977
Approves 761215 Proposed Inservice Insp & Testing Program for Period,Pending Start of Commercial Operation.Request for Relief from ASME Code Requirements Includes Insufficient Info
Project stage: Other
ML19317G4591977-03-0202 March 1977
Forwards Addl Info Supporting Request for Relief from ASME Section XI Requirements for Inservice Insp & Testing Program
Project stage: Request
ML19317G5221977-04-14014 April 1977
Requests Waiver from ASME Section XI Inservice Insp Requirements.Development & Implementation of New Inservice Insp Program Will Include Proposed Alternate Examinations in Lieu of Impractical ASME Code Requirements
Project stage: Other
ML20037A5871977-04-22022 April 1977
Requests Technical Assistance for Review of Licensee 770414 Request for Waiver of Section XI ASME Code on Inservice Insp
Project stage: Approval
ML19319C7781977-06-14014 June 1977
Forwards Request for Addl Info Re Util 770414 Request for Relief from ASME Code Requirements Re Inservice Insp
Project stage: RAI
ML19319D2281978-08-17017 August 1978
Requests Relief for Inservice Insp Program from ASME Section IWA-5210 Requirements.Requirements Impractical for Testing Repair Weld on Elbow in 14-inch Feedwater Line Connected to Steam Generator Feedwater Header a
Project stage: Other
ML20150F0691979-03-28028 March 1979
Requests Waivers from Parts of Section XI to ASME Code 1974 Edition.Wishes to Adopt Subarticles & Article 7,000 of ASME Code 1977 Edition.Needs Addl Guidelines Re Repairs,Mod & Replacement to Establish Inservice Insp Program
Project stage: Other
ML19250B8491979-04-0505 April 1979
Updates Re Insp of Stagnant Low Pressure Stainless Piping Containing Boric Acid Solutions.Util Will Perform Periodic Pressure Tests & Leak Detection to Monitor Piping for Intergranular Chloride Stress Corrosion Cracking
Project stage: Other
ML19256F8341979-12-0404 December 1979
Advises of NRC Position,In Response to 790725 Submittal Re Pump & Valve Inservice Testing Program.High & Low Pressure Interfaces W/Two or More Valves Shall Be Leak Tested Periodically.Requests Design Provisions Per Encl
Project stage: Other
ML19257C7731980-01-25025 January 1980
Responds to NRC 791204 Request for Addl Design Provisions & Test Methods Permitting Valve Leak Testing.Forwards Revision to Pump & Valve Test Program Pages & Discussion of Design Mods Necessary to Accomplish Alternative Test Method
Project stage: Request
ML19318C3271980-06-26026 June 1980
Application for Amend to License DPR-72,granting Waiver from Certain ASME Section XI Testing & Insp Requirements. Certificate of Svc Encl
Project stage: Request
ML19327A3821980-07-22022 July 1980
Forwards Fr Notice of Granting Relief from ASME Section XI Inservice Insp (Testing) Requirements by Permitting Use of Winter 1977 Addenda for Hydrostatic Pressure Test
Project stage: Other
ML19327A3841980-07-22022 July 1980
Notice of Granting of Relief from ASME Section XI Inservice Insp (Testing) Requirements by Permitting Use of Winter 1977 Addenda for Hydrostatic Pressure Test
Project stage: Other
ML19341C9481981-02-27027 February 1981
Forwards Annual Operating Rept,1980. Includes Personnel Exposure,Reactor Vessel Matl Surveillance Capsules, Production Facility Changes,Tests & Experiments & Steam Generator Inservice Insp
Project stage: Other
ML19341C9521981-02-27027 February 1981
Annual Operating Rept,1980. Includes Personnel Exposure, Reactor Vessel Matl Surveillance Capsules,Production Facility Changes,Tests & Experiments & Steam Generator Inservice Insp
Project stage: Other
ML20010G5951981-09-14014 September 1981
Requests Generic Relief from Hydrostatic Test Requirements of Article Iwc 5000 of ASME Section XI While Performing Work on Main Feedwater Piping Between Steam Generators & First Upstream Isolation Valves.Response Requested by 811015
Project stage: Other
ML20031E3221981-10-0606 October 1981
Requests Relief from Requirements of Article IWB-2000 of ASME Section XI Re Ultrasonic Insp of Vessel Ring Forging to Support Skirt Weld.Insp Is Not Safe Due to High Radiation in Vicinity of Vessel Supports
Project stage: Other
1979-12-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION 7590-01 DOCKET NO, 50-302 FLORIDA POWER CORPORATION, ET AL.
NOTICE OF GRANTING OF RELIEF FROM ASME SECTION XI INSERVICE INSPECTION (TESTING) REQUIREMENTd The U. S. Nuclear Regulatory Commission (the Commission) has granted relief from certain requirements of the ASME Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components" to Florida Power Corporation, Et A1. The relief relates to the inservice inspection (testing) program for the Crystal River Unit No. 3 Nuclear Generating Plant (the facility) located in Citrus County, Florida. 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.
The relief permits Florida Power Corporation to use the requirements of the ASME Section XI Winter 1977 Addenda in place of the Summer 1975 Addenda for a hydrostatic pressure test, after system modification, of the Make-up and Purification System. The Winter 1977 Addenda pertaining to this action has been adopted by the Commission.
The request for relief complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the letter granting relief.
8 0080 6 0/AO
," 7590-01 For further details with respect to this action, see (1) the request for relief dated June 25,1980, and (2) the Comission's letter to the licensee dated July 22,1980.
These items are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., Washington, D. C. and at the Crystal River Public Library, Crystal River, Florida. A copy of item (2) may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 22nd day of July 1980.
FOR THE NUCLEAR REGULATORY COMMISSION s
R~obert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing j
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