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
[Table View] |
Text
32 DueboruW ID L b
o, UNITED STATES I( ',E NUCLEAR REGULATORY COMMISSION s.
o WASHINGTON, D. C. 20555 Neuemhar 4. lo19 Decket No. 50-302 pregappp o 4 <im Mr. J. A. Hancock Director, Nuclear Operations Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733
Dear Mr. Hancock:
We have reviewed your submittal dated July 25, 1979, regarding the pump and valve Inservice Testing Program for Crystal River, Unit No. 3.
The staff position is that interfaces between high and low pressure systems, listed in the enclosure, having two or more valves, in series, shall be leak tested periodically. Therefore, based on the alternate testing frequency, Table 2A, of your submittal, we request you to submit design provisions and/
or procedures to permit leak testing of the valves specified in the enclosure.
Leak testing may be performed during an ascent to power.
Kindly submit your response within 45 days to allow timely resolution of this issue.
Sincerely, G/d 1/QJ Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Enclosure cc: w/ enclosure See next page 1619 058 791gsgg Q,,2 5 P
Florida Power Corporation cc: tir. S. A. Brandimore Vice President and General Counsel P. O. Box 14042 St. Petersburg, Florida 33733 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Crystal River Public Library Crystal River, Florida 32629 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 1619 059 mese m-S
Enclosure IDENTIFICATION OF VALVES REQUIRING PERIODIC LEAK TESTING CRYSTAL RIVER, UNIT NO. 3 DOCKET NO. 50-302 Decay Heat Removal System FD-302-641:
DHV-1 DHV-2 DHV-3 DHV-4 DHV-91*
DHV-93*
Reactor Coolant System FD-302-651:
RCV-12*
RCV-53*
Core Flooding System FD-302-702:
C FV-1 CFV-2 CFV-3 CFV-4 DHV-91, DHV-93, RCV-12, and RCV-53 are in series.
Only two of the valves need to be leak tested.
1619 060
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