ML20085J411
ML20085J411 | |
Person / Time | |
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Site: | Crystal River |
Issue date: | 10/10/1983 |
From: | Scott L FLORIDA POWER CORP. |
To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
References | |
REF-PT21-83-024-000 PT21-83-024-000, PT21-83-24, NUDOCS 8310130136 | |
Download: ML20085J411 (1) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEAR3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999
[Table view]Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. 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Generator Supplier Will Be Contacted to Determine Whether Deficiency Exists.Problem Suspected to Be Generic in Nature ML19331D3601980-08-0707 August 1980 Part 21 Rept Re Improper Fluid Provided W/Reactor Coolant Pump Hydraulic Shock Suppressors.Fluid Will Be Changed to Hydraulic Fluid for Use in Radioactive Environs ML19318C4291980-06-24024 June 1980 Advises That 800530 Part 21 Rept Re Mainstream Safety Valve Cracking in Valve Disc Guides Has Been Dispositioned. Forwards Analyses Determining Parts Acceptable for Use ML19310A6781980-06-0505 June 1980 Part 21 Rept Revising 800530 Rept Re Cracking of Disc Guides of Six Main Steam Safety Valves Mfg by Dresser Industries. Correct Valve Type Is 3707R.Corrective Action Is Being Determined ML19310A3611980-05-30030 May 1980 Deficiency Rept Re Extensive Cracking in Valve Disc Guide on Six Valves Mfg by Dresser Industries.Corrective Action Is Being Determined by Manufacturer & Will Be Accomplished Prior to Restart ML19323D5351980-04-15015 April 1980 Part 21 Rept Re Flow Media Through Pressurizer Pilot Operated Relief Valves & ASME Code Safety Valves.Valves Were Designed & Tested in Accordance W/Purchaser Specs Which Identified Saturated Steam as Only Flow Media ML19308D6601976-12-10010 December 1976 Dome Delamination, Final Rept ML19326B2501976-10-28028 October 1976 Suppl 2,Responses to Structural Engineering Branch Comments & Request for Addl Info Re Reactor Bldg Dome Delamination Interim Rept & Suppl 1. ML19319C9901976-06-21021 June 1976 Deficiency Rept Re Hydraulic Snubber Sightgage Leakage. Caused by Improper O-ring or Seal Matl in Sightgage & Poor Workmanship at Reservoir Connection.Sightgage Replacement or Deletion W/Dipstick Being Considered ML19329D5371976-06-11011 June 1976 Forwards 760421 Interim Deficiency Rept,Dome Delamination Separation in Containment Structure Dome Concrete.Requests Informal 760618 Meeting in Bethesda,Md to Discuss Corrective Actions & Proposed Work Schedule.W/O Encl ML19329D6841976-04-21021 April 1976 Deficiency Rept Re Separation in Containment Structure Dome Concrete.Engineers Evaluating Present Condition ML19319C9931976-02-16016 February 1976 Deficiency Rept Re Excessive Pressure Drop in Spring Loaded Stop Check Valves BSV-9,10,67 & 68.Caused by Inadequate Design.Valves to Be Replaced W/Conventional Swing Check Valves,Supplementing 750617 Ltr 1999-10-06 Category:TEXT-SAFETY REPORT MONTHYEARML20217G0191999-10-15015 October 1999
[Table view]Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 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! P. . .o.w. . .e. . .r.
I Lee H. Scott October 10, 1983 President '
l I
4 Mr. Richard C. DeYoung, Director j Office of Inspection and Enforcement i United States Nuclear Regulatory Commission l Washington, D.C. 20555
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)
Dear Mr. DeYoung:
-l l Florida Power Corporation shares with you j the concern over the apparent increase in the scope
.j of fraudulent and substandard activities by some j unscrupulous suppliers. We are totally committed .
j to a high degree of assurance that the public health 't i and safety are being protected and in no way compro-
- j mised through our activities at Crystal River Unit 3.
i
-j We maintain our vigilance in this area j through dealing with well-established, known, and reliable vendors; through surveillance at the vendor 1 facilities; and through renewed training and emphasis in our receiving inspection areas.
We appreciate your encouragement and offer of assistance as appropriate.
i
- Sincerely,
"/ &
! LHS:sg i
j 1
4 8310130136 831010 -
PDR ADOCK 05000302 G pyg (
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i 3201 Thirty-fourth Street South P.O. Box 14042,St. Petersburg, Florida 33733 813-866 5151
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