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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 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. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML20134B2301997-01-24024 January 1997 Final Part 21 Rept Re Potential Safety Concern on Matl Used for Fabrication of Permanent Canal Seal Plate.Correpondence W/Fabricator & Matl Supplier Documents Tig Automated Welding Process Used to Fabricate Angle Pieces ML20101N8441996-04-0505 April 1996 Interim Part 21 Rept Re Potential Safety Concern on Matl for Fabrication of Permanent Canal Seal Plate.Licensee Will Provide Final Rept to NRC in Approx Six Months Upon Completion of Evaluation of Welds 3F0295-15, Part 21 Rept Re GE Supplied Constant Voltage Transformers (Cvt).Vendot Supplied FPC W/Instructions on Mod of Cvts Located in Installed VBIT-1D,to Return Output Voltage to Required Values & FPC Modified Cvts1995-02-27027 February 1995 Part 21 Rept Re GE Supplied Constant Voltage Transformers (Cvt).Vendot Supplied FPC W/Instructions on Mod of Cvts Located in Installed VBIT-1D,to Return Output Voltage to Required Values & FPC Modified Cvts ML20080G3271995-01-30030 January 1995 Part 21 Rept Re Furnished Commercial grade/non-safety Related Studs,Nuts & Washers for Use on safety-related Crystal River 5th Yr post-tension Surveillance Program ML20078F5841995-01-27027 January 1995 Part 21 Rept Re Vendor Using Incorrect Acceptance Criteria on Qualification Test Rept & Acceptance Criteria Used Not Not Met by Cvts.Vendor Continues to Seek Resolution of Matter ML20076M8321994-10-28028 October 1994 Submits Followup to 940516 Part 21 Rept Informing of Investigation to Determine Data Supplied in mid-80 Used by Nuclear Utilities to Set Torque Switches in MOV ML20072A7691994-08-0808 August 1994 Interim Part 21 Rept 2 Re Weak Link Analysis for Movs.No Evidence to Support Fact of Erroneous Data Discovered. Investigation Continuing ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20118B2191992-09-23023 September 1992 Suppl to Part 21 Rept Re Potential Deviation in Some Bailey Controls Co 88 Series Modules,Transmitted Via .One Module Found Incapable of Reaching 100% Output at Max Rated Load.Recommends That Circuit Board Assemblies Be Inspected ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101M8921992-06-30030 June 1992 Initial Part 21 Rept Re non-segregated Phase Electrical Bus Duct Mfg in 1972.Initially Reported on 920427.Detailed Calculations Being Done by FPC to Evaluate Momentary Fault Current Against Supplied Ratings of All Bus Sections ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking 3F0288-13, Part 21 Rept Re Degraded Limitorque Motor Operator Valve Leads.Initially Reported on 880212.Caused by Damaged Insulation.Limitorque Contacted for Repair Method.Valves Did Not Have Insulation Type Described in IE Info Notice 87-0081988-02-15015 February 1988 Part 21 Rept Re Degraded Limitorque Motor Operator Valve Leads.Initially Reported on 880212.Caused by Damaged Insulation.Limitorque Contacted for Repair Method.Valves Did Not Have Insulation Type Described in IE Info Notice 87-008 ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced 3F0787-11, Part 21 Rept Re Dresser Pressurizer Safety Valve Not Able to Fully Lift W/Middle Ring Setting of Plus 80.Initially Reported on 870605.Dresser Informed That Middle Ring Would Not Affect Lift or Relief Capabilities of Valve1987-07-24024 July 1987 Part 21 Rept Re Dresser Pressurizer Safety Valve Not Able to Fully Lift W/Middle Ring Setting of Plus 80.Initially Reported on 870605.Dresser Informed That Middle Ring Would Not Affect Lift or Relief Capabilities of Valve ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20155A0281986-03-27027 March 1986 Part 21 Rept Re Crystal River Shaft Fracture.Addl Info Will Be Submitted When Failure Analyses & Recommendations Completed.W/O Stated Encl ML20134M7711985-08-29029 August 1985 Part 21 Rept Re Potential for Four Valves in HPI Lines to Become Inoperable If Postulated Single Failure Resulted in Total Loss of Cable Tray.Six Cables for Two Valves in HPI Line Removed from Tray & Routed Through Separate Conduits ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20085J4111983-10-10010 October 1983 Part 21 Rept Re Apparent Increase in Scope of Fraudulent & Substandard Activities by Unscrupulous Suppliers.Reliability Emphasized ML20065C7241982-09-10010 September 1982 Part 21 Rept Re Contaminants in Snubber Hydraulic Fluid. Initially Reported on 820323.Program Developed in Which Fluid Reservoirs Completely Flushed Prior to Filling W/Fresh Fluid.Containment Snubbers to Be Rebuilt by 821001 ML20040E7851982-01-22022 January 1982 Part 21 Rept Re Cracking of Power Piping Co Hydraulic Snubber Aluminum Adaptor Bushings.Caused by Misapplication of Matls,Resulting in Thermal Expansion.All Reactor Bldg Inside Snubbers Rebuilt.Remaining Snubbers to Be Rebuilt ML20010C6881981-08-0606 August 1981 Interim Deficiency Rept Re Potentially Reportable Diesel Generator Starting Air Sys Design,Initially Reported 810803. 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
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 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 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
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. TELEFXONE (815)727-26 0 g , POST C7Ft2 COX 3339 JOUET,IL 60434 CRANE .
NUCLEAR OPERATIONS CRANE VALVES
- JOUET,IL 60431 August 08,1994 Cocument Control Desk U.S. Nuclear Regulatory Comndssion
' Washington, DC 20555
SUBJECT:
INTERlhi REl4)RT #2 of 10CFR Part 21 Evaluation
REFERENCE:
Crane Letter Dated Afay 16,1994 Gentlemen:
llas letter is afollow-up to the referenced letter, in which Crane Valves Nuclear Operations advised that we were undertaking an investigation to determine of data supplied in the mid-1980's was used by Nuclear Utilities to set torque switches in Afotor Operated Valves.
As described in the Afay correspondence, over 600 issues of Engineering calculations have been generated and the scope of that evaluation is even greater than we initially anticipateil As of this date, we have uncovered no contractual evidence to support thefact that Crane supplied erroneous data to Utilities, since most orders do not specify the objective of our earlier evaluations.
Continuedprogress reports will be provided on this project andyou can direct any questions to my attention at 815 740-7597.
Sincerely, Ronald F. llornyak Afanager Quality Assurance /
. Support Engineering RFII/cs cc: John Carlson Bruce flarry [
Kevin llutchinson i File t l
94081$0206 940B08 PDR ADOCK 05000302 ;
_S PDR
- i CRANE - ALOYCO A UNIT OF CRANE VALVES I
C'RAN E ADMINISTRATIVE 0FFICES P.O. BOX 3339,104 N. CHICAGO ST. JOUET, lL 60434. (815) Tll 2600
- FAX:(815) 727 4246 12 EAST DEVONWOOD . ROME 0VILLE,lL 604411349 . (815)8861710
- FAX:(815)886-9639 ei MANUFACTURING May 16,1994 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20SSS
SUBJECT:
INTERInf REPORT OF 10 CFR PART 21 EVALUA TION
REFERENCE:
WEAK LINK ANALYSIS FOR of0 TOR OPERA TED VAL VES (hf0V's)
Gentlemen:
In accordance with 10 CFR Part 21, Article 21.21 (a) (2), Crane Valves Nuclear Operations (formerly Crane-Aloyco) hereby advises that we are undertaking an evaluation to determine of data supplied in the mid-1980's as Crane-Aloyco "0TC" Reports has been used by Nuclear Utiliths to set torque switches in Af0V's.
At issue is not the analytical methods, but the use of data beyond the intended scope. This .
issue surfaced as a result of review of revised OTC reports supplied to Florida Power Corp.
for h10V's at Crystal River Unit #3.
To date, Crane has generated over 600 OTC reports. Accordingly, the scope of the evaluation will extend beyond the 60 day reporting period of10 CFR Part 21. As part of '
our investigation, we are considering the applicability of reporting requirements in light of '
GL 89-10 and the possibility that this circumstance has already been addressed by other NRC Communications such as IN 92-41 or IN 94-18.
f Crane Valves Nuclear Operations' representatives have meet with technical and licensing representativesfrom Florida Power Corp. on two separate occasions to discuss these issues and to assure that substantial safety hazards are avoided.
We anticipate completion of this evaluation by July 29,1994, at which time the reporting requirements of10 CFR Part 21 Paragraph 21.21 will be satisfied.
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44'o5dooy W 1 l
Page2 Questions concerning thh Interim Report can be directed to our Manager of Developmental Engineering, Mr. Bruce IIarry, at 815-740-7570 or myself at 815 740-7597.
Sincerely, s 7'-
Ronald F. IIornyak Manager QA/ Support Engineering RFII/cs cc: J. Carlson K. Billingsley B. IIarry K. Ilutchinson Ja Teele File
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