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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23038A0192023-02-0606 February 2023 Curtiss-Wright Part 21 Notification for Qualtech Np Supplied Eaton TMR5 Timing Relays ML20366A0482020-12-0707 December 2020 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0114, Rev. 1 ML20366A0472020-11-18018 November 2020 Curtiss-Wright 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid Batch 17BLVS293 ML20108F5302020-03-20020 March 2020 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0129, Rev. 0, Test Stand Deficiency - EMD Fuel Injectors P/N H40084720 ML19346H8732019-12-12012 December 2019 Westinghouse Electric Company - Notification of the Potential Existence of Defect Pursuant to 10 CFR Part 21 ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19064A2312019-02-20020 February 2019 Flowserve - Spring Deflection Causing Potential Hang-Up of the Flapper (Disc), Worcester Series 44 Swing Check Valve ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18354A7422018-12-0404 December 2018 Engine Systems, Inc., Submittal of 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 1OCFR21-0123, Rev. 0 - Emo Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML18078A5362018-01-31031 January 2018 Crane Nuclear, Inc. - Interim Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem (Update) ML17311A9092017-10-31031 October 2017 Interim Report for Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem ML17194A8252017-07-11011 July 2017 Part 21 Report Re Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections ML16328A3152016-11-22022 November 2016 Part 21 - Incorrect Capacitor Used on Circuit Boards ML16281A2712016-09-30030 September 2016 Part 21 - Safety Related Component Welding by an Unqualified Welder ML16243A4752016-08-26026 August 2016 Part 21 Safety Related Component Welding by an Unqualified Welder ML16188A3742016-06-30030 June 2016 Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies ML15280A3872015-10-0707 October 2015 Part 21 Report - Electromatic Relief Valve (EMRV) Cutout Switch, Dresden, Units 2 and 3 ML15259A5212015-09-10010 September 2015 Part 21 Report - Potential Failure of Electromatic Relief Valve Cutout Switches ML15253A8592015-09-10010 September 2015 GE-Hitachi Nuclear Energy Americas, LLC - Closure of Part 21 60-Day Interim Report Notification: Potential Failure of Electromatic Relief Valve Cutout Switch ML15169A0082015-06-18018 June 2015 Attachment 1 - Us Plants Potentially Affected ML15169A0092015-06-18018 June 2015 Attachment 2 - 60-Day Interim Report Notification Information Per 21.21(a)(2) ML15169A0102015-06-18018 June 2015 Enclosure 1 - Mfn 15-042 R0 - Description of Evaluation ML15169A0072015-06-17017 June 2015 Part 21 60-Day Interim Report Notification: Potential Failure of Electromatic Relief Valve Cutout Switch ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14337A0932014-11-26026 November 2014 Part 21 - Type 67 Afr Regulators with Improperly Dedicated Diaphragm Valve Seats ML14329A7052014-11-24024 November 2014 Notification of Potential Part 21 - Type 67 Afr Regulators with Improperly Dedicated Diaphragm Valve Seats ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14329A0632014-11-19019 November 2014 Notification of Potential Part 21 Re Lack of Proper Power Supply Indication ML14275A1622014-09-25025 September 2014 Notification of Potential Part 21 Report - Electromatic Relief Valve Excessive Wear ML14261A1502014-09-17017 September 2014 Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14241A2382014-08-27027 August 2014 Interim Report -10CFR 21 Evaluation Regarding Potential Deficiencies in Ensuring Customer Wall Thickness Requirements Were Met ML14252A3092014-08-27027 August 2014 Interim Report -10CFR 21 Evaluation Regarding Potential Deficiencies in Ensuring Customer Wall Thickness Requirements Were Met ML14226A6412014-08-14014 August 2014 Written Notification to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14213A0102014-07-28028 July 2014 Notification of Potential Part 21 Report - Defects on 2 Inch Bonnets ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14210A0082014-07-18018 July 2014 Part 21 Report - Notification of Defects on 2 Inch Bonnets ML14197A3802014-07-14014 July 2014 Part-21 Notification-Assembly Errors During Breaker Refurbishment ML14147A3702014-05-23023 May 2014 Pentair Valves and Controls - Interim Report -10CFR 21 Evaluation Regarding Potential Deficiencies in Ensuring Customer Wall Thickness Requirements Were Met ML14129A4362014-05-0808 May 2014 Interim Report -10CFR 21 Evaluation Regarding Potential Deficiencies in ASME Code Required Valve and Component Testing ML14072A3282014-03-13013 March 2014 Part 21 60-Day Interim Report Notification Re Unseating of Valve Spring on SSPV ML14072A3262014-03-13013 March 2014 Enclosure 2: Description of Evaluation ML13284A0842013-10-0303 October 2013 Deficiency Report from Baldor Electric Co., on Nuclear Nonconformance Event No. 49302 ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13142A3292013-05-0606 May 2013 Notification of Potential Part 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0109, Rev. 0 ML13127A0142013-05-0303 May 2013 Part 21 Report - Fuel Injectors Failed Pressure Test ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve 2023-02-06
[Table view] Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 CP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 2024-02-02
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RSCC Wire & Cable LLC 20 Bradley Park Road East Granby, CT 06026 USA A Division of RSCC Cable Group Tel: 860-653-8300 ISO 9001 Reg istered Fax: 860-653-8420 July 20, 2012 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Final Report on RSCC Wire & Cable LLC's Firezone 3HR 600V Cables
Reference:
Initial Notification of 10CFR Part 21 Defect/
Failure to Comply dated May 30, 2012
Dear Sir or Madam:
RSCC Wire & Cable LLC has prepared and approved TR-1210 Rev 0, dated 7/19/12, entitled "Firezone 3HR Installation Guidelines" in response to the referenced Initial Notification dated May 30, 2012 and RSCC's Corrective Action Request 12-19. Copies of TR- 1210 Rev 0 have been forwarded to Comanche Peak Nuclear Power Plant and the Dresden Nuclear Power Plant for their determination of whether any installed Firezone 3HR cables could cause a substantial safety hazard.
Sincerely, Richard Brown Quality Assurance Manager
- I
- ~jZ9
RSCC WIRE & CABLE LLC Firezone 3HR Installation Guidelines TR-1210 Rev 0 7/19/2012 v
Prepared By: Robert L. Konnik Approved By: Robert A. Gehm Chief Technology Officer Applications Engineering Manager 20 Bradley Park Road WWW.RSCCNuclearCable.com Phone: (860) 653-8300 East Granby, CT 06026 Fax: (860) 653-8301
Introduction This report covers basic installation recommendations for RSCC Firezone 3HR cable.
The focus is on special instructions for this fire rated cable. All standard installation precautions for a tray cable should be followed. It is assumed that the cable has been properly sized and the installation properly designed. Since not all situations can be covered, please call the RSCC Engineering Department for more specific information.
The National Electrical Code as well as all applicable rules and regulations, including federal, state, local, and municipal laws should be followed.
Tested Configuration Firezone 3HR is qualified for 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> circuit integrity to UL 2196. The smallest conductor size qualified is 12 AWG with a minimum of 2 conductors. The cable must be installed in accordance with this installation guide which takes into account the manner that it was tested and qualified.
Cable Installation Cable installed outside the fire zone follows the same guidelines as any other tray cable and should be installed per the National Electrical Code. This includes installing Firezone 3HR cable in tray or conduit with halogenated cable.
In the fire zone, precautions must be taken to ensure other aspects of the system do not limit the survivability of the cable. This includes conduit and tray support mechanism are fire rated for the installation and that cable splices are not permitted unless cable splicing is conducted within an equivalent fire rated room.
Cable installed in conduit within the fire zone should comply with the following:
- 1) Firezone 3HR cable must be installed in a dedicated stainless steel rigid metal conduit of minimum conduit sizing of 1 1/2 inches in diameter with no other halogenated products i.e. cables and the conduit support spacing should not exceed 72 inches on center.
- 2) Firezone 3HR cable should not be installed in galvanized rigid metal conduit unless the galvanized rigid metal conduit is protected by an approved thermal barrier for the specific fire rating within the fire zone. The galvanized steel conduit would likely limit the cable survivability to less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Page 2 of 6
a *4 -
- 3) Firezone 3HR cable must not be installed in conduits that contain halogenated products i.e. cables unless the conduit is protected by an approved thermal barrier for the specific fire rating Within the fire zone.
- 4) The maximum conduit fill ratio for Firezone 3HR cable is 30%.
Cable installed in tray within the fire zone should comply with the following:
- 1) Firezone 3HR cable must be installed within a flexible or rigid stainless steel metal conduit on stainless steel or galvanized steel tray of the following types:
(solid bottom, open ladder or vented trough). Tray support spacing should not exceed 48 inches on center. Conduit fill ratio must not exceed 30%.
- 2) Firezone 3HR cable should not be installed in aluminum cable trays as the tray will melt in a fire and may limit the cable survivability.
- 3) Firezone 3HR cable must not be installed in cable trays that contain halogenated products i.e. cables unless the Firezone 3HR cable is installed within a flexible or rigid stainless steel metal conduit which provides isolation/separation from the halogenated cables and the flexible or rigid stainless steel metal conduit must not exceed 30% fill ratio.
- 4) Firezone 3HR cable cannot be installed in tray of any type unless the cable is installed within a flexible or rigid stainless steel metal conduit and conduit fill ratio must not exceed 30%.
Penetrations within the fire zone should comply with the following:
- 1) Firezone 3HR cable can run through concrete wall penetrations in rigid stainless steel conduits without halogenated products i.e. cables. Conduit fill ratio must not exceed 30%.
- 2) Firezone 3HR cable can run through concrete wall penetrations in rigid metal conduits with halogenated products i.e. cables provided the Firezone 3HR cable is installed within flexible or rigid stainless steel conduit without halogenated products i.e. cables through the wall penetration. Conduit fill ratio must not exceed 30%.
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Additional Installation Information Pulling Lubricants The following pulling lubricants may be used with Firezone 3HR cable:
Polywater LZ, CLR and Dyna Blue may be used with cables listed in this system.
Bending Radius Minimum permanent training radius is 4 times the outside diameter of the cable for cables up to 1 inch in diameter, 5 times the cable outside diameter for cables from 1.001 inch to 2 inch and 6 times the cable outside diameter for cables larger than 2 inch in diameter. Recommended pulling radius is 2 times the permanent training radius.
Conductor Tensile Strength It is assumed that the method used to attach the cable to the pull rope transfers all forces to the conductor. The tensile strength of the conductor then becomes a limiting factor for the force that can be applied. Copper elongates slightly before breaking, which changes the resistance characteristics. A safety factor is used to prevent this, as well as other items. This tension is determined by the following formula:
Tc = KxFx kcmilT Tc = Maximum allowable tension based on conductor tensile strength (pounds)
K = Factor based on material strength with a safety margin; 8 for annealed copper F = Factor to account for possible unequal tension distribution kcmilT = The sum of the circular mil area of all conductors in thousand circular mils (kcmil)
Page 4 of 6
When all conductors are the same size, the equation becomes:
Tc= K x F x kcmil x N kcmil = Circular mil area of one conductor in thousand circular mils (kcmil)
N = Total number of conductors pulled The tension distribution factor (F) is 1 for a single multiconductor cable, 0.8 when pulling more than one cable of equal conductor size, and 0.6 when pulling multiple cables of unequal conductor size. Ground wires should not be considered in these computations.
Cable Attachment Limit The maximum allowable tension is~also limited by the ability of the device used to connect the cable to the pull rope to withstand the forces applied. When pulling by gripping the conductors with a pulling eye or bolt, the maximum tension is usually limited to 10,000 pounds. This is dependent upon the pulling eye or bolt used and the method of application. The manufacturer's recommendations should be followed.
When the conductors are gripped with a properly sized and applied basket weave grip, the limit is 1000 pounds. This is based upon the hoop stress applied with a basket grip and the cable construction.
Sidewall Pressure When a cable is pulled around a bend, radial force is exerted on the insulation, and jacket as the cable is pressed against the inner arc of the bend (see Figure Below).
This is referred to as sidewall pressure and is expressed as pounds per foot of radius.
Tension Pressure Page 5 of 6
Sidewall pressure is important in cable pulling calculations for two reasons. The first is its increase in the total pulling tension due to greater pressure between the cable and the bend. The second is its crushing effect upon the cable insulation and the possibility of permanent damage to the insulation and/or the cable jacket if excessive sidewall pressures are permitted. Sidewall pressure is usually the determining factor when establishing maximum allowable pulling tension for large conductor sizes.
The maximum value for sidewall pressure depends on the cable design. For Firezone 3HR the sidewall pressure should not exceed 300 pounds per foot of bend. The formula for sidewall pressure for a single cable is as follows:
Tp= SWPxR Tp = Maximum allowable tension which will not exceed the sidewall pressure limit in pounds*
SWP = Sidewall pressure limit in pounds per foot R = Radius of bend in feet
- This value may be more limiting than the maximum tension Tp based on conductor strength. The lower value of the two governs.
Minimum Installation Temperature Handling or pulling cables in extremely low temperatures can cause damage to the cable shielding, jacketing, or insulation. To prevent damage of this nature, cables should not be removed from reels or coils, handled, or pulled, without first warming in a heated area (at least 50'F/1 00C) for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to installation. Cable should be installed as quickly as possible after warming. Minimum installation temperatures will vary depending upon the type of insulation and jacket material used on the cable. A value of -10°C (140 F) is typically recommended for all cables because this will allow for a considerable degree of rough handling.
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RSCC WIRE & CABLE LLC CORRECTIVE ACTION REQUEST CAR No.: 12-19 Issue Date: 5/30/12
-1 Robert Gl Date Response Due: 6/29/12 Responsible Manager: Robert Gehm _l Initiated By: Richard Brown Supplier: N/A Authorized By: Richard Brown Internal: Utility Source Document: 10CFR21 Audit No.: N/A Reportable per (if yes, see 10 CFR 21 procedure No Yes X 010SP004)
Description of Nonconforming Condition:
Ref.: TXU PO# S 0697703 6Sl (RSCC SO# 93435)
Firezone 3HR 600V cables were installed at the Comanche Peak Nuclear Power Plant in a configuration inconsistent with the manner in which the cables were tested and qualified to UL 2196. As a result, under fire conditions, the Firezone 3HR cables may not function as tested and qualified. No documented installation procedures are currently available for Firezone 3HR cables.
Root Cause:
Cable installation instructions, UL FHIT 31 Electrical Circuit Protective Systems, provided prior to delivery were insufficient to permit adequate installation in trays and conduit to ensure that the Firezone 3HR cable will function as tested and qualified under fire conditions during its installed qualified life.
LResponse By: Robert Gehm Date: 6/18/12 Immediate Action to be Taken:
Detailed installation guidelines for Firezone 3HR cables will be prepared and issued to purchasers that will ensure that cable qualification is maintained throughout its qualified life.
Response Robert Gehm Date: 7/19/12 Verification of Immediate Action Taken:
An installation guide, TR-12010 Rev 0, Dated 7/19/2012, Installation Guidelines for Firezone 3HR was written and approved. (R. Brown verified on 7/20/2012)
Corrective Action to be Taken to Prevent Recurrence:
The installation guideline report, TR-1210, will be provided prior to shipment of any Firezone 3HR product to customer. Copies of TR-1210 Rev 0 will be forwarded to Comanche Peak Nuclear Power Plant and Dresden Nuclear Power Plant.
Response By: Robert Gehm Date: 7//20/12 Verification of Effectiveness:
TR-1210 Rev 0 was forwarded to Comanche Peak Nuclear Power Plant and Dresden Nuclear Power Plant on 7/20/12.
Form CAR Rev 3 8/4/10
RSCC WIRE & CABLE LLC CORRECTIVE ACTION REQUEST Closed By: [Richard Brown Date:- 7/20/12 Distribution: R. Brown, D. Chalk, R. Gehm, R. Konnik, M. Mennone, D. Murphy, S. Sandberg, M.Valaitis Form CAR Rev 3 8/4/10