|
---|
Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML22075A2192021-11-29029 November 2021 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries 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 ML19210D4342019-07-11011 July 2019 Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 ML19190A0432019-06-28028 June 2019 Discusses Proprietary Information for Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19158A1312019-05-31031 May 2019 Paragon Energy Systems LLC -10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18159A0392018-06-0606 June 2018 National Technical Systems (Nts) - Potential Part 21 on Dedicated Items Not Available for Pmi Testing (NUPIC) ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML16020A4772015-12-23023 December 2015 MPR Associates, Inc., - Part 21 Report, MPR Emergency Diesel Engine Timing Module Failure, Per E.I. Hatch, Unit 2 ML16004A0302015-12-23023 December 2015 MPR Associates, Inc. - Part 21 Report, MPR Emergency Diesel Engine Timing Module Failure, Per E.I. Hatch, Unit 2 ML15223B2662015-08-0707 August 2015 Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15134A0172015-05-0101 May 2015 Part 21 Report Regarding Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML14309A5292014-10-31031 October 2014 Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc., Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML13260A0772013-09-12012 September 2013 10 CFR Part 21 Interim Report - General Electric (GE) Hitachi Nuclear Energy - Sbm Type Manual Switch ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13010A5182013-01-0909 January 2013 Part 21 Interim Report on the Failure of an Emergency Diesel Generator Excitation System ML13008A3212013-01-0404 January 2013 Anti-Rotation Pin Failure in Anchor Darling (Flowserve) Double Disc Gate Valve ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12255A0532012-09-0707 September 2012 Part 21 Interim Report - Steam Generator Tube Wear ML12255A0542012-09-0707 September 2012 Part 21 - Steam Generator Tube Wear Adjacent to Retainer Bars ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12109A0942012-04-13013 April 2012 Part 21 Interim Report - Steam Generator Tube Wear ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1025201572010-08-16016 August 2010 Initial Exam 2010-301 Final Administrative Documents 2024-01-23
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML22208A0042022-06-17017 June 2022 Nutherm International, Inc., USNRC 10CFR Part 21 Notification Reference: Arnold Magnetics Power Supply Part Number PBM-24-106 ML22153A0792022-04-0707 April 2022 10CFR Part 21 Notification for Curtiss-Wright Supplied RCS-Dresser Actuator P/N: SURE-24-10-4 ML21294A0292021-10-0404 October 2021 Flowserve Part 21 Notification for Limitorque Supplied DC Motor ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML20049A0742020-01-31031 January 2020 Fairbanks Morse Part 21 Re Fm Notification Report Serial Number 20-01 Fairbanks Morse ML20028D3802020-01-13013 January 2020 10CFR21 Notification for Ashcroft 2-1/2 & 3-1/2 1009, 63mm 2008, 63mm & 100mm 1008 Industrial Gauges, Weksler 3-1/2 Regal Gauges ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) 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 ML19253A0532019-08-29029 August 2019 Azz Nuclear - Report of Potential 1O CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19158A1312019-05-31031 May 2019 Paragon Energy Systems LLC -10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19168A0122019-05-31031 May 2019 Paragon Energy Solution LLC-10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19120A1062019-04-17017 April 2019 Interim Report of Potential 10 CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19101A0972019-04-0404 April 2019 Weir Valves & Controls USA, Inc. Part 21 Written Notification - Event Number: 53973 - 24 Class 150 Globe Alve for RHRSW HX Isolation MOV, E1150F068B at Detroit Edison - Fermi, Unit 2, Experienced Two Stem Failures ML19087A2512019-03-11011 March 2019 Weir Valves & Controls USA, Inc. - 10 CFR Part 21 Report: 24 Class 150 Globe Failed to Fully Open Due to the Failure of the Anti-Rotation Key ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18341A2472018-12-0606 December 2018 Mirion Technologies - 10 CFR Part 21.21 Report Re Relays Defect 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 ML18087A0032018-03-21021 March 2018 Crane Nuclear, Inc. - Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve (Updated) ML18079A0142018-03-0606 March 2018 Crane Nuclear, Inc., 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl I0x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML18003A2602017-12-19019 December 2017 Crane Nuclear, Inc. - 10 CFR Part 21 Notification of Defect on Weak Link Analysis for Chapman Gate Valve Figure L900, Item #18, Drawing CC05307, Revision B 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 ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17039A5692017-02-0303 February 2017 Final Part 21 Report on Defect, Potential for Test Induced Damage 0867F Series Main Steam Safety Relief Valves ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML16243A4742016-08-26026 August 2016 Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16238A1862016-08-15015 August 2016 Update - Report of Potential l0CFR Part 21, Allen Bradley Timing Relay Model 700RTC-NRC Event Number 51030, Accession Number ML15134A016 ML16232A6042016-08-15015 August 2016 Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML16196A0642016-07-10010 July 2016 Part 21 Report - Materials Not Properly Dedicated 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 ML16154A2072016-05-26026 May 2016 Part 21, Azz/Nli Nuclear Logistics, Inc., Potentially Unqualified Component in Certain Allen Bradley Timing Relays Model 700RTC ML16194A1992016-05-25025 May 2016 Azz/Nli - Update - Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML16139A8322016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close 2023-12-14
[Table view] |
Text
07/08/2015 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 1 Part 21 (PAR) Event# 51206 Rep Org: CRANE NUCLEAR, INC. Notification Date I Time: 07/08/2015 07:49 (EDT)
Supplier: CRANE NUCLEAR, INC. Event Date / Time: 07/07/20 15 (CDT)
Last Modification: 07/08/2015 Region: 3 Docket #:
City: BOLINGBROOK Agreement State: Yes County: License #:
State: IL NRC Notified by: JASON KLEIN Notifications: ANN MARIE STONE R300 HQ Ops Officer: STEVE SAN DIN GERALD MCCOY R200 Emergency Class: NON EMERGENCY MARK HAIRE R4DO 10 CFR Section: PART 2 1/50.55 REACTORS EMAIL 21.21(a)(2) INTERIM EVAL OF DEVIATION PART 21 INTERIM REPORT - NOTIFICATION OF PRESSURE SEAL VALVE YOKE MATERIAL COMPLIANCE The following information was received via fax:
"This letter provides interim notification of Crane Nuclear's investigation into ASME Boiler and Pressure Vessel
[B&PV] Section III Code design Pressure Seal Valve orders for yokes with integral hubs acting as retaining rings.
The information required for this notification is provided below:
"(i) Name and address of the individual or individuals informing the Commission.
Jason Klein Sustaining Engineering Manager Rosalie Nava Director Safety and Quality Crane Nuclear 860 Remington Blvd Boling brook, IL 60440
"(ii) Identification of the basic component supplied for such facility or such activity within the United States which may fail to comply or contains a potential defect This is an interim report. Crane Nuclear is currently investigating Pressure Seal Valve orders potentially having misclassified material and non-destructive examination requirements for Yokes with integral hub retaining ring designs. The material requirements are specified per Crane Procedure 03-107 which utilizes ASME B&PV Code
07/08/2015 U.S. Nuclear Regulatory Commission Operations Center Event Report Case N-62-7 as guidance for material classification.
Page 2 L
"(iii) Identification of the firm supplying the basic component which fails to comply or contains a defect.
Crane Nuclear 860 Remington Blvd Bolingbrook, IL 60440
"(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
Crane Nuclear 'Classification of Valve Parts', Procedure 03-107, is guidance for appropriate material and NDE requirements for processing valve and valve part orders. The procedure is based on the ASME Code Case N 7. A yoke incorporating a threaded hub should be treated in the same manner as a threaded retaining ring requiring the material to be purchased Safety Related, ASME B&PV Section II, Part D materials, and required NDE (reference Category 3 valve items per N-62-7). Yokes with integral hubs acting as retaining rings may have been processed to material requirements without required CNI Classification per Procedure 03-107.
"(v) The date on which the information of such defect or failure to comply was obtained.
Crane Nuclear Engineering initiated investigation correspondence to Crane Nuclear Director of Safety and Quality via email correspondence dated Feb 20th, 2015.
"(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.
Crane has yet to determine the extent of Pressure Seal Valve designs sales order numbers (SO#) affected prior to 2001; the following Utility and Sites were supplied non-compliant CNI Procedure 03-107 Classification yokes for the following valve assemblies:
- 1. CNI SO# 24237-01, TVA, Browns Ferry, P.O. 00031943 - Quantity shipped = 1, Chapman, 8 [inch], Figure L953, Class 900, ASME Class 2, 95 Ed., 96 Add., no N stamp
- 2. CNI SO# 39501-.01, Georgia Power, Hatch, P.O. SNG10016537 - Quantity shipped = 3, Crane, 3 [inch], Figure 776U, Class 600, ASME Class 3, 71 Ed., W71 Add.
- 3. CNI SO# 39745-01, Southern California Edison, San Onofre, P .0. 4500456451 - Quantity Shipped = 1, Aloyco, 4 [inch], Figure N5247PSB, Class 900, ASME Class 3, 71 Ed., S73 Add.
"(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
Crane Nuclear has completed sales orders search of Pressure Seal Valve designs with integral retaining ring hubs from 2001 to present identifying a total of 25 orders where three orders are impacted, as identified in part iv of this report (see above). Crane Nuclear is currently investigating sales orders previous to 2001, which will require an additional 30 days to complete (estimated completion date, August 6th, 2015).
Corrective action by Crane Nuclear is to review documentation of supplied material to determine if yokes can be recertified as currently supplied. A revision to Crane Nuclear Procedure 03-107 to add figures reflecting configurations, and clarify classifications with applicable training, is in-process.
"(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
Crane Nuclear is notifying sites affected and are developing a plan to address the valve items.
07/08/2015 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 3
"(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
Not applicable.
"Should you have any questions regarding this matter, please contact Jason Klein, Sustaining Engineering Manager at (630) 226-4953 or Rosalie Nava, Director of Safety and Quality at (630) 226-4940."
JUL. 8.2015 7:49AM NO 122 P, TELE*-lONfE (630) 2264900 1wwwcrflanInQc!C.af.com
- NUCLEAR CRANE NUCLE.AR, INC. 880 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 Date: Xtily 7, 2015 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-001
Subject:
10 CFR Part 21 Interim Report Notification of Pressure Seal Valve Yoke Material Compliance
Dear Sir or Madam:
This letter provides interim notification of Crane Nuclear's investigation into ASME Boiler and Pressure Vessel Section IlI Code design Pressure Seal Valve orders for yokes with integral hubs acting as retaining rings. The information required for this notification is provided below:
(i) Name and address of the individualor individuals informing the Commission.
Jason Klein Sustaining Engineering Manager Rosalie Nava Director Safety and Quality Crane Nuclear 860 Remington Blvd Bolingbrook, IL604.40 (ii) Identificationof the basic component suppliedfor such facility or such activity within the United States which may fail to comply or contains a potentialdefect This is an interim report. Crane Nuclear is currently investigating Pressure Seal Valve orders potentially having misclassified material and non-destructive examination requirements for Yokes with integral hub retaining ring designs. The material requirements are specified per Crane Procedure 03-107 which utilizes ASME B&PV Code Case N-62-7 as guidance for material classification.
(iii) Identification ofthe firm supplying the basic component which fails to comply or contains a defect.
Crane Nuclear 860 Remington Blvd Bolingbrook, It. 60440
('iv} Nature of the defect orfailure to comply and the safety hazard which is createdor could be created by such defect or failure to comply.
Page 1 of 3
JUL. 8,2Q15 7:49AM NO, 122 P. 2 TELEPHONE (630) 226-4900 NUCLEAR CRANE NUCLEAR, INC. 880 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 Crane Nuclear "Classification of Valve Parts", Procedure 03-107, is guidance for appropriate material and NDE requirements for processing valve and valve part orders. The procedure is based on the ASME Code Case N-62-7. A yoke incorporating a threaded hub should be treated in the same manner as a threaded retaining ring requiring the material to be purchased Safety Related, ASME B&PV Section II,Part D materials, and required NDE (reference Category 3 valve items per N-62-7). Yokes with integral hubs acting as retaining rings may have been processed to material requirements without required CNI Classification per Procedure 03-107.
(v) The date on which the information of such defect or failure to comply was obtained.
Crane Nuclear Engineering initiated investigation correspondence to Crane Nuclear Director of Safety and Quality via email correspondence dated Feb 20'*, 2015.
(vi) In the case of a basiccomponent which contains a defect orfoils to comply, the number and location of these components in use at, suppliedfor, being suppijed for, or may be suppliedfor.
manufactured, or being manufacturedfor one or more facilities or activitiessubject to the regulationsin this port.
Crane has yet to determine the extent of Pressure Seal Valve designs sales order numbers (SO#)
affected prior to 2001; the following Utility and Sites were supplied non-compliant CNI Procedure 03-1.07 Classification yokes for the following valve assemblies:
- 1. CNI SO# 24237-01, TVA, Browns Ferry, P.O. 00031943 - Quantity shipped = 1, Chapman, 8", Figure L953, Class 900, ASME Class 2, 95 Ed., 96 Add., no N stamp
- 2. CNI SO# 39501-01, Georgia Power, Hatch, P.O. SNG3.003.6537 - Quantity shipped =3, Crane, 3", Figure 776U, Class 600, ASME Class 3, 71 Ed., W71 Add.
- 3. CNI SO# 3974S-O1, Southern California Edison, San Onofre, P.O. 4500456451) - Quantity shipped = 1, Aloyco, 4", Figure N5247PSB, Class 900, ASME Class 3, 71 Ed., S73 Add.
(vii) The corrective action which has been, is being, or will be token; the name of the individual or organizationresponsiblefor the action; and the length of time that has been or will be taken to complete the action.
Crane Nuclear has completed sales orders search of Pressure Seal Valve designs with integral retaining ring hubs from 2001 to present identifying a total of 25 orders where three orders are impacted, as identified in part iv of this report (see above). Crane Nuclear is currently investigating sales orders previous to 2001, which will require an additional 30 days to complete (estimated completion date, August 6 , 2015).
Corrective action by Crane Nuclear is to review documentation of supplied material to determine if yokes can be recertified as currently supplied. A revision to Crane Nuclear Procedure 03-107 to add figures reflecting configurations, and clarify classifications with applicable training, is in-process.
Page 2 of 3
JUL. 8.2015 7:49AM NJO. 122 P. 3 TELEPHONE (630) 226-4900 NUCLEARt CRANE NUCLEAR, INC. 860 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 (viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
Crane Nuclear Is notifying sites affected and are developing a plan to address the valve items.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
Not applicable.
Should you have any questions regarding this matter, please contact Jason Klein, Sustaining Engineering Manager at (630) 226-4953 or Rosalie Nave, Director of Safety end Quality at (630) 225-4940.
Jason Klein Page 3 of 3