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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 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 ML21014A2342020-12-0707 December 2020 Fourth Interim Notification Per 10 CFR Part 21 Re 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 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 ML19199A0342019-07-0505 July 2019 Lake Engineering Co., Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 ML19071A1122019-03-0101 March 2019 Lake Engineering Co., Corrected Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 11KLVS146 Final Report, Per 10 CFR Part 21 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 ML18295A1992018-09-24024 September 2018 Lake Engineering - Second Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 ML18211A3022018-07-25025 July 2018 Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11 KLVS146 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) 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 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 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 ML17243A1362017-08-28028 August 2017 Fisher Information Notice, (FIN) 2017-04 - Erroneous Rotary Seating Torque Calculation in Flowscanner Software ML17212A6282017-07-24024 July 2017 Lake Engineering Co. - Potentially Degraded Snubber SF1154 Hydraulic Fluid Second - Interim Notification Per 10 CFR Part 21 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 ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling 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 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 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 ML16111A4202016-04-0808 April 2016 Part 21 Report No. P21-04302015, Rev. 1 Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays, Per Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML15159A5682015-04-30030 April 2015 Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14303A2582014-10-27027 October 2014 10 CFR Part 21 Notification of an Error in Powerplex MCPR and LHGR Limit Input for Browns Ferry, Unit 2 ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX 2023-12-14
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 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 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule 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 ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision 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 NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) 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 ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles 2024-02-01
[Table view] |
Text
GE Hitachi Nuclear Energy
March 22, 2010 MFN 10-123
Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Part 21 60-Day Interim Report Notification: Failure of HPCI Turbine Overspeed Reset Control Valve Diaphragm
Reference:
NRC Event Notification Report 45227, HPCI Inoperable Due to Oil Leak in Mechanical Trip Hold Valve NRC Event Notification Report issued July 24, 2009 NRC Event Notification Report retracted September 23, 2009
This letter provides information concerning an evaluation being performed by GE Hitachi Nuclear Energy (GEH) regarding the failure of a HPCI Turbine Overspeed Reset Control Valve Diaphragm discovered at Browns Ferry Unit 1. This condition was the subject of the referenced Event Report submitted by the Tennessee Valley Authority on July 24, 2009 and retracted on September 23, 2009. As stated herein, GEH has not concluded that this is a reportable condition in accordance with the requirements of 10CFR 21.21(d) and continued testing and evaluation is required to determine the root cause of this failure.
A description herein GEH includes in the investigation of this failure at Browns Ferry one additional diaphragm that was manufactured in the same lot (May, 15, 2006) as the failed diaphragm provided to Browns Ferry. All of the diaphragms from this lot have been returned to GEH for evaluation, including the diaphragm that failed.
The information required for a 60-Day Interim Report Notification per §21.21(a)(2) is provided in Attachment 3. The commitment for follow-on actions is provided in Attachment 3, item (vii).
Dale E. Porter GE-Hitachi Nuclear Energy Americas LLC Safety Evaluation Program Manager 3901 Castle Hayne Rd., Wilmington, NC 28401 USA T 910 819-4491 Dale.Porter@GE.Com MFN 10-123 Page 2 of 2 If you have any questions, please call me at (910) 819-4491.
Sincerely, Dale E. Porter Safety Evaluation Program Manager
GE-Hitachi Nuclear Energy Americas LLC
Attachments: 1. Description of Evaluation
- 2. US Plants With GEH supplied diaphragms
- 3. 60-Day Interim Report Notification Information per §21.21(a)(2)
cc: S. S. Philpott, USNRC J. F. Harrison, GEH J. G. Head, GEH P. L. Campbell, GEH Washington
A. A. Lingenfelter, GNF PRC File DRF Section No. 0000-0115-3176
MFN 10-123 Page 1 of 2 Attachment 1
- Description of Evaluation Summary: GE Hitachi Nuclear Energy (GEH) became aware of a failure of a High Pressure Coolant Injection (HPCI) Turbine Overspeed Reset Control Valve Diaphragm (GEH Part Number Q25471-A2) at a domestic BWR. The evaluation of this failure has not determined the root cause of the failure or determined if a deviation from technical requirements was the cause of this failure. Additional testing and evaluation is required to determine if this is an isolated failure or represents a latent design error, manufacturing defect, or if the failure is a random occurrence.
GEH issues this 60-Day Interim Report in accordance with the requirements set forth in 10CFR 21.21(a)(2) for the delivered lot of diaphragms from which the identified failure occurred so that continued testing and subsequent evaluations can be completed.
Background GEH initiated a 10CFR Part 21 evaluation due to a reported failure of a GEH supplied High Pressure Coolant Injection (HPCI) Turbine Overspeed Reset Control Valve Diaphragm (part number Q25471-A2) that failed at a domestic BWR. This failure was the subject of an Event Report filed with the NRC; therefore, the NRC is aware of this failure. The HPCI turbine overspeed reset control valve is a Robertshaw Model VC-210. The diaphragm is part of that Robertshaw valve. The utility, where the failure occurred, attributed the failure of the diaphragm to a lack of uniformity in reinforcing material throughout the diaphragm that may be regarded as a manufacturing defect. GEH is collaborating with the supplier of the diaphragm and Robertshaw to determine/confirm the root cause of the diaphragm failure. The failed diaphragm was one of three diaphragms purchased from Robertshaw that were supplied from a single lot manufactured on 5/15/2006. GEH has recalled and received these three diaphragms, which includes the failed diaphragm.
Safety Basis Failure of the HPCI turbine overspeed reset control valve's diaphragm could result in a loss of lube and control oil through the failed diaphragm. This could result in a failure of the HPCI System resulting in a reduction in reactor vessel level below the top of active fuel during an accident. A Substantial Safety Hazard would not be created since no fuel damage would occur due to the availability of redundant ECCS systems such as ADS.
Corrective/Preventive Actions GEH is collaborating with the diaphragm supplier and Robertshaw to determine the root cause of the diaphragm failure. Results of this analysis will make it possible to determine if a reportable condition exists within the context of 10CFR Part 21.21(d) and will provide input for the development of a solution to prevent future recurrence. Completion of the 10CFR Part 21 evaluation will be based upon the findings of this root cause analysis. Completion of this evaluation is scheduled for July 23, 2010.
Refer to Attachment 3, Item (vii) for corrective actions.
MFN 10-123 Page 1 of 1 Attachment 2
- US Plants With Subject Diaphragms Utility Plant X Florida Power and Light Duane Arnold X Tennessee Valley Authority Browns Ferry 1 - 3
MFN 10-123 Page 1 of 2 Attachment 3 Day Interim Report Notification Information per §21.21(a)(2)
(i) Name and address of the individual providing the information: Dale E. Porter Safety Evaluation Program Manager, GE Hitachi Nuclear Energy 3901 Castle Hayne Road, Wilmington, NC 28401
(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States that contains a deviation or failure to comply: The basic component that failed is a HPCI Turbine Overspeed Reset Control Valve Diaphragm; GE Hitachi Nuclear Energy Part Number Q25471-A2.
(iii) Identification of the firm constructing the facility or supplying the basic component which contains a deviation or failure to comply: GE Hitachi Nuclear Energy (iv) Nature of the defect or safety hazard which could be created by such a deviation or failure to comply:
GE Hitachi Nuclear Energy HPCI Overspeed Turbine Reset Control Valve Diaphragm Q25471-A2, failed for reasons yet to be determined, in the area adjacent to the outer edge of the diaphragm at a preformed radius. This failure could result in a failure of the HPCI System resulting in a reduction in reactor vessel level below the top of active fuel during an accident. A Substantial Safety Hazard would not be created since no fuel damage would occur due to the availability of redundant ECCS systems such as ADS.
(v) The date on which the information of such a deviation or failure to comply was obtained:
A Potential Reportable Condition Evaluation in accordance with 10CFR Part 21 was initiated on January 22, 2010.
MFN 10-123 Page 2 of 2 (vi) In the case of a basic component which contains a deviation or failure to comply, the locations of all such components in use or being supplied: Diaphragms from a single vendor lot, fabricated on May 15, 2006, are the primary suspect component and are the subject of this 60-Day Interim Report as listed below.
Plant Quantity Ship Date Part Number Duane Arnold 1 7/5/2007 Q25471-A2 Browns Ferry 2 10/5/2006 Q25471-A2 (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 (note, these are actions specifically associated with the identified deviation or failure to comply):
GEH Component Engineering is collaborating with the diaphragm supplier and Robertshaw to determine the root cause of the diaphragm failure. Results of this analysis will make it possible to determine if a reportable condition exists within the context of 10CFR Part 21.21(d), and will provide input for the development of a solution to prevent future recurrence. Completion of the 10CFR Part 21 evaluation will be based upon the findings of this root cause analysis. Completion of this evaluation is scheduled for July 23, 2010.
(viii) Any advice related to the deviation or failure to comply about the facility, activity, or basic component that has been, is being given to purchasers or licensees:
The failed diaphragm and all additional diaphragms from the suspect lot have been recalled by GEH for further analysis. All diaphragms from the suspect lot have been received by GEH. Any additional diaphragm failures should be reported to GEH.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
There are no early site permit concerns.