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MONTHYEARML0607302642006-03-0707 March 2006 Closure Memorandum: Issue for Resolution 2005-083: Evaluation: Part 21 - Engine Systems - Governor Drive Coupling Element Project stage: Other 2006-03-07
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Category:Memoranda
MONTHYEARML24019A0342024-01-30030 January 2024 Public Meeting Summary - 01-04-2024 - Comanche Peak LRA - Structures Monitoring Program ML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ML23303A0662023-11-0606 November 2023 October 2023 Environmental Scoping Meetings Re Perry Nuclear Power Plant License Renewal Application Meeting Summary Memo ML23303A2032023-11-0101 November 2023 October 24, 2023, Summary of Comment Gathering Public Meeting on Lessons Learned from the ITAAC Hearing Process for Vogtle Units 3 and 4 ML23279A1052023-10-0606 October 2023 Memorandum from the Secretary to the Board and Parties ML22348A0862023-07-25025 July 2023 Finding in Accordance with 10 CFR 52.103(G) That All Acceptance Criteria Are Met for Vogtle Electric Generating Plant, Unit 4 ML23151A1232023-05-31031 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Shearon Harris Nuclear Plant ML23115A0382023-05-0909 May 2023 Summary of Readiness Group Public Meeting on April 20, 2023 ML23115A0662023-05-0101 May 2023 Summary of Public Meeting with Southern Nuclear Operating Company to Have Presubmittal Meeting for Vogtle Electric Generating Plant, Unit 4 IR 05000424/20040252023-04-28028 April 2023 Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375 ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML22214B4882023-02-0808 February 2023 Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 4 ML22355A0322023-01-0303 January 2023 Revised Charter for the Vogtle Readiness Group to Oversee the Transition to Operations for Vogtle Units 3 and 4 ML22334A0812022-12-0101 December 2022 Update to Targeted Inspections, Tests, Analysis, and Acceptance Criteria for Vogtle Electric Generating Plant Unit 4 ML22322A1672022-11-28028 November 2022 Summary of 11/15/2022 Public Meeting on Lessons Learned ML22304A1912022-11-23023 November 2022 Aging Management Audit Plan Regarding the License Renewal Application Review ML22237A0782022-08-0505 August 2022 American Nuclear Insurers, Notification of Change in the Number of Power Reactors in the Secondary Financial Protection (SFP) Program ML20290A2812022-08-0101 August 2022 103g - Final Memorandum ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22130A0302022-05-0909 May 2022 Summary of Public Meeting on 2021 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20220350 ML22123A0652022-05-0202 May 2022 Public Meeting Summary Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 50-424, 50-425, 52-025, 52-026, Meeting Number 20220330 ML22075A3592022-03-17017 March 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21337A0032021-12-0707 December 2021 Summary of Vogtle Readiness Group Public Meeting on December 2, 2021 ML21322A1502021-12-0202 December 2021 Summary of November 10, 2021 Public Meeting with Southern Nuclear Operating Company ML21316A0692021-11-22022 November 2021 November 4, 2021 Summary of Public Meeting with Southern Nuclear Operating Company ML21259A1492021-10-26026 October 2021 CPNPP, Unit Nos. 1 and 2 - Meeting Summary for Environmental Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21280A2962021-10-22022 October 2021 Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150) ML21295A0882021-10-21021 October 2021 Fiscal Year 2021 Research and Test Reactors Inspection Program Completion Status ML21288A0392021-10-18018 October 2021 September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor ML21259A1402021-10-0505 October 2021 Meeting Summary for Safety Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21230A0102021-08-24024 August 2021 Summary of Public Meeting with Southern Nuclear Operating Company on August 12, 2021 ML21209A0222021-07-29029 July 2021 Closed Predecisional Enforcement Conference with River Bend Station ML21154A2772021-07-20020 July 2021 Summary of a Public Meeting with Southern Nuclear Operating Company on May 27, 2021 ML21194A0402021-07-20020 July 2021 Summary of June 24, 2021 Public Meeting with SNC ML21190A0622021-07-16016 July 2021 Summary of July 8 2021 Public Meeting to Discuss Late-Filed Allegation Process for Vogtle Electric Generating Plant Units 3 and 4 ML21194A0392021-07-16016 July 2021 July 8, 2021 Summary of Public Meeting with Southern Nuclear Operating Company ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21176A1292021-06-25025 June 2021 CPNPP FFD Inspection Doc Request 2021 ML21174A0942021-06-23023 June 2021 Reactor Trip on June 7, 2021 - Management Directive 8.3 Screening ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21131A1472021-05-11011 May 2021 Public Meeting Summary 2020 Annual Assessment Meeting Regarding Brunswick Steam Electric Plant, Docket Nos. 50-325 and 50-324; and Shearon Harris Nuclear Power Plant, Docket No. 50-400, Meeting Number 20210385 ML21124A0052021-05-10010 May 2021 Memo for Environmental Pre-Submittal Meeting for Initial License Renewal Application ML21124A2032021-05-0606 May 2021 ASME Alternative ALT-16 Pre-submittal Meeting Summary 4-29-21 ML21123A1432021-05-0505 May 2021 April 22, 2021, Summary of a Public Meeting with Southern Nuclear Operating Company RA-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits2021-03-15015 March 2021 Notification of Permit Revision Request Regarding Copper and Zinc Limits 2024-01-08
[Table view] Category:Safety Evaluation
MONTHYEARML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23243B0492023-12-19019 December 2023 VEGP Units 3 and 4, Safety Evaluation, LAR-22-002, TS 3.8.3 Inverters Operating, Completion Time Extension - Enclosure 3 ML23335A1232023-12-19019 December 2023 Safety Evaluation Final Integrated Plan ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 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 ML23326A1362023-11-28028 November 2023 Safety Evaluation for Amendment 195 & 192 for TS 3.1.9 More Restrictive Action ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23159A1022023-07-31031 July 2023 Safety Evaluation - Vogtle Electric Generating Plant, Unit 3 Amendment No. 192 (LAR 23-001) ML23158A0182023-07-31031 July 2023 Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML23158A2062023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Safety Evaluation ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology ML23109A0702023-05-0404 May 2023 Enclosure - Safety Evaluation for VEGP3&4 ISI1-ALT-18 ML23072A2742023-05-0101 May 2023 Enclosure 3 - LAR 22-005 Safety Evaluation ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23095A2962023-04-14014 April 2023 Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds (Vegp 3&4-Isi1- Alt-17) ML23095A2972023-04-14014 April 2023 Enclosure - VEGP 3&4-ISI1-ALT-17 Safety Evaluation ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23037A0912023-02-0808 February 2023 Safety Evaluation - Vogtle Unit 3 Amendment No. 190, Tech Spec Exceptions for In-Containment Refueling Water Storage Tank Operability Prior to Initial Criticality (Exigent Circumstances) ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML23013A2202023-01-13013 January 2023 Safety Evaluation for License Amendment No. 189 Tech Spec Limiting Conditions for Operability Reqs for Auto Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22284A1332022-11-22022 November 2022 LAR-22-003 U4 Electrical ITAAC Consolidation Amendment Safety Evaluation ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22286A1252022-11-16016 November 2022 Issuance of Amendments Nos. 217 & 200 Regarding Revision to Technical Specifications to Adopt TSTF-283-A, Revision 3, Modify Section 3.8 Mode Restriction Notes ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22265A1802022-09-27027 September 2022 Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML22259A1822022-09-22022 September 2022 Request for Proposed Inservice Testing Alternative ALT-VR-01 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22249A0922022-09-14014 September 2022 Enclosure - Safety Evaluation the Requirements of the ASME Code for Main Turbine System Valve Testing, VEGP 3&4-IST-ALT-02 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 2023-09-29
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March 7, 2006 MEMORANDUM TO: Mary Jane Ross-Lee, Chief Operating Experience Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation FROM: Eric J. Benner, Team Leader /RA/
Clearinghouse Team Operating Experience Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
CLOSURE MEMORANDUM: ISSUE FOR RESOLUTION 2005-083:
EVALUATION: PART 21 - ENGINE SYSTEMS - GOVERNOR DRIVE COUPLING ELEMENT The staff from Operating Experience Branch (IOEB) and Component Performance Branch (CPTB) of Office of Nuclear Reactor Regulation (NRR) have completed their evaluation of the Issue for Resolution (IFR) 2005-083: Evaluation: Part 21 - Engine Systems - Governor Drive Coupling Element. Based on staffs review of the information provided by the licensee (ADAMS Accession Number ML052650354) and the information received from potentially affected licensees - Grand Gulf, River Bend, Perry, Vogtle, Shearon Harris, and Comanche Peak, the staff concludes that the issue of governor drive coupling element has adequately been investigated by the supplier and corrected by the affected licensees, and is not of safety-significance. Staff concludes that all the affected plants have taken timely and appropriate actions to replace potentially affected coupling elements.
Additionally, this operating experience has been captured in the Reactor Operating Experience database for future tracking and trending purposes.
Based on the staffs evaluation, the Operating Experience Branch has closed IFR 2005-083, and associated TAC MC8519, in accordance with NRR Office Instruction LIC-401.
Enclosure:
Staff Evaluation of Issue for Resolution 2005-083: Evaluation: Part 21 - Engine Systems -
Governor Drive Coupling Element.
CONTACTS: Omid Tabatabai, NRR/DIRS/IOEB 301-415-6616 Steven Unikewicz, NRR/DCI/CPTB 301-415-3819
ML060730264 OFFICE IOEB:DIRS CPTB:DCI BC:CPTB:DCI TL:IOEB:DIRS NAME OTabatabai SMUnikewicz SSLee EJBenner DATE 3/6/06 3/6/06 3/7/06 3/7/06 Staff Evaluation of the Issue for Resolution (IFR) 2005-083, Part21- Engine Systems - Governor Drive Coupling Element Purpose of Evaluation The purpose of this evaluation is to document the evaluation of potential defect with Engine Systems Inc. (ESI) governor drive coupling element and its significance, as well as to make recommendations for applying the lessons learned.
Description of the Issue In June 2005 the Shearon Harris plant removed a coupling element from their diesel engine and observed the material to be swollen and deformed. A subsequent technical report provided by the site's Materials Services Section found the material composition of the element to be isoprene (natural rubber). The design of the coupling specifies the material to be polychloroprene (neoprene). The isoprene material is not suitable for the high temperature, oil rich environment of the engine gear case and is susceptible to failure after prolonged exposure.
In its September 9, 2005 letter (ADAMS Accession Number ML052650354), ESI informed NRC that it had supplied the governor drive coupling element, P/N AK-007-001, to several utilities that were fabricated from an incorrect material. The coupling assembly is used on a vertical drive shaft to transmit power from the engine gear train to the governor in order to allow engine speed sensing and regulating capability. Failure of the element would cause the coupling assembly to fail which would result in inoperability of the governor. In its letter, ESI indicated that it had supplied potentially incorrect coupling elements to Grand Gulf, River Bend, Perry, Vogtle, Shearon Harris, and Comanche Peak nuclear plants.
Significance Evaluation NRC staff contacted the licensees of the Grand Gulf, River Bend, Perry, Vogtle, Shearon Harris, and Comanche Peak nuclear plants to determine whether the ESIs governor drive coupling element P/N AK-007-001 had been installed in any diesel generators and to inquire about licensees actions for the replacement of the defective governor drive coupling elements.
The Shearon Harris licensee confirmed that it had received ESI coupling elements made from isoprene rather than neoprene and that it had replaced with neoprene couplings on both emergency diesel generators (EDGs) in Fall 2005.
The Vogtle licensee confirmed that they had received ESI coupling elements made from isoprene but they were never installed. The licensee also confirmed that the elements were removed from the warehouse and returned to the manufacturer for replacement.
The Grand Gulf licensee confirmed that they had received two coupling elements subject to this Part 21. One of these elements was removed from stock and returned to vendor. The second element is installed on the Division I Diesel Generator. This coupling element installed on the Division I EDG is planned for replacement during a system outage in May 2006.
Enclosure
The River Bend licensee confirmed that the incorrect material (isoprene vs. the correct neoprene) has been used in River Bend Stations since December 2003 for Division 2, and January 2004 for Division 1. River Bend also confirmed that condition report (CR) RBS-2005-03279 tracks the replacement of the coupling and that the replacement of the couplings for both Division 1 and 2 EDGs is currently scheduled for May 2006.
The Perry licensee confirmed that they have not installed any of ESI's EDG governor susceptible material into the EDGs. Three elements were procured on 11/18/02. Two of these were installed and one was placed into spares. The laboratory test results confirmed the spare from this order is a neoprene material. Six additional elements were purchased in September 1994 and March 2005. The laboratory test results indicated an isoprene blend. These are in still inventory and have not been installed.
The Comanche Peak licensee confirmed that they had installed ESI coupling elements made from isoprene on both Units EDGs. They also confirmed that the elements on both Unit 1 EDGs were replaced during 1RF11 refueling outage in Fall 2005 and the elements on the Unit 2 EDGs are currently scheduled to be replaced during 2RF09 refueling outage in Fall 2006.
Operating Experience History Transamerica Delaval issued a 10 CFR Part 21 report on 6/23/82 which indicated that a potential defect existed for isoprene couplings, and that they should be replaced with neoprene couplings. An operating experience (OE) search was conducted by NRC Region II on the INPO Web Site for governor drive coupling failures or events. The following events were specifically reviewed, and none of the events were caused by improper coupling material: LER 96-010-00 (EDG Governor Failure), OE6098 (EDG Booster Pump Coupling Failure), OE 10395 (EDG Fan Shaft Coupling Failure).
Note: INPO documents are considered Limited Distribution and are not to be distributed outside the agency in accordance with Field Policy Manual (NUREG/BR-0075) No. 9.
Staff Conclusion and Recommendation ESI has informed all of its customers of this condition and recommended that they inspect and remove from their inventory any coupling element made from isoprene, or replace them if any isoprene elements had been installed on their EDGs. Additionally, ESI has informed its customers that it would provide replacement elements free of charge until December 31, 2005.
NRC staff issued a morning report (H-2005-0023) when first became aware of this condition on August 12, 2005. Subsequently, staff issued a second morning report (H-2005-0024) on September 26, 2005, after ESI concluded its investigation and issued a 10 CFR Part 21 report.
Staff concludes that the ESI has correctly identified the root cause of this condition and has made appropriate recommendations to its customers to investigate and replace suspected elements. Additionally, staff has confirmed with affected licensees that they are aware of this condition and have and/or planned for replacing unsuitable coupling elements. The staff does not recommend any generic communication or further action.
Additionally, this operating experience has been captured in the Reactor Operating Experience database for future tracking and trending purposes.
Based on the staffs evaluation, the Operating Experience Branch has closed IFR 2005-083, and associated TAC MC8519, in accordance with NRR Office Instruction LIC-401.