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| | issue date = 07/14/2014 | | | issue date = 07/14/2014 |
| | title = Notification of the Potential Existence of Defects Pursuant to 10CFR Part 21 | | | title = Notification of the Potential Existence of Defects Pursuant to 10CFR Part 21 |
| | author name = Gresham J A | | | author name = Gresham J |
| | author affiliation = Westinghouse Electric Co, Westinghouse Electric Co, LLC | | | author affiliation = Westinghouse Electric Co, Westinghouse Electric Co, LLC |
| | addressee name = | | | addressee name = |
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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML22314A0132022-11-0404 November 2022 EN 56209 - Part 21 Report Re Schneider Electric P/N ASP840-000 Modicon Primary/Secondary Power Supply Failures ML20024E2552020-01-0909 January 2020 Engine Systems, Inc., Submittal of Selenium Surge Suppressor, Emo P/N 8403049 ML19091A0502019-03-21021 March 2019 Engine Systems, Inc. 10 CFR 21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0124, Rev. 0, Excitation Transformers for Vickers Voltage Regulator System ML19087A2522019-03-21021 March 2019 Engine Systems, Inc. - 10 CFR 21 Reportable Notification on Excitation Transformers for Vickers Voltage Regulator System ML19042A0802019-01-25025 January 2019 Part 21 Report No. 10CFR21-0124-INT; Rev. 0 - Saturable Reactor (Magnetic Amplifier) for Vickers Voltage Regulator System, P/N 8408218-ESI 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 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 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 ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16196A0652016-07-0909 July 2016 Part 21 Report - Nonconformance on Struthers-Dunn Relay for Psge Nuclear LLC ML16162A6792016-06-0808 June 2016 Part 21 Report - Nonconformance on Struthers-Dunn Relay for PSEG Nuclear LLC ML16139A8312016-05-13013 May 2016 Part 21 Notification - Potential Defect Applicable to Hytork XL1126 Pneumatic Actuators ML16126A1112016-04-29029 April 2016 National Technical Systems (Nts) Request for Extension, for Potential Part 21 on Safety Clip, Siemens Part Number 401-158 ML16098A4452016-03-22022 March 2016 Part 21 Notification - Sense and Transfer Module Resistive Short ML16112A2102016-03-14014 March 2016 National Technical Systems - Potential Part 21 on Siemens 401-158 Safety Clip, Per Wolf Creek, Salem, and Arkansas Nuclear One ML15223B2642015-08-0606 August 2015 Part 21 Report - Notification of Deviation Regarding Hk Circuit Breaker Pivot Pin ML15134A0182015-05-0707 May 2015 Part 21 Report Regarding Struthers Dunn Relays with Contact Resistance Greater than One Ohm ML15146A0222015-05-0707 May 2015 Qualtech Np - Potential 1O CFR Part 21 Notification on Struthers Dunn Relays ML15089A4352015-03-27027 March 2015 Part-21 Notification - Sense and Transfer Module Resistive Short ML15089A4372015-03-20020 March 2015 Part 21 - Dual Alarm Modules That May Contain Faulty Diodes in Single State Relays ML15049A4582015-02-0606 February 2015 Thermo Gamma-Metrics, LLC - Part 21 Report Regarding Shutdown Margin Monitor Environmental Qualification Noncompliance ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification 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 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 ML14197A2812014-07-15015 July 2014 Part 21 Report - Potential Failure of Reactor Coolant Pump Turning Vane Bolts ML14197A2742014-07-14014 July 2014 Notification of the Potential Existence of Defects Pursuant to 10CFR Part 21 ML14113A3702014-04-18018 April 2014 Part 21 - Thomas and Betts Printed Circuit Boards ML14113A3982014-04-17017 April 2014 Part 21 - Bearing Defect ML14303A5262014-03-28028 March 2014 Interim Part 21 Report - Misaligned Separators in LCR-25 Standby Batteries ML14085A0132014-03-19019 March 2014 Part 21 Report Re Defects & Non-Compliance of Thomas and Betts Printed Circuit Boards in Which the Power Supplies Incorrect Strap Installed on the Trasformers of Cyberex P/N ML14079A3532014-03-17017 March 2014 Notification of Part 21 Re Bearing Defect 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 ML13102A3032013-04-10010 April 2013 Part 21 Involving a Potential Weld Defect ML13099A2382013-03-27027 March 2013 Notification of Potential Part 21 Report Re Series 24 Csr Relays with Oversized Cam Drive Components ML13095A0112013-03-25025 March 2013 Update to Event Number 48798: 10 CFR Part 21 Notification, Dual Alarm Modules and Single Alarm Modules ML13079A3202013-03-18018 March 2013 Notification of Potential Part 21 Interim Report Re Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters ML13063A4432013-03-0101 March 2013 10 CFR Part 21 Report Notification, Dual Alarm Modules and Single Alarm Modules ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12363A0472012-12-10010 December 2012 Part 21 Report Re Failure to Comply with Certain PSEG Specifications as Required by PSEG Purchase Order ML12318A0412012-11-0808 November 2012 Part 21 Report - Commercial Grade Dedication Not Properly Applied to Butterfly Valves ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12066A1182012-03-0202 March 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 2022-11-04
[Table view] Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - 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Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information 2024-02-06
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Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company W estinghouse Engineering, Equipment and Major Projects 1000 Westinghouse Drive, Building 3 Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643 Document Control Desk Direct fax: (412) 374-3846 11555 Rockville Pike e-mail: greshaja@westinghouse.com Rockville, MD 20852 LTR-NRC- 14-46 July 14, 2014
Subject:
Notification of the Potential Existence of Defects Pursuant to 10CFR Part 21 The following information is provided pursuant to the requirements of I0CFR Part 21 to report a potential defect that could lead to a substantial safety hazard. This issue concerns potential failure of certain Westinghouse reactor coolant pump (RCP) turning vane bolts. This issue is limited to Westinghouse RCPs that employ turning vane bolts that are 1.0 inch nominal size, made from A286 material.
These bolts hold the turning vane-diffuser assembly in place inside the RCP, above the pump impeller.
Bolt failures have occurred at one plant such that the turning vane-diffuser assembly dropped inside three of the four RCPs and in two of these RCPs the assembly contacted the impeller.(i) Name and address of the individual or individuals informing the Commission.
James A. Gresham Westinghouse Electric Company Engineering, Equipment and Major Projects 1000 Westinghouse Drive, Suite 310 Cranberry Township, Pennsylvania 16066 (ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.The delivered basic components are the RCPs which include turning vane bolts of 1.0 inch nominal size made from A286 material.
These bolts are part of the model 93A RCPs delivered to Salem Unit 2 and Surry Units I & 2. Each RCP at these units has 20 bolts holding the turning vane-diffuser assembly to the thermal barrier flange.Other model 93A RCPs and model 93A- 1 RCPs have larger turning vane bolts of 1.5 inch diameter, and the bolted assembly uses 23 or 24 bolts. Westinghouse evaluated the RCPs with these bolts and determined that a failure could not result in a substantial safety hazard, even if left uncorrected.
The basis for this is the inspection data which shows a very low incidence of bolt failure, likely due to the reduced bolt stress associated with the fastener size and load distribution.(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066© 2014 Westinghouse Electric Company LLC All Rights Reserved C LTR-NRC- 14-46 Page 2 of 3 (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.The originally supplied turning vane bolts are made of A286 material, and have experienced inter-granular stress corrosion cracking (IGSCC). Inspection of the Salem Unit 2 RCPs revealed that three out of four RCPs had turning vanes which dropped due to failure of the bolts. Of those three, two RCP turning vane diffusers made contact with the impeller because rubbed metal on the impeller and diffuser was observed.
One of the impellers had a discrete unworn profile that could be used to estimate the amount of material removed by contact. There was no adverse impact on RCP operation, as reported by the Licensee.Operating experience from Salem suggests that normal operation of the RCP post-turning vane drop was experienced.
In the case of the two Salem RCPs which did experience impeller contact, this contact resulted in some removal of material, which left a smooth finish, with clearance that would have preserved coastdown capability after the clearance was established.
If turning vanes have dropped at other plants resulting in establishing clearance between the contacting surfaces, the coastdown capability would not be diminished significantly.
Safety analysis of the plant assumes a single Locked Rotor event.It is highly unlikely that one Locked Rotor event could occur, and even more unlikely that more than one would occur simultaneously.
Westinghouse determined in its evaluation that the only scenario that could potentially result in a substantial safety hazard would be if more than one RCP rotor simultaneously"locked" as a result of simultaneous failures of turning vane bolts, and the turning vanes contacting the impellers.
However, the possibility of multiple simultaneous locked rotors occurring is extremely unlikely.
Since Westinghouse could not establish with certainty that a multiple locked rotor event could not occur, Westinghouse concluded that this deviation could potentially result in a substantial safety hazard if left uncorrected.(v) The date on which the information of such defect or failure to comply was obtained.The Westinghouse president was informed of the recommendation of the Westinghouse Safety Review Committee on July 14, 2014.(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.The model 93A RCPs with 1.0 inch turning vane bolts were delivered to Salem Unit 2 and Surry Units I & 2.(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.The Salem Unit 2 RCPs have been repaired with 1.0-inch replacement bolts of 316 SST, a material which is more resistant to IGSCC. Later manufactured Model 93A RCPs have the aforementioned 1.5-inch fasteners.
LTR-NRC- 14-46 Page 3 of 3 (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.
Westinghouse believes that close study of RCP seal inlet and outlet temperatures may identify a change condition that would indicate that the turning vane diffuser has dropped.As stated above, continued operation after drop would assure sufficient running clearance and, therefore, coastdown capability.
Additional advisory information will be provided in a subsequent Westinghouse Nuclear Safety Advisory Letter (NSAL) to be issued to affected licensees.(ix) In the case of an early site permit, the entities to whom an early site permit was transferred This issue does not apply to plants licensed under 10 CFR 52.Very truly yours,)ames A. Gresham, Secretary Westinghouse Safety Review Committee cc: E. Lenning (NRC MS 0-11-Fl)