|
---|
Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors 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 ML20304A1612020-10-14014 October 2020 Lake Engineering Co., Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 Final Report Per 10 CFR Part 21 ML20097B6912020-03-20020 March 2020 Second Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 ML18241A0292018-08-23023 August 2018 Hex Inverter Chip on Westinghouse 7300 Process Analog Control System Circuit Cards W3F1-2018-0040, Interim Report of a Deviation or Failure to Comply2018-07-0505 July 2018 Interim Report of a Deviation or Failure to Comply ML18081A1192018-03-15015 March 2018 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1154 and Model 1154 Serles H Pressure Transmitters and 01154-0153-0002 Amplifier Circuit Card Assemblies ML17325B0222017-11-17017 November 2017 Fisher Controls International LLC Information Notice (FIN) 2017-05 ML17324A9792017-11-17017 November 2017 Part 21 Report Re Fisher Type 461 Valve Plug Machining 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 ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16188A3762016-06-21021 June 2016 Part 21 Interim Evaluation of Deviation - Contractor Failure ML16139A8342016-05-10010 May 2016 Electroswitch - Transmittal of 10CFR Part 21 Reporting of Defects and Noncompliance Regarding Vendor Inspection of Electroswitch Corporation Docket No. 99900833 ML15303A0042015-10-23023 October 2015 Part 21 Report Regarding Westinghouse Type KIR-60 Current Transformer, Per Waterford, Unit 3 ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML15089A4362015-03-21021 March 2015 Part-21 Report - Valve Seat Leakage Defect W3F1-2014-0069, Part 21 Report of Time-Delay Relay Failure2014-11-12012 November 2014 Part 21 Report of Time-Delay Relay Failure 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 ML14265A0492014-09-12012 September 2014 Amendment to Part 21 Report from Abb, Inc Re Deviation of K-Line Circuit Secondary Close Latch (Event #50371) ML14237A1212014-08-15015 August 2014 Notification of Potential Part 21 Re Notice of Deviation Regarding K-Line Circuit Breaker Secondary Close Latch W3F1-2014-0042, Part 21 Report of Pneumatic Valve Actuator Reverse Action2014-07-0909 July 2014 Part 21 Report of Pneumatic Valve Actuator Reverse Action ML14171A3562014-06-12012 June 2014 Masoneilan Actuators Discovered to Fail-Closed Instead of the Required Fail-Open Configuration ML14170A0132014-06-0909 June 2014 Part 21 (Event 50025) - Barton Model 288A and 289A Differential Pressure Switch Defect ML14101A4672014-04-11011 April 2014 (Waterford 3)- Notification of Potential Part 21 Report of Time-Delay Relays Spurious Actuation W3F1-2014-0026, Notification of Potential Part 21 Report of Time-Delay Relays Spurious Actuation2014-04-11011 April 2014 Notification of Potential Part 21 Report of Time-Delay Relays Spurious Actuation ML14079A0282014-03-13013 March 2014 Part 21 - Allen Bradley Type 700RTC Relay Spuriously De-Energizing ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13099A2382013-03-27027 March 2013 Notification of Potential Part 21 Report Re Series 24 Csr Relays with Oversized Cam Drive Components 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 ML12283A2452012-09-28028 September 2012 Part 21 - Defective Masoneilan Transducer Model 8005N 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 ML11363A1882011-12-0202 December 2011 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0098, Rev. 3, Amot Thermostatic Valve Element P/N: 9760X ML11336A3692011-12-0101 December 2011 Notification of Potential Part 21 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML11251A1982011-09-0606 September 2011 Notification Under 10 CFR Part 21 on Certain Rosemount Model 1153 Series B, 1164 and 1154 Series H Pressure Transmitters, May Not Perform Their Intended Safety Function ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML0934301402009-12-0202 December 2009 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 1OCFR21-0098, Rev. 0, Amot Thermostatic Valve Element, P/N: 9760X ML0930304542009-10-23023 October 2009 Hilti, Inc., Potential Delivery of Nonconforming Washers, and Affected Utilities or Plants Are Pilgrim, Brunswick, Arizona Public Service, and Waterford 3 2024-09-06
[Table view] Category:Letter
MONTHYEARIR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24268A1132024-09-24024 September 2024 Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000382/20230032023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 2024-09-06
[Table view] |
Text
W3F1 April 1 U.S. Nuclear Attn: Document Control Desk 11555 Rockville Pike Rockville
Subject:
Dear Sir or Madam:
Pursuant to 10 Station, Unit 3 (Waterford 3) associated with spurious a reported to the NRC The attachment to this letter provides the information required by 10 CFR details This report contains no new commitments. Please contact Assurance Manager, Sincerely, MRC/
Attachment:
W3F1-2014-002 6 1 1, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville , MD 20852
Subject:
Part 21 Report of Time Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50 License No. NPF
Dear Sir or Madam:
Pursuant to 10 CFR 21.21(d)(3)(ii), Entergy is providing the Station, Unit 3 (Waterford 3) associated with spurious a reported to the NRC The attachment to this letter provides the information required by 10 CFR details associated with This report contains no new commitments. Please contact Assurance Manager, Sincerely, /JDW
Attachment:
Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays 6 Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike 20852 Part 21 Report of Time Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50
-License No. NPF
Dear Sir or Madam:
CFR 21.21(d)(3)(ii), Entergy is providing the Station, Unit 3 (Waterford 3) required written notification of the identification of a defect associated with spurious a ct uation reported to the NRC Operations Center on March 13, 2014.
The attachment to this letter provides the information required by 10 CFR associated with s purious This report contains no new commitments. Please contact Assurance Manager, at (504) 739 Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays Regulatory Commission Attn: Document Control Desk Part 21 Report of Time
-Delay Relays Spurious Actuation Waterford Steam Electric Station, Unit 3 (Waterford 3)
-382 License No. NPF
-38 CFR 21.21(d)(3)(ii), Entergy is providing the required written notification of the identification of a defect uation of time Operations Center on March 13, 2014.
The attachment to this letter provides the information required by 10 CFR purious a ctuation This report contains no new commitments. Please contact at (504) 739
-6685 if you have questions regarding this information.
Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays Delay Relays Spurious Actuation Waterford Steam Electric Station, Unit 3 (Waterford 3)
CFR 21.21(d)(3)(ii), Entergy is providing the required written notification of the identification of a defect of time-delay r elays Operations Center on March 13, 2014.
The attachment to this letter provides the information required by 10 CFR ctuation of certain t ime This report contains no new commitments. Please contact if you have questions regarding this information.
Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays Delay Relays Spurious Actuation Waterford Steam Electric Station, Unit 3 (Waterford 3)
CFR 21.21(d)(3)(ii), Entergy is providing the Waterford Steam Electric required written notification of the identification of a defect elays. This information was initially Operations Center on March 13, 2014.
The attachment to this letter provides the information required by 10 CFR t ime-delay r elays This report contains no new commitments. Please contact John if you have questions regarding this information.
Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays 10 CFR Delay Relays Spurious Actuation Waterford Steam Electric Station, Unit 3 (Waterford 3)
Waterford Steam Electric required written notification of the identification of a defect This information was initially The attachment to this letter provides the information required by 10 CFR 21.21, including elays at Waterford 3 John P. Jarrell , Regulatory if you have questions regarding this information.
Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays 10 CFR 21.21 Waterford Steam Electric required written notification of the identification of a defect This information was initially 21.21, including at Waterford 3. , Regulatory if you have questions regarding this information.
Entergy Operations, Inc.
17265 River Road Killona, LA 70057
-Tel 504-739-6660 Fax 504-739-667 8 mchisum@entergy.com Michael R. ChisumSite Vice President Waterford 3 21.21 21.21, including if you have questions regarding this information.
Entergy Operations, Inc.
-3093 8 @entergy.com Michael R. Chisum Site Vice President
W3F1-2014-0026 Page 2 cc: Mr. Marc L. Dapas, Regional Administrator U.S. NRC, Region IV RidsRgn4MailCenter@nrc.gov U.S. NRC Project Manager for Waterford 3 Alan.Wang@nrc.gov Michael.Orenak@nrc.gov U.S. NRC Senior Resident Inspector for Waterford 3 Marlone.Davis@nrc.gov Chris.Speer@nrc.gov
Attachment to W3F1-2014-0026 Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays
W3F1-2014-0026 Attachment Page 1 of 3 Waterford 3 Part 21 Report of Allen Bradley 700RTC Relays This written notification information follows the format of and addresses the considerations contained in 10CFR21.21(d)(4)(i)-(ix).
I. Name and Address Michael R. Chisum 17265 River Road Killona, LA 70057 II. Facility, Activity or Component The basic component is an electrical relay. Allen Bradley 700RTC relays installed at Waterford Steam Electric Station, Unit 3 (Waterford 3) susceptible to the deviation are used in monitoring undervoltage conditions for the 3A3, 3B3, 3A31, and 3B31 safety related electrical buses, as well as other applications, such as time delay relays for starting Engineered Safety Features Actuation Signal (ESFAS) equipment.
Ill. Constructor or Supplier The basic component containing a defect was provided by QualTech NP as the qualifying vendor of the Allen Bradley manufactured 700RTC relays. QualTech NP has been notified of the 10CFR Part 21 notification and provided failure analysis documentation.
IV. Defect and Safety Hazard Nature of the defect:
Waterford 3 has experienced spurious actuations of Engineered Safety Features Actuation Signal (ESFAS) equipment. The direct cause of the reported spurious actuations of ESFAS equipment that have occurred at the site was determine to be the Allen Bradley 700RTC relays associated with each ESFAS circuit spuriously de-energizing. The spurious de-energization of the associated relays caused the ESFAS equipment to perform its required safety function. Independent failure analysis performed by Southwest Research Institute (SwRI) and National Technical Services (NTS) have found Allen Bradley model 700RTC00110U1 relays that have failed in service at Waterford 3 contain inadequate solder joints and degraded C25 capacitors. The C25 capacitors when tested did not meet the manufacturer's specifications for capacitance and effective series resistance. SwRI reported that installation of the C25 capacitor at the factory may have contributed to failure of the capacitor, specifically the way in which the capacitor leads had been bent to fit the much wider spacing of the holes in the coil-control circuit board on which the capacitor is installed. SwRI and NTS were not able to repeat the failure mode experienced at Waterford 3 of Allen Bradley relays de-energizing intermittently while control power is maintained on the relay coil through laboratory testing. Inadequate solder joints and the failed C25 capacitors were found during destructive failure analysis W3F1-2014-0026 Attachment Page 2 of 3 after initial relay testing had been performed. Disassembly of an Allen Bradley 700RTC00020U1 that had failed in service by Waterford 3 personnel indicated inadequate solder joints and a failed C25 capacitor subsequent to SwRI and NTS failure analysis being received.
Safety hazard which could have been created: Four Allen Bradley 700RTC relays susceptible to the deviation are used in monitoring undervoltage conditions for the 3A3, 3B3, 3A31, and 3B31 safety related electrical buses. If an undervoltage condition occurs concurrent with a Loss of Offsite Power or concurrent with a Safety Injection Actuation Signal while the Emergency Diesel Generator Load Sequencer is between the S3 and S8 load blocks (192 seconds), then these relays will initiate a sequencer lock out and the white "Lock Out" light for the sequencer will be lit. Under this scenario, the Emergency Diesel Generator will automatically start and come up to rated voltage within 10 seconds. Once the sequencer detects the bus is at full rated voltage after a Loss of Offsite Power, it will begin to sequence on loads. During the loading sequence, if the observed failure mode occurs between the S3 and S8 load block, then the lockout feature will be active. All loads previously sequenced on, prior to the lockout, will remain running. At the point of the spurious actuation of the relay, no further automatic loading will occur until the sequencer is reset manually. The most limiting failure of an Allen Bradley relay at Waterford 3 occurred at three years of service, the under voltage relays listed above have been installed for under three years (currently 2.9 years). These relays installed in the 3A3, 3B3, 3A31, and 3B31 safety related electrical buses could be susceptible to this condition had they been installed for greater than three years. In this instance, the relays could prevent safety functions from being accomplished due to Engineering Safety Features equipment not receiving power in the time sequence assumed by the safety analysis.
V. Date On 3/12/2014, Engineering evaluation determined the Deviation could create a Substantial Safety Hazard, as defined in 10CFR21, and provided the Site Vice President (responsible officer) information of the Defect the same day. NRC Headquarters Operations Center was notified by telephone on 3/13/2014 (Ref. EN#49911).
VI. Location and Number of Defective Components Thirty three (33) Allen Bradley 700RTC relays are installed at Waterford 3. These applications are used in monitoring undervoltage conditions for the 3A3, 3B3, 3A31, and 3B31 safety related electrical buses, as well as other applications, such as time delay relays for starting Engineered Safety Features Actuation Signal (ESFAS) equipment. Waterford 3 has determined that the other Entergy nuclear operated facilities utilizing these Allen Bradley relay types, possibly in a safety related application, is at James A. Fitzpatrick and Cooper Nuclear Station, at which this condition has been made known and entered into their Corrective Action Program.
W3F1-2014-0026 Attachment Page 3 of 3 VII. Corrective Action Nine of the Allen Bradley 700RTC relays have been replaced by Entergy's Electrical Maintenance organization at Waterford 3 as of 4/9/2014. The four Allen Bradley 700RTC relays used in monitoring undervoltage conditions for the 3A3, 3B3, 3A31, and 3B31 safety related electrical buses are to be replaced by Entergy's Electrical Maintenance organization at Waterford 3, due prior to ascending to Mode 4 (Hot Shutdown) at the conclusion of Refueling Outage 19. Refueling Outage 19 is scheduled to start April 13, 2014. Reduce the relay replacement preventative maintenance tasks frequency from eighteen years to three years for the twenty nine Allen Bradley 700RTC relays. The remaining four perform alarm only functions and will not have replacement frequency revised. This action is to be performed by Entergy's Engineering organization at Waterford 3 and is due by 4/26/2014. Perform an Engineering Study to determine possible solution to resolve Allen Bradley 700RTC relay failures that have occurred at Waterford 3. Issue additional actions to implement the results of the engineering study to resolve Allen Bradley 700RTC relay failures at Waterford 3. This action is to be performed by Entergy's Engineering organization at Waterford 3 and is due by 8/29/2014 VIII. Advice Failure analysis indicated internal heat degradation of the relays' sub-components. Operating the relays at 12% overvoltage and 120°F ambient temperature is causing the Allen Bradley 700RTC relays installed in Auxiliary Relay Cabinets to degrade faster than expected. The effect of both higher operating voltage and temperature together should be evaluated in aggregate. IX. Early Site Permit This is not an early site permit concern.