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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24302A2772024-10-28028 October 2024 57243-EN 57243_5 - Rssc Dba Marmon - Update 20241030 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML20279A5772020-11-23023 November 2020 U.S. Nuclear Regulatory Commission'S Analysis of Public Service Enterprise Group Nuclear, LLC Decommissioning Plans Update for Salem Generating Station, Hope Creek Generating Station and Peach Bottom Independent Sfsis ML20296A2762020-10-0606 October 2020 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21 - Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML19325C0942019-11-0707 November 2019 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch ZJS1518 Final Report Per 10 CFR Part 21 ML19263A6662019-09-0909 September 2019 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19008A0432019-01-0404 January 2019 Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML18159A0392018-06-0606 June 2018 National Technical Systems (Nts) - Potential Part 21 on Dedicated Items Not Available for Pmi Testing (NUPIC) ML17355A1392017-12-0505 December 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report Per 10 CFR Part 21 ML17250A1572017-08-31031 August 2017 Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML17206A0392017-07-13013 July 2017 Part 21 - Hex Cap Screws Produced with Pre-existing Cracks ML17101A3662017-04-0606 April 2017 Part 21 Notification - Failure of Vishay Diodes ML17096A2692017-04-0303 April 2017 Part 21 Notification - Failure of Vishay Diodes ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16328A3102016-11-18018 November 2016 Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML15303A0142015-10-26026 October 2015 Part 21 Report Regarding Pressure Seal Valve Noncompliance, Per Millstone ML15224A5432015-08-10010 August 2015 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 ML14259A3892014-09-0808 September 2014 Part 21 - Failure to Meet Specified Irradiation During Testing of Coated Test Panels ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14105A0182014-04-11011 April 2014 Part 21 - Model 1154HP Transmitters with Integral 1159 Remote Diaphragm Seals May Exhibit Degraded Functional Reliability ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12258A3992012-09-10010 September 2012 Potential Part 21 Issue Related to Tyco Timing Relay ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld 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 ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1018907392010-07-0101 July 2010 Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm ML1015305642010-05-28028 May 2010 Part 21 Notification from C & D Technologies, Inc., Post Corrosion on Dcu Batteries ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0810701722008-04-0909 April 2008 Notification of Potential Part 21 Regarding Torus Immersion/Vapor Phase Coatings ML0520003332005-07-14014 July 2005 Part 21 Communication: Circuit Breaker Replacement Primary Bushings Not Tested to ANSI Standards ML0506302442005-03-0202 March 2005 Part 21 Report Concerning MCPR Limits and MCPR Monitoring ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable 2024-08-23
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LAKE ENGINEERING CO.
P.O. Box296 10 Austin Avenue Greenville, RI 02828 Tel: 401-949-4733 Fax: 401-949-0220 December 5, 2017 U S Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555-0001
Subject:
Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report per 10 CFR Part 21 This letter reflects new information available since our interim ~eport dated November 3, 2017.
Three Mile Island We have concluded that a substantial safety hazard does not exist at this plant as a result of the subject fluid. _
Millstone**,
. . We have concluded that a substantial safety hazard does not exist at this plarit as a result oMhe
- The status of the subject issue as it applies to US nuclear plants to which SF1154 fluid from Batch 14ELVS145 was shipped by Lake Engineering Company is summarized in the following table.
Millstone Fluid used in some installed snubbers No substantial safety hazards exist.
Nine Mile Point , Fluid not used No substantial safety hazards exist.
Duane Arnold Fluid not used No substantial safety hazards exist.
Monticello Fluid not used No substantial safety hazards exist.
Pilgrim Fluid not used No substantial safety hazards exist.
Three Mile Island Fluid used in some installed snubbers No substantial safety hazards exist.
Grand Gulf Fluid used in some installed snubbers No substantial safety hazards exist.
Peach Bottom Fluid used in some installed snubbers No substantial safety hazards exist.
U S Nuclear Regulatory Commission December 5, 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Page2 Final Report per 10 CFR Part 21 If there are any questions or if additional information is required, please contact the writer by mail or by phone using the contact information provided above or by email at dbrown@lakeengineeringri.com.
Very truly yours, LAKE ENGINEERING COMPANY D. P. Brown, P.E.
President DPB/d/let120517.nrc cc: P. Guay- QA Mgr.