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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML21225A0812021-08-0404 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 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 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 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 ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling 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 ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers 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 ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology 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 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 ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld 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 ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML12038A0282012-02-0202 February 2012 Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12032A2402012-02-0101 February 2012 Notification of Potential Part 21 - 60-Day Interim Report Notification: Failure of CRD Collet Retainer Tube/Outer Tube Weld ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1122401422011-08-11011 August 2011 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11140A0872011-05-13013 May 2011 Sor Event 46821 Evaluation of Deviation for Defect ML11126A0152011-05-0404 May 2011 Sor, Inc., Pressure Switch with Possible Sub-Standard Electrical Lead Terminations ML1104800542011-02-15015 February 2011 Notification of Potential Part 21 Reportable Condition: Crack Indications in Marathon Control Rod Blades ML1104604872011-02-15015 February 2011 Notification of Potential Part 21 Reportable Condition Re Design Life of D and s Lattice Marathon Control Blades ML1035100312010-12-15015 December 2010 Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1035001742010-12-15015 December 2010 Notification of Potential Part 21 Re 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1030601022010-10-29029 October 2010 Notification of Potential Part 21 Transfer of Information Concerning Control Components Inc. (CCI) Drag Valves ML1029305052010-10-20020 October 2010 GE Hitachi Nuclear Energy - Notification of Potential Part 21 60-Day Interim Report: Crack Indications in Marathon Control Rod Blades ML1029502812010-10-20020 October 2010 Part 21 Notification - Crack Indications in Marathon Control Rod Blades ML1027300632010-09-27027 September 2010 Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1027006142010-09-27027 September 2010 Part 21 60-Day Interim Report 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 ML1018201602010-07-0101 July 2010 Notification of Potential Part 21 Reportable Condition Re Failure of HPCI Turbine Overspeed Reset Control Valve Diaphragm ML1008200592010-03-22022 March 2010 GE Hitachi Nuclear Energy, Part 21 60-Day Interim Report Notification: Failure of HPCI Turbine Overspeed Reset Control Valve Diaphragm NG-09-0608, Notification of Potential Part 21 Re Duane Arnold Energy Center Identification of Defect2009-07-30030 July 2009 Notification of Potential Part 21 Re Duane Arnold Energy Center Identification of Defect 2021-08-04
[Table view] Category:Letter
MONTHYEARL-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) 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 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 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan ML22089A0492022-05-12012 May 2022 Sfmp Review Letter NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22007A2722022-02-11011 February 2022 Cover Letter - NRC Duane Arnold Exemption Issuance NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML22033A0802022-02-0202 February 2022 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition IR 05000331/20210012022-01-25025 January 2022 NRC Inspection Report Nos. 05000331/2021001(DNMS); 07200032/2021001(DNMS); and 07200032/2021002(DNMS) - Duane Arnold Energy Center ML21172A2172022-01-21021 January 2022 Issuance of License Amendment to Adopt ISFSI-Only Technical Specifications NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister 2024-01-25
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I t I BERGEN POWER PIPE SUPPORTS P.O. Box 461 (724) 379-5212 Donora, PA 15033 (724) 379-9363 Fax January 15, 2007 Document Control Desk US Nuclear Regulatory Agency 11555 Rockville Pike Rockville, MD 20852-2746
Subject:
10 CFR 21 Notification Identification of Defect NRC Event No. 43071 Enclosed is a copy of a 10CFR21 Notification that Bergen Power has received from Fronek A/DE concerning Hydraulic Snubbers filled with GE SF1154 Silicone fluid, Batch AD965. We have determined that units were shipped to four customers. These customers are TVA, Entergy, Eletrobras, and Ergytech.
Enclosed are copies of the notifications that have been sent to our customers.
If we can be of further assistance, please contact us.
Thomas P. Haynes QA Manager e-mail: tomhaynes@bergenpower.com cc: James M. Bonetti President
Fronek AIDE, Inc. A Wholly Owned Subsidiary 86 Doris Ray Court by Piping Technology & Products Laconia, NH 03246 PO Box 34506 Tel: (603) 528-1931 Houston, Texas 77234-4506 Fax: (603) 528-6381 Bergen Power Pipe Supports January 12, 2007 PO Box 461 ( alt. 484 Galiffa Drive)
Donora, PA 15033 Attention: Tom Haynes
Subject:
10 CFR21 Notification, Quality Assurance Mgr. Identification of Defect, NRC Event No. 43071 Pursuant to 10 CFR 21.21 notification requirements, Fronek Anchor Darling Enterprises, Inc (Fronek) hereby informs Bergen Power that we have provided you with Hydraulic Snubbers filled with GE SF1154 Silicone Hydraulic Fluid, Batch AD965 which has been identified as containing a defect as described in NRC Event No.
43071, as filed with the NRC by FPL Duane Arnold Energy Center(DAEC), Palo, IA. The attached document lists the applicable Bergen Power Purchase Orders, Descriptions of the Snubbers and their applicable Fronek assigned Serial Numbers.
To fulfill its obligations under 10 CFR 21.21 (c)(1), Fronek is in the process of completing its evaluation on the effects of snubber performance while using the defective batch of GE SF1154. The gallon sample of fluid we are using in our evaluation testing was returned to us by DAEC (it is one of the two gallons identified in their notice to the NRC). We are very early into our investigation, but in order to facilitate the most rapid circulation of information with regard to the Subject event, we have completed a sufficient number of tests to report the following initial findings.
To reiterate, DAEC, in its initial notification to the NRC, has postulated that the foreign material in the defective fluid could restrict flow through the bleed orifices in a snubber, potentially reducing the flow through the snubber control valve to zero. This may cause the snubber to remain locked following activation. The resulting locked snubber would prevent the function of allowing for some piping movement associated with normal system movement.
In our preliminary snubber performance evaluation, we have witnessed the behavior described in DAEC's postulation above, but its likely possibility seems to be limited to loads applied in extension to our smallest size snubber (an 1-1/2" Bore with a 3 Kip Load Rating). Thus far, we have conducted Performance (Lock-Up &
Bleed) Testing on our two smallest size snubbers (the aforementioned 3 Kip and the 2-1/2" bore 10 Kip) where the control valve bleed orifices are among the smallest (approximately 24 and 16 tests, each in both directions, on the 3 and 10 Kip, respectively). Only the 3 Kip snubber loaded in the extension direction has sporadically (twice) demonstrated the behavior described above (i.e., zero bleed rate) and only if the load remains continuously applied in that direction. After the 3 Kip hasbecome locked in the extension direction, any load reversal, no matter how slight, returns the control valve to its normally open state in the extension direction.
In addition, of the behavior that we have observed thus far, the results are consistent with the fact that Fronek's 3 Kip Extension bleed orifice also happens to be its smallest, having a nominal cross section dimension of 0.005".
By comparison, the dimensions of the orifices in the 3 Kip Compression, 10 Kip Extension and 10 Kip Compression directions are 0.007", 0.006" and 0.009", respectively. We have witnessed only occasional partial blockages in the larger orifices and that the apparent likelihood of those partial blockages becomes even more infrequent as the orifice size increases. One can reasonably expect that the orifices in the larger bore snubbers, which are incrementally larger with increasing bore size, will exhibit further diminished probability of becoming partially blocked from the effects of the defective fluid.
Fronek A/DE, Inc.
To: Bergen Power Pipe Supports January 12, 2007 PO Box 461 (alt. 484 Galiffa Drive)
Donora, PA 15033 We believe that our initial approach to the testing completed thus far has been very conservative, for three primary reasons:
- 1) The objective in this initial test phase was to overestimate the concentration of the particulate in the test units to obtain results which should reasonably exceed the expected probability of flow blockage in field installations.
The difficulty in quantifying the initial amount of particulate and then measuring the amount introduced into the test units would have unnecessarily delayed this initial test phase. We chose a conservative visual means of introducing the amount of particulate into the test units which we believe to be no less than twice that amount observed in the original sample.
- 2) At various intervals in the testing sequence, we change the orientation (with respect to gravity) of the test unit. We do so because we have observed that the larger particulate settles to the lowest point in the fluid at a relatively rapid rate (all but the finest particles settle out in approximately 10 to 20 minutes). We flip the unit upside-down from its test orientation and stroke it several times in an effort to keep the majority of the particulate in suspension. We then flip it back and then immediately run the next series of tests.
- 3) We are also running the bleed portion of the test for a much longer duration (nearly full stroke) than a typical Snubber Performance Test (SPT). In a typical SPT, the bleed portion of the test (conducted post-activation while the snubber remains locked at rated load) requires approximately 5 to 10 seconds. This is normally a sufficient length of time for the bleed rate to reach a steady-state condition. That 5 to 10 seconds equates to moving the snubber through about 1 inch of its stroke. The test data thus far suggests that it would be highly unlikely to detect the presence of the defective fluid during a test having a bleed duration this short. All of the flow blockages observed thus far, either total blockages or partial ones, have not occurred until approximately 2 to 3 inches of stroke have been traversed while at rated load. The nature of these blockages does not provide sufficient evidence which can be used to unequivocally state that the presence of the particulate will never be detected during a typical SPT, but at this point in time, the data indicates that this is the most probable result.
Further, we have found that the fluid particulate, introduced into our test units in the way that it has, has no discernible effect on snubber Drag characteristics, nor has it impacted the snubber's Lock-Up characteristics. At this point in the evaluation, all of the observed behavior leads us to reasonably assert that Fronek snubbers which contain this fluid will remain unaffected with regard to their intended seismic function.
We trust that the above information serves to address the immediate concerns of Bergen Power with regard to snubbers which are filled with this particular batch of SF1154 and that we assume are installed in Nuclear Power Plants subject to the provisions of 10 CFR 21 Reporting. A formal evaluation report will be forthcoming and distributed to all parties involved in accordance with the provisions of 10 CFR 21.21 (d)(4). It will present the above test results and the results from more of our future testing. However, we believe that the best impending test results, i.e., the results that will bear the best information with regard to snubber performance, will be obtained from units that were filled with this batch of fluid sometime ago. Toward that end, we intend to contact anyone who may be able to provide such units, or provide us with field test results obtained from such snubbers, in order for us to conduct the most thorough evaluation possible. If we can be of further assistance, please contact us.
Best Regards, Walter Paszul, PE General / Engineering Manager c: Thorn Wormhood, QA Mgr.
Attachment
Attachment to Bergen Power 10CFR21 Notification Letter, Dated January 12, 2007 Fronek S/O# Qty Description Serial Nos. BP PO No. PO Line No. BP Tag No Ship Date HUN3807 4 70 Kip x 6" Snubber ADH-7003-162 thru -165 #11628 1 7755a 04/17/2002 1 50 Kip x 6" Snubber ADH-5003-475 2 1 20 Kip x 6" Snubber ADH-2003-1560 3 HUN3907 1 50 Kip x 6" Snubber ADH-5001-476 #11659 1 7801a 06/20/2002 4 10 Kip x 6" Snubber ADH-1001-3275 thru -3278 2 HUN3942 3 3 Kip x 6" Snubber ADH-300-2634,-2635 & -2636 #11683 1 7831a 08/28/2002 HUN4144 1 30 Kip x 6" Snubber ADH-3000-900 #11805 1 802dy 08/20/2003
BERGEN POWER PIPE SUPPORTS P.O. Box 461 (724) 379-5212 Donora, PA 15033 (724) 379-9363 Fax January 15, 2007 TVA Nuclear Nuclear Assurance and Licensing 1101 Market Street Chattanooga , TN 37402-2801 Attn: Manager, Operating Experience.
Subject:
10 CFR 21 Notification Identification of Defect NRC Event no. 43071 Enclosed is a copy of a 10CFR21 Notification that Bergen Power has received from Fronek A/DE concerning Hydraulic Snubbers filled with GE SF1154 Silicone fluid, Batch AD965. One (1) 30 Kip Hydraulic Snubber, A/DE serial No. ADH-3000-900 containing this fluid was furnished to your facility on your PO No.
00001630 Release 00098, Item No. 1 in September, 2003 A copy of this notification has been forwarded to the US NRC Ifwe can be of further assistance, please contact us.
Thomas P. Haynes QA Manager e-mail: tomjhaynes@bergenpower.com cc: James M. Bonetti President
BERGEN POWER PIPE SUPPORTS P.O. Box 461 (724) 379-5212 Donora, PA 15033 (724) 379-9363 Fax January 15, 2007 Entergy Nuclear Northeast James A. Fitzpatrick NPP 268 Lake Road Lycoming, NY 13093 Attn: Vice President Operations
Subject:
10 CFR 21 Notification Identification of Defect NRC Event no. 43071 Enclosed is a copy of a I0CFR21 Notification that Bergen Power has received from Fronek A/DE concerning Hydraulic Snubbers filled with GE SF1154 Silicone fluid, Batch AD965. Three (3) 3 Kip Hydraulic Snubbers, A/DE serial No. ADH-300-2634, -2635 & -2636 containing this fluid were furnished to your facility on your PO No. 4500514359, Item No. 1 in September, 2002 A copy of this notification has been forwarded to the US NRC If we can be of further assistance, please contact us.
Thomas P. raynes QA Manager e-mail: tomhaynes@bergenpower.com cc: James M. Bonetti President
BERGEN POWER PIPE SUPPORTS P.O. Box 461 (724) 379-5212 Donora, PA 15033 (724) 379-9363 Fax January 15, 2007 Eletrobras Termonuclear S.A Gerencia de Suprimentos -GSU A Rua da Candelaria no. 65 -90 andar CEP: 20091-020 Rio de Janeiro - RJ Brasil
Subject:
10 CFR 21 Notification Identification of Defect NRC Event no. 43071 Enclosed is a copy of a 10CFR21 Notification that Bergen Power has received from Fronek A/DE concerning Hydraulic Snubbers filled with GE SF1 154 Silicone fluid, Batch AD965. One (3) 50 Kip Hydraulic Snubber, A/DE serial No. ADH-5001-476, and four (4) 10 Kip Hydraulic Snubbers, A/DE serial No. ADH-1001-3275 thru -3278 containing this fluid were furnished to your facility on your PO No. 4500034326, Item No. 1 & 2 in June, 2002 In addition, Four (4) 70 Kip Hydraulic Snubbers, A/DE serial No. ADH-7003-162 thru -165, one (1) 50 Kip Hydraulic Snubber, A/DE serial No. ADH-5003-475, and one (1) 20 Kip Hydraulic Snubber, A/DE serial No. ADH-2003-1560 containing this fluid were furnished to your facility on your PO No. 4500030221, Item No. 1 thru 5 in April, 2002 by way of Ergytech, Inc. on their PO 45030221 to us.
A copy of this notification has been forwarded to the US NRC If we can be of further assistance, please contact us.
Thomas P. Haynes QA Manager e-mail: tom-haynes@bergenpower.com cc: James M. Bonetti President
.6 BERGEN POWER PIPE SUPPORTS P.O. Box 461 (724) 379-5212 Donora, PA 15033 *(724) 379-9363 Fax January 15, 2007 Ergytech, Inc.
2400,Augusta, Suite 310 Houston, TX 77057
Subject:
10 CFR 21 Notification Identification of Defect NRC Event no. 43071 Enclosed is a copy of a 10CFR21 Notification that Bergen Power has received from Fronek A/DE concerning Hydraulic Snubbers filled with GE SF1154 Silicone fluid, Batch AD965. Four (4) 70 Kip Hydraulic Snubbers, A/DE serial No. ADH-7003-162 thru -165, one (1) 50 Kip Hydraulic Snubber, A/DE serial No. ADH-5003-475, and one (1) 20 Kip Hydraulic Snubber, A/DE serial No. ADH-2003-1560 containing this fluid were furnished to Eletrobras Termonuclear on your PO No. 45030221, Item No. 1 thru 5 in April, 2002.
A copy of this notification has been forwarded to the US NRC If we can be of further assistance, please contact us.
Thomas P. Haynes QA Manager e-mail: tom-haynes@bergenpower.com cc: James M. Bonetti President