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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24004A2092023-12-12012 December 2023 Flowline, Inc. - Interim Part 21 Report Notification Regarding Supply of 1 Sch. 80 (0.179 Wall) SB466 Uns C71500 Buttweld Long Radius 90 Degree Elbow; Manufacturer: Flowline; Heat No: 27668; 27 Pieces - Heat Code ML23352A2382023-12-0808 December 2023 56882-EN 56882 - Tioga Pipe, Inc Interim Part 21 Report Re Supply of 1 Inch Sch. 80 SB466 Uns C71500 Buttweld Long Radius 90 Degree Elbow ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML21322A0512021-10-27027 October 2021 Paragon Energy Solutions, LLC, P21-09282021, Rev. 0, Final Notification of a Deviation with Inverter Assembly (Model NLI-072034-CSI-K-5-A) ML21295A2472021-10-18018 October 2021 Engine Systems, Inc., Part 21 Reportable Notification on a Pressure Regulator Valve ML21260A0072021-09-0909 September 2021 Ametek Solidstate Controls, Notification of Potential Defect - 10CFR Part 21 Report Re Omron Timer Relay ML19024A1642019-01-0707 January 2019 Ametek - Notification of Potential Defect - 10CFR Part 21 Re Solidstate Controls Safety-Related Operational Spare Parts Kits ML18102A5292018-04-0303 April 2018 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0121, Rev. 0, Refurbished Pressure Regulator Assembly, P/N 1776 506. ML18087A0032018-03-21021 March 2018 Crane Nuclear, Inc. - Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve (Updated) ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML18079A0142018-03-0606 March 2018 Crane Nuclear, Inc., 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl I0x8x10 and 6x4x6 Bolted Bonnet Gate Valve 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 ML17142A3232017-05-11011 May 2017 Interim Report Concerning Supply of Stainless Steel Tubing ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16281A2712016-09-30030 September 2016 Part 21 - Safety Related Component Welding by an Unqualified Welder ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves ML16243A4752016-08-26026 August 2016 Part 21 Safety Related Component Welding by an Unqualified Welder ML16188A3742016-06-30030 June 2016 Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna ML15265A4182015-09-21021 September 2015 Sor, Inc. - Part 21 Notification of Deviation - ML15251A212 Irradiation Certification with Insufficient Margin BSEP 15-0054, Part 21 Notification Regarding Allen Bradley Model 700RTC Relays2015-06-25025 June 2015 Part 21 Notification Regarding Allen Bradley Model 700RTC Relays ML15162A0232015-06-0909 June 2015 Part 21 - Incorrect Part Number Relay Shipped to Brunswick Nuclear Plant ML15173A0162015-06-0808 June 2015 Engine Systems, Inc. - 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 10CFR21-0112, Rev. 0, Incorrect Relay Installed in Governor Control Panel, P/N 8002096-PANEL ML15155A5772015-05-28028 May 2015 Part 21 Notification Regarding Allen Bradley 700RTC Relay Configuration ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring 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 ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0092014-07-21021 July 2014 Part 21 Report - Incorrect Valve Solenoids Provided ML14070A1832014-02-14014 February 2014 Part 21 Report - Failed Pressure Regulator During Post Installation EDG Pressure Testing ML13340A3822013-12-0505 December 2013 Part 21 Reportable Condition Notification: Failure of Relay Logic Card Modules in 2 Out of 4 Voters ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve 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 ML12318A0412012-11-0808 November 2012 Part 21 Report - Commercial Grade Dedication Not Properly Applied to Butterfly Valves ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12177A0562012-06-21021 June 2012 Part 21 - Reliability Degradation of Resistors in Trip Units and Readout Assemblies ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12123A0892012-04-27027 April 2012 Abb, Inc., Notification of Potential Part 21 Report - Hk Circuit Breaker Studs Failed to Meet Specification 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 ML11278A0762011-09-28028 September 2011 Abb, Inc. - 10 CFR Part 21 Notification of Potential Defect, Solid State Relays - Update of Previous Notification 2023-05-24
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0512812015 U.S. Nuclear Regulatory Commission OperationsCenter Event Report page I Power Reactor Event# 51095 Site: BRUNSWICK Notification Date I Time: 05/28/2015 13:18 (EDT)
Unit: 1 2 Region: 2 State : NC Event Date I Time: 05/26/2015 15:36 (EDT)
Reactor Type: [1] GE-4,[2] GE-4 Last Modification: 05/28/2015 Containment Type: MARK I MARK I NRC Notified by: MARK TURKAL Notifications: KATHLEEN O'DONOHUE R2DO HQ Ops Officer: JOHN SHOEMAKER PART 21/50.55 REACTOREMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
21.21(d)(3)(i) DEFECTS AND NONCOMPLIANCE Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 100 Power Operation 100 Power Operation 2 N Yes 100 Power Operation 100 Power Operation PART 21 NOTIFICATION - ALLEN BRADLEY 700RTC RELAY CONFIGURATION "This is a non-emergency notification, required by 10 CFR 21.21 (d)(3)(i).
"Brunswick has determined that Allen Bradley relays, base model 700RTC, contain an unevaluated Complex Programmable Logic Device (CPLD). This was an unpublished design change that was implemented to replace an obsolete integrated circuit chip. The undocumented design change did not result in a part number change from Allen Bradley. There was no change to the external appearance of the relay that would indicate that a design change had been made to the relay configuration. Therefore, qualification/dedication of the modified relays have not included additional testing for the new CPLD component. Testing, performed by Duke Energy, has demonstrated that this CPLD can be affected by electrical noise from operation of nearby relays which can reset the timing of the relay. This condition was discovered as a result of a post-maintenance test of an emergency diesel generator. Additional details associated with the discovery of this condition are contained in Brunswick Licensee Event Report 1-2015-002, dated May 20, 2015.
"Brunswick purchased, as commercial grade, 25 of the modified Allen Bradley 700RTC relays beginning in October, 2008. Duke Energy dedicated these relays for use in safety related applications at Brunswick. The dedicated relays were not provided to any third party customers.
"The NRC Senior Resident Inspector has been notified."
Brunswick has taken applicable compensatory measures to insure no equipment is inoperable because of these relays.
This problem was previously reported in EN#51030.
9£e.
05/28/2015 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page I PAGE 01/02 9104573014 PROGRESS ENERGY BNP 05/28/2015 11:57 Fax" To: NRC Operations Center From: Mark Turkal - Brunswick Fax 301 816-5151 Pages: 2 (Cover p!us 1)
Phone: 301 816-5100 Dat? 5/28/15 Re. Part 21 - Allen Bradley Relays CC: N/A
I -
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PROGRESS ENERGY BNP PAGE 02/02 05/28/2015 11:57 9104573014 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-200o) OPERATIONS CENTER REACTOR PLANT I EVENT NOTIFICATION WORKSHEET EN #
NRC f OPERATION 8d01415-0550TELEPHONE NUMBER: PRIMARY ., 301-816-5100 or 800-532.3469, and f3rdl 301-415-0553 *ilesnseeswhoBACKUPS llst]
maintain -their own 301-951-0550 or 800-449-3694" FT am nrnulrded these talenhone numbat.
NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
Brunswick 1& 2 Mark Turkal (910) 457-3066 EVENT TIME &ZONE EVENT DATE POWERIMODE BEFORE POWER/MOOE AFT* R 1536 EDT' 05/2612015 Unit 1; &2 - 100% 1Mode'l Unit 1 &2 - 100% 1Mode 1 EVENT CLASSIFICATIONS 1,-Hr. Non-Emergancy 10 CFR 60(72(b)(1) 5 (vXA) 5/ Oanllity Wte AINA oj GENERAL EMERGENCY GENIAMEG TS Deiation ADEY 'E5 0)(9) RHR capebflitY AINS O SITU AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 80,72(b 2) 0 CMC) Con*,i 0?Red Release AING O ,LERT AEAEC -- ,.L(I) TS RequIred S/D ASHU [E (vy)(D) AccidentMitilation AINDg E] UNUSUAL EVENT UNU/AAEC [J (lxA) ECCS *ischarge to RCS ACCES (xli) OffslehMedlcmal AMED El 50.72 NON-EMERGENCY -(see nect olumn) " (lvXB) RPf ACtion (warn) ARPS E] (xAI Loss Commn/Aarnt/esp ACOM
[3 PHYSICAL SECURITY 73.71) ODDD 5* x) I Oftt Nodlmlceion APRE 60-Day O tional 10 CFR 5(.73(X 1)
[o MATERIAIX( SURE B??? 8-Hr.iNon-Emrgeny 10 CFR 50.72(b)(3) Invlid Specified Sy7lemActlon AINV o FITNESS FOR DUTY" HFIT 5] (i)4A) 0taded Condition ADEG Other Unspecified Requlemnent (Identff*)
o OTHER UNSPECIFIO REOMT. (seelasteolurn) f (i,(B) Unaalyzed Co4nditlon AUNA 0 10 CFR 21.21 - Defects & Noncompliance NONR O0 iNFORMIATiON ONLY NiNIP Wv cuainAS PAi NN DESCRIPfTON Include: Systems effec*d, actuaons afd their initmtng ignals, causes, effect of event on plmt, acions %ken or plann-e, etc. (Cofniru on bntcl ALLEN BRADLEY 700RTC RELAY CONFIGURATION This is a non-emergency notification, required by 10 CFR 21.21(d)(3)(i).
Brunswick has determined that Allen Bradley relays, base model 700RTC, contain an unevaluated Complex Programmable Logic Device (CPLD). This was an unpublished design change that was implemented to replace an obsolete integrated circuit chip. The undocumented design change did not result in a part number change from Alien Bradley. There was no change to the external appearance of the relay that would indicate that a design change had been made to the relay configuration. Therefore, qualification/dedication of the modified relays have not included additional testing for the new CPLD component. Testing, performed by Duke Energy, has demonstrated that this CPLD can be affected by electrical noise from operation of nearby relays which can reset the timing of the relay. Tibs condition was discovered as a result of a post-maintenance test of an emergency diesel generator. Additional details'associated with the discovery of this condition are contained in Brunswick Licensee Event Report 1-2015-002, dated May 20, 2015.
Brunswick purchased, as commercial grade, 25 of the modified Allen Bradley 700RTC relays beginning in October, 2008. Duke Energy dedicated these relays for use In safety related applications at Brunswick. The dedicated relays were not provided to any third party customers.
The NRC Senior Resident Inspector has been notified.
/!:1 1NO"!1(ATIONS 'YES NO0MILL I BeANYTHING E UNUSUAL OR 'flYS (!,Iait above) [ O IO NRC RESIDENT " 07.1f4 L. NOT UNDERSTOOD?
STATE(s) LI £ 0JDID ALL SY'STEMSWES]N (xpanaoe NO (Expiaan above)
LOCAL .- - FUNCTION AS REQUIRED? Z6Y OTHER GOV AGENCIES, _C3 .r Q to r OPAR.T:STIMAT"D OpaTION. Rp ADDI7I0ONA- INFO CN BACK MIEDIAPRWES RELEASIEI 0 0 _0_
EI UNTILCORREC'TUO I ,.(M.MU$" [] NIA RES1ATE N YE NOs NRCF0RMW1 (12-2000)
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