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| | issue date = 07/28/2016 | | | issue date = 07/28/2016 |
| | title = Bnp Commercial Grade Dedication Issue (Printable) | | | title = Bnp Commercial Grade Dedication Issue (Printable) |
| | author name = Cain L M | | | author name = Cain L |
| | author affiliation = NRC/RGN-II, NRC/RGN-II/DFFI | | | author affiliation = NRC/RGN-II, NRC/RGN-II/DFFI |
| | addressee name = | | | addressee name = |
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| | docket = 05000324, 05000325 | | | docket = 05000324, 05000325 |
| | license number = | | | license number = |
| | contact person = Cain L M | | | contact person = Cain L |
| | package number = ML16010A484 | | | package number = ML16010A484 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACRS Briefing:Brunswick Nuclear Power Plant Emergency Diesel Generator Commercial Grade Dedication FindingJuly 28, 2016Mike Cain, SRI BWXT Allen Bradley700-RTC Relay2 3Integrated ChipCPLDAllen Bradley 700-RTC Relay Internals | | {{#Wiki_filter:ACRS Briefing: |
| | Brunswick Nuclear Power Plant Emergency Diesel Generator Commercial Grade Dedication Finding July 28, 2016 Mike Cain, SRI BWXT |
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| |
|
| TIMELINE*3/17/15 -Emergency diesel generator (EDG)3 output breaker fails to close during LOOP portion of LOOP/LOCA test*3/18 -New RCR and RCR-X Allen Bradley 700-RTC relays are installed, EDG3 passes LOOP/LOCA test satisfactorily*3/19-21-EDG4 taken out of service for maintenance, RCR relay is proactively replaced . EDG4 LOOP test performed, output breaker attempted to close four times (chattered) before finally closing*3/21 -all 9 Allen Bradley 700-RTC relays in stock were bench tested and all chattered*3/22 -EDG4 original RCR relay reinstalled, no chattering*3/23 -Due to EDG4 issues, EDG3 relay was re-tested and this time failed due to relay chatter. Licensee installed a suppressive diode across the RCR-X relay to prevent electromagnetic interference (EMI) determined to be the cause of the relay chatter. It was later determined that the installation of a recorder across the RCR-X relay had acted as a suppression device, masking EMI and resulting in a SAT test on 3/18 CauseWhat causes the trip of the output breaker -On a LOOP, the RCR relay has a 0.7 second time delay between the time the DG output breaker is tripped and when it can reclose (breaker itself takes longer).The RCR relay energizes first on an emergency diesel start signal, closing the contact to energize the RCR-X relay. The RCR-X relay energizes to close the DG output breaker. DG3 passed the LOOP/LOCA portion of the test where the DG is originally in standby when the output breaker is closed, but failed the subsequent LOOP portion of the test where the DG is running when the output breaker is opened and then recloses. The failure occurred when the breaker closed and reopened several times, causing an anti-pump lockout, and a trip of the output breaker. | | Allen Bradley 700-RTC Relay 2 |
| IssueTesting confirmed that the 'new' series of Allen Bradley relays had a complex programmable logic device (CPLD) instead of the old style 16 pin Motorola timing IC chip, and were now susceptible to 'DC Inductive Kick' produced by the downstream RCR-X relay when it de-energizes.5/1/15, Nuclear Logistics Inc. (NLI) issues a Part 21, stating that Allen Bradley 700-RTC relays had undergone an unannounced design change by the manufacturer sometime in the 2009-2010 timeframe. These relays are commercial grade items. Brunswick commercial grade dedication did not detect the vendor design change.A CPLD meets the NEI definition of a 'digital-device' per NEI guidance 01-01 What Happened Next*PI&R follow-up inspection conducted week of June 15*This issue was complex and encompassed several different aspects to include:*Design control
| | |
| *Operability of the other diesels*Past operating experience (North Anna, Diablo Canyon, and Vogtle). Same Brunswick EDG 3 relay chattered in 2013; however, breaker still closed*Duke commercial grade dedication processes | | Allen Bradley 700-RTC Relay Internals Integrated Chip CPLD 3 |
| *Vendor issues for both relay manufacturers and commercial grade dedication entities*Part 21 reporting *Cyber issues with the introduction of digital assets Where We Ended UpRII issued two GREEN, NRC Identified violations to Brunswick for:*Failure to meet requirements of 10CFR50 App. B, Criterion III -Design Control*Failure to meet the requirements of 10CFR50 App. B, Criterion XVI -Corrective Action, more specifically for failure to promptly identify conditions adverse to quality, one of which was significantHQs issued the following generic communications:*"The Operating Experience Note," #008, July 2015 included an article concerning the subject relays*Issued OpECOMM in August 2015 detailing the BNP issue | | |
| *Issued IN 16-01 and a RISconcerning Commercial Grade Dedication Questions | | TIMELINE |
| }} | | * 3/17/15 - Emergency diesel generator (EDG)3 output breaker fails to close during LOOP portion of LOOP/LOCA test |
| | * 3/18 - New RCR and RCR-X Allen Bradley 700-RTC relays are installed, EDG3 passes LOOP/LOCA test satisfactorily |
| | * 3/19 EDG4 taken out of service for maintenance, RCR relay is proactively replaced . |
| | EDG4 LOOP test performed, output breaker attempted to close four times (chattered) before finally closing |
| | * 3/21 - all 9 Allen Bradley 700-RTC relays in stock were bench tested and all chattered |
| | * 3/22 - EDG4 original RCR relay reinstalled, no chattering |
| | * 3/23 - Due to EDG4 issues, EDG3 relay was re-tested and this time failed due to relay chatter. Licensee installed a suppressive diode across the RCR-X relay to prevent electromagnetic interference (EMI) determined to be the cause of the relay chatter. It was later determined that the installation of a recorder across the RCR-X relay had acted as a suppression device, masking EMI and resulting in a SAT test on 3/18 |
| | |
| | Cause What causes the trip of the output breaker - |
| | On a LOOP, the RCR relay has a 0.7 second time delay between the time the DG output breaker is tripped and when it can reclose (breaker itself takes longer). |
| | The RCR relay energizes first on an emergency diesel start signal, closing the contact to energize the RCR-X relay. |
| | The RCR-X relay energizes to close the DG output breaker. DG3 passed the LOOP/LOCA portion of the test where the DG is originally in standby when the output breaker is closed, but failed the subsequent LOOP portion of the test where the DG is running when the output breaker is opened and then recloses. The failure occurred when the breaker closed and reopened several times, causing an anti-pump lockout, and a trip of the output breaker. |
| | |
| | Issue Testing confirmed that the new series of Allen Bradley relays had a complex programmable logic device (CPLD) instead of the old style 16 pin Motorola timing IC chip, and were now susceptible to DC Inductive Kick produced by the downstream RCR-X relay when it de-energizes. |
| | 5/1/15, Nuclear Logistics Inc. (NLI) issues a Part 21, stating that Allen Bradley 700-RTC relays had undergone an unannounced design change by the manufacturer sometime in the 2009-2010 timeframe. |
| | These relays are commercial grade items. Brunswick commercial grade dedication did not detect the vendor design change. |
| | A CPLD meets the NEI definition of a digital-device per NEI guidance 01-01 |
| | |
| | What Happened Next |
| | * PI&R follow-up inspection conducted week of June 15 |
| | * This issue was complex and encompassed several different aspects to include: |
| | * Design control |
| | * Operability of the other diesels |
| | * Past operating experience (North Anna, Diablo Canyon, and Vogtle). Same Brunswick EDG 3 relay chattered in 2013; however, breaker still closed |
| | * Duke commercial grade dedication processes |
| | * Vendor issues for both relay manufacturers and commercial grade dedication entities |
| | * Part 21 reporting |
| | * Cyber issues with the introduction of digital assets |
| | |
| | Where We Ended Up RII issued two GREEN, NRC Identified violations to Brunswick for: |
| | * Failure to meet requirements of 10CFR50 App. B, Criterion III - |
| | Design Control |
| | * Failure to meet the requirements of 10CFR50 App. B, Criterion XVI |
| | - Corrective Action, more specifically for failure to promptly identify conditions adverse to quality, one of which was significant HQs issued the following generic communications: |
| | * The Operating Experience Note, #008, July 2015 included an article concerning the subject relays |
| | * Issued OpE COMM in August 2015 detailing the BNP issue |
| | * Issued IN 16-01 and a RIS concerning Commercial Grade Dedication |
| | |
| | Questions}} |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML21041A4532021-02-17017 February 2021 Brunswick/Nrc Pre-submittal Meeting: LAR to Adopt TSTF-505, Rev. 2 (Risk-Informed Completion Times) Presentation ML21011A0822021-01-12012 January 2021 Pre-Submittal Meeting January 12, 2021, Revision to VRR-01, Full Stroke Testing of Safety/Relief Valves - Presentation Material ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting Slides ML20034F2842020-02-0303 February 2020 Implementation of TSTF-564 - NRC Conference Call - February 5, 2020 ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17297B7892017-10-26026 October 2017 Meeting Slide for Partially Closed Pre-submittal Public Meeting with Duke Energy for License Amendment Request to Adopt Areva'S XM-11 Fuel Methodology for Brunswick Steam Electric Plant ML17229B2942017-08-22022 August 2017 Meeting Slide Regarding Partially Closed Pre-submittal Public Meeting with Duke Energy for a License Amendment Request for Brunswick Steam Electric Plant ML16231A1322016-08-18018 August 2016 Materials for 8/18/16 Pre-Application Meeting Brunswick Mellla+ LAR ML16210A5152016-07-28028 July 2016 Bnp Commercial Grade Dedication Issue (Printable) ML16134A1742016-05-12012 May 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Brunswick, Units 1 and 2 ML15125A4602015-05-0505 May 2015 Summary of Public Meeting to Discuss the Annual Assessment of the Brunswick Steam Electric Plant with the Public for the Period of January 1, 2014, Through December 31, 2014 ML14140A1882014-05-19019 May 2014 Summary of Public Meeting - 2013 Annual Assessment Regrading Brunswick Steam Electric Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13277A0382013-09-24024 September 2013 GEH Presentation on Methods Applicability to Areva Atrium 10XM Fuel ML13277A0372013-08-20020 August 2013 Duke Energy Presentation - Brunswick Mellla+ Methods Applicability, Pre-Application Meeting, August 20, 2013 ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML12188A0712012-07-11011 July 2012 G20120473/ EDATS: OEDO-2012-0404 - Briefing Book - Briefing Package for Meeting with Duke Energy on July 11, 2012 ML12158A3442012-06-0606 June 2012 Meeting Slides for Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2 ML12152A1452012-05-31031 May 2012 20120531 Bnp NRC Pre-LAR Application Meeting Final ML1115109972011-05-31031 May 2011 Category 1 Public Meeting - Meeting Summary - Annual Assessment of Brunswick Steam Electric Plant ML1020304622010-07-20020 July 2010 Groundwater Protection Status ML1016705232010-06-0808 June 2010 NRC Fire Protection Screening Criteria, Brunswick Nuclear Plant ML1015404182010-05-27027 May 2010 Meeting Summary - Public Meeting - Brunswick Steam Electric Plant Annual Assessment - Reactor Oversight Program 2009 Presentation Slides ML1001507632010-01-15015 January 2010 Meeting Presentation Brunswick Nuclear Plant Human Performance ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML1019404532008-05-21021 May 2008 Email from Grzeck, Lee to Heather Gepford, Austin, Joe, George Kuzo, England, Louise, Kemp, Daniel and Dale.Dusenbury@Ncmail.Net; Subject: Storm Drain Collection Basin and Storm Drain Stabilization.Pdf; Sampling Locations Data Updated 5-19- BSEP 07-0108, Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request2007-07-31031 July 2007 Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request ML0711503272007-04-23023 April 2007 Brunswick, EOC Slides, Cy 2006 ML0710803842007-04-18018 April 2007 Presentation Slides from Public Management Meeting to Discuss Brunswick Site and Emergency Diesel Generator Improvements ML0710804062007-04-0505 April 2007 Emergency Diesel Generator No. 1 Trip and Failure of Engine Crankshaft Bearing ML0615301932006-03-27027 March 2006 NFPA 805 Pilot Observation Visit Trip Report - March 2006 - Handouts ML0607903052006-03-10010 March 2006 Meeting Handouts for Summary of Meeting W/Carolina Power & Light Regarding the Fuel Transition Process and Licensing Submittals for Brunswick, Units 1 & 2 ML0529003762005-10-0505 October 2005 Meeting with Carolina Power & Light, Meeting Handouts, MSIV Leakage Rate Limit License Amendment Request ML0523604402005-08-11011 August 2005 Attachment 4 - Progress Energy Slides ML0511004572005-04-12012 April 2005 NRC CY2004 Annual Assessment Meeting - Brunswick - Southport, North Carolina, April 12, 2005 ML0504003192005-02-0404 February 2005 Summary of Meeting with Progress Energy Re Brunswick Steam Electric Plant ML0503902102005-01-27027 January 2005 Scoping Meeting Slides Re Brunswick Steam Electric Plant, Units 1 & 2 ML0436402692004-12-0909 December 2004 Progress Energy, Meeting Briefing of 12/9/04, Fire Protection Program ML0901504242004-08-25025 August 2004 Progress Energy Carolinas, Inc., Handouts for the Brunswick and H.B. Robinson NPP Tours During the Shearon Harris Scol Environmental Site Audit of Alternative Sites ML0403505052004-01-0707 January 2004 Meeting Handouts with Progress Energy to Discuss Fire Protection Initiatives ML0333601902003-11-25025 November 2003 Meeting Summary - Brunswick Steam Electric Plant ML0327206212003-09-24024 September 2003 Examiner - Vendor Matrix with Phone Number 2024-04-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22109A2122022-04-20020 April 2022 Duke Energy Pre-Submittal Public April 20, 2022, Meeting Presentation ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML21322A3262021-11-29029 November 2021 Duke Energy November 29, 2021 Pre-Submittal Public Meeting Slides for EOF Relocation Licensing Amendment Request ML21090A1162021-03-31031 March 2021 Combined 2020 Aam Presentation ML21041A4532021-02-17017 February 2021 Brunswick/Nrc Pre-submittal Meeting: LAR to Adopt TSTF-505, Rev. 2 (Risk-Informed Completion Times) Presentation ML21033A7022021-02-0303 February 2021 Pre-submitting for Planned LAR for Standby Liquid Control Tank Volume Increase ML21011A0822021-01-12012 January 2021 Pre-Submittal Meeting January 12, 2021, Revision to VRR-01, Full Stroke Testing of Safety/Relief Valves - Presentation Material ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting Slides ML20099C9992020-04-0808 April 2020 Har 2019 Mtg Slides ML20099D1282020-04-0808 April 2020 Bru 2019 Mtg Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML19123A3532019-05-0202 May 2019 Public Meeting Summary - Brunswick Steam Electric Plant, Docket Nos. 05000325 and 05000324 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17297B7892017-10-26026 October 2017 Meeting Slide for Partially Closed Pre-submittal Public Meeting with Duke Energy for License Amendment Request to Adopt Areva'S XM-11 Fuel Methodology for Brunswick Steam Electric Plant ML17229B2942017-08-22022 August 2017 Meeting Slide Regarding Partially Closed Pre-submittal Public Meeting with Duke Energy for a License Amendment Request for Brunswick Steam Electric Plant ML16231A1322016-08-18018 August 2016 Materials for 8/18/16 Pre-Application Meeting Brunswick Mellla+ LAR ML16210A5152016-07-28028 July 2016 Bnp Commercial Grade Dedication Issue (Printable) ML16134A1742016-05-12012 May 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Brunswick, Units 1 and 2 ML14140A1882014-05-19019 May 2014 Summary of Public Meeting - 2013 Annual Assessment Regrading Brunswick Steam Electric Plant ML14135A5092014-04-17017 April 2014 Enclosure 1 to BSEP 14-0048, Duke Energy Presentation - Brunswick Mellla+ Methods Applicability, Pre-Application Meeting ML14135A5112014-04-17017 April 2014 Enclosure 4 to BSEP 14-0048 - Areva Mellla+ Methods Applicability Presentation (Non-Proprietary Version) ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13277A0382013-09-24024 September 2013 GEH Presentation on Methods Applicability to Areva Atrium 10XM Fuel ML13277A0372013-08-20020 August 2013 Duke Energy Presentation - Brunswick Mellla+ Methods Applicability, Pre-Application Meeting, August 20, 2013 ML13130A2552013-05-10010 May 2013 4/24/2013 - Meeting Summary - Category 3 Public Meeting - Annual Assessment of Brunswick Steam Electric Plant ML12181A0362012-06-29029 June 2012 Meeting Summary - Category 1 Public Meeting - Annual Assessment of Brunswick Steam Electric Plant, Docket Nos. 50-325, 50-324 ML12158A3442012-06-0606 June 2012 Meeting Slides for Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2 ML11102A0052011-04-12012 April 2011 Progress Energy - Slides for NFPA 805 Pre-LAR Application Meeting April 12, 2011 ML1020304622010-07-20020 July 2010 Groundwater Protection Status ML1016705232010-06-0808 June 2010 NRC Fire Protection Screening Criteria, Brunswick Nuclear Plant ML1015404182010-05-27027 May 2010 Meeting Summary - Public Meeting - Brunswick Steam Electric Plant Annual Assessment - Reactor Oversight Program 2009 Presentation Slides ML1001507632010-01-15015 January 2010 Meeting Presentation Brunswick Nuclear Plant Human Performance ML1001507042010-01-14014 January 2010 Human Performance Slides ML0930206712009-10-22022 October 2009 Emergency Diesel Generators - Progress Energy ML1019400952009-10-0808 October 2009 Marsh, River, and Creek Tritium Results Updated 10/08/09 ML1019400932009-10-0808 October 2009 Groundwater Well Samples Results, Updated 10/08/09 ML0923210802009-08-20020 August 2009 MELLLA Plus Implementation ML0921609632009-08-0404 August 2009 Meeting Summary - Public Meeting Category 1 - Preliminary White Finding - Brunswick Steam Electric Plant ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML1019404532008-05-21021 May 2008 Email from Grzeck, Lee to Heather Gepford, Austin, Joe, George Kuzo, England, Louise, Kemp, Daniel and Dale.Dusenbury@Ncmail.Net; Subject: Storm Drain Collection Basin and Storm Drain Stabilization.Pdf; Sampling Locations Data Updated 5-19- ML0813006662008-05-0101 May 2008 EOC 2007 Progress Energy Slides ML0813006582008-05-0101 May 2008 EOC 2007 NRC Slides ML1019405012008-04-0101 April 2008 Annual Report Slides BSEP 07-0108, Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request2007-07-31031 July 2007 Areva Presentation Slides for Brunswick Fuel Transition License Amendment Request ML0711503272007-04-23023 April 2007 Brunswick, EOC Slides, Cy 2006 2024-04-09
[Table view] |
Text
ACRS Briefing:
Brunswick Nuclear Power Plant Emergency Diesel Generator Commercial Grade Dedication Finding July 28, 2016 Mike Cain, SRI BWXT
Allen Bradley 700-RTC Relay 2
Allen Bradley 700-RTC Relay Internals Integrated Chip CPLD 3
TIMELINE
- 3/18 - New RCR and RCR-X Allen Bradley 700-RTC relays are installed, EDG3 passes LOOP/LOCA test satisfactorily
- 3/19 EDG4 taken out of service for maintenance, RCR relay is proactively replaced .
EDG4 LOOP test performed, output breaker attempted to close four times (chattered) before finally closing
- 3/21 - all 9 Allen Bradley 700-RTC relays in stock were bench tested and all chattered
- 3/22 - EDG4 original RCR relay reinstalled, no chattering
- 3/23 - Due to EDG4 issues, EDG3 relay was re-tested and this time failed due to relay chatter. Licensee installed a suppressive diode across the RCR-X relay to prevent electromagnetic interference (EMI) determined to be the cause of the relay chatter. It was later determined that the installation of a recorder across the RCR-X relay had acted as a suppression device, masking EMI and resulting in a SAT test on 3/18
Cause What causes the trip of the output breaker -
On a LOOP, the RCR relay has a 0.7 second time delay between the time the DG output breaker is tripped and when it can reclose (breaker itself takes longer).
The RCR relay energizes first on an emergency diesel start signal, closing the contact to energize the RCR-X relay.
The RCR-X relay energizes to close the DG output breaker. DG3 passed the LOOP/LOCA portion of the test where the DG is originally in standby when the output breaker is closed, but failed the subsequent LOOP portion of the test where the DG is running when the output breaker is opened and then recloses. The failure occurred when the breaker closed and reopened several times, causing an anti-pump lockout, and a trip of the output breaker.
Issue Testing confirmed that the new series of Allen Bradley relays had a complex programmable logic device (CPLD) instead of the old style 16 pin Motorola timing IC chip, and were now susceptible to DC Inductive Kick produced by the downstream RCR-X relay when it de-energizes.
5/1/15, Nuclear Logistics Inc. (NLI) issues a Part 21, stating that Allen Bradley 700-RTC relays had undergone an unannounced design change by the manufacturer sometime in the 2009-2010 timeframe.
These relays are commercial grade items. Brunswick commercial grade dedication did not detect the vendor design change.
A CPLD meets the NEI definition of a digital-device per NEI guidance 01-01
What Happened Next
- PI&R follow-up inspection conducted week of June 15
- This issue was complex and encompassed several different aspects to include:
- Operability of the other diesels
- Past operating experience (North Anna, Diablo Canyon, and Vogtle). Same Brunswick EDG 3 relay chattered in 2013; however, breaker still closed
- Cyber issues with the introduction of digital assets
Where We Ended Up RII issued two GREEN, NRC Identified violations to Brunswick for:
- Failure to meet requirements of 10CFR50 App. B, Criterion III -
Design Control
- Failure to meet the requirements of 10CFR50 App. B, Criterion XVI
- Corrective Action, more specifically for failure to promptly identify conditions adverse to quality, one of which was significant HQs issued the following generic communications:
- The Operating Experience Note, #008, July 2015 included an article concerning the subject relays
- Issued OpE COMM in August 2015 detailing the BNP issue
Questions