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Category:Deficiency Report (per 10CFR50.55e and Part 21)
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Calhoun, Perry, River Bend, South Texas Project ML15357A0422015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML16020A4762015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML15205A2892015-07-24024 July 2015 Notification of Part 21 Report - Deviation in Nozzle Modeling Internal Reports ML15188A0662015-06-25025 June 2015 Part 21 Report - Deviation in Nozzle Modeling Internal Reports ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML15159A5682015-04-30030 April 2015 Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML15089A4372015-03-20020 March 2015 Part 21 - Dual Alarm Modules That May Contain Faulty Diodes in Single State Relays ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14174A9362014-06-16016 June 2014 Retraction of Interim Part 21 Notification Report ML14113A5882014-04-21021 April 2014 Interim Part 21 Notification Report ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13102A3032013-04-10010 April 2013 Part 21 Involving a Potential Weld Defect ML13063A4432013-03-0101 March 2013 10 CFR Part 21 Report Notification, Dual Alarm Modules and Single Alarm Modules 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 ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12137A1952012-05-11011 May 2012 Enersys, Inc., Interim Report Concerning Battery Cells with Potentially Reduced Discharge Capacity ML12136A5632012-05-0707 May 2012 Letter from William R. Ross to NRR, Follow Up to the Interim Report Sent to the Commission by Enersys on March 12, 2012 ML12073A3472012-03-13013 March 2012 Interim Report Concerning Battery Cells with Potentially Reduced Discharge Capacity ML12073A3512012-03-12012 March 2012 Notification of Potential 21 Report in Regards to a 2GN-23 Battery Manufactured by Enersys and Installed as Part of Station Battery 2-2 at the Dominion Virginia Power ML0915202562009-05-29029 May 2009 Notification of Potential Part 21 Re Missing Parts on Asco Solenoid Valves ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0903502172009-01-27027 January 2009 Notification of Potential Part 21 Report from Fisher Controls International - Water Quality Deficiency ML0831900172008-11-12012 November 2008 Notification of Potential Part 21 on All Dimensionally Verified Commercial Grade Items Processed Per Fisher Manufacture Procedure Fmp 2K28 ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches ML0734402112007-12-0707 December 2007 Deficiency Report Part 21 Potential Insufficient Thread Engagement for Certain Pressure Transmitters ML0732000862007-11-0909 November 2007 Notification of Potential Part 21 Report Conval Valves Weld Qualifications ML0727503422007-09-26026 September 2007 Notification of Potential Transnuclear Part 21 Re Dry Cask Canister Documentation Lost ML0727504702007-09-21021 September 2007 MPR Associates, Inc. - Report of Defect in Accordance with 10 CFR 21 ML0721203252007-07-27027 July 2007 Part 21 Notification - Failure of Enersys (Exide) Battery for North Anna, Units 1 & 2 ML0710002292007-04-0606 April 2007 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1152 Pressure Transmitters 2023-09-06
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 2326 1 March 9 , 2005 U.S. Nuclear Regulatory Commission Serial No.05-069 Attention: Document Control Desk NL&OS/ETS Rev. 1 Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 N PF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2 PART 21 NOTIFICATION - IDENTIFICATION OF DEFECT Pursuant to 10 CFR 21.21.d, Dominion is providing the required 30-day written notification of the identification of a defect. This information was initially reported to the NRC Operations Center on February 10, 2005. During pre-installation testing of Allen-Bradley 700RTC relays, abnormal contact response was observed. The attachment to this letter provides the information requested by 10 CFR 21.21.
This letter does not establish any new commitments. Should you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.
Very truly yours, W
Leslie N. Hartz Vice President - Nuclear Engineering Attach ment
cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. M. S. King NRC Senior Resident Inspector North Anna Power Station Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike MaiI Stop 8- H12 Rockville, Maryland 20852 Mr. J. E. Reasor Old Dominion Electric Cooperative lnnsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060
Attachment 10 CFR 21.21 Notification Allen-Bradley 700RTC Relays Virginia Electric and Power Company (Dominion)
North Anna Power Station Units 1 and 2
Part 21 - Regarding the abnormal response of Allen-Bradley 700RTC relays when configured with the NC contact in the C5C6 position.
Responsible Officer: W. R. Matthehs. Senior Vice President - Nuclear Operation 5000 Dominion I3lvd.
Glen Allen. Virginia, 23060 Event Date: February 8. N O 5 Unit Name: North Anna Power Station Component Information (as applicable):
Manufacturer: Allen-Bradley Part Number: 700RTC I I I IOU1
==
Description:==
Abnormal contact response was observed during pre-installation testing of Allen-Bradley 700RTC relays. The 700RTC relays are solid state timing relays used in several Safety Related applications at North Anna. The 700RTC relay provides a wide time adjustment. The relay has two timed contact positions and two instantaneous contact positions. The relays are ordered to a part number that specifies a certain contact arrangement, but the contacts are fully interchangeable and may be configured by the end user in any combination of Normally Open/Normally Closed (NO/NC). Removable contact cartridges mount in the contact slots. At North Anna, Allen-Bradley part number 700RTC11 I IOU I i s used, which is a contact configuration of NO, NC, NO, NC.
The relays were setup and tested in a NO, NO, NC, NC configuration when it was discovered that the instantaneous contact (CS-C6 position), with a NC contact cartridge installed, behaved like a timed contact. The CS-C6 position changed state according to the setting of the timer. All other contact positions worked properly. With a NO contact installed in the C5-C6 position, the contact position behaved as expected (as an instantaneous contact). Different NC contact cartridges were installed in the C5-C6 position of the relay and the anomaly still occurred. Forty-five (45) relays were tested for this anomaly. Twelve of 45 relays failed testing (C5-C6 with NC contact behaved like a timed contact). The relays were returned to Allen-Bradley for failure analysis. Allen-Bradley has duplicated the anomaly using the returned relays and one from their stock. This defect could cause the failure of a safety system to actuate or perform its intended safety function.
The 700RTC relays are used as replacements for Agastat Relays in certain safety-related applications. Over the past twelve years, 700RTC relays have been installed in various locations at North Anna. There are 88 installed timers in two circuits - SBO Diesel and EDG Load Sequencing circuits affecting several plant safety systems. In addition, six timers are installed in the non-safety related instrument air system.
At North Anna, the 700RTC relays are purchased commercial grade then upgraded for safety-related use using the commercial grade dedication process. The upgrade is performed by the North Anna Materials Verification Lab using an approved commercial grade dedication plan. Prior to identification of this anomaly, the dedication testing verified proper contact operation of the contact cartridges in the as-received configuration. The dedication process now verifies proper contact operation in all possible contact configurations.
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Current and planned 700RTC relay installations were reviewed. The majority of installed 700RTC relays are configured with the contact cartridges arranged according to the 700RTClll lOUl part number (NO. NC, NO, NC). In a few locations, the contact cartridges are configured NO, NO, NC, NC. North Anna does not utilize the CS-C6 position with the NC contact cartridge in any of 700RTC locations.
Prior to installation, 700RTC relays are bench tested for satisfactory operation.
Causes: Cartridge tolerance is not fully compatible with the relay causing the normally closed instantaneous contact to act as a timed contact. This is generally due to the variation in sensitivity to the eddy currents developed in the relay field poles that operate the contacts. In addition, the contacts do not always have consistent sensitivity, so when their positions are changed there can be incompatibilities between field poles and contacts.
Immediate Corrective Actions: Nine of the relays that failed bench testing were sent back to Allen-Bradley for analysis.
Industry Notification: OE notification No. 19273 - Abnormal response of Allen-Bradley 700RTC relays when configured with the NC contact in the CS-C6 position Page 2 of 2