|
---|
Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML22208A0042022-06-17017 June 2022 Nutherm International, Inc., USNRC 10CFR Part 21 Notification Reference: Arnold Magnetics Power Supply Part Number PBM-24-106 ML22153A0792022-04-0707 April 2022 10CFR Part 21 Notification for Curtiss-Wright Supplied RCS-Dresser Actuator P/N: SURE-24-10-4 ML21294A0292021-10-0404 October 2021 Flowserve Part 21 Notification for Limitorque Supplied DC Motor ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18341A2472018-12-0606 December 2018 Mirion Technologies - 10 CFR Part 21.21 Report Re Relays Defect ML18354A7422018-12-0404 December 2018 Engine Systems, Inc., Submittal of 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 1OCFR21-0123, Rev. 0 - Emo Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts 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 ML18003A2602017-12-19019 December 2017 Crane Nuclear, Inc. - 10 CFR Part 21 Notification of Defect on Weak Link Analysis for Chapman Gate Valve Figure L900, Item #18, Drawing CC05307, Revision B 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 ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML16243A4742016-08-26026 August 2016 Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays ML16238A1862016-08-15015 August 2016 Update - Report of Potential l0CFR Part 21, Allen Bradley Timing Relay Model 700RTC-NRC Event Number 51030, Accession Number ML15134A016 ML16232A6042016-08-15015 August 2016 Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML16196A0642016-07-10010 July 2016 Part 21 Report - Materials Not Properly Dedicated 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 ML16154A2072016-05-26026 May 2016 Part 21, Azz/Nli Nuclear Logistics, Inc., Potentially Unqualified Component in Certain Allen Bradley Timing Relays Model 700RTC ML16194A1992016-05-25025 May 2016 Azz/Nli - Update - Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML16111A4202016-04-0808 April 2016 Part 21 Report No. P21-04302015, Rev. 1 Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays, Per Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - 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 ML15159A5682015-04-30030 April 2015 Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML14303A2582014-10-27027 October 2014 10 CFR Part 21 Notification of an Error in Powerplex MCPR and LHGR Limit Input for Browns Ferry, Unit 2 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 ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose ML14220A0212014-07-29029 July 2014 Final Report - Closure for Iterim 10CFR Part 21 Report (PMT No. 14-01, Ncr Event No. /Accession No. ML14192A040) ML14213A0992014-07-24024 July 2014 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) 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 ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14192A0402014-07-0303 July 2014 Interim Report - 10CFR Part 21 Evaluation Regarding Potential Deficiencies 2023-12-14
[Table view] |
Text
0610412014 U.S. Nuclear Reru torv Commission Overations Center Event ReDortPpoo IPart 21 (PAR) Event# 50172Rep Org: AREVA INC Notification Date / Time: 06/04/2014 15:22 (EDT)Supplier:
AREVA INC Event Date I Time: 06/04/2014 (PDT)Last Modification:
06/04/2014 Region: 4 Docket #:City: RICHLAND Agreement State: YesCounty: License #:State: WANRC Notified by: ALAN B MEGINNIS Notifications:
DEBORAH SEYMOUR R2DOHQ Ops Officer:
CHARLES TEAL NICK TAYLOR R4DOEmergency Class: NON EMERGENCY PART 21 GROUP EMAIL10 CFR Section:21.21(d)(3)(i)
DEFECTS AND NONCOMPLIANCE PART 21 -DEFECT IDENTIFIED IN SINGLE LOOP OPERATION MINIMUM CRITICAL POWER RATIOThe following is a synopsis of information received via facsimile from AREVA:AREVA identified a defect is in the calculation of the single loop operation (SLO) minimum critical power ratio(MCPR) operating limits for Browns Ferry Units 1, 2, and 3. Specifically, the defect is associated with the usage ofnon-conservative inputs in the SLO pump seizure analyses for the three plants, which results in non-conservative limits for SLO.Individual informing the Commission:
Alan B. Meginnis, AREVA Inc., 2101 Horn Rapids Road, Richland, WA 99354.
-AREVA6/4/2014 3:22:25 PM PAGE1/003 Fax ServerAREVAREVAAREVA Inc.FAXTo: NRC Operations CenterCompany:
U.S. NRCDate: 6/4/2014 Time in: 3:22 PMPages to follow: 2From: Alan B. MeginnisTelephone:
509-375-8266 MB: 36E] Original to be mailed [ Via fax onlyReceiving fax: 301-816-5151 Telephone:
301-816-5100 Extra Distribution to:Sending fax: 434-382-5541 Fax verification:
509-375-8266 Message:Please see attached defect noticeAREVA Inc.2101 Horn Rapids RoadRichland, WA 99354-5102 Telephone:
(509) 375-8100Operator:
Log No.:Ti me Sent:
AREVA 6/4/2014 3:22:25 PM PAGE 2/003 Fax ServerReportable Defect(i) Name and address of the individual or individuals informing the Commission.
Alan B. Meginnis, AREVA Inc., 2101 Horn Rapids Road, Richland, WA99354.(ii) Identification of the facility, the activity, or the basic component supplied for such facility orsuch activity within the United States which fails to comply or contains a defect.The defect is in the calculation of the single loop operation (SLO) minimum critical power ratio(MCPR) operating limits for Browns Ferry Units 1, 2, and 3. Specifically, the defect is associated with the usage of non-conservative inputs in the SLO pump seizure analyses for the threeplants, which resulted in non-conservative limits for SLO.(iii) Identification of the firm constructing the facility or supplying the basic component whichfails to comply or contains a defect.AREVA Inc.(iv) Nature of the defect or failure to comply and the safety hazard which is created or could becreated by such defect or failure to comply.This issue is a defect as defined in 10 CFR 21.3. The calculated MCPR is used to confirm that thecore is operated within the required Operating Limit MCPR (OLMCPR).
The OLMCPR isestablished to ensure that the Technical Specification Safety Limit MCPR (SLMCPR) is notviolated during anticipated operational occurrences (AOOs). The defect in the SLO pump seizureanalyses produced a non-conservative prediction of MCPR. If a SLO pump seizure occurred inany of the three Browns Ferry Units, and that reactor was operating on the specified OLMCPR,the technical specification MCPR safety limit could have been violated.
Therefore, the issue isconsidered a defect.(v) The date on which the information of such defect or failure to comply was obtained.
The issue was first documented in the AREVA Inc. Corrective Action Program on April 15, 2014.Page 1 of 2
-AREVA6/4/2014 3:22:25 PM PAGE3/003 Fax Server(vi) In the case of a basic component which contains a defect or fails to comply, the number andlocation of these components in use at, supplied for, being supplied for, or may be supplied for,manufactured, or being manufactured for one or more facilities or activities subject to theregulations in this part.The defect exists in the calculation of SLO MCPR for the following reactors:
Browns Ferry Unit 1Browns Ferry Unit 2Browns Ferry Unit 3(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be takento complete the action.As the responsible organization, AREVA Inc. has provided recommended compensatory actionsto all affected plants. The compensatory actions involve restricting the range of core power,core flow, and margin to thermal limits during single loop operation to compensate for the non-conservative prediction of SLO OLMCPR. The operability analyses used as a basis for thecompensatory operating restrictions will be formally reviewed per AREVA's approved qualityassurance process which complies with the criteria set forth in 10 CFR 50 Appendix B. AREVAInc. will provide TVA the formal operating restrictions on core power, core flow, and margin tothermal limits applicable to Browns Ferry Unit 1 Cycle 10, Browns Ferry Unit 2 Cycle 18 andBrowns Ferry Unit 3 Cycle 17. The schedule for completion of the formal documentation is July31, 2014. Analyses and documentation for future operating cycles for the three units which arelicensed by AREVA Inc. will occur on the normal reload schedules for cycle specific milestones.
(viii) Any advice related to the defect or failure to comply about the facility,
- activity, or basiccomponent that has been, is being, or will be given to purchasers or licensees.
This defect only had the potential to violate the SLMCPR during SLO. The Browns Ferry plantsnever operated in SLO while they were supported by the supplied limits. Therefore, the plantsnever operated where SLMCPR could have been violated.
Additionally, the current licensing methodology used by AREVA Inc. is believed to be overly conservative in determining thermalmargins specific to the SLO pump seizure event. AREVA Inc. currently has a new high fidelitytransient methodology under review by the USNRC referred to as AURORA-B.
Scoping andpreliminary SLO pump seizure analyses with this new method have demonstrated that thermallimits would not have had the potential to be violated if AURORA-B had been used for thelicensing calculation.
AURORA-B is not yet approved for licensing calculations, but does providesupport that the current method is overly conservative.
Page 2 of 2