NL-14-0838, LER 14-003-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer than Allowed by Technical Specifications: Difference between revisions

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{{Adams
#REDIRECT [[05000348/LER-2014-003]]
| number = ML14153A684
| issue date = 06/02/2014
| title = LER 14-003-00 for Joseph M. Farley Nuclear Plant, Unit 1, Regarding Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer than Allowed by Technical Specifications
| author name = Gayheart C A
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000348, 05000364
| license number =
| contact person =
| case reference number = NL-14-0838
| document report number = LER 14-003-00
| document type = Letter, Licensee Event Report (LER)
| page count = 7
}}
 
=Text=
{{#Wiki_filter:Cheryl A.GayheartSouthernNuclear Vice Presicteni
-Farley Operating Company, Inc.Farley Nuclcar PlantPostOfficeDrawer470Ashford.Alabama 36312 Tel 334.814.4511 Fax 334.814.4575 June 2,2014 COMPANY Docket No.;50-348 NL-14-0838 50-364U.S.NuclearRegulatoryCommission ATTN: Document Control Desk Washington,D.C.20555-0001 Joseph M.FarleyNuclearPlant-Units1and2 Licensee Event Report 2014-003-00 Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer Than Allowed bv Technical Specifications Ladies and Gentlemen:
This Licensee Event Report,"Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer Than Allowed by Technical Specifications," is being submitted pursuanttothe requirements of the Code of Federal Regulations, 10 CFR 50.73(a)(2)(i)(B)asan operation or condition prohibited by Technical Specifications.Thislettercontainsno NRC commitments.
Ifyouhaveany questions regardingthesubmittal, please contact Mr.BillArensat(334) 814-4765.Sincerely,>heart Vice Pre^deVtt-Farley CAG/WNA
 
==Enclosure:==
Units1 and 2 Licensee Event Report 2014-003-00 U.S.Nuclear Regulatory Commission NL-14-0838 Page 2 cc: Southern Nuclear Operating Company Mr.S.E.Kuczynski, Chairman, President&CEO IVIr.D.G.Bost, Executive Vice President&Chief Nuclear Officer Mr.B.L Ivey, Vice President-Regulatory Affairs Mr.C.R.Pierce, Regulatory Affairs Director Mr.D.R.Madison, VicePresident-FleetOperations Mr.R.R.Martin, Regulatory Affairs Manager-Farley Mr.J.E.Purcell, Nuclear TechnicalSpecialist-Farley Ms.K.A.Walker,Senior Engineer-Farley RTYPE: CFA04.054 U.S.Nuclear Reoulatorv Commission Mr.V.M.McCree,Regional Administrator Mr.S.A.Williams, NRRProjectManager-Farley Mr.P.K.Niebaum,SeniorResident Inspector-Farley Mr.J.R.Sowa,ResidentInspector-Farley Mr.R.E.Martin,SeniorProjectManager-Farley M.Farlev Nuclear Plant-Units 1 and 2 NL-14-0838 Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer Than Allowed by Technical Specifications EnclosureUnits1and2 LicenseeEventReport 2014-003-00 NRC FORM 366 (02-20t4)U.S.NUCLEARREGULATORYCOMMISSIONAPPROVEDBYOMB:NO.
31504104 EXPIRES: 01/31/2017 LICENSEE EVENT REPORT (LER)(SeePage2for requirednumberof digits/charactersforeach block)Eslimaled burden per response lo comply with this mandatory coOeetion re(piest: 80 hours.Repotted lessons learned are incorporated inio the lioensiRg process and fed to Indu^.Said comments regantng burden esSmale to#>>FOIA, Prhaqf and Irtfomalion CoSecSons Branch (T-S FS3).U.S.Nudea;Regulatcty Commission.
Washington, DC 20555^X101.
of by Internet ennail to Inlocoaeels.Resouiiee9nic.ge>>.
and to the Desk Officer.Of6c<<d InformaSon
^20503.Ha means used to impose an inlcrmation coUecSon does nd dsplay a cunerfly OMB cortrel nunber, the NRCmaynot conduct or sponsor.theintormationcolleclioa to.FACIUTY NAME Joseph M.FarleyNuclearPlant, Unit 1 12.DOCKET NUMBER 05000 348 3.PAGE Page1of4 TITLE Scaling Errors Result in Inoperable Steam Flow Channels for Durations Longer ThanAllowedbv Technical Specifications 5.EVENT DATE MONTH DAY YEAR 04 02 2014 9.OPERATING MODE 10.POWER LEVEL 100 6.LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.2014-003-00 7.REPORT DATE MONTH DAY YEAR 06 2014 8.OTHERFACILITIESINVOLVED OOCKET NUMBER 05000 364 FACnJTYNAMEFarleyNuclearPlant-Unit 2 FAaUTYNAME 11.THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR&sect;;(Cheek all that apply)20.2201(b) 20.2203(a)(3)(i)
U 50.73(a){2)(l)(C)
U 50.73(a)(2)(vil) 20.2201(d) 20.2203(a)(3)(li) 50.73(a)(2)(il)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(il)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1){l)(A) 50.73(a)(2)(iil) 50.73(a)(2)(lx)(A) 20.2203(a)(2)(li) 50.36(o)(1)(ll)(A) 50.73(a){2)(lv)(A) 50.73(a)(2){x) 20.2203(a)(2)(iil) 50.36(0(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(lv) 50.46(a)(3)(il) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a){2)(l)(A) 50.73(a)(2)(v)(C)
OTHER20.2203(a)(2)(vi)
E!50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
NRCFonn366A 12.UCENSEECONTACTFORTHISLER UCENSEE CONTACTWilliamN.Arens-Licensing Supen/isor LEPKONE NUMBER (b (334)814-4765 ia.COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU FACTURER REPORTABLE TOEPIX CAUSE SYSTEM COMPONENT JE FT MANU FACTURER F180 REPORTABLE TOEPIX 14.SUPPLEMENTAL REPORT EXPECTEDYES (If yes, complete 15.EXPECTED SUBMISSIC^
DATE)13 NO CAUSE SYSTEM COMPONENT JE FT IS.EXPECTED SUBMISSION DATE B080 MONTH DAY YEAR ABSTRACT (Umll lo 1400 spaeas, i.e., approxmalely IS single-spaced typewritten llnesf At 1819 CDT on April 2,2014, with Unit 1 operating in Mode 1 at 100 percent power, a review of scaling data identified that Unit 1 steam generator steam flow transmitter calibration procedures contained incorrect scaling data.Further analysis determined that the IB Steam Flow Channel Q1C22FT0484 was outside allowable Tech^Specification tolerance since being calibrated with the incorrect scaling data dunng the Fall 2013 re'ueling outage.This steam flow channel was subsequently re-scaled and returned to operable status on Apnl 5,2014 at 0821.At 1300 CDT on April 8,2014.with Unit 2 operating in Mode 1 at 100 percent power, the continuing review of scaling data also identified that Unit 2 steam generator steam flow transmitter calibration procedures conta^ed iricorrect scaling data.As a result, the 2C Steam Flow Channel Q2C22FT0494 was outside of its allowable T^hniwl Specification tolerance since being calibrated during the Spring 2013 refueling outage.This steam flow channel was subsequently re-scaled and returned to operable status on April 9,2014 at 0040.Since both of these channels had been incorrectly scaled since the beginning of each unit's operating cycle (October, 2013 for Unit 1 and May 2013 for Unit 2)this represents a condition prohibited by Technical Specifications and is reportable pursuantto10 CFR 50.73(a)(2)(i)(B).
NRC FORM JMitffi.MM)
!ICF0RM3<<6A l02-2UI4)UA NUCLEAR REGULATORY COM\nSSION APPROVED BY OMB: NO.3IS0-0IM EXPIRES: 01/31/201 Estmaied burden per response to comply wilh this mandatory collection Branch (T-5 F53), O.S.Nuclear Regulatory raac ASiiora'>>c&" M Washington, DC 20501II a means used to impose an intormation coBectwn does not (Js^ayalcwr^vaEd OMB control number.Ifte NRC may not conduct Of spotw*.and a person IS not LICENSEE EVENT REPORT (LER)CONTINUATION SHEET 1.FACILITY NAME 2.DOCKET Joseph M.Farley Nuclear Plant, Unit 1 05000 348 NARRATIVE YEAR 2014 6.LER NUMBER SEQUENTIAL t^MBER 003 REV NO.00 3.PAGE 2 of 4 Westinghouse
-Pressurized Water Reactor Energy Industry Identification Codes are identified in the text as[XXJ.RequirementforReport This report is required per 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications due to the Unit 1 Steam Flow Channel Q1C22FT0484
[FT]and the Unit 2 Steam Flow Chanel Q2C22FT0494
[FT]being inoperable without the applicable Required Actions of Techniral Specification 3.3.2 (Engineered Safety Feature Actuation System (ESFAS)Instrumentation) being perfomied within the required Completion Time.Unit Status at Time of Event From the time of the first discovery on April 2.2014 of an incorrectly scaled steam flow channel until both channels were properly scaled, both units operated in Mode 1 at 100 percent thermal power.Descriptionof Event At 1819 on April 2,2014, during an extent of condition review of an unrelated scaling issue, Engineering personnel identified that Unit 1 procedures for calibration of steam flow channels contained scaling data due to the transmitter span information not being updated from the P^fvious^erating^cj^^^^
Further review identified that as a result of the incorrect scaling data, steam flow chann^Q1C22^0484, the IB Steam Generator Channel 111 Steam Flow instrument, was outside of its a"owed Technical Specification tolerance.
The steam flow channel was declared inoperable and the applicable Technical Specification Required Action was entered at 2104 on April 2,2014.The steam flow subsequently re-calibrated using a corrected steam flow calibration procedure and*0 oPstatus at 0821 on April 5,2014.Since this steam flow instrument had been incorrectly calibrated during the most recent refueling outage in the Fall of 2013, the 72-hour Required Action o'Jf hnical Specification 3.3.2 (ESFAS Instrumentation) to place the channel in the tripped condition that becarne applicable on October 25,2013 was not met due to station personnel being unaware of The remainder of the Unit 1 steam flow channels, although impacted by the scaling error, remained withintheallowableTechnicalSpecificationtolerance.
On April 8,2014, during continued extent of condition reviews.Engineering personnel Identified that Unit 2 procedures for calibration of steam flow channels also contained transmitter span data that was^updated from the previous cycle.Further review of Unit 2 steam generator scaling data idei^ifted that steam flow channel Q2C22FT0494, the 2C Steam Generator Channel III Steam Flow"Jf^, outside of its allowed Technical Specification tolerance.
The steam flow channel was and the applicable Technical Specification Required Action was entered at 1145 on April 8,2014 Th^steam flow instrument was subsequently re-calibrated using a corrected steam flow P"^^""^and restored to operable status at 0040 on April 9,2014.Since this steam flow instrument had l^en incorrectly calibrated during the most recent refueling outage in the Spring of 2013, Action of Technical Specification 3.3.2 (ESFAS Instrumentation) to place the channel'"^he tripped condHion that became applicable on May 8,2013 was not tnet due to S!ha JST the scaling error.The remainder of the Unit 2 steam flow channels, although impacted by the scaling error, remained within the allowable Technical Specification tolerance.
NRC FORM 3<<6A (Ol-MM) lNRCFORM3e6A l(02-:014)
U.S.NUCLEAR REGULATORY COMMISSION LICENEE EVENT REPORT (LER)1 1.FACILITY NAME 2.DOCKET 6.LER NUMBER 3.PAGE 1 1 Joseph M.Farley Nuclear Plant, Unit 1 05000 348 YEAR SEQUENTIAL NUMBER REV NO.3 of 4 1 2014 003 00 Cause of Event The direct cause of this event is due to steam flow instrument transmitter span data tables not being updated with current cycle information prior to instrument calibration during the most recent refueling outage for each unit.These instrument tables had not been updated due to a combination of an oniission in procedure FNP-O-ETP-4509 (Scaling Engineer Guidelines) and knowledge weaknesses among the Engineering personnel performing the scaling activities.
Safety Assessment Steam flow channels perfonn a safety function by providing a high steam flow input to main steam line isolation logic circuitry.
Each of the three steam generators is equipped with two redundant steam flow transmitters.
A high steam flow signal from one of the two steam flow transmitters on two of the three steam generators coincident with a low-low reactor coolant system (RCS)average temperature signal from two of three RCS temperature channels generates a main steam line isolation signal that causes closureofallmain steamlineisolation valves.During the time periods of the Unit 1 FT-484 and Unit 2 FT-494 out-of-tolerance condition, the redundant steam flow transmitters remained capable of performing their safety function.Therefore, sufficient inputs to the main steam line isolation circuitry were available to actuate a mam steam line isolation at the proper setpoint.At no time was there a loss of safety function.Additionally, Unit 1 FT-484 and Unit 2 FT-494 remained capable of actuating during a high steam flow condition, although slightlyabovethe allowed setpoint.A diverse means of providing a main steam line isolation in the event of a steam line break is the low-steam-pressure main steam line isolation signal.This function remained fully capable of performing the main steam line isolation function during the periods that these two steam flow channels were known to be out of tolerance.
A diverse means of providing a main steam line isolation in the event of a steam line break inside Containment is the high-high Containment pressure main steam line isolation signal.This'unction remained fully capable of performing the main steam line isolation function during the periods that thesetwosteam flowchannelswere knowntobeoutoftolerance.
Steam flow channels also provide a control function associated with the steam generator water level control system.The steam flow channel scaling errors caused minimal impact to the steam generator water level control systems with no observable effects on the function of these systems.Based on the above considerations this condition is considered to have low safety significance.
Corrective Action Unit 1 steam flow transmitter FT-484 was rescaled per work order SNC564824 and returned to operable status at 0821 on April 5,2014.Unit 2 steam flow transmitter FT-494 was rescaled per work order SNC566091 and was returned to operable status at 0040 on April 9,2014.The remainder of the instruments impacted by this scaling error issue have been rescaled per separate work orders.Calibration procedures for all protection instrument channels on both uriits controlled by the pr(wedure FNP-O-ETP-4509 (Scaling Engineer Guidelines) have been reviewed with no other instances of scaling errors being identified that impacted channel operability.
NRC FORM 3<<6A (tC-3)l4>
NRCFORM366A (02-2014)U.S.NUCLEAR REGULATORY COMMISSION L FACILITY NAME LICENEE EVENT REPORT (LER)CONTINUATION SHEET 2.DOCKET YEAR 6.LER NUMBER SEQUENTIAL NUMBER Joseph M.FarleyNuclearPlant,Unit1 05000 348 2014 003 NARRATIVE REV NO.00 3.PAGE 4 Of 4 The error in procedure FNP-O-ETP-4509 (Scaling Engineer Guidelines) has been corrected.
Additionally, an improved and less cumbersome process for incorporating scaling data into calibration procedures is being pursued.Training of Engineering personnel regarding this event has been conducted.
An engineer training plan forscalingand normalization processes willbedeveloped.
Additional Information Joseph M.Farley Nuclear Plant Unit 2 LER 2013-001-00 was submitted on July 26,2013 to report two instances of a condition prohibited by Technical Specificationsduetothe untimely renormalization of SteamFlowTransmitter FT-494atthebeginningoftwooperatingcycles.
Joseph M.Farley Nuclear Plant Unit 1 LER 2013-003-00 was submitted on January 3,2014 to report a condition prohibited by Technical Specificationsduetothe untimely renormalization of Steam Flow Transmitter FT-495atthe beginningofanoperatingcycle.
NRC FORM 366A (02-2014)}}

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