ML18012A580

LER 97-005-00:on 960320,failure to Perform Core Flux Mapping Following Plant Operation with Reactor Power Greater than 100% Occurred.Cause Was Implemented Containing Inappropriate Guidance for Short Excursions.Change withdrawn.W/970317 Ltr

ML18012A580
Person / Time
Site:	Harris
Issue date:	03/17/1997
From:	Robinson W, Verrilli M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-97-069, HNP-97-69, LER-97-005, LER-97-5, NUDOCS 9703240130
Download: ML18012A580 (7)

Text

CATEGORY REGULATORY INFORMATiON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9703240130 DOC.DATE: 97/03/17 NOTARIZED:

NO FACIL:,50-490 Shearon Harris, Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VERRILLI,M.

Carolina Power&Light Co.ROBINSON,W.R.

Carolina Power!'ight Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000400.

SUBJECT:

LER 97-005-00:on 960320,failure to perform core flux mapping following plant operation with reactor power greater than 100%occurred.Cause was implemented containing inappropriate guidance for short excursions.Change withdrawn.W/970317 lt D1STRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for permit renewal filed.05000400 G RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POOREiW.NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LE,N, AEOD SPD NAB CENTER RR D EEGB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCEgJ H.NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D U E NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25

Carolina Power&Ught Company PO 8ox 165 New Hill NC 27562 William R.Robinson Vice President Harris Nuclear Plant MAR 17 1997 U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-97-069 10CFR50.73 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 97-005-00 Sir or Madam: In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.

This report describes Technical Specification violation involving the failure to perform flux mapping after short period of plant operation with the reactor greater than 100%power.Sincerely, MV.Enclosure c: Mr.J.B.Brady (HNP Senior NRC Resident)Mr.L.A.Reyes (NRC Regional Administrator, Region II)Mr.N.B.Le (NRC-NRR Project Manager)9703240i30 9703i7 PDR ADOCK 05000400 S PDR"40068 IIIUI!Illtllll!IIIU[llll!tgUIIIUIXUU State Road 113'ew Hill NC Tel 919362-2502 Fax 919362-2095 U.S: Nuclear Regulatory Commission Document Control Desk/HNP-97-069 Page 2 of 2 bcc: Mr.T.C.Bell Mr.H.K.Chernoff (RNP)Mr.B.H.Clark Mr.J.M.Collins: Mr.G.W.Davis Ms.S.F.Flynn Ms.J.P.Gawron (BNP)Mr.H.W.Habermeyer Mr.M.D.Hill Mr.W.J.Hindman Ms.C.W.Hobbs (HEEC)Ms.W.C.Langston Mr.C.W.Martin (BNP)Mr.R.D.Martin Mr.J.W.McKay Mr.P.M.Odom (RNP)Mr.W.R.Robinson Mr.G.A.Rolfson Mr.R.F.Saunders Mr.C.N.Sweely Mr.M.A.Turkal (BNP)Mr.T.D.Walt Mr.R.L.Warden (RNP)HNP Real'Time Training INPO Harris Licensing File Nuclear Records NRC FORM 366{4 95)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED BY OMB No.3150-0104 EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY OIFORMATION COLLECTION REQUEST: 50JI HRS.REPORTED lESSONS lEARNEO ARE OICORPORATEO INTO THE UCENSDIG PROCESS ANO fEO BACK TO DIOUSTRY.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE OIFORMATIN ANO RECORDS MANAGEMENT BRANCH IT@f33L US.NUCLEAR REGUlATORT COMMISSIOIL WASHINGTON, OC 205550001, AND TO THE PAPERWORK REDUCTION PROJECT{3(50 0104L Off ICE OF MANAGEMENT ANO BUDGET.WASHINGTOIL OC 205M.FACIUTY NAME Ill Harris Nuc(ear Plant Unit-1 DOCKET NUMBER I2)50-400 PAOE isl 1 OF2 TITLE (4I Failure to perform core flux mapping following plant operation with reactor power greater than 100%.MONTH OAY YEAR EVENT DATE (5)LER NUMBER (6)SEQUENTIAL NUMBER REVISION MONTH NUMBER OAY YEAR REPORT DATE{7)FACIUTY NAME FACIUTY NAME OTHER FACILITIES INVOLVED{6)DOCKET NUMBER DOCKET NUMBER 20 96 97-005-00 17 97 05000 OPERATING MODE (9)POWER LEVEL{10)NAME 100%50.73(a)(2)(i) 20.2203(a)(2)(v)20.2201(b) 50.73(a)(2)(viii)50.73(a)(2)(x) 50.73(a)(2)(ii)50.73(a)(2)(iii)20.2203(a)(3)(i)20.2203(a)

(3)(ii)20.2203(a)

{1)20,2203(a)(2)(i)73.71 OTHER low 50.73(a)(2)(iv), 50.73(a)(2)(v)50.73(a)(2)(vii)20.2203(a)(4) 50.36(c){1)50.36(c)(2)20.2203(a)(2)(ii) 20.2203(a)

(2)(iii)20.2203(a)

(2)(iv)Specify in Abstract be or rn NRC Form 306A LICENSEE CONTACT FOR THIS LER{12)TELEPHONE NUMBER anclrrde Area Code)THIS REPORT IS SUBMITTED PURSUANT To THE REQUIREMENTS OF 10 CFR 5: (Check one or more)(11)Michael Verrilli Sr.Analyst-Licensing (919)362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS CAUSE SYSTEM COMPONENT'ANUFACTURER REPORTABLE TO NPROS SUPPLEMENTAL REPORT EXPECTED{14)YES{If yes, comp(ate EXPECTED SUBMISSIONDATE).

X No EXPECTED SUBMISSION DATE (15)MONTH OAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximateiy 15 singio.spaced typewritten lines)(16)On March 20, 1996, a calculated reactor power level of 100.08%was identified during the daily secondary calorimetric heat balance.Following verification of the reactor power calculation, reactor power was reduced from approximately 99.9%to 99.5%indicated power.Technical Specification (TS)3.2.3 action C.1 requires reactor core flpux mapping to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially entering the"prohibited region.of operation." This region is defined by TS figure 3.2-3, which has a vertical line at exactly 100.0%power.Flux mappmg was not performed following this event based on guidance contained in the bases for TS 3.2.3, which was inserted following a previous violation of this technical specification (reference LER 096-03).This guidance was intended to clarify when thermal power is considered to be within 100.0%rated thermal power and'was implemented for the pending continuous calorimetric capability.

However, following additional review and delays m implementing the contmuous calorimetric, the TS bases revision was considered inappropriate.

On February 13, 1997, the bases revision was withdrawn, thereby resulting in the March 20, 1996 event being considered reportable as a violation of TS 3.2.3 for not performing core flux mapping.This event was caused when the bases change for TS 3.2.3 was implemented containing inappropriate guidance for short power excursions over 100.0%power.(reference CP&L letter to NRC dated February 8, 1996)Corrective actions included withdrawing the TS 3.2.3 bases change and issuing an Operations Night Order communicating this action to Operations personnel.

NRC fOAM 366A H.95I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION US.NUCLEAR REGULATORY COMMISSIOII fACILITY NAME ill Shearon Harris Nuclear Plant~Unit tl DOCKET 50400 LER NUMBER 16)SEOUENTIAL REYISION NUMBER NUMBER 97-005-00 PAGE 131 2 OF 2 TEXT rrimart spat N sopor'trE tso talfsind o~af HRC foes JBQI 1131 EVENT DESCRIPTION:

On March 20, 1996, a calculated reactor power level of 100.08%was identified during the daily secondary calorimetric heat balance (Operations Surveillance Test, OST-1004).

Following verification of the reactor power calculation, reactor power was reduced from approximately 99.9%to 99.5%indicated power.Technical Specification 3.2.3, Heat Flux Hot Channel Factor and RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, action C.1 requires reactor core'flux mapping to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially entering the"prohibited region of operation." This region is defined by TS figure 3.2-3, which has a vertical line at exactly 100.0%power.Flux mapping was not performed following this event based on guidance contained in the bases for TS 3.2.3, which was inserted following a previous violation of this technical specification.(reference LER b'96-03)This guidance was intended to clarify when thermal power is considered to be within 100.0%rated thermal power and was implemented for the pending continuous calorimetric capability.

However, following additional review and delays in implementing the continuous calorimetric, the TS bases revision was considered inappropriate.

On February 13, 1997, by CP&L letter to the NRC, the bases revision was withdrawn, thereby resulting in the March 20, 1996 event being considered reportable as a violation of TS 3.2.3 for not performing core flux mapping.CAUSE: This event was caused when the bases change for, TS 3.2.3 was implemented containing inappropriate guidance for short power excursions over 100.0%power.(reference CP&L letter to NRC dated February 8, 1996)SAFETY SIGNIFICANCE:

There were no safety consequences as a result of this event.Short periods of reactor power less than 102%rated thermal power are accounted for in accident and hot channel factor analyses.This is being reported per 10CFR50.73.a.2.i.B as a violation of Technical Specifications.

PREVIOUS SIMILAR EVENTS: LER 96-003 was submitted on February 23, 1996.CORRECTIVE ACTIONS COMPLETED:

1~The TS 3.2.3 bases change was withdrawn by letter to the NRC dated February 13, 1997, thereby deleting the intended clarification of 100.0%rated thermal power.2.An Operations Night Order was issued on February 5, 1997 to inform Operations personnel of the intent to delete the TS bases guidance for 100%rated thermal power.