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{{#Wiki_filter:CATEGORY REGULATORY INFORMATiON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9703240130 DOC.DATE: 97/03/17 NOTARIZED:
{{#Wiki_filter:CATEGORY REGULATORY INFORMATiON DISTRIBUTION SYSTEM           (RIDS)
NO FACIL:,50-490 Shearon Harris, Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION VERRILLI,M.
ACCESSION NBR:9703240130           DOC.DATE:   97/03/17   NOTARIZED:   NO       DOCKET  ¹ FACIL:,50-490 Shearon Harris, Nuclear Power Plant, Unit 1, Carolina               05000400.
Carolina Power&Light Co.ROBINSON,W.R.
AUTH. NAME           AUTHOR AFFILIATION VERRILLI,M.         Carolina Power & Light Co.
Carolina Power!'ight Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000400.
ROBINSON,W.R.
RECIP.NAME Carolina Power   !'ight Co.
RECIPIENT AFFILIATION


==SUBJECT:==
==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power greater than 100%occurred.Cause was implemented containing inappropriate guidance for short excursions.Change withdrawn.W/970317 lt D1STRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:Application for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:
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 Cause was implemented containing inappropriate guidance for short excursions.Change withdrawn.W/970317 lt D1STRIBUTION CODE: IE22T COPIES RECEIVED:LTR                 ENCL       SIZE:
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  
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Application for permit renewal         filed.                             05000400 G RECIPIENT           COPIES            RECIPIENT          COPIES ID CODE/NAME          LTTR ENCL        ID CODE/NAME         LTTR ENCL PD2-1 PD                 1    1      LE,N,                  1    1 INTERNAL: ACRS                       1    1      AEOD SPD NAB            2    2 AEOD/SPD/RRAB             1    1            CENTER            1    1 NRR/DE/ECGB               1    1        RR D EEGB              1    1 NRR/DE/EMEB               1    1      NRR/DRCH/HHFB          1    1 NRR/DRCH/HICB            1     1       NRR/DRCH/HOLB          1    1 NRR/DRCH/HQMB            1    1      NRR/DRPM/PECB           1    1 NRR/DSSA/SPLB            1     1     NRR/DSSA/SRXB            1     1           D RES/DET/EIB              1     1     RGN2    FILE 01        1     1 EXTERNAL: L ST LOBBY WARD            1     1       LITCO BRYCEgJ H        1     1 NOAC POOREiW.            1     1     .NOAC QUEENER,DS        1     1 NRC PDR                  1     1       NUDOCS FULL TXT        1     1 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.
Carolina Power & Ught Company                                                         William R. Robinson PO 8ox 165                                                                           Vice President New Hill NC 27562                                                                     Harris Nuclear Plant MAR     17 1997 U.S. Nuclear Regulatory Commission                                                       Serial: HNP-97-069 ATTN: NRC Document Control Desk                                                                     10CFR50.73 Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 97-005-00 Sir or Madam:
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)
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%
(3)(ii)20.2203(a)
power.
{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)
Sincerely, MV     .
(2)(iii)20.2203(a)
Enclosure c:       Mr. J. B. Brady (HNP Senior NRC Resident)
(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).
Mr. L. A. Reyes (NRC Regional Administrator, Region II)
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 hours 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.
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
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.
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)
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:
Mr. B. H. Clark Mr. J. M. Collins
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).
: Mr. G. W. Davis Ms. S. F. Flynn Ms. J. P. Gawron (BNP)
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 hours 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.
Mr. H. W. Habermeyer Mr. M. D. Hill Mr. W. J. Hindman Ms. C. W. Hobbs (HEEC)
However, following additional review and delays in implementing the continuous calorimetric, the TS bases revision was considered inappropriate.
Ms. W. C. Langston Mr. C. W. Martin (BNP)
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:
Mr. R. D. Martin Mr. J. W. McKay Mr. P. M. Odom (RNP)
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.
Mr. W. R. Robinson Mr. G. A. Rolfson Mr. R. F. Saunders Mr. C. N. Sweely Mr. M. A. Turkal (BNP)
PREVIOUS SIMILAR EVENTS: LER 96-003 was submitted on February 23, 1996.CORRECTIVE ACTIONS COMPLETED:
Mr. T. D. Walt Mr. R. L. Warden (RNP)
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.}}
HNP Real'Time Training INPO Harris Licensing File Nuclear Records
 
NRC FORM 366                               U.S. NUCLEAR REGULATORY COMMISSION                               APPROVED BY OMB No. 3150-0104
{4 95)                                                                                                                EXPIRES    04/30/96 ESTIMATED BURDEN PER RESPONSE       TO COMPLY WITH THIS MANDATORY OIFORMATION COLLECTION REQUEST: 50JI HRS. REPORTED lESSONS lEARNEO ARE LICENSEE EVENT REPORT (LER)                                              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 (See reverse for required number of                                WASHINGTON, OC 205550001, AND TO THE PAPERWORK REDUCTION PROJECT {3(50 digits/characters for each block)                                0104L OffICE OF MANAGEMENT ANO BUDGET. WASHINGTOIL OC 205M.
FACIUTY NAME   Ill                                                                         DOCKET NUMBER I2)                                      PAOE isl Harris Nuc(ear Plant Unit-1                                                                     50-400                             1 OF2 TITLE (4I Failure to perform core flux mapping following plant operation with reactor power greater than 100%.
EVENT DATE (5)                 LER NUMBER (6)               REPORT DATE {7)                           OTHER FACILITIES INVOLVED {6)
FACIUTY NAME                                DOCKET NUMBER SEQUENTIAL    REVISION MONTH        OAY    YEAR                                        MONTH    OAY      YEAR NUMBER      NUMBER FACIUTY NAME                                DOCKET NUMBER 20       96       97     005           00                 17       97                                                           05000 OPERATING                   THIS REPORT IS SUBMITTED PURSUANT To THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)
MODE (9)                     20.2201(b)                     20.2203(a)(2) (v)                     50.73(a)(2)(i)                         50.73(a) (2) (viii) 20.2203(a) {1)                20.2203(a)(3) (i)                     50.73(a)(2) (ii)                       50.73(a)(2)(x)
POWER        100%
LEVEL {10)                     20,2203(a)(2) (i)             20.2203(a) (3) (ii)                   50.73(a)(2) (iii)                     73.71 20.2203(a)(2)(ii)             20.2203(a)(4)                         50.73(a) (2) (iv),                    OTHER 20.2203(a) (2)(iii)            50.36(c) {1)                         50.73(a) (2) (v)                  Specify in Abstract be low or rn NRC Form 306A 20.2203(a) (2)(iv)             50.36(c) (2)                         50.73(a) (2) (vii)
LICENSEE CONTACT FOR THIS LER {12)
NAME                                                                                              TELEPHONE NUMBER anclrrde Area Code)
Michael Verrilli Sr. Analyst - Licensing                                                                   (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE                                                                                REPORTABLE CAUSE         SYSTEM     COMPONENT     MANUFACTURER                               CAUSE         SYSTEM       COMPONENT     'ANUFACTURER TO NPROS                                                                                  TO NPROS SUPPLEMENTAL REPORT EXPECTED {14)                                               EXPECTED MONTH      OAY          YEAR YES                                                                                                 SUBMISSION
{If yes, comp(ate EXPECTED SUBMISSIONDATE).                           X No                             DATE (15)
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 hours 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 US. NUCLEAR REGULATORY COMMISSIOII H.95I LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION fACILITYNAME ill                                  DOCKET             LER NUMBER 16)                 PAGE 131 SEOUENTIAL     REYISION NUMBER       NUMBER Shearon Harris Nuclear Plant        ~ Unit  tl                      50400 97   -     005     -     00 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 hours 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.}}

Latest revision as of 04:54, 22 October 2019

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 Duke Energy icon.png
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)
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Text

CATEGORY REGULATORY INFORMATiON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9703240130 DOC.DATE: 97/03/17 NOTARIZED: NO DOCKET ¹ FACIL:,50-490 Shearon Harris, Nuclear Power Plant, Unit 1, Carolina 05000400.

AUTH. NAME AUTHOR AFFILIATION VERRILLI,M. Carolina Power & Light Co.

ROBINSON,W.R.

RECIP.NAME Carolina Power  !'ight Co.

RECIPIENT AFFILIATION

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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N, 1 1 INTERNAL: ACRS 1 1 AEOD SPD NAB 2 2 AEOD/SPD/RRAB 1 1 CENTER 1 1 NRR/DE/ECGB 1 1 RR D EEGB 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 D RES/DET/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCEgJ H 1 1 NOAC POOREiW. 1 1 .NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 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 William R. Robinson PO 8ox 165 Vice President New Hill NC 27562 Harris Nuclear Plant MAR 17 1997 U.S. Nuclear Regulatory Commission Serial: HNP-97-069 ATTN: NRC Document Control Desk 10CFR50.73 Washington, DC 20555 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 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 3150-0104

{4 95) EXPIRES 04/30/96 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY OIFORMATION COLLECTION REQUEST: 50JI HRS. REPORTED lESSONS lEARNEO ARE LICENSEE EVENT REPORT (LER) 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 (See reverse for required number of WASHINGTON, OC 205550001, AND TO THE PAPERWORK REDUCTION PROJECT {3(50 digits/characters for each block) 0104L OffICE OF MANAGEMENT ANO BUDGET. WASHINGTOIL OC 205M.

FACIUTY NAME Ill DOCKET NUMBER I2) PAOE isl Harris Nuc(ear Plant Unit-1 50-400 1 OF2 TITLE (4I Failure to perform core flux mapping following plant operation with reactor power greater than 100%.

EVENT DATE (5) LER NUMBER (6) REPORT DATE {7) OTHER FACILITIES INVOLVED {6)

FACIUTY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH OAY YEAR MONTH OAY YEAR NUMBER NUMBER FACIUTY NAME DOCKET NUMBER 20 96 97 005 00 17 97 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT To THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

MODE (9) 20.2201(b) 20.2203(a)(2) (v) 50.73(a)(2)(i) 50.73(a) (2) (viii) 20.2203(a) {1) 20.2203(a)(3) (i) 50.73(a)(2) (ii) 50.73(a)(2)(x)

POWER 100%

LEVEL {10) 20,2203(a)(2) (i) 20.2203(a) (3) (ii) 50.73(a)(2) (iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a) (2) (iv), OTHER 20.2203(a) (2)(iii) 50.36(c) {1) 50.73(a) (2) (v) Specify in Abstract be low or rn NRC Form 306A 20.2203(a) (2)(iv) 50.36(c) (2) 50.73(a) (2) (vii)

LICENSEE CONTACT FOR THIS LER {12)

NAME TELEPHONE NUMBER anclrrde Area Code)

Michael Verrilli Sr. Analyst - Licensing (919) 362-2303 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT 'ANUFACTURER TO NPROS TO NPROS SUPPLEMENTAL REPORT EXPECTED {14) EXPECTED MONTH OAY YEAR YES SUBMISSION

{If yes, comp(ate EXPECTED SUBMISSIONDATE). X No DATE (15)

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 US. NUCLEAR REGULATORY COMMISSIOII H.95I LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION fACILITYNAME ill DOCKET LER NUMBER 16) PAGE 131 SEOUENTIAL REYISION NUMBER NUMBER Shearon Harris Nuclear Plant ~ Unit tl 50400 97 - 005 - 00 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.
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